DUKE ENERGY°.7I South

4 DUKE 526 South Churh SreeCharlotte, NC 28202ENERGY°.7I Mailing Address:

EC12 / P.O. Box 1006Charlotte, NC 28201-1006

Serial: NPD-NRC-201 5-053

December 10, 2015

U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555

Levy Nuclear Plant Units 1 and 2Docket Nos. 52-029 and 52-030ROADMAP OF CHANGES IN COMBINED LICENSE APPLICATION, REVISION 8

Reference: Letter from Christopher M. Fallon (DEE) to U.S. Nuclear Regulatory Commission,dated December 7, 2015, "Levy Nuclear Plant Units 1 and 2 Submittal of COLApplication, Revision 8", Serial: NPD-NRC-201 5-031

Ladies and Gentlemen:

The purpose of this letter is to provide information supporting the recent Duke Energy revision ofthe Combined License Application (COLA) for Levy Nuclear Plant, Units 1 and 2 (seereferenced letter). Attached is a roadmap of the changes included in the December 7, 2015submittal along with an enclosure providing an explanation of the information contained in theroadmap.

If you have any questions, or need additional information, please contact me at (704) 382-4046.

Sincerely,

Robert KitchenDirector - Nuclear LicensingNuclear Development

Enclosure/AttachmentEnclosure: Levy Nuclear Plant Units 1 and 2 Roadmap of Changes in Combined LicenseApplication Revision 8 Explanation by Column in Attachment 1Attachment: Attachment 1 - LNP COLA Revision 8 Roadmap of Changes

cc : U.S. NRC Region II, Regional Administrator (w/o Enclosure and Attachment)Mr. Donald Habib, U.S. NRC Project Manager (w Enclosure and Attachment)Ms. Mallecia Sutton, U. S. NRC Environmental Project Manager (w Enclosure andAttachment )

Enclosure to Serial: NPD-NRC-2015-053Page 1 of 1

Levy Nuclear Plant Units I and 2Roadmap of Changes in Combined License Application Revision 8

Explanation by Column in Attachment I

Column Explanation

Change ID# Unique identifier for tracking purposes

COLA Identifies the change as STD (standard) or

LNP specific

COLA Part Part 1 (PT01) through Part 11 (PTI1)

Chapter FSAR or ER Chapter

Section Section/Subsection of the Chapter or Part

Basis for Change The source of the change

Change Summary Short description of the change

Attachment 1 - LNP COLA Revision 8 Roadmap of Chooges

Change IO# COLA COLApr Chapter Sect~on BasIs for Change Change SoummaryPaPart

[NP-155 -LNP 1 01.01.04 Revision to list of Revisions to Part 1 directors and officers boned on the latest Cake board meeting and other changes

directors and officersLNP-l99 [NP 1 - 3____ 1 .01 .04 Addition ofldirector Revision to Port 1 directors[NP-t70 [NP 1 Change from Coke Revisions to Part 1 based or corporate name change from Coke Energy Florida, inc. to Dske Energy Flordia, LLC

Energy Florida, Inc. toCake Energy Florida,

_____ _____ ___________L[C

LNP 1 Figaro 1.1-f Florida Progroso Change figure block for Florida Progress Corporation to read Florida Progress, LLCCorporat ion Is changed

to Florida Progress, [[C

Part 2

[NP-00l LNP 2 1 o1.08T/T1.8-201 NPC-NRC-201 4-038 levine Table 1.8-201 as shown in Item 1 of Enclosure7uof the subiect letter.[NP-188 LNP 2 1 01.O8T/T1.8-201 ,Correction Revise CCLA Part 2, Chapter 1, Table 1.0-201 in the Ceparture Cesuription Summary column and the FEAR Section or Subsection column for LNP COP 3.2-1 to delete

180.9 as there is no longer any change to the references section.L.NP-148 [NP 2 1 5)1.O8T/T1.8-201 ,4PC-NRC-2g015-008 Revise COLA Port 2, Chapter 1, Table 1.8-201 to odd dteparture [NP COP 6.2-1 as set forth in Enclosure 3to NPC-NRC-2015-008.

[NP-002 [NP 2 1 01.08T/T1.8-201 NPD-NRC-2015-014; Revise CC[A Part 2, Chapter 1, Table 1.8-201 to add departure LNP COP 8.4-1 as set forth in Item 1 of Enclosure 1ito NPC-NRC-2018-042osuperseded by'Encloosure 1 uf!NPD-NRC-20158-042

'NP-DO3 LNP 2 1 01.O8T/1"1.8-201 NIPC-NRC-20t5-003 Rgevise COLA Part 2, Chapter 1. Table 1.8-201 to add departure [NP COP 8.4-2 as set forth in Encloaure 4 to NPC-NRC-2015-003[NP-D92 LNP 2 1 01.O8T/T1.8-202 NPC-NRC-2105-0t4 Revise CO[A Part 2, Chapter ito add a departtare from CCC Table 1.6-1 as new Table 1.6-202, with a LMA of [NP COP 8.4-1 as set forth in Item 2 of Enclosure4 to NPC-

_____________________________________________NRC-2015-0 14.LNP-iS8 LNP 2 1 O1.O8TIT1.8-201 i'PC-NRC-2018-015 Rlevine Table 1.8-20100s shown in Item 1 of Enclosure 8 of the subiectletter.LNP-171 LNP 2 1 0i.08T1T1.8-201 l.PC-NRC-2015-038 Revise Table 1.8-201 to add departure [NP COP 7.2-1 os shown in Onctoosur 3StoNPC-NRC-2015-038.

LNP-004 LNP 2 1 01.09.04.02.02 l.PC-NRC-2015-00l COLA Part 2, FSAR Chapter1, will be revised to odd the following as the first item in Subsection 1.9.4.2.3, with a [MA of [NP COP 6.4-1:

NPC-NRC-2015-014Revise the secund sentence in the first paragraph of the APi1000 Response for Issue 83 in CCC Subsection 1.8.4.2.3 as follows:

If ac power is unavailable for more than 10 minutes aot i"High-2" particalate or iodine radioactivity is detected in the main contrel room supply air duct, which reould lead toecceeding G~enerat Cosign Crieria 10 operator dose limits, the protection and safety macluoring system astomatically isolates the main control room and operator habitabilityrequirements are then met bylthe malo control room emergency habitability system (YES).

[NP-O05 [NP 2 1 glAA/Appendio 1AA NFCP-NRC-2015-014 CCLA Part 2, FSAR Appendic lMARegulatory Guide 1.82 Rev 3, 8101 conformance ststement will be revised as follows. with a [MA of [.NP COP 8.4-1,to read:

Conformance with the design and operational aspects is as stated is the CCC, with the enception of Criteria Section C.4.9 and Table I. Conformance with Section C.4.6 and

Table 110s documented below.

C.4.8 Conforms

Table 1 Cnnforms

[NP-172 [NP 2 - 1 01.01 change from Cake •Change from Cake Energy Florida, tno, to Coke Energy Florida, [[C to reflect corporate name change

01.OiTIT1.1-201 Energy Floeids, Ian. to01.04.01 Couke Energy Florida,

[[C

[NP-173 [NP 2 2 02.01.01.01 change from Coke change from Cake Energy Florida, Inc. to Coke Energy Florida, [[C to reflect corporate name changegEnergy Florida, Inc. toCoke Energy Florida,[[C

[NP R8 Rsadmap Pinal f~or Submltal.xlsx ae1 f2Page I of 22

Attachment 1 - LNP COLA Revision B Roadmap of Changes

Change I09 COLA COLA Chapter Section Basis for Change Change SeminaryPart

[NP-0O6 [NP 2 3 03.01 .0 NIPD-NRC-2015-001NqPD-NRC-20"I 5-014 COLA Part 2, FSAR ChapterS3, will be revised to update Section 3.1 IBR statement, to read:

3.1 Confonnance With Nuclear Rogulatory Commission Gonoral Den/go Criteria

Thin section of the referenced DCD 10 incorporated by referenco with the following departures and/or sepplements.

LNP-007 [NP 2 3 03.01.02 NqPD-NRC-2015-SS1 COLA Part 2, FEAR Chaptor 3. will he rooerise to add new Sabsection 3.1,2, with a [MA of [NP DEP 6.4-1, to rood:NIPD-NRC-201 5-014

3.1.2 Protection by Multiple Fission Product BarriersRevise the tirot sentence of the third paragraph of APi1000 Compliance section of Criterion 1 9- Contrml Room of DOD Subsection 3.1.21to road an follows:

if ac power is unavailahle for more than 10 mioutes or if "High-2" particulate. low prosostrizer pressare isodetected, or"High-2" iodine radioactivity is dotected in the maincontrol room supply air dact, which woold lead to exceeding Goneral Design Criteria IS operator dooo limits, the protection and safety moniotoing system actomaticallyisolates the main control room and operator habitability reqairemento are then met by the main control room emergency habitability system (VESS).

LNP-005 [NP 2 3 03.57T£1T3.7-257 NJPD-NRC-2015-003 COLA PartS2, PSAR Section 3.7, will be reamsed to add a departure from DOD Tahle 3.7.3-1,Seismic Category I Eqaipmont DOuts/do Containment by Room Number, Sheets 1 of 3 and 2 of 3, an newFSAR Table 3.7-207, Sheets 1 and 2, with a [MA of [NP DSP 6.4-2. Thin Tunic shall also be added tothbe lint of tables in Chapter 3. Table 3.7-207, Sheets 1 and 2, in shown in the attachment to Enclosure 4 of NPD-NRC-2015-053.

[NP-OhS [NP 2 3 3.09T/T3.9-202 NPD-NRC-2515-003 COLA Part 2, FSAR Section 3.5, will be rosined to add a departare from DOD table 3.9-12,List of ASME Class 1,2, and 3 Active Valves, Sheet 6 of 7, an new FSAR Table 3.9-202w'ith a LMA of LNP DEPS6.4-2. Thin Table shall also be added to the lint of tab1es in Chapter3. Table 3.9-202 is shown in the antaohment to Enclosure 4 of NPD-NRC-2515-502.

[NP-OlD [NP 2 3 3.SST/T3.9.253 NPD-NRC-2515-003 COLA Part 2, FEAR Section 3.9, will be revised to add a departure from DOD Table 3.9-16,Valve Innervice Test Requirements, Sheet 23 of 26, 0s new FEAR Table 3.9-203w'ith a [MA of LNP DEP 6.4-2. Thin Table shall also be added to the list of tables in Chapter3. Table 3.9-203 is shown in the attachmeot to Enclosare 4 of NPD-NRC-2515-053.

LNP-011 [NP 2 3 03.11TIT3.11-202 NPD-NRC-201-5-03 COLA Part 2, FEAR Section 3.11 twill be revised to add a departure from DOD Table 3.1-I-,Environmentlaiy Oualified Electrical and Mechanical Equipment, Sheets 17, 30 and 47 of S1, as newFEAR Table 3.11-202, Sheets 1, 2 and 3, with a [MA of LNP DEP 6.4-2. This Table shall aloo be addedto the list of tables in Chapter 3. Table 3.11-202, Sheets 1, 2 aed 3, isshown is the attachment to Enclnosre 4 of NPD-NRC-25l1h-00S.

LNP-093 LNP 2 3 03.D NPD-NRC-251 5-003 COLA Port 2, FEAR ChapterS., will be rosined to opdtato Appendix 3D EBR statement to read:

T'his section of the referenced DOD in incorporated by, reference with the followino departures and /or supplements..NP-012 [NP 2 3 03.DF/F3.D-201 ,NPD-NRC-251h-003 COLA Part 2, FEAR Section 3.0, will be roomsed to add a departure from DOD Figare 3.D.5-

1, Typical Abnormal Environmental Toes Profhlns: Main Control Room. Sheet I of 3, as new FEARFigaro 3.D-251 with a LMA of [NP DEPS6.4-2. This Figare shall also be added to the list of figores

________________ n Chaster 3. Finure 3.D-251 is shown in the attachment to Ecnclosre 4 of NPD-NRC-2015-003._NP-094 LNP 2 5 03.1 NPD-NRC-201 5-003 COLA Part 2, FEAR ChapterS3, will be revised to update Appendix 31 IBR statement to read:

________fhin section of the referenced DOD is incarporated byf reference with the following departares and /or sunplements.LNP-S1S [NP 2 3 h3.1TIT3.1-201 NiPD-NRC-2015-003 C3OLA Part 2, FEAR Section 3.1, will he revioed to add a departure from DOD Table 3.1.6-2,

List ef Potential High Frequency Sensitive APl000 Safety-Related Electrical and Electro- MechanicalEquipment, Sheet 11 of 29, as new PEAR Table 3.1-201 with a LMA of [NPDEP 6.4-2. This Table shall also be added to the li/statf tables in Chapter 3. Table 3.1-201 is

_________ ________________shown in the attachment to Enclosure 4 of NPD-NRC-2515-003.LNP-01 4 [NP 2 3 53.1TIT3.1-252 NPD-NRC-2015-053 =COLA Part 2, FEAR Section 3.1, will be revised to odd a departure from DOD Table 3.1.6-3,

lost of AP1000 Safely-Related Electrical and Mechanical Eqoipment not High Frequency Seesitive,Sheets 10 and 28 of 32, as new FEAR Table 3.1-202, Sheets 1 and 2, with a [MA of [NP DEP 6.4-2.Thin Table shall also be added to the list of tables in Chapter 3. Table

_____________________ _____________________________________3.1-202, Sheets I and 2. is shows is the attachment tn Enclosura 4 of NPD-NRC-20'I5-003.

LNP R8 Roadmup Final for Sabwmttal.olnoPg 2s2Page 2 of 22

Attachment 1 - LNP COLA Revision 8 Roadmap of Changes

ChangelD#l COLA COLA Chapter Section BasIs for Change Change Summary

PartLNP-149 2 6 06.02.04.06.01 NPD-NRC-20l15-600 COLA Part 2, PSJOR ChapterS6, will be revised to odd new Subsection 6.2.4.5.1, with a LMA

of LNP DSP 6.2-1, to road:

6.2.4.6.1 Preoperational Inspection and Testing

Hydrogen Ignition Subsystem

Revise the second paragraph of DCD Subsection 6.2.4.5.1, Hydrogen Ignition Subsystoem, to rood as follows:Pro-operational inspection Is performed In vorify the location of openings throogh tho ceilings of the passive corn cooling system valoolaccumulator rooms wtih respect tothe containment pressure boundary. An onolysis will ho osed to demonstrate that postulated hydrogen relnases thmough these openings do not result in a foilure of thecontainment shell.

LNP-015b LNP 2 6 66.02.01.01.01 Errata Re-word the lend-in for the chongeoto FSAR 6.3.1.1.1 to read, "Revise the first bullet and add new second and third bullets in the first paragraph of DCD Subsection6.2.1.1.1 to rood as follows:" in order to ranform the COLA departore in this subsection with the change in the DCD

LNP-0I16 LNP 2 6 06.S3.01.S1.01 E-rrata Addsa nnw first boltet in Sobsection 6.2.1.1.1 of COLA Port 2. FSAR to read as follows: "- The passive residual heat removal heot eschanger astomaticeliy actuates to

provide reactor coolant system cooling."

LNP-151 LNP 2 6 66.02.01.01.64 Pmevieas CDLARAI COLA Port 2, PSAR Chapterf6, will be revised to add the following:

responseReploce the first sentence of the fourth parograph (old third paragraph) of DCD Ssbsection 6.2.1.1,4 with thn following:

Por loss of coolant accidents, when the core mokeop tank level meachen the aotomatic depresoudzatisn system actuaation setpoint and other postuelated events whome orpower sources are lost but passion residual hoot removal heat exchanger operation is not estended or is eshausted, the automatic depreussudztion system will be initiated.

LNP-15l7 LNP 2 6 06.03S.51.02.01l Correction Add the following asoanew first paragraph to COLA Part 2, FSARmSubsectionh6.2.1.2.1:The passive residual heat removal heat exchanger is designed to cost thin reactor coolant system to 420"F in 26 hours, wrth or without reactor coolant pumps operating. This

allows the reactor coolant system to be dopressunized and the stress In the reactor coolant system and connecting pipe to he reduced to tow levels. This also allows plantconditions to be established for initiation of nornol residual heat removal system operation. This non-boarding, conservative evaluation is discussed in subsection1696.4. 10.2.

LNP-156 LNP 2 6 06.03.01t.62.01 -Errato Revise COLA Part 2, FSAR Subsection 6.2.1.2.1, now 2nd paragraph, 6irat sentence to moad:The passive residual heat removal heat enchanger, in conjunction with the in-containment refueling water storage tank, the condensate return features and the passive

containment cooling system, has the capobility te maintain the reactor coolant system in the specified, long-term safe shutdown condition of 420Fl" for at least 14 days le aclosed-loop mode of operation.

LNP-l159 LNP 2 6 n6.02.02.01.01 Errata Revise the end nf the first sentence of the 7th paranranh of COLA Part 2. FSAR Subsection 6.2.2.1.1 from "ot least 72 hours" to "greater than 14 days",LNP-160l LNP 2 6 n6.02.02.fl1.Sl Errata fRevise the lost line of the 6th paragraph of COLA Part 2. FbAR Sohsectionf6.2.2.1.1 from "an estended period nf time" to"ngreater than 14 days"LNP-0f17 LNP 2 6 06.03.0l2.0l2.07.01l Correction Re-wntd the lead-in for the change to FSAR 6.3.2.2.7.1 to read. "Add a new first naranebga to DCD Subsection 6..2.22.7,1 to read as follows:"LNP-161 LNP 2 6 06.n3.n3.54.St Errata Change the revision of the last sentence of the 4th paragraph of COLA Part 2, PSAR Subsection 6.2.2.4.1 to read: "T'hisoanowsfitotuofuctionas a heat sink for greater than

_________14 days."LNP-016 LNP 2 6 06.03.03.086.01 Errata The subsection numbertfor "Loss of Startup Feedwater During Heat-Uns" needs to he revised from 6.2.2.6.1 to 6.3.2.4.1LNP-019f LNP 2 6 66.04. NqPD-NRC-2016-001 COLA Part 2, FSAR Chapter 6, wilt be revised to update Section 6.4, with a LMA of [NP DSP 6.4-Ito add the following before Subsectionf6.4.3:

NqPD-NRC-20 15-01146.4 Hobitablilty Systems

R•evise the first sentence of the third paragraph of DCD Section 6.4 to read as follows:

l on power is unavailable for more than 10 minstes or 6 "High-2" particulate or iodine radioactivity is detected in the main control room supply air duct, which would lead toosceeding General Design Crieria 10 operator dose limits, the protection and safety monftoring system autometiralny isolates the main controt room and operator habitability

requirements are than met by the main control moom emergoncy habitability system (iVES).

LNP R8 Roadmap Final for Submittalvix Pge2of2Page 3 of 22

Attachment 1 - INP COLA Revision 8 Roadmsap of Changes

Change 1D# COLA COLA Chapter Section Basin for Change Change BSummaryPart

LNP-020 LNP 2 B 06.04.02.02 NPD-NRC-2015-003 COLA Part 2, FSAI4 Chapter g, will be revised to add new Subsection 6.4.2.2, with a LMA of LNP DEP 6.4-2, to read:

6.4.2.2 General Description

Revise the ninth paragraph of DCD Subsection 6.4.2.2 to read an follows:

In the unlikely onset that power to the eaclear inland nonrudioactiee ventilation system in unavailable fur more than 72 hears, MCR habitability is maintained by operatingone at the two MCR ancillary furs to supply outside air at or below the maximum normal site amabient temperature to the MCR. See subsection B.4.t fur a description af thiscoolirg mode of operation. Doors and dudts may be opened to provide s supply pathway and an exhuanst pathway. Likewise, outside air in supplied to division B ord Cinstrumertation and conroel roams in order to maintain the ambient temperature below the qualification tomperuatre of the eqsipmovt,

LNP-02t LNP 2 6 uf6.04.02.03 NPD-NRC-2btit--tO3 COLA Part 2, PSAR Chapter 6, will be revised to add new Subsection 6.4.2.3, with a LMA ofLNP DEP 6.4-2, to read:

6.4.2.3 Companent Description

Revise the first paragraph of DCD Subsection 6.4.2.3 and add a new toarteenth bullet to read anfollows:

The main controt room emergency habitability system camprenssed air supply cantairs a net of staorge looks connected ta a main and an alternate air delivery litne andequipmert tn provide electrical toad de-energizutian. Companeots common to both hines include a manaual isatation valve undoa pressure regulating valve. Single activefailure protection is provided by the use at redundant, remotely operuted isolation valves, which urn located within the MCR pressure boundary. In the event of insufficient orencessive flow is the main delivery line, the main delivery lione is isolated and the alternate delivery live is manually untested. Thle alternate delivery tine contains the samecomponents as the main delivery line with the exception of the remotely operated isolation valves, and than is capablo of supplying compressed air to the MCR pressureboundary at the required air tlowrate. The VES piping and penetrations for the MCR envelope are dosigneted as equipment Clans C. Additional details an Class Cdesignation are provided is subsection 3.2.2.5. The classification of yES components is provided in Table 2.2-2, an appropriate.

* MCR Load Shed ParelsThe de-energizatior ot tho Main Control Room (MCR) electrical loads will be perfarmed using Clans l1Elequipment. nquipment within each at the twn electrical panels will beactuated froom the "mule control room isolation, air supply initiation and electrical load do- energization' engineered safety feature. The de-energization in separated into woastages to provide operators with the maxirnum available non-safely equipment, white maintaioing the MCR heat loud within the requirements of the yES.

Each electrical panel will have redundant relays and timers controlled by both PMS Division A and PMS Division C. Either division will he capable of actuating the timers sodrelays associated with each electrical panel independent of one another. This configuration prevents routine maintenance or single faileres of a PMS cabinet from creating aspurious loon of MCR electrical loads, while still providing for single failurn proteciton. In order to accomplish the "Do-energize MCR Electrical Loads" function, one set atStage I and Stage 2 timers in each electrical panel mart receive the PMS cnommand.

Reluyu is both electrical panels most he actauatd in order to carry out the overall function; however, overall actuatino may occur via different combinations of Division Aand Division C commands.

LNP0

-022 LNtrP 2 6 fl6.04.02.06 NPD-NRC-20tt5-001 COLA Part 2, FSAR Chapter 6, will be revised to add new Subsection 6.4.2.6, with a LMA at LNP DEP 6.4-1,0 ro rad:

NPD-NRC-2015-0146.4.2.6 Shielding Design

Revise DCD Subsection 6.4.2.60to read as follows:

The design basis loss-of-coolant acctdent (LDCA) dictates the shielding requirements for the male control room. Main control roam shielding design bases are discussed inSection 12.3. In addition to shielding provided by building structural festurns, consideratlon is given to shielding provided by the VES filter shielding. Descriptions of thedesign basis LDCA source terms, main control moom shielding parameters, and evaluatian of dunes to main cantrol room perasonel are presented in Section 10.6.

The main control room and fins location in the plant are shows in Figure 12.2-1.

LNP Ra Roadmap Final for SubmitalxlsxPge4of2 Page 4 of 22

Attachment I - LNP COLA Revision 8 Roadmap of Changes

ChangelD#A COLA COLA Chapter Section Basts for Change Change SummaryPart _______

[NP-523 [NP 2 6 06.04.03.02 NPD-NRC-2Si5-0S1 COLA• Part 2, FSAR Chapterf6, will be revised to add new Subsection 6.4.3.2, with a [MA of LNP IJEP 6.4-ito resd:NPD-NRC-20i15-03NPD-NRC-20t15-04 6.4.3.2 Emergency Made

R•evise the first ballet af the first paragraph at DCO Subsection 6.4.3.2 ta read as fallows:

* High-2" patticulute yr aisdie radioactivity in the main control room supply sir duct

R•evise the first sentence of the second paragraph at DCD Subsectinon 6.4.3.2 to read as follows:

The nuclear island nonradioactive ventilation system Is isolated tram the main control roam prescore boundary by automatic closure of the isolation devices located in thenuclear inland nonradioactive ventilation system ductwork if radiation levels ir the main control room supply air duct eoceed the =High-2+ setpoint or if ac power is lost tarmnore than lit minutes.

Continue to revise Subsection 6.4.3.2, with a [MA at [Np COP 6.4-2, to read:

Reviae the fifth paragraph at DCD Subsection 6.4.3.2 to read as follows:

The temperature and humidity in the main control room pressure boondaty following a loss at the nuctear island nonradinactive ventilation system remain within limits forr eliahin human porformance (References 2 and 3) ever a 72-hour period. The temporaturnlrelative humidity values calculated doting the 72 hours following a design basis

accident eqeuate to so effective temperature at6 85

P eFr less (considering operators performing light work, with no credit tor the coaling effect at air velocity, and a relative

humidity of less than 50 percent) to support rtellble human perfonnence constraints (References 2 and 3). Non-ilE MCR beat loads ore des-energized by PMS automaticactions and the 24 hour bantery heat loads ame tenninated or enhausted at 24 hours to maintain the assumed heat soad values in Table 6.4-3, whIch then maintains theancupied zone at the MCR and the zones containing qualifted safety-related equipment within the temperature censtraints at 72-hours post VES actuation. The occupiedzone Is considered Is be the area between the raised floor sod 76f. above the flour which encompasses the roaster operator and senior reactor operator consoles.

LNP-524 LNP 2 6 06.04.034 NPC-NRC-2ht15-014 3OLA Part 2, FSAR Chapter 6, will ho revised to updtate Subsection 6.4.4, withbaLMA of [NPCOEP 6.4-ito mead:

6.4.4 System Safety Evaluation

Revise the third paragraph of DCD Subsection 6.4.4 to read so follows:

I•efer to Item it of Enclsosre 4 of NPD-NRC-2Stft5i04 for the changes to the third paragraphi

LNP-525t LNP 2 6 06.04.04 NPD-NRC-201i5-001 COLA Part 2, PSAR Chapter 6, wilt be revised to update Subsection 6.4.4, with a [MA of [NP DEP .4-t, to add:

NPD-NRC-2iti5-0146.4.4 System Safety Etvaluation

Revise the first bullet of the thirteenth paragraph at DCD Subsection 6.4.4 s weatt aso foltaow:

" High-2" particulate or aiodin radioactivity In MCR air supply duct

.NP-026 [NP 2 6 06.04.04 NdPD-NRC-2oth5t04 COL.APart 2, FSAR Chapter 6, will be revised to update Subsection 6.4.4, with a LMA at [NPDSP 6.4-1, to add:

6•.4.4 System Safety EvaluationRevise the last sentence stflte sixteenth paragraph of DCC Subsection 6,4.4 to read au

follows:

The following cases are evaluated since they involve releases that extend beyond 24 hours after the initation of the event:

Large Break [OCA 4.4 rem T600Steam Line Break

(Pro-evicting iodine spike) 1.2 rem TlED

(Accident-initiated iodine spike) 2.0 remn TEDE

[NP Rn Roadmap Pinal for SshmittaLotsaxaefta2 Page 5 of 22


C'hange IDE COLA COLA Chapter Sect~on Basis for Change Change SammaryPart

LNP-027 LNP 2 6 06.04.05.01 NPD-NRC-2015-003 COLA Part 2, FSAR Chapter 6, will be revised to add new Subsection 6.4.5.1,with a LMA ofLNP DEP 6.4-2, to reed:

6.4.6.1 Preoperoficonal Inspection and Testing

Revise the third porograph of DCD Subsection 6.4.6.1 to rend aso follows:

Temperatures wifthin the MOR where tire operators are located ore voritied by anolysis and/or testing to remain wihim limits for reliable human performance (References 2and 2) for a 72-hour period following a bounding scenario with MCR isolation and non-safety ac powsr ovailable (see Table 6.4-3 for heelt oads assumed in onalysis) and a

station blackout (battery bucked buads only).

LNP-028 LNP 2 6 06.04T/T6.4-202 NPD-NRC-2Olt5-001 COLA Part 2, FSAR ChapterE6, will be revised to add a departure from DOD Table 6.4-2, Main Control Room Habitability Indications and Alarms, as new FEAR Tuble 6.4-

NPD-NRC-2O015-014 202, with a LMA of LNP DEP 6.4-1. This table will also be added to tin list of tables from Chapter 6. This table is contaioed in Item 7 of Enclosure 4 of NPD-NRC-20165-O01

LNP-o29 LNP 2 6 66.04T/T6.4-203 NPD-NRC-26156-002 COLA Part 2, FSAR Section 6.4, will be revised to addsa departure from DOD Table 6.4-2, Loss of AC Power Heat Load Limits, as new FSAR Table 6.4-203, with a LMA of

LNP DEP 6.4-2. This Table shall also be added to the list of tables in Chapter 6. Table 6.4-202 is shown in tire attachrment to Enclosure 4 of NPD-NRC-2016-002.

LNP-174 2 7 d7.02F1P7.2-201 NPD-NRC-2015-026 COLA Part 2, FOAR Section 7.2, will be revised to add a departure from DOD Figure 7.2-1, Functional Diagram: Nuclear Stattup Protection, Sheet 2 of 21,oas new FSARFigure 7.2-201,withuaLMA of LNP DEP 7.2-1. This Figure shall aloo be added to tire list of figares in Chapter 7. Figure 7.2-201 (Sheet 1 of 2) is shown in Enclosure 3of

NPD-NRC-201 6-026LNP-030 LNP 2 7 017.02F/F7.2-201 NPD-NRC-2016-003 COLA Part 2, FSAR Section 7.2, will be revised to add a departure from DOD Figure 7.2-1, Functional Diagram: Containmeot aod Other Protection, Sheet 12 of 21, with a

,MA ofLNP DEPE6.4-2. Finore 7.2-201, sheet 2of 2, is shown in tire attachrmentato Enclosure 4 of NPD-NRC-2015-003.

LNP-095 LNP 2 7 7.03 NJPD-NRC-20156-002 COLA Part 2, FSAR Chapter 7, will be revised to opdate Section 7.2 EBR statement to read:NPD-NRC-2015-014

This section of tire referenced DOD is incorporated by retereoce with the following departores and or supplements.

LNP-175 LNP 2 7 67.02.01.02.14 NPD-NRC-2015-036 Revise the lout twa senteoces of the fourth paragraph of DOD Subsection 7,2.1.2.14 to read:This source renge foux doubting signol mop be manually blocked to permit ptant startup and normal power operation when reactor coolant average temperature Is above theP-n setpoint. It Is automatically reinstated when reactor power is decreased below the P-6 power level daring hshtdown or reactor coolant average temperature decreasesbelow the P-8 setpoint.Add s new hairt paragraph soO DD Subsection 7.2.1.2.14 to read as follows: Toe Fluc Doubling function can aloo be manoally blocked dudngairotdown conditions whenbelow the P-8 reactor coolant average temperature. Whben blocked during shutdown conditions, the OVS demloerulized water system isolation valves are

automatically closed to prevent inadvertent boron dilution.

LNP-021 LNP 2 7 07.02.01.02.17 NPD-NRC-2515-002 COLA Part 2. FOAR Ohapter 7. will be revised to add new Subsection 7.2.1.2.17, with a LMA of LNP DEPE6.4-2, to read:

NPD-NRC-20156-0147.2.1.2.17 Main Cootrol Room Isooation, Air Supply Initiation, end Electrical Load De-energization

Revise the first, second, fifth sod oioth paragraphs of DOD Suboection 7.2.1.2.17 to read as follows:

Signals to infliate isolation of tie main control room, to initiate the air sspply, to open the main control room pressure relief isolation valves and lo de-energize nsn-esserdial

main control room electrical loads are generated from ony of tire following conditions:1. Highr-2 control room air sopply radioactivity level2. Loss of an power sources (low Class 10 battery charger input voitage)3. Manual initiation

Condition 1 is tire occurrence one of two main control roam sir supply radioactivity monitomsdetecting the iodine or part iculate radioactivity level above the H-igh-2 selpoint.

Condition 2 consists of two momentary controls. Manual actuation of either of the two controls wilt result In main control room isolation, air supply iniflation, and electrical

load do- energizotlon.

The functionat logic relating to main control room isolation, sir supply initiation, and electrical load de- onergizotion is illusitrated in Figaro 7.2-1, shoot 13.

LNP-176 LNP 2 7 k7.03T1T7.3-201 NPD-NRO-2015-038 COLA Part 2, FEAR Section 7.2, will be revised to add a deportare from DOD Table 7.3-1, Engineered Safely Features Actuation Signals, Sheets 6 nod 7 sf6g, as nowFEAR Teble 7.2-201, sheets l and 2, with a LMA of LNP DEP 7.3-1. This Table shall also be added to the list of tables in Chapter7,. Table 7.2-201, sheets l and 2, withdeparture 7.3-1, is shown in Encnosure 2 of NPD-NRC-2015-038.

LNP Rn Roadmap Final for Subm~al.xlsx ae6 f2Page 6 of 22


ChangelDf# COLA COLA Chapter Sestion Basis for Change Change SummaryPart __ _

LNP-032 LNP 2 7 07.03T/T7.3-201 NIPD-NRC-201 5-003 COLA Part 2, FSAN Section 7.3, will be revised to add esother departure from DCD Table 7.3-1, Engineered Safety Features Actuatino Signals, Shoot 7 of 9, with a [MA ofLNP DEP 6.4-2. Table 7.3-201 shoot 2 witb dopartsre 6.4-2 is shows in the attachmont to Enclosure 4sof NPD-NRC-20t5-003,

[NP-h33 LNP 2 7 s7.O3T/T7.3-202 IJPD-NRC-201it-003 COLA Part 2, FSAR Sectlos 7.3, will be revised to add a doparture frets DCD Table 7.3-3, System-Level Manual Input to the Engineered Satety Features Actuation System,Shoot 2 sf 2, as sew PSAR Toble 7.3-202, mitb a LMA of LNP COP 6.4-2. This Table shall also be added to the list of tables is Chapter 7. Table 7.3-202 Is shows in the

attachment to Enclosure d ot NPD-NRC-2015-003.

[NP-i177 LNP 2 7 07.03TiT7.3-203 NJPD-NRC-201 5-030 COLA Part 2, FSAR Section 7.3, will be revised to add a departure from DCD Table 7.3-2, [ntedocks for Engineered Safety Features Actuatios System, Sheet 1 of 4, as newPSAR Table 7.3-203, with a [MA of LNP DSP 7.3-1. This Table shall also be added to the list of tables is Chapter 7. Table 7.3-203 is shows as Table 7.3-202 is Enclosure

3sof NPD-NRC-20t15-0 35.

[NP-139 LNP 2 7 07.04 NJPD-NRC-2015-015 COLA Part 2, FOAR Chapter 7, Section 7.4, will be revised with a [MA of [NP DSP 3.2-t, as follows:

7.4 Systems Required fur Safe Shutdown

Revise the fifth paragraph sf DCD Section 7.4 to read as follows:

The long-term safe shutdown conditions are the some as the short-term1 conditions eseept thot the coolsot temperature shall he less than d20°F. This long-term conditionmust be achieved within 36 boors and followingsa non-LOCA event osing the PRHR 1-X as shown is Chapter 19SE. These safe shutdown conditions can be maintained bythe PRHR HX for greater than 14 days based en a non-boonding, conservative analysis that snip credits cusing safety-related equipment. In addition, these safe shutdownconditions con be maintained indefinitely using the ADS and passive injection and recirculotiun as discussed in 7.d.1.1. Also refer to Subsection 6.3.1.1 for additionoldiscussion on safe shutdown requirements.

LNP-162 LNP 2 7 e7.04.0l1.01 baste Revise the sesond sentence of the 6th paragraph of COLA Part 2. PFtARftubsection 7.4.1.11to read as follows: "This presents loss of water inventory from containment andpermits operation of the passive residual heat removal heat exchanger and the in-containment refueling water storage tank tsr greater thav 14 days."

[NP-163 LNP 2 7 07.04.01.01 Errata Revise the last sentence of the 8th paragraph of COLA Part 2, FSAR Subsection 7.4.1.1 to read as follows: "The system provides core decoy heat removal in thisconfiguratlon far greater than 14 days with a limited increase in the containment woter level."

LNP-034 LNP 2 7 07.05T/T7.5-203 NJPD-NRC-2016-003 COLA Part 2, FSAR Section 7.5, will be revised to add a departure from DCD Table 7.5-1, Post-Accident Monitoring System, Sheet 11 of 12,0 Oas nePSAR Table 7.5-203,with a LMA of [NP CEP 6.4-2. This Table shall also be added to the list of tahles in Chapterl7. Table 7.6-203 is shown in the attachment to Enclosure 4 ofNPC-NRC-201 5-003.

LNP-035 [NP 2 7 07.05T/T"7.5-204 NqPD-NRC-2015-003 ,COLA Part 2, FSAR Section 7.5, will be revised to addoa departure from DCD Table 7.5-7, Summary of Type D Variables, Sheet 4 old4, as new FSAR Table 7.5-204, mitb aLMA of LNP DEP 6.4-2. This Tabte shall also be added to the list of tables is Chapter 7, Table 7.5-204 is shown is the attachment to Enclosure 4 of NPD-NRC-2015-003.

LNP-036 [NP 2 9 09.02.06.01.01 NPD-NRC-2015-001 COLA Part 2, PSAR Chopter it, will bo revised to add new Subsection 9.2.6.1.1, with a LMuA of [NP DEP 6.4-1, to read:

NPD-NRC-20t5-ft46.2.6.1.1 Shfety Design Oasis

Revise the first sentence of the finst paragraph of DCD Subsection 9.2.6.1.1 to read as follows:

The asaitory drainage system Isolates the SDS vent penetration in the main control room boundary on High-2 particuleat or iodine concentraftions in the main control room

air supply an on out ended loss of ac power to support operation of the main control room emergency habitability system as described in Section 6.4.

[NP-178 LNP 2 9 ,09.03.06.03.07 NPD-NRC-2015-038 COLA Part 2, FSAR Chapter 9, will be revised to odd new Subsection 9.3.6.3,7, with a LMA of [NP DEP 7.3-1, to read:

9.3.6,3.7 Chemical and Volume Control System Valves

Demineraliced Water System Isolation Valves

R•evise the second sentence of the fitrot paragraph of DCD Subsection 9.3.6.3.7, Demineralized Water" System Isolation Valves, to read as follows:

These valves close on a signal from the protection and safety monitorivg system derived by either a reactor trip signal, a source range flay doubling signal, low onput voltage

0000oss nof power) tomte iE do and uninterruptable power sopply system battary chargers, orea safety injection signal, isolating the demineralized waler source to preventinadvertent boron dilotion events and, daring shutdown conditions, whenever the fgas doubling signal is blocked to prevent inadvartent boron dilution.

[NP R8 Roadmap Final for Submittaloxlsx ae7s2Page 7 of 22


Change lIf# COLA COLA Chapter Section Basis for Change Change SummaryPart _______

LNP-179 LNP 2 9 09.03.06.04.05.01 NPD-NRC-2015-038 COLA Part 2, FSAR Chapter 9. will be rosined to add new Subsection 9.3.6.4.5.1, with a LMA of LNP DEP 7.3-1, to road:

9.3.6.4.5.1 Boron Dilation Events

Add a new last sontenoe to the third paragraph of DCD Sobsectian 9.3.6.4.5.1 an follows:

In addition, when the flax doublinig signal is blocked during shstdown, the demineralized water system isolation valves are cloned to prevent inadvertent boron dilution.

LNP-180 LN4P 2 9 09.93.06.07 NPD-NRC-20t 5-039 COLA Part 2, FSAR Chapter 9, will he revised to add new Subsection 9.3.6.7, winh a LMA of LN4P DEP 7.3-its read:

9.3.6.7 tnstrumentation Requirements

Revise the fourth bullet of the third paragraph of DCD Subsection 9.3.6.7 to read as follows:

Damineralized water system isolation valves- To prevent inadvertent boron dilution, the demineralized water system isolation valves clone on a signal from thepretection and safety monitodng syatem derived from either a reactortrip signal, a source range fanxdoubling tignal, low input voltage (lossoalsopower) to the iF doandaninternuptibie power supply system battery chargers, or a safety Injection aignal providing a sntety-related method of stopping an inadvertent dilution. In addition, when thefanx doublinig logic is blocked dadng shstdown, the valves are closed to prevent inadvertent boron dilution. The main control room and remote shutdown workstation provide

manual control for thene vutoes.

LNP-937 LNP 2 9 09.94.01.91.01 NPD-NRC-2015-001 COLA Part 2, FSAR Chapterg9, will be rovosed to add new Subsection 9.4,i.1.1, with a LMA of LNP DEP 6.4-ito read:

NPD-NRC-2015-0149.4.1.1.1 Safety Design Basis

Revise the second bullet in the first paragraph of DCD Subsection 9.4.1.1.1 to mead as follows:

*Isolates the HVAC penetrations in the main control room boundary on High-2 particulate or iodine concentrations in the main control room supply air or on ectended loss

of ac power to support operation of the main control room emergency habitability system as described in Section 6.4

LNP-038 LNP 2 9 99.94.01.01.02 NPD-NRC-2019-001 COLA Part 2, PSAR Chapterf9, will ho revised to add new Subsection 9.4.1.1.2, with a LMsA of LNP DEP 6.4-ito read:NPD-NRC-2015-903NPD-NRC-2015-914 9.4.1.1.2 Power Generation Design Basis

Main Cnntroi Room/Control Support Area (CSA( fleas

Revise the third bullet in the 9irst paragraph of DCD Subsection 9.4.1.1.2 to read as follwow:

*Isolates the main control moom and/or CSA area tram the normal oatdnor air" intake and provides filtered oatdoor airto pressurize the main control room and CSA areas to

a positive pressure of at least 119 inch wg when a High-i radioactivity concentratinn (gaseous, particulate, or iodine) is detected in the main control room supply air duct

Continue to revine Sushection 9.4.1.1.2, with a LMA of LNIP DEP 6.4-2, to read:

Post-72-llour Denign Basis

Main Control Room

Revise the first paragraph to read as follows:

The specific function of the noclear inland nonradiouctive ventilation system in to maintain the main control room below the Oimits shown in Pigure 3D.5-1 based en operation

at the maximum normal site ambient temperaturm.

LNP-039 LNP 2 9 99.04.01.92.01.01 NIPD-tNRC-2015-t01 COLA Part 2. PSAR Chapter 9, wilt be rovosed to add new Subsection 9.4.1.2.1.1, with a LMA of LNP DEP 6.4-1, to read:

NPD-NRC-2015-0149.4.1.2.1.1 Main Control Room/Control Support Area HVAC Subsystem

Revise the second to last sentenco of the second paragraph of DCD Subseotion 9.4.1.2.1.1 to read an follows:

These machtors initiate operatinn of the nonsafety-milated supplemental air filtration units on High-I radioactivity concentrationa (gaseous, particulate, or iodine) and isolatethe main control room hrow the naclear island nonnradioactive ventilation system on High-2 particslate or iodine radioactivity concentrations.

LNP R8 Roadmap Pinal for Submostalolsoxaao2 Page 8 of 22

Attachment I - LNP COLA Revision 8 Roadmap at Changes

ChangetlDt COLA COLA Chapter SectIon Basts for Change Chaong SeminaryPart

LNP-040 LNP 2 9 09.04.01.02.03.01 NPD-NRC-20159-001 COLA Part 2, PSAR Chapter 9, will be revised to add new Subsoctisn 9.4.1.2.3.1, with a [MA of LNP DSP 6.A-l, to road:

NPD-NRC-20156-003NJPD-NRC-20156-014 9.4.1.2.3.1 Main Cantrol RoonmlCastrol Sapport Area HVAC Sabsystem

R:evise the second and third sentesces of the tirot paragraph of the Abnoarmal Plant Operation section of DCDrSubsection 9.4.1.2.3.1 to rtad as fellows.

The frsttis'High-l"radioactivity based apes radieactivity inssrumentatien (gaseeou, padticalata, or iedise). The second isoHigh-2"radioactivity based open e~ther particulateor indite radioactivity instruments,

R•evise the tirot sentence of the second paragraph of the Ahnortmal Plant Operatian necttles of DOD Suboection 9.4.1.2.3.1 to read an follows:

if "High-i' radioactividy is detected is the main control room supply air dent and the wale control reem/controt support area HVAO subsystem is operable, both supplemental

air fitration unto eautomatically start to preosaurize the main control room and OSA areas te at least 1/h loch wg with respect to the surrounding areas and the ostsideeanvironment using filaered makeup air.

R•eviso the tirot sentence of the third paragraph of the Abnormal Plant Operation section of DOD Subsection 9.4.1.2.3.1 to road as fellows:

;f so power insunavailablo for were than 10 minmates or if"High-2" particulate or iodine radioactivity is detected is the main control room supply air duct, which weould lead toonxceeding GDC 10 operator dose limits, the protection and safety monitoring system astomatically isolates the main control room from the normal main control roomlcontrol

support area HVAO sabsystem by closing the sapply, retain, and toilet exhaust isolation valves.

Continue to revise Subsection 9.4.1 .2.3.1, with a [MA of [NP DSP 6.4-2, to read:

R•evise the eighth paragraph oftthe Abnormal Plant Operation section of DOD Subsectiono9.4.1.2.3.1 to road as follows:

Whnen complete ac power is lost and the eatside air is acceptable radiologically and chemically, MOP habitabilfty is maintained by operating one of the twos MOP ancillary

tans to supply outside air to the MCP. It is expected that outside air will be acceptable within 72 hours following a radiological release. See subsection 6.4.2.2 for details.The outside sir pathway to the ancillary tons is provided through the nonradioactive ventilation system air intake opening located on the roof, the mechanical room at teenre=levation 139-3', and nonrodleactive ventilation system sapply dact. Warm air from the MOP In vented to the annoy bailding throagh stairway S50, into the remote shatdownroom and the cinan accent corridor at elevation 100 '-0. The ancillary fan capacity and air tlow rate maintain the MOP environment below the limits shows in

Pigure 3D.5-1 based on operotian at the washroom normal site ambient temperatsre. The ancillary fans and tlow path ame located within the auxiliary building which in a

Seismic Category I strscturo.

[NP-041 [NP 2 9 uhFlF9

.4-2

Ol NIPD-NRC-2016-001 COLA. Part 2, PSAR Chapter 9will be revised so add new Figare 9.4-201 as feted en Page 12 of ae6 ofSnclosure 4to NPD-NRO-20t5-f01. Pigure 9.4-201 will also be

________ _____________________________________ IPD-NRC-2019-014 rdded to the list of Itinuos from ChapterS9.LNP-led LNP 2 9 09.05.O1TITO9.61-201 Errata I-n FSAR Chapter 9, Table 9.5.1-201. the end of the third sentence oftthe "Remarks," reolace "at least 14 days' with 'greater than 14 days".LNP-t42 LNP 2 11 11.01. NIPD-NRC-2015-027 COLA Part 2, PEAR Chapter 11, wilt be revised to spdate Section 11.1 IBR statement, to read:

11.1 Source Terms

This section of the referenced DOD is incorporated by reference wish the following deoarturoo and/or sapylements.

[NP-043 [NP 2 r1t 11.01TiTi11.1-201 NJPD-NPO-2015-027 COLA Part 2, PEAR Chapter 11, will be revised to add a departare from DOD Table 1 1.1-4, Parameters Coed To Calcalate Secondary Coolant Activity, as new PEAR Table11.1-201 with a [MA of [NP DEP 6.4-1. This table will also be added to the list of tables from Chapter 11. ThIs tabletis contained in Item 21 of Eoctosoroe4 ofNPD-NRC-

_____ 20 15-027.LNP-044 [NP 2 11 11.O1T/T1I.1-202 NJPD-NRC-2015-t27 COLA Part 2, PEAR Chapter 11, will be revised to add adeparture from DCD Table 11.1-5, Desigo Basis Steam Generator Secondary Side [iquid Activity, as new PEAR

Table 11,1-202, with a [MA of [NP DEP 6.4-1. This table will alto be added to the list of tables from Chapter 11, Thin table is contained in Item 22sof Enclosuire 4 of NPD-

NRC-2015-027

LNP-045 LNP 2 11 11.O1T/T11.1-203 NqPD-NRC-20t6-027 COLA& Part 2, PEAR Chapter 11, will be revised to add a departuretfrom DOD Table 11.1-0, Design Basis Steam Generator Secondary Side Steam Activity, as new PEARTable 11.1-203, with a [MA of [NP DEP 6.4-I. This table will also be added to the list of tables from Chapter 11. This table is contained in Item 23 of Enclosure 4 of NPD-

NPC-2019-027LNP-049 LNP 2 11 11.09.01.01 NIPD-NRC-2015-027 COLA Part 2, PEAR Chapter 11, will be revised to add new ESubsection 11.5,1.1, with a [MA of [NP DSP 6.4-ito read:

11.9.1.1 Safety Design Basis

R~evise the third and foorth ballets in the third paragraph of DOD Etbsection 11,9.1.1 to read as follows:

4 * Initiate main control room suipplemental hiltratios is the event of abnormally high particulate, iodine, or gaseous radioactivity in the main control room supply air (High-i)

Initiate main control room ventilation isolation and actuate the main control room emergency habitability aystem in the event of abnormally high particulate or iodineradioactivity in the main control room sapply air (High-2)

[NP Rh Roadmap Pinal for Sabmittalolsoxaeht2 Page 9 of 22

Attachment I - LNP COLA Revisions8 Roadrnap of Changes

Change 1D# COLA COLA Chapter Section Basis for Change Change SummaryPart

LNP-547 LNP 2 11 11.05.02.03.01 NPD-NRC-2015-027 COLA Part 2, FSAR Chapter 11t will be revised to add sew Subsection 11.5 .2.3.1, with a LMA of LNP DEP 6.4-1, to read:

1 1.5.2.3.1 Fluid Process Monitors

R•evise the second to lost sentence of the first paragraph of the Main Control Room Supply Air Duct Radiation Monitors section of DCD Subsection 11.5.2.3.1 to road as

follows:

W/hen predetermnined selpoints are exceeded, the monitors provide signals to initiate the nupplemental air filtration system ensa High-i gaseous, particulate, or iodineconcentration, and to isolate the main control room air intake and eshaust ducts and activate the main reotrol room emergency habitabitlty system on High-2 particulate oriodine concentrations.

LNP-Si96 LNP 2 12 12.02.01.03 NPO-NRC-2515-527 COLA Part 2, FSAR Chapter 12, wiil be revised to add new Subsection 12.2.1.3, with a LMVA of [NP DEP 6.4-fto read:12.02,.01 .03.0112.02.01.03.02 12.2.1.3 Sources for the Core Melt Accident

Revise the last paragraph of DCD Subsection 12.2.1.3 to read as follows:

12.2.1.3.1 Containment

If there is core degradation, core cooling would be proeided by the passive core cooling system which is totally inside the containment such that no high activity sumpsolution woald be recirculated outside the containment. The shielding provided for the containment addresses this post-LOCA coerce term. The coerce strengths as afunction of time are provided in Table 12.2-20 and the integrated source strengths are provided in Table 1 2.2-21.

12.2.1.3.2 Main Control Room HVAC Fillers

During operation of the nuclear island nonradioactive ventilation system (VESI supplemental filtration or the main control moom emergency habitability system 0/ES),Shotrs is the control room HVAC moth to remove particulate and iodine from the air. As radioactivity accumulates within the fiflers, this becomes a potentialsooroe of dose. These source strengths asa function of time are provided in Table 12.2-28 and the integrated source strengths are provided in Table 12.2-25.

LNP-057 LNP 2 12 12.03.02.02.07 NFD-NRC-2015-0t27 COLA Part 2, FSAR Chapter 12. will be revised to add new Subsection 12.3.2.2.7, with a [MA of LNP DEP 8.4-1,to read:

12.3.2.2.7 Control Room Shielding Design

Revise DCD Subsection 12.3.2.2.7 to read as follows:

The design basis loss-of-coolant accident dictates the shielding reqairements for the control room. The rod ejection accident dictates the shielding requirements Sot the maincontrol room emergency habitability 0/ES) fiter in the operator break room. Consideration is given to shielding provided by the shield building structare. Shielding combinedw'ith other engineered safety features is provided to permit access and occpupacy of the control room following a postulated losos-f-coolant accident, so that radiation doses

are limited to five rem whole body from contribsting modes of exposure for the duration of the accidenf, in accordance with General Design Criterion 15.

Shielding of the VES Siltration andl is accomplished by safety-related metal shielding. This shielding Is composed of either tungsten that is 0.25 inches thick or stainless steelshown to provide an equivalent amount of shielding. The length and width of the shielding are designed to match the length and width of the filtration anit being shielded.

LNP-200 [NP 2 12 12.04.01.09.02 Change from Duke Change from Doke Energy Florida, Inc. to Duke Energy Florida, [[C to reflect corporate name changeEnergy Florido, Inc. toDuke Energy Florida,

________L[C

LNP-598 LNP 2 12 12.02T/T12.2-201 NFO-NRC-2015-027 COLA Part 2, PSAR Chapter 12, will be revised to add a departore fmom DCD Subsection 12.2 to add new ODCD Table 12.2-28, Core Melt Acoident Source Strengths FromMTCR HVAC Filters as a Fanction of Timne, Sheets l and 2, as new FSAR Table 12.2-201,.with a LMA of [NP DEP 6.4-1. This Table shall also be added la the list of tables

________ n Chapter 12. Table 12.2-201 is shown on Panes 17usnd 18 of Enclosure 4of NPD-NRC-201 5-027.LNP-099 LNP 2 12 12.02T/T12.2-202 _ NPD-NRC-2015-027 COLA Part 2, FSAR Chapter 12, will be revised to add a departure from DCO Subsection 12.2 to add new DCD Table 12.2-29, Core Mall Accident lntegrated Source

Strengths From MCR 1-IVAC Filters, us a Function of Time, us new FSAR Table 12.2-202,with a [MA of [NP DEP 6.4-1. This Table shall also be adtded to the list of tables________ n Chapter 12. Table 12.2-202 is shown on Page 19 of Enclosure 4 of NPD-NRC-2015-027.

LNP-048 LNP 2 12 12.03FlF12.3-201 NPO-NRC-2015t-027 COLA Part 2, FSAR Chapter 12, will be revised to add adeparture from OCO Figore 13.3-1, Radiation Zones, Normal OporationlShutdown, Nuclear island, Elevation 100 '-0"

&, 107'-2" (Sheet 6sof 16), with a [MA of LNP DEP 6.4-1:

Note number 9 of DCO Figure 12.3-1 will be revised on follows as new PSAR Figure 12.3-201, and Figure 12.3-201 wilt also be added to the list of figures for Chapter 12:

S. Blowdown Piping May Reach Zone Ill [ovals W'ith Concertent Fool Cladding Defects of 0.25% and Steam Oenerator Tube [eakage of 300ogpd.

[NP RB Roadmap Final for Submittaloxlsx ae1 f2Page 10 of 22


C.hange D6 COLA COLA Chapter Section Basis for Change Change SummaryPart

LNP-049 LNP 2 13 13.05.02.02.05 NPD-NRC-2Ol14-032 Revise COLA Part 2, Chapter 13, to insert teat in tire second sentence of Subsection 13.,5.2.2.8, withba LMA of LNP COL 13.5-ito road as follows:

A discussion of security procedures is provided is the Security Piao.

The Special Nuclear Material (SNM) Physical Protection Program describes the 10 CFR Part 70 required protection program In effect for the period of time during which new

fuel as SNM or sos-fast SNM is received asd stored in a controlled access area (CAM), in accordance with the requirements of 10 CFR 73.67.

LNP-050f LNP 2 14 14.52.fl9.01.06 NPD-NRC-20I15-003 COLA Part 2, PSAR Chapter 14, will be revised to add new Subsection 14.2.9.1.6, with a LMA of LNP DEP 6.4-2, to mead:

14.2.9.1.6 Momn Costrol Room Emergency Habitability System Testing

General Test Acceptance Criteria and Methods

Revise paragraph (fl of DCD Subsection 14.2.9.1.6. General Test Acceptance Criteria and Methods section, to read us follows:

f) The ability tomaintain the main control room environment within specified limits for72 hoars(Reference subsection 6.4.2.2)insverified witbhafotesimulating a lssof thenuclear island nonradioactive enstilation system. This testing demonstrates the control momn heutup from S tnS hours with the actual heat loads from the battery poweredequipment and personnel specified for this time period(forfthe MOR (room 12401), there is automotic de- energization of specific non-safety MCR heat loads). The controlroom temperature versus time versus heat load data are used to verity the analysis basis used to assure that the contmol moom conditions remain within specifoed limits farthe 72 hoar time period. Periodic grab samples will be taken of the control room air environment to support analyses to conhirm that speclifed limits woaldt not boececeeded

for 72 hours.

[NP-t8r [NP 2 14 14.02T1T14.3-202 NPD-NRC-2fl15-538 COLA Part 2, FSAR Chapter 14, will be revised to add additional changes to DCD Table 14.2-2, Sheetsa9and 12 of 17, as Table 14.3-202, Sheetsn3and 4 of 4, with a LMA

of [NP DSP 7.3-1, as shown in Enclosure 3St NPD-NRC-2016-03a.

[NP-051 [NP 2 14 14.53T'1T14.3-203 iNPD-NRC-2fl15-fl01 COLA Part 2, ESAR Chapter 14, wilt be revised to add a departare haom DCD Table 14.2-7, Radiological Analysis (Sheet 2of 2), as new PSAR Table 14.2-203, with a LMANPD-NRC-20l15-514 of [NP DSP 6.4-1. This table will also be added to the list of tables haom Chopter 14. This table is contained in item 22 of Enclnsane 4 of NPD-NRC-201 5-014.

_NP-052 LNP 2 14 14.n3T/T14.3-204 NPD-NRC-2fl15-003l COLA Part 2, FSAR Section 14.2, will be revised to add a departure haom DOD Table 14.2-7, Radiological Analysis, Sheet 1 of 3, as new FSAR Table 14.2-204, wits a [MAof [NP DSP 6.4-2. ThIs Table shalt also be added to the list of tables in Chapter 14. Table 14.2-204 is shown in the attachment to Enclosure 4 of NPD-NRC-2015-002.

[NP-tOO [NP 2 15 15.00.11.01 NPD-NRC-2015-014 COLA Part 2, FSAR Chapter 15, will be revised to add new Subsection 15.0.11.1, with a LMA of[NP DEP 6.4-1, to read:

15.0.11.1 FACTRAN Computer Code

Revise the first bullet of DCD Subsection 15.0.11.1 to read as follows:

*A sufficiently large number of radial apace inccements to handle fast transients

LNP-l1Ol [NP 2 15 15.Ofl.1fl.06 NPD-NRC-201it-014 COLA Part 2, PSAR Chapter 15. will be revised to add new Subsection 15.0.11.6, with a LMA of

[NP DEP 6.4-1, to read:

15.0.11.6 ANC Computer Code

Add new DCC Subsection 15.0.11.6 to read as follows:

The ANC computer code is used to salve the two-group neutron difhusion equation in three spatial dimensions. ANC can also solve the three-dimensional kinetics equations

for sin delayed neutron groups.

[NP-1 02 [NP 2 5 5f.O0T/T15.fl-201 NPD-NRC-20l15-0l14 COLA Part 2, PSAR Chapter 15, will be revised to addsa departure tram DCD Table 15.0-2,Summary of Initial Conditions and Computer Codes Used )Sbeet 4 0f15), as new FSAR Tablel15.0-201, with a LMA of LNP DSP 6.4-1. Tbis table will also be added to the list of tables haomChapter 19. Table 15.0-201 in contained in Item 29sof Enclosure 4 of NPD-NRC-2019-fl14.

[NP-053 [NP 2 5 15.01. NPD-NRC-2015-001 COLA Part 2, PSAR Chapter 15, will be revised to update Section 15.1 ISR statement, to read:NPD-NRC-2015-014

15.1 Increase is Heat Removal From the Primury System

This section of the referenced DCD is incorporated by reference with the following departures andlar supplements.

[NP R9 Roadmap Final for Submstal.olso ae11o2Page 11 of 22

Attachment I - LNP COLA RevisionS8 Roadmap of Changes

Change ID# COLA COLA Chapter Section BasIs for Change Change SeminaryPart _______

LNP-054 LNP 2 15 15.01.05.04.01 N]PD-NRC-2015-O01 COLA Part 2, FSAR Chapter15, will be revised to odd now Sebsection 15.1.5.4.1, with a LMA of LNP DEP 6.4-ito read:

N]PD-NRC-2015-01415.1 .5.4.1. Source Term

Revise the fourth paragraph of DOD Subsection 15.1.5.4.1 to road as follows:

The roaster coolant noble gas concentrations ore assumed to So those associated with equilibriurm operating limits for primary coolant noble gas activity. The reactor coolantalkali metal concentrations are based so those associated with the design basis fuel defect level.

Resinse the last paragraph of DOD Sebsection 15.1.5.4.1 to read as follows:

The secondary coolest is assumed to have an iodine source tenm of 0.01 IpCifg dose equivalent 1-131. This is 1 percent of the maximom primary coolant activity at

equilibrium operetiog condditoos. The secondary coolant alkali metal concentration is also asoumed to be I perceot of the primary csocentratioo.

LNP-055 LNP 2 15 15.01.05.04.06 NJPD-NRC-2015-001 COLA Part 2, FSAR Chapter 15, will he revised to add now Sebsection 15.1.5.4.h, wdth a LMA of LNP DSP 6.4-1,to road:

N]PD-NRC-2015-01415.1.5.4.6 Doses

Revise the test of DOD Sebsection 15.1.5.4.6 to moad as tollows:

Using the assumptions from Table 15.1.5-1, the calculated total effective dose equivalent (TEDS) doses for the case with accident-initiated iodine spike are determined lo beloss then 0.6 rem at the site boandary for the limiting 2-hour interval (4.0 to 6.0 hours) and 1.1 rem at the low popalatiso zone outer boundary. These doses are smallfractions of the dose geideline of 25 rem TEDE identihied in 10 CPR Part 50.24. A 'smell fraction' in dehined, consistent with the Standard Review Plan, as being 10 percentor less. The TEDS doses for the case with pro- esisting iodine spike are determined to be less than 0.5 mam at the site boundary for the limiting 2-hoer internal (0 to 2 hears)and 0.4 rem at the low population cone actor boondary. Those doses are within the dose goidetines sf 10 CFR Part 50.34.

At the time the main steam line break occurs, the potential esists forea coincident loss of spent fool pool cooling mitb the result thut the pool could reach boiling and a portionof the radioactive iodine in the spent fuel pool coeld be released la the environment. The loss of spent feel pool canting has been evaluated forea deration sf 30 days. The30-day contribution to the dose at the site boundary and the low population zone boundary is less than 0.01 rem TEDS. Wren this is added to the dose calculated for themain steam line brook, the resulting total dose remalns tens than the voices reported above.

LNP-056 LNP 2 15 ,5.O1TIT15.1-201 NPD-NRC-2015-f01 COLA Part 2, FSAR Ohapter 15, will be revised to add a departure from DOD Table 15.1.5-1, Parameters Used In Evaluating The Radiological Consequences Of A MainNPD-NRO-2015-014 Steam Line Broak, as new FSAR Table 15.t-201, with a LMA of LN4P DSP 6.4-i. This table will also be added to the list of tables from Chapter 15. This table is contained in

______________Item 39Sot Enclosare 4 of NPD-NRC-20t15-014.LNP-103 LNP 2 15 15.03 NJPD-NRC-20t5-614 COLA Part 2,, FSAR Chapter 15, will be revised to epdate Subsectiso 15.2 IBR statement, to read:

15.2 Decrease in Reactor Coolant System Flow Rate

This section of the referenced DOD is incorporated by reference with the following departures and/or supniements.LNP-104 LNP 2 15 15.03.02.03.01 NIPD-NRC-2015-014 COLA Part 2, FSAR4 Chapter 15, will be revised to add new Suboection 15.3.3.3.1, with a LMsA of LNP DEP 6.4-ito read:

16.3.3.3.1 Source Term

Revise the last paragraph of DOD Sobsection 15.2.2.2.1 to read an follows:

_________The initial seconders coolant activity is assemed to be I nercent nf the maximem equilibrium primary coolant activity for iodines and alkali metals.LNP-lfS LNP 2 15 15.O3T~i-15.3-201 NqPD-NRC-2015-0114 COLA Part 2, FSAR Chapter 15, mill be rosined to edit a departure from DOD Table 15.3-3, Parameters Used In Evaluating The Radiological Consequences OfIA Locked

Rotor Accident (Sheet 1lof 2), an num FSAR Table 15.3-261,with a LMA of LNP DSP 6.4-1. Thisotabte will also be added to the list of tables heom Chapter 15. Table 15.3-________201 in contoined in Item 42 of Enclosure 4 of NPD-NRC-2015-014.

LNP-lf06 LNP 2 15 15.04 NpD-N RC-2015-014 COLA Part 2, FSAR Chapter 15, mill be revised to update Subsection 15.4 tBR statement, to mead:

15.4 Reactivity and Power Distribution Anomalies

________ _____________ rhi Sb section of the referenced DOD is incorporated by reference wgfh the following departures and/or supplements.LNP-1107 LNP 2 15 15,04.05.01.01.03 NIPD-NRC-2015-f014 CO•LA Part 2,FSAR Chapter 15,willbe revised toadd new Subsectiosn15.4.8.1.1.3, with aLMAof LNP DEP 64-1Itoread.

15.4.0.1.1.3 Reactor Protection

Raevine DOD Subsection 15.4.0.1.1.3 to road as follows:

Tbhe reactor protection in the event atea rod ejection accident is described is WCAP-15806 P -A (Reference 4). The protection for this accident is provided by the highn=eutron fIuo trip (high and low selling) and the high rate of neutron fanx increase trip. Those protection functions ame descritbed in Section 7.2.

LN4P R8 Roadmap Final for Submittaloxlsoxes12f2 Page 12 of 22


ChangelD#8 COLA COLA Chapter Section Santo for Change Change Summary

_______Part[NP-lO8 [NP 2 15 15.04.05.01.02 NPD-NRC-2015-0i4 COLA Port 2, FSAR Chapter 15, will be rosined to odd new Subsection 15.4.8.1.2, with a [MA of [NP DEP 8.4-ito rend on shown in Itemn 45 of Enclosure 4of NPD-NRC-

2015-014,

[NP-l09 LNP 2 15 15.04.08.02 NIPD-NRC-201 5-014 COLA Part 2, FSAR Chapter 15, will be revised to add new Subsection 15.4.8.2, with a [LMA of [NP DSP 6.4-1, to read as shown in Itoe 48 of Enclosure 4of NPD-NRC-

2015-014.

LNP-ltO [NP 2 15 15.04.08.02.01 NPD-NRC-2015-014 COLA Port 2, FSAR Chapter 15, will be revised to add new Subsection 15.4.8.2.1, with a LMA of[NP DSP 6.4-ito read:

15.4.8.2.1 Calculation of Basic Parameters

Revise DCC Subsection 15.4.5.2.1 to read as follows:

Input parameters for the onalysis are conservatively selected as doochieS to Reference 4.

[NP-Ill [NP 2 15 15.04.08.02.01.01 NlPD-NRC-20t5-014 COLA Part 2, PSAR Chapter 15, will be revised to add new SubsectIon 15.4.8.2.1.1, with a [LMAof LNP DSP 6.4-1, to rend:

15.4.8.2.1.1 Ejected Rod Wortho and Hot Channel Footers

Revise DCD Subsection 15.4.5.2.1.1 to read as follows:

The values for ejected rod worths and hot channel factors are calculated using three dimensional static methods. Standard nuclear design codes are used in the analysis.

The calculation is performed for the maximum allowed hank insertion at a given power level, as determined by the rod insertion limits. Adverse nernon distributions are

considered in the calculation.

Appropriate safety analysis allowances are odded to the ejected rod worth and hot channel factors

to accoant for caiculational uncertainties, including an allowance for nuclear peaking due to

densificatinon as discussed in Reference 4.

LNP-112 [NP 2 15 15.04.08.02.01.02 NPD-NRC-2018-014 COLA Part 2, PSAR Chapter 15, will be revised to add new Subsection 15.4.8.2.1.2, with aoLMA of LNP DSP 6.4-Ito read:

15.A.8.2.i.2 Reactivity Feedback Weighting Fosters

Revise DCD Subsectien 15.4.8.2.1.2 to read as follows:

15.4.8.2.1.2 Not Used

[NP-113 [NP 2 18 15.04.08.02.01.03 NPD-NRC-201 5-0t4 COLA Part 2, PSA.R Chapter 15. will be revised to add new Subsection 15.4.8.2.1.3, with a LMA of [NP DSP 8.4-ito read:

15.4.8.2.1.3 Moderator and Doppler Coefficients

Revise DCD Subsection 15.4.5.2.1.3 to read as fellows:

The critical bores concentration is adjusted in the nuclear code to obtain a moderator temperature coefficient that is conservative compared to actual design condiheons for

the plant consistent with Retenence 4, The fuel temperature feedback in the nestronics code is reduced consistent with Reference 4 requirements.

[NP-i114 [NP 2 15 15.04.08.02.01.04 NPD-NRC-20t5-014 COLA Part 2, FOAR Chapter 15. will be revised to add new Subsection 15.4.8.2.1.4, with aoLMA of [NP DSP 6.4-ito read:

15.4,8.2.1.4 Delayed Neutron Fraction, 1peff

Revise DCD Subsectinon 15.4.5.2.1.4 to read asnfollows:

CalculatIons st the effective delayed neutron fraction (p~eftj typically yield values no less than 0.50 percent at end of cycte. The accident is aencitive to 1peft if the ejected rod

worth is equal to or greater than p3eff. To allow for futuae cycles, a peossmintic astimate of pelt 0.44 percent in used in the analysis.

[NP-it5 [NP 2 15 15.04.08.02.01.05 NPD-NRC-2015-014 COLA Fart 2, FSAR Chapter 15, will be revised to add new Subsection 15.4.8.2.1.5, with aoLMvA of [NP DSP 6.4-1, to read:

15.4.8.2.1.5 Trip ReactivitylInsertion

Revise the frst paragraph of DCD Subsection 18.4.8.2.1.5 to read on follows:

The trip reactivity insertion accounts o thne effect of the ejected rod and one adjacent stuck rod. The trip reactivity Is simulated by dropping a limited set of rods of the

required worth into the core. The start of rod motinon occurs 0.8 second ahter the high neutron 8lno trip setpoint in reached. This delay is assumed to consist of 0.582 second

for the instrument channel to prodace a signal, 0.187 second for the trip breakers to open, and 0.15 second for the cell to release the rods. A carve of trip rod insertion

versus lime is used, which assumes that insertion to the daohpot does not occur until 2.7 seconds otter the start of fall. The chaice of snoh a conservative insertion rate

means that there in overtI second after the trip netpoint is reached before significant shutdiowe reactivity is inserted lots the core. Thin conservatism is important for the hot

fall power accidents.

[NP R8 Roadmap Final for Submettaolux Pge12of2Page 13 of 22

Attachment 1 - [NP COLA Revision S Roadmap of Changes

Change 108 COLA COLA Chapter Section Basin for Change Change Summaiy

Pert _________ _

[NP-lift [NP 2 15 15.54.08.02.01.07 •IPD-NRC-2015-014 COLA Part 2, FSAR Chapter 15, will be revised to add new Subsection 15.4.8.2.1.7, with a [MA of LNP DSP 6.4-ito road:

15.4.8.2.1.7 Resolts

Replace the first three paragraphs of DOD Subsection 15.4.8.2.1.7 wdth the following four paragraphs, to read as follows:

For all cases, the core is preconddtioned by asooming a fuel cycte depletion with control rod insertion that is coneservative relative to expected bateload operation. All casesassume that the mechanical shim and asial offset control RCCAs are inserted to their insertion limits before the coast and aenon is skewed to yield a caonervative initial

asial power shape. The limiting RCCA ejection cases, a typical cycle are summarized following the criteria outlined in sobsection 15.4.8.1.2.

*POMI and high cladding temperature (hot zero power)

The resslting maximum fool average estholpy rise and waxiroom fool overage enthalpy are loss than the criteria given in subsection 15.4.8.1.2.

*High cladding tempertatre (>05% rated thermal power)

The fraction of the core calculated to have a DNBR less than the satety analysis limit is lest than the amount ot failed foal assumed is the dose analysis described

in subsection 15.4.8.2.

*Core coolability

The resolting masiroom foal average enthalpy is less than the criterion giver is sohsection 15.4.8.1.2. Fuel melting is not predicted to occur at the hot spot.

Theme are no tueal failures duelso tha fuel enthalpy daposition, i.e., both feet and cladding enthalpy limits were met. Additionally, the coolahility criteria for peak fuel enthalpyand the fuel melting criteria were met. Therefore, the foal dispersal into the coolant, ai sodden prossure increase from thermal to kinetic eoergy cooversion, gross lattice

distortion, or oevare shook moves are precluded.

The nucleor power and fuel transiunto for the limiting cases are presented in Figures 15.4.8-1 through 15.4.8-3.

The calculated sequence of events for the limoioig cases is presented in Table 15.4 1. Reactor trip occurs early in tha transients, after which the nuclear power excursion is

terminated.

[NP-117 LNP 2 lb nS.d4.08.52.Oi.08 NPD-NRC-2015-0i4 COLA Parr 2, FSAR Chapter i5, will be revised to add new Subsectioe 15.4.8.2.1.8, with a [MA of [NP DSP 6.4-ito road:

15.4.8.2.1.5 Fission Prodoct Release

Revise the ftrst paragraph of DOD Subsection 15t.d.8.2.1,8 to read so follows:

It is assumed that fission products are released from the gaps of all rods entering DNB. In the cases considered, less than 10 perceot of the rods are assumed to enter DNB

based on a detailed three-dimensionul kinetics and hot rod analysis. The maoimum fuel overage aenthalpy rise of rods predicted to enter DNB will be less than 60 cay/g. Fuel

melting does not occur at the hot spot.

[NP-lift [NP 2 iS 15.04.08.02.01.09 NPD-NRC-20i5-5i4 COLA Purl 2, FSAR Chapter 15, will be revised to add naw Suhsection 15.4.8.2.l.9, withr a LMA of [NP DSP 5.4-1. to road:

15.4.8.2.1.8 Peack Reactor Coolant Systam Pressure

Revise DCD Subsection 15.4.8.2.1.8 to read as follows:

Calcularlons of the peak reactor coolant system demonstrate that the peak prossura does not exceed that which woulOl causoe the stress to exceed the Service Level C Limit

als described in the ASME Code, Section III. Therefore, the accidant for this plant does not result lo an excessive pressure dose or further damage to the reactor coolant

syste m.

[NP RB Roadmap Final for Submitalolsoxae14o2 Page 14 of 22

Attachment 1 - [NP COLA Revision a Roadmap of Changes

Change lO# COLA COLA Chapter Section Basis for Change C3hange SummaryPart

LNP-119 LNP 2 15 15.04.08.03 NPD-NRC-2015-014 COLA• Port 2, FEAR Chopter 15, will be revised to arid now Subsection 15.4.8.3, withs [ MA of [NP DEP 6.4-ito read:

15.4.8.3 Radiological Consequences

Revise the first two poragrophs of DOD Subsection 15.4.8.3 to read so follows:

T'he evaluation of tbe radiological consequences efra postulated rod ejection accident assumes that tbe reactor is operating with a limited number of fuel rods containing

c•ladding defects and that leaking steam generator tubes result in a buildup of activity in the uecondary coolant. See subsection 15.4.8.3.1 and Table 15.4-4.

As a result of the accident, 10 percent of the fuel rods are assumed to be damaged (see subsection 15.4.8.2.1.8) such that the activify contained in the fuel cladding gap is

released to the reactor coolant. No font melt is calculated to occur assa result of the rod ejection (see subsection 15.4.8.2.1.8).

LNP-120 LNP 2 15 15t.04.0h.03.01 NPD-NRC-2015-014 COLA Part 2,FSAR Chapter 15.will berevised toadd new Subsection 15.4.8.3.1,with aLMAofL[NP DEP6.4-1, toread:


R•evise DCD Eubsection 15.4.8.3.1 to read as follows:

T'he significant radionuclide releases daevts the rod ejection accident are the iodines, alkali metals, and noble goons. The meacfor coolant iodine source term assumes a pro

evxisting iodino spike. The reactor coolant noble gas concentrations are assumed to be thosen ussoclintd whth equilibrium operating limits for printory coolant noble gasactivity. The initial reactor coolant alkali metal concentratinon are assumed to be those associated with the design fuel defect level. These initial reactor coolant activities areof secondary importance compared to the release of hission products frmm the portion of the core assumed to foil.

Based on NUREG 1465 (Reference 12), the hission product gap fraction is 3 percent of fuel inventory. For this analysis. the gap fractiono are modified following theguidance of Dreft Guide 1188 (Reference 25), which incorporates tho effects of enthalpy rise in the fuel following lbs reactivity insertion, consistentrwith AppendicfB of SRP4t.2, RevisionS3 (Reference 24). Draft Guide 11889 included expanded guidance for determining nuctide gap fractions available for release followingsa rod ejection. Reference28 was issued so a clarithcation to the gop fraction guidance in Dragt Guide 1199. An enthalpy rise of 80 caltgme is sused to calculate the gap fractions (see subsection

15.4.8.2.1.8). Atso, to address thu factithat the failed fuel rods may hone been operating at power levels above tho core average, the source term is increased by the lead

rod radial peaking factor. No fuel roet is calculated to occur as a result of the rod ejection (see subsection 15.4.8.2.1.8).

[NP-121 [NP 2 15 18.04.08.03.05 NqPD-NRC-2015-014 COLA Part 2, FEAR Chtapter 15. will be revised Is add sew Subsection I5.4.8.3.5,with a [LMA of LNP DSP 6.4-1,to read:

15.4.8.3.5 Identification of Conservatisms

R~evise the second bullet of DCD Subsection 15.4.8.3.51to read as follows:

*The reactor coolant activities are based on conservative assumptions (refer to Tabln 15.4-4): whereas, the activities based on thu expected fuel defect level are furless (see Section 11.1).

LNP-122 [NP 2 15 15.04.08.03.08 NPD-NRC-2015-014 COLA Part 2, FEAR Chapter 15, will be revised to add new Subsection 15.4.8.3.6,with a LMfA of [NP DEP 8.4-1, to read:

15.4.8.3.6 Doses

Revise DCD Subsection 15.4.8.3.6 to read as fullows:

Uoing the assamptions from Table 15.4-4, the calculated total effective dose equivalent (TEDE) doses urn determined to be 4.0 remn at the site boandary for the limfting 2-hour interval(Otu2 hours) and 5.5 remn at the low population zone cater boundary. Those doses are weli within the d:ose guideitne of 28 rem TEDE identified in 10 CFR Part

50.34. The phrase "well within" is taken as being 25 percent or less.

[NP-123 [NP 2 15 15.04.10 NqPD-NRC-2015-014 COLA Part 2, FEAR Chapter 15, will be revised to add new Subsection 15.4.10, with a [MA of LNP DEP 6.4-1, is read us shown in Item 60loffEnclosure 4of NPD-NRC-

20158-01 4.LNP-124 [NP 2 15 15.04T/T15.4-201 NIPD-NRC-2015-014 COLA Part 2, FEAR Chapter 15, will be revised to add a departure from DOD Table 15.4-1, Time Sequence of Events for Incidents Which Reselt in Reactivity and Power

Distribution Anomaties (Sheets 2 and 3), as new FEAR Table 15.4-201 (Sheets 1 end 2), with a [MA of [NP DEP 8.4-1. This table will also be added to the list of tables

'-em Chapter 15. Table 15.A-201 is contained in Item 81 of Enclosure 4 of NPD-NRO-2015-014

LNP-125 [NP 2 15 15.04T/T15.4-202 NPD-NRC-2015-014 COLA Part 2, FEAR Chapter 15, will be revised to odd adeparture from DOD Table 15.4-4, Parameters Used In Evaluating the Radiological Consequences of a RodEjection Acctdent (Sheets l and 2), as new PEAR Table 15.4-202 (Sheets 1 and 2), with a LMA of [NP DEP 6.4-1. This table will also be added to the list of tables from

,Chapter 15. Table 15.4-202 is contained in Item 62 of Enclosure 4 of NPD-NRC-2015-014.

[NP-150 [NP 2 15 15.04T/1"15.4-203 NPD-NRC-2015-014 COLA Part 2, FEAR Chapter 15, will be revised to add adeparture from DOD Table 15.4-3, as new FEAR Table 15.4-203, with a [MA of [NP DIEP 5.4-1. This table will also

be added to the list of tables from Chapter 15. Table 15.4-203 indicates thai Table 15.4-3 has been deleted per Item 46 of Enclosure 4 of NPD-NRC-2015-014.

LNP-125 [NP 2 18 15i.04F1F15.4-201 NPD-NRO-20185-14 COLA Part 2 FEAR Chapter 15 will be revised to add a departure from DOD Figure 15.4.8-1, Nuclear Power Transient Versus Time at Beginning of Ute, Fall Power, as newPEAR Figure 15.4-201, Nuclear Power Transient Versus Time for the POMI Rod Ejection Accident, with a [MA of [NP DSP 6.4-1. This figure will also be added to the list of

______________ _____ _____________ _________ figur'emo here Chanter 15, Figure 15.4-201 is contained In Item 63 of Enclosure 4 of NPD-NRC-2015-014.

LNP Re Roadmap Final for Subrottalxlsoxae15st3 Page 15 of 22


ChangelID# COLA COLA Chapter Section Basis for Change Change SummaryPart

LNP-127 LNP 2 15 ,5.O4FIFI5.4-252 NPD-NRC-2015-014 COLA Part 2FSAR Chapter 15will be rosined toadd adeparturef1mmDOD Figure 15.4.6-2, HotSpotFoal,'Average Foot, and Cater Cladding Teroperatara Verona Timeat Beginning of Life, Foil Power, an new FEAR Figaro 15.4-202, Nuclear Power Transient VerasosTime tor the High Cladding Temperature Rod Ejection Accident, with aL.MA of LNP DEP 6.4-1. This figure wilt alsoe be added to the lint of figares from Chapter 15. Figaro 15.4-202 in contained In Item 64 of Enclosure 4 of NPD-NRC-2015-014.

LNP-128l LNP 2 15 15.04FIFI5.4-203 NPD-NRC-2015-014 COLA Part 2 FEAR Chapter lb will be reaised to add adeparture from DOD Figure 15.4.8-2, Nootear Power Trannient Vernon Time at Sod of Life, Zero Power, on newFSAR Figure 15.4-203, Nuclear PowerTransient Versus Time for the Peak Enthalpy and Fool Ceotedine Temperature Rod Ejection Accident, with a LMA of LNP DSP 6.4-1.Thin figare will eans be added la the lint of figures from Chapter 15. Figaro 15.4-203 in contained In Item 65 of Enclosure 4 of NPD-NRC-201 5-014.

[NP-129 LNP 2 15 15.fl4F/F15,4-204 NPD-NRC-20l15-fl14 COLA Part 2 FEAR Chapter lb will be revseod to add a departure from DOD Figure 15.4.5-4, Hot Spot Fuel, Average Fueet and Cater Cladding Temperature Versus Time atEnd at Life, Zero Power, an FEAR "Figure 15.4-204 Not used", with a LMA of LNP DSP 6.4-I. This figure will also be added to the list of tigures from Chapter 15. Figaro15.4-24 in contained in item 66sof Enclosure 4 of NPD-NRC-2015-014.

LNP-130 LNP 2 15 15.06.02.05 NPD-NRC-2fll5-014 COLA Fart 2, FEAR Chapter 15, mitt be rosined to add new Sabsection 15.6.2.6, witha LMA of LNP DSP 6.4-Ito read:

15.6.2.6 Donse

Revise the first paragraph of DCD Subsection 15.6.2.6 to read an follows:

U~sing the unnumptions from Table 1 5.6.2-1, the calculated total effective dose equivalent (TEDS) doses are determined to be 1.2 remn atthe exclusion area boandary and0.6 rem at the low population zone outer boundary. These doses are a small traction of the done guideline sf 25 rem TEDS identified in 100CFR Padt 50.24. The phrase "asmall fraction' in taken as being ten percent or lass.

LNP-121 LNP 2 15 15.05.03.03.01 NqPD-NRC-2015-014 COLA Part 2, FEAR Chapter 15, will be rosined to add new Subsection 15.6.3.3.1, with a LMA of LNP DSP 6.4-ito read:


Ravine the last paragraph of DCD Suhsection 15.6.2.2.1 to read an follows:

The secondary coolant iodine and alkali metal activity is asnumed lo be 1 percent of the reoximum equilibrium primary coolant actisity.

LNP-122 [NP 2 15 15.06.03.02.Of6 NPD-NRC-2015-014 COLA Part 2, FEAR Chapter 10, will be revs~ed 10 add new Subsection 15l.6.3.3.6,wihh a [MA of [NP DSP 6.4-ito read:

15.6f3.3,36 Doses

Raevine the first two paragraphs of DCD Suboection 15.6.3.3.6 to read an follows:

Using the assumptions from Table 15.6.3-3, the calcatated TEDS doses for the case in which the iodine spike in assumed to he infliated by the accident are determined tobe 0.7 rem at the excluoion urea boondary for the limiting 2-hour interval (0-2 hours) and 0.5 rem at the low population zone outer boundary. These doses are a smallfraction at the dose guideline of 25 remn TEDS identified in 10 CFR Part 50.34. A "small fraction" is defined, consistent with the Standard Review Plan, an being ten percentor leon.

Forths cane in which the SGTR is assamed to occur coincident with a pre-esisting iodine spike, the TEDS doses are determined to 6e01.4 rem at the euclusion areaboundary for the limiting 2- hour interval (0 to 2 floors) and 0.7 rem of the low population zone outer boundary. These dsses are within the dose guideline sf 25 rem TEDSidentified In 10 CFR Part 50.34.

[NP-133 [NP 2 15 15.O6T/TIS5.6-201 NIPD-NRC-2015-514 COLA Pert 2. FEAR Chapter 15, will be revised to add a departure trom DCD Table 15.6.2-1, Parameters Used tn Evaluating the Radiological Consequences Of ASmullLine Break Outside Containment, an new FEAR Table 15.6-201. with a [MA of [NP DSP 6.4-I. This table will also be added to the list of tablen from Chapter iS. Table 15.6-

___;_ 01 is contained in Item 70 of Enclosare 4of NPo-NRC-201 5-014.LNP-134 [NP 2 16 r15.06TIT1S.6-202 NIPD-NRC-2015-014 COLA Part 2, FEAR Chapter 15, will be revisedlto add a departure from DCD Table 15.6.3-3, Parameters Used to Evaluating the Radiological Consequences Of ASteam

Generator Tube Rapture, as new FEAR Table 15.6-202, with a [MA of [NP DSP 6.4-1. This table will also be added to the list of tabtes from Chapter 16. Table 156.5-202 in_______ ____________________ ______________ ontainad in Item 71 of Snolonure 4 of NPD-NRC-2015-014.

LNP RS Roadmap Final for Submaittlslsnxae1 f2Page 16 of 22


Change 1D# COLA COLA Chapter Section Basks for Change change SeminaryPart

LNP-182 [NP 2 15 15.06.05.03.02 NPD-NRC-2015-035 COLA port 2, FSAR Chapter 15, will be revised to add a new Subsection 15.6.5.3.2,with a [MA of LNP DSP 6.4-ito rood:

15.6.5.3.2 In-containment Activity Removal Processes

A.dd the following paragraphs at the end of DCD Subsectinon 15.6.5.32.2

Particolates removed from the containment atmosphere to the containment shell ore assumed to be washed off the shell by the flow of water resulting from cundensingsteam (i~e. condensate flow). The particutates may be either washed into the vamp, which is controlled to a pH- ->7 post-accidentor inte the IRWST, which is not pH controlled post-occident. Due to the conditions in the IRWST, a portion of the particulate iodine washed into the IRWST may chemically

.onned to an elemental form and re-evolve, subject to partitioning, as uirbrore. A water-steam partition factor of 10 for elemental iodine is applied. Thin value bounds the

time-dependent partition factors calculated using the NUREGICR-5550 (Rufemence 25) models and the calculated IRWST water temperature and pH as a function of time.

T'he IRWST isou closed tank with weighted louvers, and without boiling, there would be no motive tome for the release of re-evolved gaseous iodine from the IRWST gasspace to the containment. Thus, the assumption of boiling in the IRWST liquid is imposed to force the release of the re-evolved iodineoto the contaiamest atmosphere. Aportion (2%) of the re-evolved elemental iodine is assumed to convert to an organic form upon its release to containment.

[NP-057 [NP 2 15 15.06.05.03.05 NPD-NRC-20t15-001 COLA Part 2, FSAR Chapter 15, will be revised to add new Subsection 15.6.5.2.5, with asLMA of [NP DSP 6.4-f, to read:NPD-NRC-20t 5.014

15.6.5.3.5. Main Cuntrol Room Dose Model

Revise the first sentence of the second paragraph of DOD Subsection 15.6.5.3.5 to read as follows:

Aternativoly, if the normal HVAC is inoperable or, if operable, the supplemental filtration train does not function pmoperly resulting in increasing levels of airborne iodine in

the male coentral room, the emergency habitability system (Section 6.4) would be actuated when H-igh-2 iodine or particulate activity is detected.

Revise the seound sentence of the fourth paragraph of DOD SubsectIon 15.6,5.3.5 to read as toltows:

With the VES in operation, airbomne activity is removed from the main control room atmosphere via the passive recirculation ftitration portion of the VES.

LNP-135 LNP 2 15 15.O6.S5.O3.06.01 NPD-NRC-2015-014 COLA Part 2, FSAR Chapter 15, will be revised to add new Subsection ld.6.5.3.S.l, with a LMA of [NP DEP 6.4-1Ito mead:

15.6.5.3.5.1 Offoite Doses

Revise the first sentence of the second paragraph of DOD Subsection 16.6.5.3.8.1 to read as follows:

The reported occlusion area boundary doses are for the time period of 1.3 to 3.3 hours.

LNP-055 [NP 2 lit 15.06.05.03.05.02 NPD-NRC-2515-001 COLA Part 2, FSAR Chapter 15, will be revised to add new Subsection 15.6.5.3.5,2, with a [MA of LNP DEP 6,4-1,to read:

NPD-NRC-2015-01415.6.5.3,5.2. Doses to Operators in the Main Control Room

Revise the second and third sentence of the first paragraph of DOD Subsection 15.6.it.3.b.2 to read as follows:

Also listed en Table 15.6.5-3 are the doses due to direct uhine from the activity in the adjacent buildings, shine from radioactividy accumulated on the VhS or VBS filters, andsky-shine from the radiation that streams out the top ef the esontainment shield building and is reflected back down by air-scattering. The total of these dose paths is withinthe dose cittada of 5 remn TEDS as defined in GDC 15.

LNP-153 [NP 2 15 15.06.06 NPD-NRC-201 5-035 COLA Part 2, FSAR Chapter 15, will be revised touadd anew Subsection 15e6e, mitb a [MA of [NP DSP 6.4-1,to read:

15.6.6 References

Add the fsllowing to DOD Subsection 16.6.6.

36. Beahm, E. C. at al., NURESICR-595b0, "Iodine Evolution and pH Control," December 1552.

[NP-0it9 [NP 2 15 15.O6TIT15.6-203 NdPD-NRC-201 5-501 COLA Part 2, FSAR Chapter 15, will be invised to odd a departure twin DOD Table 15.6.5-2, Assumptions And Parameters Used In Calculating Radiological ConsequencesNPD-NRC-2015-014 Of A Los-Of- Coolant Accident (Sheets 1 through 3), as new FSAR Table 15.6-203 (sheets 1 through 3), with a LMtA of LNP DSP 6.4-I. Th~is table is contained in Item 76

______ ____________ of nEncluosre 4 of NPD-NRC-2515-014.

LNP R8 Roadway Final for Sobmhtal.clso ae17s2Page 17 of 22

Attachment I - [NP COLA Revision 8 Roadmap of Changes

Change 186 COLA COLA Chapter Section Basis for Change Change SeminaryPart

LNP-OS0 [NP 2 15 i5.06T/TiS.6-204 l.PD-NRC-2015-014 C3OLA Part 2, FSaR Chapter 15, will be revised to add a departure fromr DOD Table 15.6.5-3, Radiological Consequences OI A Loss-Of-Coolant Accident With Core Malt, asnew FEAR Table 15.6-204, with aLMA of LNP DEP 6.4-1, This tabte will also be added to the list of tablesnfrom Chapteri15. This table is contained in Item 76sofEnclosure 4sof NPD-NRC-20t5-0i4.

LNP-125 [NP 2 15 15.07.04.05 NPD-NRC-2015-014 COLA Part 2, FEAR Chapter 15, will be revised to add new Subsection 15.7.4.5, withua LMvA of LNP DISP 6.4-ito read:

15.7.4.5 Ofosite Doses

R•evise the first sentence of the first paragraph of DOD Subsection 15.7.4.0 to read as follows:

Using the assumptions from Table 15.7-i, the calcalated dunes from the initial releases are determined to be 2.5 raw TEDS at the site boundary and 1.2 rem TEDS at the

low population zone outer boundary.

LNP-137 LNP 2 iS 15.07T/T15.7-20i NPD-NRC-2015.014 ;COLA Part 2. FEAR Chapter 15. will be revised to add adeparture from DOD Table i5.7-1, Assumptions Used to Determine Fuel Handling Accideot RadiologicalOsonseqoences, no vow FEAR Table 15.7-201, with a [MA of [NP DEP 6.4-1. This table will also be added to the list of tables from Chapter 15. Table 15.7-201 is contained

in Item 76 of Enclosure 4sof NPD-NRC-2015-014.LNP-06i LNP 2 15 1nA.03.01.02 ,NPD-NRC-2015-001 COLA Fart 2, FEAR Chapter 15, will be revised to add new Subsection 1SA.3.1.2, with a LMA of LNP DSP 6.4-its read:

NPD-N4RC-201 5-014iEA.2.1.2 Secondary Coolant Source Term

Revise the first sentence of the finst paragraph of DOD Eabseotion 15A.3.i1.2 to read as follows:

The secondary coolant source term used in the radiological consequences analyses is conservatively assumed to be 1 percent of the primary coolant equilibniam sourceterm.

[NP-052 [NP 2 15 150. N4PD-NRC-2015-001 CODLA Part 2, FEAR Chapter 15, will be revised to update Subsection inn IBR statement, Is read:NPD-NRC-201 5-014

Appendix 158 Removal of Airborme Activity form the Containment Atmosphere following a LOCA

This section of the referenced DOD is incorporated by reference with the following departares and/or supplements.

[NP-E63 LNP 2 i5 i5B.Oi NPD-NRC-201 5-001 COLA Part 2, FEAR Chapter 15, will be revised to add new Subsection i5B.1,with a LMA ot [NP DSP 5.4-1,to reed:NPD-NRC-2015-014

168.1 Elemental Iodine Removal

Revise the second full paragraph of DOD Subsection 100.1 to read as follows:

The available deposition surface is 251,000gt2. and the containment building nettmreevolume is2.E06l x 05ft5. From these inputs, the elemental iodine removal coefficient is

1.0 hr".[NP-165 LNP 2 10 i9.59T/T19.59-201 Errata In COLA Part 2, FEAR Chapter i9, Table 10.50-202, revise the end of the mirs sentence of the "Insight" associated witb 6.2.2.1.1 & 6.3.7.6 from "at least 72 Soars" to

"greater than 14 days."[NP-i84 LNP 2 10 196.2.7.2 NPD-NRC-2016-038l COLA Part 2, FEAR Chapter 19, will be revised to add new Subsection i0E.2.7.2,wdth a [MA of LNP DSP 7.3-1, Is read:

10E.2.7.2 Design Featares to Address Shutdown Safety

Revise the third paragreph of DOD Eubsectiun 15E.2.7.2 to read as follows:

The safely analysis of boron dilution accidents is provided in Chapter 15 and is discussed in subsection 19E.4.5 of this appendin. Fur dilution events that occur duringuhatdown, the source-range flun-doubling signal cloves the safety-related remotely operated OVE makeup fone isolation valves to terminate the event. In addition, the signalis used to isolate the line from the deminerulized waler system to the makeup pump section by closing the two oufety-related remotely operated valves. The three-way pumpsaction control valve atigns the makeup pumps to lake suction from the bordc acid tank and, therefore, slops the dilution,

[NP-166 [NP 2 10 I9E.4.10.2 Errata In COLA Part 2, FEAR Chapter 10, revise the last two sentences of the 4th paragraph of iOE.4.1S.2 by deleting the nest-to-last sentence and re-wording the last sentenceto read "The WEOTHIC model provides the time-depeodent condensate retain rate which was incorporated into the [OFTRAN computer code described in Subsection1 5.0.i1i.2 to demonstrate that the ROE could be cooled to 420'F within 36 hours."

LNP-064 [NP 2 i0 100.4.10,2 Errata In Port 2, PEAR, Chapter 10, middle of poge 100-2, correct the statement and reviston of the Sobt paragraph (old third paragraph)tn mead astfolluws.

Revise the flvet -etee-.w.nc ft.th.-Slth paregraph (old third poragraph)of DOD Subsection t19E.4.t0.2 Is read as follows:

Summarizing this transient, the loss of normal an power (offsohe and onsile) occurs, followed by the reactor trip. The PRHR HX is actuated an the law steam generetoronarrow range level coincident with low startup feed water flow rate sigoal. Sventaually a safeguards actuation signal is actuated son low cold leg tempeatuare and the CMTsrar actuated.

LNP R8 Roadmap Final for EabmitaLulsoxae16s2 Page 18 of 22

Attachment I - LNP COLA RevisionS8 Roadmap of Changes

Change ID# COLA COLA Chapter Sect~on Basis for Change Change Summary

PartLNP-t40 LNP 2 19 192.4.10.2 NPD-NRC-20t5-51S COLA Part 2, FSAR Chapter 19, Subsection 19E.4.10.2, sloth paragraph, will be revised as follows:

19E.4.10.2 Shutdown Temperature Evaluation

Revioe the ninth paragraph (old fourth paragraph) of DOD Subsection 19E.4.10.2 to read an follows:

Once actuated, at about 2,700 oecoods, the CMTs operate in reciraulation mode, enjecting uotd berated water iota the ROS. la the first part of their operation, dae la theinjection of acid water, the CMTs operate in conjunction with the PRHIR HX to reduce ROE temperature. Due to the primary system cooldown, the PRHR heat transfercapability drops belew the decay heat and the ROE cooldown in essentially drives by the CMT cold injection flew. However, at about 9,000 seconds, the CMT cooling effectdecreases and the ROE ctarts heating up again (Figare t 9.E.4.tO-1). The ROE temperature increases until the PRHR HX can match decay heat. At about 49,700 secondo,the PRHR heat trunster matches decey boat and it continues ts operate to reduce the ROE temperature to below 420°F within 36 hours. As sean from Figare 199.4.10-f,the cold leg temperature in the asop with the PRHR is reduced to 420°F within 92,900 seconds, while the core overage temperature reaches 420°F within 120,900 secondsrnpnrsoxmatein 34 hours).

LNP-167 LNP 2 19 19E.4.12.2 Errata In COLA Part 2, FEAR Chapter 19, renise the eighth paragraph at DOD Subsection 19E.4.10.2, second sentence, to read:"In uddition, the analysis supporting this section shows the PRHR HX is expected to maintain safe shutdown conditions for greater than 14 days."

LNP-l6S LNP 2 19E19.9 Correction In COLA Part 2, FEAR Chapter 19, remove the change to 19E.9 to "not use" Reference 14, so that there will no long]er be adepurture from the DOD references.LNP-141 LNP 2 19 19E.04T/T1OE.4.10-201 NPD-NRC-20159-015 COLA Partg2, FEAR Section 192, Table 19E.4.10-201, Sequence of Events Following aLoss of AC Power Ftowmwith Condensate from the Containment Shell Being

Returned to the IRWET, will be revised to show the modified timings for events resulting from the reamsed condensate retain analysis methodology. Table lflE.4.t9-291 isshown in the antachment to enclosure Eatf the subiect 1ettcr.

LNF-142 LNP 2 19 19E.04F/F19E,4.10-20f NPD-NRO-20f15-019 COLA Part 2, FEAR Section 192, Figure 19E.4.10-201 mill be renised toochow theamodified results bused on the revised condensate return analysis methodology. FigureflE.4.10-201 is shown in the attachment to enclosore 9 of the subiect laster.

LNP-143 LNP 2 19 19E.04F/F19E.4.t0-202 NPD-NRC-20t015-f5 COLA Part2, FEAR Section 192,'Figure 19E.4.10-202wmillbe revisedtoohawthe modified results basedan the resised condensate retaumanalysis methodology. Figure19E5.4.1 fi-202 is shown in the attachment to enclosureS8 of the suhiect laster.

LNP-144 LNP 2 19 i9E.04F/Ff 92.4.1 0-203 rNPD-NRO-2015b-Ol5 COLA Part2, FEAR Section 192, Figure 19E.4.10-203 willbe revised toshow themodified results basedon the revised condensate returnanalysis methodology.Figaro19E.4.10-203 is shown in the attachment to enclosure h ot the subject latter.

LNP-145 LNP 2 19 19E.04F/F19E.4.lt0-204 NPD-NRC-2015-015 COLA Part2,FEAR Section192,'Figure 192.4.10-204will berevised toshowthe modifiedinsults basedon the revised condensate return analysis methodology.Figure19E.,4j.30-24 is shown in the attachment to enclosura 9 of the subiect loster.

Part 4LNP-O65 LNP 4 iS 2.0.4 NPD-NRC-2014-03h Revise Technical Specification ER 3.9.4.7. SURVEILLANCE, to read as follows: Varify by visual inspection that the IRWET gunter and downspout screens arc not restricted

by debris.LNP-009 LNP 4 TEE 2.9.4 NPD-NRC-20t4-038 Revise the Beanes for Technical Specification SR 3.9.4.7, SURVEILLANCE REQUIREMENTS, to read as tollnws:This surveillance requires visual inspection of the IRWET

gonfer and downspout scroens to vedify that the return flow to the IRWET will not ha restdcted by debds. A Frequency of 24 months is adequate, since there are no knownsources of debria with which the gutter or downspout screans could become restricted.

LNP-097 LNP 4 TS$37.4 NPD-NRC-20t5-dt01 COLA Part 4, Technical Specifications Section 3.7.4 will be revised as shown in Item 92 of Enclaosred4to NPD-NRC-2015-014, with u LMA of [NP DEP 6.4-1.

NPD-NRC-2015 -OldLNP-068 LNP 4 TS B 3.4.10 NPD-NRC-20t a-sot COLA Part 4, Technical Specifications Bases Section 3.4.10 Applicable Safety Anatyses, the last sentence of the third paragraph will be revised us shown in Item 93 of

NPD-NRC-2015-0fl4 Enclosure 4 ta NPD-NRC-2015-014.

LNP-069 LNP 4 TS593.7.4 NPD-NRC-2Ol 5-001 COLA Part 4, Technical Spocifications Eases Section 3.7.4 Applicable Safety Anatysos and LCD wilt ha revised as shown in Item 94 of Enclosurea4lo NPD-NRO-20t 5-014.NPD-NRC-2015-014

LNP-070 LNP 4 TEEB 3.7.6 NPD-NRC-20tE5-00f COLA Part 4, Technical Specificatiaon Eases Section 3.7.h will be revised, specifically, the first paragraph of the Background and the first faur paragraphs of the ApplicableNPD-NRC-2015-014 Eafety Analyses will be revised as shown in Item 65 of Enclosure 4 to NPD-NRC-2019-014.

LNP-071 LNP 4 TS 3.3.2 NPD-NRC-2015-003 Revise COLA Part 4, TE 3.3.2, Required Action F.2.2, to read as follows:

P.2.2 Verity main central roam isolation, air supply initiation and electrical loaud de-energination manoal controls are OPERABLE.

LNP-072 LNP 4 TS53.3.2 NPD-NRC-20t 5-003COLA Part 4, TE 3.2.2, Table 3.3.2-1 (page 11 offI 3), Engineered Safeguards Actuation System Instrumentatison, FUNCTION 20, will be revised to read as follows:

20. Main Control Room Isolation., AJr Eupply Initiation, and Electrical Load De-energization

a. Main Control Room Air Supply Radiation - High 2

LNP-073 LNP 4 TE 3.7.6 NPD-NRO-201 5-003 Revise COLA Part 4,7T53.7.6, ACTIONS, to read as shown in Item 29 of Enclosure 4dto NPD-NRC-20l15-003

LNP-074 LNP 4 T753.7.6 NPD-NRO-20t 5-003 Revise COLA Part 4,7T53.7.6, SURVEILLANCE REOUIREMENTS, to mead as shown in Item 29 of Enclsosure 4 to NPD-NRO-20t 5-003

LNP R9 Roadmnap Final for SubmaittaslsnPg 1 f2Page 19 of 22

Attachment 1 - LNP COLA Revision B Roadmap of Changes

ChangelD#U COLA COLA Chapter Section Basis for Change C3hange Seminary_______Pert

LNP-075 LNP 4 TO Bl 3.3,2 NPD-NRC-20156-003 R•evise Pert 4, TO Bases B 3.3.2, ApplIcable Safety Analyses, [COo, and Applicabitliy, FUNCTION 20, to read as follows:

2•0. Main Control Room Isolation, Air Supply Initiation, end Electrical Load Do-onongization

Isolation of the main control roam and initiotion of the yES air supply provides a breathable airosupply for the operators following an oncontrollod release of radiation. Do-e=nergizing non-essential main control room electrical loads maintains the room temperatere writhin habitable limits. This Fonction is reqoired to be OPERABLE inMODESE 1, 2, 3, end 4, and during movement of irradiated fool beoase of the potential fore hfssion prodacit release following a feel hondling accident, or other OBA.

2.0,a, Main Control Room Air Supply Radiation - High 2

Two radiatioo monitors ore provided on the main control room air intake. If eithen monitor ecceeds the High 2 setpoint, control room isolation is actuatod.

I.NP-076 LNP 4 TO B 3.3.2 1 IPD-NRC-20115-003 Revise Pert 4. TO Blaoes B 3.3.2. ACTIONS P.1. P.2.1, P.2.2 and K.1, to wead as shown in Item 21 of Enclosure 4to NPD-NRC-2016-503LNP-077 LNP 4 I'S B 3.7.6 IJPD-NRC-201-5-03 Revise Part 4. TOl BaoesBEl3.7.6,. BACKGROUND, to read as shown in Item 32 of Enclosare dieo NPD-NRC-2015-003LNP-675 [NP 4 TO B 37,7. I IPD-NRC-2015-053 Revise Pert 4, TO Baseo B 3.7.8, LCD, to reed as shown in Item 33sof Enclosure 4 to NPD-NRC-201l-5-03LNP-sn0 [NP 4 TO B3 3.7.B NqPD-NRC-20tb-5-03 R•evioe Part 4, TO Bases B 3.7.B, ACTIONS, to read as shown in Item 34 of Enclosare 4 to NPD-NRC-2015-553LNP-581 [NP 4 TO B 3.7.B NqPD-NRC-201b-0103 Revise Port 4. TO BosesoB 3.7.6. SURVEIL[ANCE REQUIREMONTS, to need aso shown in Item 36 of Enclosure4 toNPD-NRC-2515-663[NP-582 [NP 4 TOO E 3.7.it NPD-NRC-20165-E03 Reavise Part 4, TO Bases B 3.7.0, Figure Bl 3.7.0-2. Compressed Air Storage Tanks Minimom Volume - One Buank of VES Air Tanhs (8 Tanks) Inoperable, as shown in the

attashed ligure in Bnclossure 4 of NPDl-NRC-2015-603

[NP-185 [NP 4 TS 3.3.2 IJPD-NRC-2015-03B R•evise Part 4, TO Table 3.3.2-1, Functions 15 and 18, as shswn in Enclosare 3to this letter.

[NP-lEE [NP 4 TO 3.3.2 NIpD-NRC-2015-038 Revise Part 4, TO Bases B 3.3.2, APPLICABLE SAFETY ANA[YSES, LCOo, and APPLICABILITY, Item 15, Boron Dilution Block, to read as follows, with a LMA of [NPDEP 7.3-1:

The black of boron dilution is accomplished hy closing the OVO maheup line isolation solves or closing the OVO demineralized water system isolation valve. Thio Function isactauted by Source Range Neutron Plan Doabling and Reactor Trip.

[NP-187 [NP 4 TO 3.3.2 •IPD-NRC-2015-036 Revise Part 4, TO Bases Bl 3.3.2, APPLICABLE SAFETY ANALYSES, LCOs, and APP[ICABILITY, Item 15a, Source Ronge Neutron Plan Doubling, sioth sentence, to readas follows, with a LMA of [NP DSP 7.3-1:

On a coincidence of escessively increasing scarce range neatron luon in two of the four divisions, deminerulized water is isolated (CVS demineralized water system isolationvalves closed) from the makeup pumps and reactor coolant makeup is baisoed (CVS mokeap line isolation valves closed) from the reactor coolant system to preclude a

boron dilution event.

[NP-l8h LNP 4 T'l 3.3.2 iJPD-NRC-2015-t038 Revise Pert 4, TO BaeonEB 3.3.2, APPLICABLE SAFETY ANALYSES, LCOs, and APPLICABILITY, Item 15.b, Reactor Trip (Function 18.6), first sentence, to read asfollows, wdfh a LMA of LNP DEP 7.3-I:

Deminerelized Water Makoap is also isolated (CVS demineraliced water system isolatian vatves closed and the boric acid tank aligned to the CVS makeup pumps) by all IhaFonctinon that indiuite a Reactor Trip.

LNP-189 [NP 4 TO 3.3.2 l.IPD-NRC-250-5-36 Revise port 4, TO Boson EB 3.3.2, APPLICABLE SAFETY ANALYSES, [COs, and APPLICABILITY. to add a new Item 18.d, Reactor Coolant Average Temperature, P-B, toread as follows, with a [MA of LNP DEP 7.3-1:

The P-B Interlock is provided to permit a manual block of or to reset amanual block of the automatic Source Range Nectron Plus Doubling actuation of the Boron DilutionBlock (Function 15.a).

The Boron Dilation Block may be manually blocked to permit plant startup and normal power operation when above the P-B rooctor coolant average temperature.

The Boron Diluhion Block is automatically reset upon decrease of the reactor coolant average temperature to below P-B.

,Once the reactor coolant average temperoture is below P-B, the Source Range Neutron Floe Doobling actuation of the Boron Dilation Block Punction may be manually

blocked to prevent inadvertent actuation during refueling oparations and pout-retooling control rod testing.

When the Boron Dilation Block is manoally blocked below P-B during shatdiown conddisnon, the CVO domineralized water system isolation salves ore automatically closed to

prevent inadvertent boron dilotion.

JThe P-B interlock Is required to be OPERABLE in MODES 2, 3, 4 and 5. This Punction is not applicable in MODES 3, 4 and 5, if the demineraliced water makeup flaw path isiisoloted. In MODE B, a dilution event is precluded by the requirement in [CO 3.9.2 Isoclate, lock and secure at least one valve in each unborated waler osorce flow poth.

LNP R0 Roadlmap Final for Submitaxlsxs ae2 f2Page 20 of 22

Attachment I - [NP COLA Revision B Roadmap of Changes

Changel1D# COLA COLA Chapter Section Basis for Change Change SummnaiPart __ _

[NP-lBS L.NP 4 TB 3.3.2 NPD-NRC-2015-C38 Ravine Part 4, TB" Bases B3.3.2, APPLICABLE SAFETY ANALYSES, [COn, and APPLICABILITY, to rn-label old Items I8.d, 1B.e and l1B.f as l1s.e 18,f, and 18.g, with aLMA of LNP DSP 7.3-1.

LNP-1B1 LNP 4TE 3.3.2 NPD-NRC-201 5-038 Ravine Part 4, TO Banns 8 3.3.2. ACTIONS, ,J.1 and J.2, first sentence, to read as follows, with a [MA of [NP DSP 7.3-1,

CnnditionoJ applies to the P-6l, P-B, P-Il, P-12, and P-IS loterlockrs.

Part 5

Part 7LNP-BB3 [NP 7 _____NPD-NRC-2014-03B Ravine LNP DEP 3.2-1 as shown in Itern 3sf Enclosure 7sof the sublect tetter.[NP-tS9 [NP 7 Correction COLA Part 7, Departures and Exemption Requents, Departure [NP DEP 3.2-1 will be revised in the Host of Affected DCDIFSAR Sections, to delete 'and Subsection 198.9".

LNP-193 [NP 7 Change trom Cube Change from Duke Energy Flordda, Inc. to Coke Energy Florida, [[C in two places inSection B, Exemption Requests to reflect corporate name changeBoergy Florida, Inc. toDuke Energy Florida,LLC

LNP-BB4 [NP 7NPD-NRC-2014-536 Revine Exemption Renuest4 as shown in Item4sof Enclosure7nof the subiect etuter.[NP-CB5 [NP 7NPD-NRC-2B15-S61 COLA Part 7, Departures and Exemption Requests, will be revised to add departure 6.4-1 as shown in Item 85sof Enclosure 4 to NPD-NRC-2Blb-014,, on updated by Item 4

NPD-NRC-2B15-B14; as of Enclosure 1 of NPD-NRC-2015-B09 and ltem 2of Enclosure 1sof NPD-NRC-2B1 5-042updated by NPD-NRC-3015-039 and NPD-NRC-

_____2015-042

LNP-SO6 LNP 7 NPD-NRC-2B1i5-B01 COLA Part 7, Departures and Exemption Requests, will he revised to add Exemption Request 5as shown in Item 86B of Enclosured4to NPD-NRC-2015-014. [NOTE: UseNPD-NRC-20I15-014 float tatter for this item]

_____NPD-NRC-201 5-042LNP-0B7 [NP 7 NPD-NRC-2Ol15-003 COLA Part 7, Departures and Coemption Requests, will be revised to add departure 6.4-2 as shown in Enclosure 4 to NPD-NRC-2Oli5-003

LNP-0S8 [NP 7 NPD-NRC-2015-003 COLA Part 7, Departures and Exemption Requests, will be revised to add Exemption RequestS6 as shown in Enclosure 4to NPD-NRC-2015-003

[NP-145 [NP 7 NPD-NRC-2015-015 COLA Part 7, Departures and Exemption Requests. Departure [NP DSP 3.2-1 will be reniaed as shown in item 6 of Enclosure B ts NPD-NRC-201B5-015.

[NP-147 [NP 7 NPD-NRC-2015-C15 COLA Part 7, Departures and Exemption Requests. Exemption Request 4will he revised as shown in Item 7sof Enclosure 6to NPD-NRC-2015-015.

[NP-152 [NP 7 r4PD-NRC-2015-0OB COLA Part 7, Departures and Exemption Requests, Departure [NP DSP 6.2-1 will be revised ax shown in Enclosure3 to NPD-NRC-20tb-OO8.

[NP-153 [NP 7 NPD-NRC-2015-C08 COLA Part 7. Departures and Exemption Requests. Exemption Request 7will be revised as shown in Enclosure 3Sto NPD-NRC-201 5-008.

[NP-i194 [NP 7 NPD-NRC-2015b-03B COLA Part 7, Departures and Exemption Requests, will be revised to add departure 7.3-1, "Source Range Neutron Flux Doubling Block Pernissive"

[NP-i195 [NP 7 NPD-NRC-201 5-038 COLA Part 7, Departures and Exemption Requests, will be revised to add exemption Request B, 'Source Range Neutrnn Flux Doubling Block Permissive"

Part B9 ___ ____ _________ ________

LNP-197 LNP 9 Financial Metdco Change from Duke fChange from Duke Energy Plodda, Inn, to Duke Energy Florida, [[C to ref ect corporate name uhange; update oftfnancial informationInf[Dukeo Energy Florida, c.t

Informationk Energy Florida,In.t

________ ______ LLC and Update of________ _____ _____ _______________________Financial Information

LNP-COB LNP T0 NPD-NRC-201 5-001 COLA Part 10O, License Conditions and ITAAC, Appendix B, will be rovised to add the following departure from the APIBOBO DCD Tier I ITAAC, Section 2.7,1:

I ~NPD-NRC-201 5-014INPD-NRC-20i15-027 Nuclear Island Nonradloactive Ventilatinon System ITAMC

(cuprcees pevius) Revise the sloth and seventh sentences of the Design Description information in DCD Tier 1 Section 2.7.1 with an [MA of [NP DSP 6.4-1 to read as follows:

In addition, the VBS isolates the NVAC penetrations in the main control room boundary on "High-2" particulate nr iodine radioactivity in the main control room supply air duct_______ ____ Ioronna lass of an power for more than 101 minutes. The Banitary Drainage System (0DB) also isotlaes apenetration is the main control room boundary on "High-2"

______ ______ _______________ _______________,articulate or iodine radioactivity in the main control room supply air duct ur onsa loss of an power for more thee 10 minutes.

LNP RB Roadmop Final tor Suhmdtal.xlunPge2xs2 Page 21 of 22

Attachment 1 - LNP COLA Revision 6 Roadmap of Chenges

Change ID# COLA COLA Chapter Section basis for Change Change SommaryPart ___

LNP-090 LNP 10 NIPD-NRC-20l15-003 COLA Padt 10, Appendix B. Inspections, Tosts, Analyses and Acceptance Criterio, APl0SO DOD Tier 1 ITAAC, will be revised to add the following departare.

NIPD-NRC-2015-042Main Control Room Emergency Habitability System ('dES) ITAAC

VdES components are identfied an the preferred, safety-related connection poiot far post-72 hoar sapplemental air. Component nambers for temporary instrument isolation

valves are added to DOD Tier 1 Table 2.2.5-1, with a LMA of LNP DEPB6A-2. The heat load values fnr the Main Control Room Envelope (MORE) shown loion Te Table 2.2.5-4, with a LMA of LNP DSP 8.4-2, are revised to correct for the moat limiting design basis event and to account for actual equipment in the AP1O000 design.

In addition, ahielding is added below the VES fiter In rdor toensure mainnonroe room doses are belowan acceptoblo localdaringV'ES operation. Item 7.e is added la the

Design Dosaription information in DCD Tier 1 Section 2.2.51 ro rad as follows:

a) The usysem provides shielding below the dES filter that ia stu~inint to ensure main control room doses are below an acceptable level daring 'dES operation.

An MOR filter shielding component in added to DOD Tier 1, Table 2.2.5-1 and Table 2.2.5-5, wfth a LMA of LNP DEP 6.4-1.

These changes described above ore made to provide assaranco that ITAAC design commitments will be met. These tables, with the sabject information added, are provided

as Tables 2.2.5-1, 2.2.5-4 sod 2.2.5-5.

Protection and Safety Monitoring Syctem (PMS) ITAAO

New load shed panels are added to automatically do-energize non-essential equipment in the Main Control Room Envelope (MORE) to ensare the MORE is maintainedwithin human performance limits. The electrical load de-energizalion featare is addedt to Tier 1 Tables 2.5.2-3 and 2.5.2-4, with a LMA of LNP DEP 6.4-2.

:These uhsnges are made to provide assurance that ITAAC design commitments will be met. These tables, with the subject information added, are provided easTables 2.5,2-,3 and 2.5.2-4. with a LMA of LNP DEP 6.4-2.

LNP-091 LNP t0 NIPD-NRO-2015-o03 In Port 10, Appendix B, tnspections, Teots, Analyses and Acceptance Criteria, insert the foar sheeto from DOD Tier 1 Tables 2.2.5-1, 2.2.5-4, 2.5.2-2 and 2.5.2-4 containedin the attachment to Esclosuare 4sof NPD-NRO-2015-003 containing the component numbers far temporary instrument isolation valves, revised MORE heat load vaales, sorte=lectrical lood de-energizotion feature associated with LNP DSP 6.4-2 prior la the Table 2.6.9-2 Physical Security ITAAO.

LNP-154 LNP 10 NlPD-NRO-2015l-008 In COLA Part 10, AppendixoB. Inspections, Tools, Analyses and Acceptance Criteria, APl O0S DOD Tier I ITAMC, will be revised to add the following departure.

Containment Hydrogen Control System ITAAOThe ITAAC Acceptance Criteria for the is-containment PXS compartment vents one revised to reflect the current piant configuration. The ITAAO acceptance criteria for

Table 2,3.9-3, Item 2, are clarified to read as uhown in the antached Table 2.2.9-3, with a LMA of LNP DEP 6,2-1.

LNP-201 LNP 15 NqPD-NRO-2015-042 In COLA. Part 10, Appendix B. Inspections, Tools, Analyses and Acceptance Criteria, APtl000 DOD Tier 1 ITjOAC, will be revised to add the departures in Tables 2.2.5-1 and

2.2.5-S detailed in Items S and 6 of Enclosure 1 of NPD-NRO-2015-042, with a LMA af LNP DEP 6.4-1.

Part 11

LNP ES Roadmap Final for Submdtahxlsuxae2 f2Page22of22

DUKE ENERGY°.7I South

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