0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

39
0 , UNITED STATES _. 0 "NUCL"AR REGULATORY COMMISSION Q , ,WASHINGTON, D. C. 20555 April 12, 1982 Docket No. 50-237/249 LS05-82-04-034 Mr. L. DelGeorge Director of Nuclear Licensing VZO Commonwealth Edison Company Post Office Box 767 IV Chicago, Illinois 60690 f Dear Mr. DelGeorge: The Commission has issued the enclosed Amendment No. 69 to Provisional Operating License No. DPR-19 for Dresden Station Unit No. 2 and Amend ment No. 61 to Facility Operating License No. DPR-25 for Dresden Station Unit No. 3. The amendments are in response to your letter of October 21, 1980, as supplemented June 12, 1981 and February 17, 1982. The amendments modify the Technical Specifications to incorporate Limiting Conditions for Operation and Surveillance Requirements related to modifications to the fire protection system required by our March 22, 1978 Safety Evaluation Report (SER). Your submittal was in response to Section 7.0 of the NRC staff's SER which stated that the Technical Specifications would be modified to incorporate limiting conditions for operaticns and surveillance require ments for the approved fire protection modifications. During our review we identified several .changes to your proposed specifications that were necessary. We discussed these changes with your staff and they accepted our changes. We have reviewed your proposed Technical Specification changes and con clude that the revisions are in accordance with our Fire Protection SER and with your Fire Hazards Analysis Report and are consistent with the fire protection requirements contained in the BWR Standard Technical Specifications. These modifications represent an increased effectiveness of your Fire Protection System; On this basis, we find the proposed Technical Specification changes acceptable. We have deteimined that the amendments do not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR §51.5(d)(4), that an environmental impact state ment, or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of these amendments. / ,,

Transcript of 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

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0 , UNITED STATES _.

0 "NUCL"AR REGULATORY COMMISSION Q , ,WASHINGTON, D. C. 20555

April 12, 1982

Docket No. 50-237/249 LS05-82-04-034

Mr. L. DelGeorge Director of Nuclear Licensing VZO Commonwealth Edison Company Post Office Box 767 IV Chicago, Illinois 60690 f

Dear Mr. DelGeorge:

The Commission has issued the enclosed Amendment No. 69 to Provisional Operating License No. DPR-19 for Dresden Station Unit No. 2 and Amendment No. 61 to Facility Operating License No. DPR-25 for Dresden Station Unit No. 3. The amendments are in response to your letter of October 21, 1980, as supplemented June 12, 1981 and February 17, 1982.

The amendments modify the Technical Specifications to incorporate Limiting Conditions for Operation and Surveillance Requirements related to modifications to the fire protection system required by our March 22, 1978 Safety Evaluation Report (SER).

Your submittal was in response to Section 7.0 of the NRC staff's SER

which stated that the Technical Specifications would be modified to incorporate limiting conditions for operaticns and surveillance requirements for the approved fire protection modifications. During our review

we identified several .changes to your proposed specifications that were

necessary. We discussed these changes with your staff and they accepted

our changes.

We have reviewed your proposed Technical Specification changes and conclude that the revisions are in accordance with our Fire Protection SER

and with your Fire Hazards Analysis Report and are consistent with the

fire protection requirements contained in the BWR Standard Technical Specifications. These modifications represent an increased effectiveness of your Fire Protection System; On this basis, we find the proposed Technical Specification changes acceptable.

We have deteimined that the amendments do not authorize a change in

effluent types or total amounts nor an increase in power level and will

not result in any significant environmental impact. Having made this

determination, we have further concluded that the amendments involve an

action which is insignificant from the standpoint of environmental impact

and, pursuant to 10 CFR §51.5(d)(4), that an environmental impact state

ment, or negative declaration and environmental impact appraisal need not

be prepared in connection with the issuance of these amendments.

/ ,,

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- 2 - April 12, 1982

We have concluded, based on the considerations discussed above, that: (1) because the amendments do not involve a significant increase in the probability or consequences of accidents previously considered and do not involve a significant decrease in a safety margin, the amendments do not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by this action, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.

Sincerely,

Original signed by

Dennis [. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing

Enclosures: 1. Amendment

License 2. Amendment

License 3. Notice of

No. 69 to No. DPR-19 Nlo. 61 to No. DPR-25 Issuance

cc w/enclosure: See next page

DISTRIBUTION

NRC PDR Local PDR ORB Reading NSIC ORB #2 Reading DCrutchfield DVassallo HSmith SNorris PO'Connor JHegner OELD OI&E ACRS (10) SEPB LSchneider RDi ggs 1.

TBarnhard (8)

P(I

DL: ORB #5 DL.'~ TWambach GLaina _4ý .,/-/8 2 .w 4/ q//

/SA s

_____________ - w *'L D__DL_____

o -IC B... . #5 DL: ORB #2 DL: ORB #? OELD DL: ORB #2 DL: ORB #5 Dl'UU'¢'" -45'" .." ..... ... ......... .... .. . .... . . .. . . . . .. ... ;. . .. .... ..... .... ...

SURNAME) PO'Connor:ccH t JHeqner SNorris Dassiq ..J~ i2.r .it.J........ .. ... ..... ! .... ... .. 1 f7s a o .. .l r

DATE . . . ... .... ...... .... ....... J.' NRC~~~~~~~...... FOM38.1-0.N..04.FIC A EC R OP S. ..8.-.3..9.0

,V "r. L. Del George

OFFICIAL RECORD COPYNRC FORM 318 (10-80) NRCM 0240 USGPO: 1981--335-960

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- 3 - April 12, 1982Mr. L. DelGeorge

cc Isham, Lincoln & Beale Counselors at Law One First National Plaza, 42nd Floor Chicago, Illinois 60603

Mr. Doug Scott-Plant-Superintendent Dresden Nuclear Power Station Rural Route #1 Morris, Illinois 60450

The Honorable Tom Corcoran United States House of Representatives Washington, D. C. 20515

U.' S. Nuclear Regulatory Commission Resident Inspectors Office Dresden Station RR #1 Morris, Illinois 60450

Mary Jo Murray Assistant Attorney General Environmental. Control Division 188 W. Randolph Street Suite 2315 Chicago, Illinois 60601

Chairman Board of Supervisors of

,Grundy County "Grundy County Courthouse Morris, Illinois 60450

John F. Wolf, Esquire. 3409. Shepherd Street Chevy Chase, Maryland 20015

Dr. Linda W. Little 500 Hermitage Drive Raleigh, North Carolina 27612

Judge Forrest J. Remick The Carriage House - Apartment 205 2201 L Street, N. W. Washington, D. C. 20037

Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704

U. S. Environmental Protection Agency Federal Activities Branch Region V Office ATTN: Regional Radiation Representative 230 South Dearborn Street Chicago, Illinois 60604

James G. Keppler, Regional Administrator Nuclear Regulatory Commission, Region III 799 Roosevelt Street Glen Ellyn, Illinois 60137

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0* REG&

UNITED STATES NUCLI=AR REGULATORY COMMISSION

WASHINGTON, D. C. 20555

COMMONWEALTH EDISON COMPANY

DOCKET NO. 50-237

DRESDEN STATION UNIT NO. 2

AMENDMENT TO PROVISIONAL OPERATING LICENSE

Amendment No.-69 License No. DPR-19

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment (the licensee) dated October 2 June 12, 1981 and February 17, standards and-requirements of as amended (the Act),'and the set forth in 10 CFR Chapter I;

by Commonwealth Edison Company !1, 1980, as supplemented

1981, complies with the the Atomic Energy Act of 1954, Commission's rules and regulations

B. The facility will operate in conformity with the application, the provisins of the Act, and the rules and regulations of the Commission;

C. There is reasonable assurance (i) that the activities authorized

by this amendment can be conducted without endangering the health

and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations;

D. The issuance of this amendment will not be inimical to the common

defense and security or to the health and safety of the public; and

E. The issuance of this amendment is in accordance with 10 CFR Part.

51 of the Commission's regulations and all applicable requirements have been satisfied.

8204260. I

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-2-

2. Accordingly, the license is amended by changes to the Technial Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Provisional Operating License No. DPR-19 is hereby amended to read as follows:

Technical Specifications

The Technical Specifications contained in Appendix A as revised through Amendment No. 69, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Dennis M. Crutchfield -Operating Reactors Branch #5 Division of Licensing

Attachment: Changes to the Technical

Specifications

Date of Issuance: April 12, 1982

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ATTACHMENT TO LICENSE AMENDMENT NO. 69

PROVISIONAL OPERATING LICENSE NC. DPR-19

DOCKET NO. 50-237

Change the Appendix A Technical Specifications by removing the pages described below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.

REMOVE INSERT

156d 156d 156e 156e 156f 156f 156g 156g 156h 156h 156i 156i 156j 156j 156k 156k 1561 1561 156m- 156m 156n* 156n 156o 156o 156p 156p

-- 156q

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S - .................... S... I . ION lDPR-19 4.12 StRMVILUJICK RrqUtI21U 3.12 Li

3.12 IIRE FRIOTECTIOW S 4.12 FIRE rROTECTIOW STSTUi

f

Applies to the fire Protection Systems whenever the equipment or Systems being protected are required to be operable.

Objective:

To ensure that adequate protection against fires Is maintained during all modes.of facility operation.

Specification:

A. Fire Detection Instrumentation

1. As a minimum, the fire detection Instrumentation for each fire detection zone uhoon In Table 3.12-1 shall be operable at all times when equipment in that fire detection zone is required to be operable.

2. With the number of operable fire detection Instruments less than required by Table 3.12-1;

a. Perform an inspection of the affected zone, if accesslble, "within-l hour. Perform additional inspections at least once per hour. except in inaccessible areas.

Aplicability:

nPpplls to the !priodic testbig require-. monte .f the firm protection systems whenever the fire protection systems are required to b e o p e ra b le . % .,- 6. .. ... .

2Uje.tIve:4.

I

etc Spe ationI

A. Fire Detection tnutrvu.N.tkti.o

10 fiach of the fire detection instrv.. mentl given by Table 3.17-1 shall be demonstrated OPERABLE at least Svery 6 months by a channel functional test.

b. Restore the Inoperable instrwteqt(s) to operable status uithin 14 days, or prepare and submit a report too" the Commission pursuant to Specification 6.6.1.2 wuthin the next 156d 30 days outlining the cause of the malfunction and the plans for restoring the instrument(s) to ophrable stntus.

C. Ile provi.sonn of Speclfication 3.0.A are tint applicable.

Amendment No. (2, 69

PTo vertfy operability of the fire protection Systesm.

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]H I T I M e i r n u n r it 1 "n u e t pr v w . , , . ,e" J. 12 L•

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DPR~-193.1Z LIMITING CONDITIONS FOR OPERATION

'4.12 StM�VElLLANCi: REQUIREIIUtITS0. Fire Suppression Water System

1. The Fire Suppression Water System shall be operable at all times with:

a. A flow path capable or taking suction from the 213 Intake Canal for Unit 2/3 Fire Pump.

b. A flow path capable of taking suction from the Unit 1 Intake Canal for Unit 1 f Ire punp.

c. The lhnit 2/3 fire pump (2000 GM) with Itf discharge aligned to the fire suppression header (from Unit 2/3 Intake Structure).

d. The Unit I fire pump (2000 GPM) with Its discharge aligned to the fire suppression header (from Unit 1 Intake Struc bire).

e. Automatic Initiation logic for each fire punp.

f. Fire suppression header piping with sectional control valves to:

1) The yard loop. 2.) The front valve ahead of the

water flow alarm device on each sprinkler or water spray system.

3) The standpipe system.

2. With an Inoperable fire pump or nssociated water supply, restore Die Inoperable equipment to operable status within 7 days, or prepare and submit a report to the Commission pursuant to Specification.6.6.11.2 within the next 30 days outlining the plans and Procedures to be used to provide for the loss of redundancy in this system.

• ?

B. Fire Suppression Water System I ' The Fire Suppresslion Rate

demons tra ted operable'...,... ..

a. At least once per 31- days by verifying valve" -positions.

b. At least once per 12 months by cycling each testable valve In the flow path. through one complete cycle. c. At least once per yebir by perfonmance of a system flush. d. At least once per operating cycle:

' I j

I

1) By perfouminq a system functional test which includes simulated automatic actuation of the system throughout its operating sequence and verifying that

} each automatic valve in the flow path actuates to Its correct position.

2) By verifying that the Unit 2/3 fire pump develops at least 2000 gpm at a system head of 238 feet.

3) By verifying that the Unit I fire pump starts and develops at least 2000 gpm at a system head of 238 ft.

4) Cycling each valve in the flow path ( that is not testable during plant. operation through at least one complete cycle of full travel.

e. At least once per 3 years by performing. flow tests of the system-in accordance with the "Test of Water Supplies" Chapter in the NFPA Fire. Protection Handbook.''

4

1 � 6eAmendment. No,. 36, 69

.4.12 SURVEILLANCE REI•JIREtIENTS

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DPR-]9

3.12 LItIlTIN4G CONDITIONS FOR OPERATION

3. With no Fire Suppression Water System operable, within 24 hours;

a. Estphblsh a backup Fire Suppression Water System.

b. Notify the Commission pursuant to Specification 6.6.0.1 outlininq the actions taken and the plans and. schedule for restoring the system to operable status.

4. If the requirements of 3.12.6.3.a cannot be met, an orderly shutdown shall be initiated, and the reactor shall be In cold shutdown condition within 24 hours.

4.12 SURVEILLANCE REQIIIR14ENTS

' '

Amendment No. 3fG

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3 .1 2 LINITIIIG CONDITIONS FOR OPERATION

C. Sprinkler Systems

1. The sprinkler systems given In Table 3.12-2 shall be operable at all times when equipment

in the area that is sprinkler protected is

required to be operable.

2. With a sprinkler system inoperable, establish

fire inspections with backup fire suppression equipmennt within 1 hour.

a. in the 'Unit 2/3 turbine mezzanine 538'

elevation area or Unit 2 hydrogen seal oil

area, a continuous fire watch is to be established.

b. In all other-areas given in Table 3.12-2 perform inspection hourly.

3. Restore the system to operable status within 14 days, or prepare and submit a report to the Co.•nission pursuant to Specification 6.6.B.2 within the next 30 days outlining the cause of Inoperability, action taken and the plans for restoring the system to operable status.

4. The provlnitns of Specificntion 3.O.A are not applicable,

.. COt System

1. The CO2 Storage Tank shall have a minimum standby level of SO percent and a minimum pressure of 250 psig.

2. The CO2 System given in Table 3.12-3 shall be operable.

4.1

C

2' SURVEILLANCE REQUIREM ENTS

Inkler System

At least once per 31 days by verifying that

each valve, manual, power-operated, -or-- .* -.

automatic, in the flow path is in its J

correct position. .

2. At least once per 12 months by cycling each testable valve in the flow path through

at least one complete cycle of full travel. C"h '

3. At least once per operating cycle:

a. A system functional test shall be performed which includes simulated automatic

actuation of the system and verifying

that the automatic valves in the flow

path actuate to their correct positions.

b. The sprinkler headers shall be inspected to verify their integrity.

c. Each nozzle's spray area shall be inspected to verify no blockage of the spray pattern.

4. At least every other operating cycle, a flow

test will be performed to verify that each.

open head spray nozzle is unobstructed.

D. CO2 System

1. -t least once per 7 days the CO2 Storage

Tank level and pressure will be verified.

2. At least Once per 31 days by. verifying tha.t.

" each valve, manual, power-operated, or auto

matic, in tne liow path is in the correct position. ' . .

3. At least once per operating cycle, the system valves and associated dampers will be verified

to actuate automatically and manually. A brief -- --... -hnal ho mnAA to uprifv flow from

-I' -�

DPR-19DPR-lq

16

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3.12 ...... R.A.... Ti Irr

6.The provslol'ne of Specification 3.O.A are not applicable*

E. Fire Hose Stations

1. The Fire Hose Stations given in Table 3.12-4 shall be operable at all times when the equipment in the area Is required to be operable.

2. With a hose stotion Inoperable route an additional equivalent capacity hose to the unprotected area from an operable hose station within I hour.

3. When a hose station becomes Inoperable, restore to operable status within 14 days or report to the CuntissIon pursuant to specification 6.6.8.2 within the next 30 days outlining the cause of Inoperability and plans for restorinq the hose station to operability.

4. The provls'on9 of tSpecificntion 3.o.A ore not applicables'

I �3. Specifications 3.12.0.1 and 3.12.0.2 above apply when the equipment In the areas given In Table 3.12-3 Is required to be operable.

4. With a COz System inoperable, establish fire Inspection with backup, fire suppression equipment In unprotected areas within I hour, and perform inspection at least hourly.

5. Restore the system to operable status within 14 days, or prepare and subnit a report to the Commission pursuant to Specification 6.6.8.2 within the next 30 days outlining the cause of Inoperability, action taken and the plans and schedule for restoring the system to operable status.

Fire Hose Stations

1. At least once per 31 days, a visual inspection of each fire hose station shall he made to assure all equipment is available at the. station.

2. At least once per operating cycle, the hose will be renoved for Inspection and repacked. Degraded gaskets In the couplings will be replaced.

3. At least once per 3 years, each hose station valve will be partially opened to verify valve operability and no blockage.

4. At least once per 3 years a hydrostatic test will bee conducted on -each. hose at a pressure at least 50 psig above line pressure at that station.

Amendment No.

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4.12 SURYFItEANCE 14116iflio 11

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1.12 L IMIT IING, 11111TIONS- FOR OPERATYIONl

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156h

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'A 1'

r)pg-I 93.12 LIMIING CONDUIIOINS FUR OPERATION

F. Penetration Fire Barriers

1. All penetration fire barriers (including fire doors and fire dampers) protecting safety related areas shall be intact, except as stated in specification 3.12.F.2 below.

2. With one or more of the required penetration fire barriers not Intact, establish a continuous fire watch on at least one side of the affected penetration within 1 hour when the area on either side of the affected

netration contoins equipment required to operable.

3. •he provisions of Speci1ication 3.O.A are not applicables

4. Restore the non-functional fire barrier penetrations to operable status within 7 days or prepare and submit a report to the Commission pursuant to Specification 6.6.B.2. within the next 30 days outlining the cause of inoperability3 action taken and the plans and schedule for restoring the penetration fire barriers to operable status.

0. See 3.12.B.

1561

4.12 SUHV[ILLRNLL RLJUIR ELfNI

F. Penetration Fire Barriers

1. Each of the required penetration fire barriers shall be verified to be Intact by a visual

-Inspection:

a.. At least once per 18 months, and

b. Prior to declaring a penetration fire ( barrier Intact follpwinq repairs or

.maintenance.

G. Fire Pump Diesel Engine

1. The fire pump diesel engine shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying:

1) The fuel storage day tank contains at least 150 gallons of fuel, and

2) The diesel starts for ambient conditions and operates for at least 3t minutes.

I 3) The fuel transfer pump starts and transfers fuel from the storage tank to the day tank.

b. At least once per 92 days a sample of diesel fuel shall be checked for viscosity, water and sediment. The" procedure used shall be consistent with existing station procedures used to check diesel fuel in the main storage tanks.

Amendment No. -6 ,2

ý,2

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3.12 LltlIIMIH CUODITIONS FOR OPERATIOfiwP-l')

4.12 SURVEIL

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C. At

2)

LAKUE REQUIRIMENTS least, once per 10 months', by:

Subjecting the diesel to an Inspec tion in accordance with procedures prepared In conjunction with Its. manufacturer's reconwnendatIons for

.- the class of service, and

Verifying the diesel starts from**u l!~ 5Pl -- WIIUT I L lU ll) U II L ioth a U t ,

start signal and operates for ;h 30minutes while loaded with the "-fi re pump.

2. The fire pump diesel engine batteries shail. be demonstrated operable:

a. At least once per 7 days by verifying that: 1) The electroylyte level of each

battery Is above the plates, and

2) The overall battery voltage Is24 volts.

b. At least once per 92 days by verifying that the specific gravity is appropriate for continued service of the Iattery.

c. At least once per 18 months ,by verifyinj that:

156 j

1) The batteries and battery racks show no visual Indication of physical damage or abnorme. .deterioration, and

2) The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anticorrosion material.

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Amendment No. _3ý, )c

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A. in..

r)PR1-19

3.12 Ll.4ITTIN OONDITIO.S FM OPERATIlN 4.12 SURVFJIAWR. RnUJTRI•JWMV

H. Ilalon System . . . .

1. The following Hlalon system shall be OPIMARL. with the storage tanks havingqat least 951 of fullcharqe weight and 90% of full charge pressure.

a. Auxiliary Rlectrical "Iurmient Room

2.' With one or more of the above required Ilalon systems inoperable, establish a continuous fire watch with backup fire suppiression equipment for the unprotected areai(s) iwithin" 1 hIurl restore the system to OPMFL/IE •status within 14 days or, prepare and submit a report to the Commission pursuant to Specification. 6.6.E within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPFlEABUL status.

II. Halon Systepm .....

1. At least Once per 31 days, verify.that each,. valve in'the flow path, is in the correct position.

2. At least once per 6 months, the ilalon storage tank weight and pressure will be verified.

3. At least once per operating cycle, the system, including associated ventilation dampers, will be verified to actuate manually and automatically. A flow test shall be made through headers and nozzles to assure no blockage.

Amendment No. 9

*1

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Bases: Fire Protection Systems

tt Operability of the fire detection Instrunentation ensures that adequate warning capability Is

available for the prompt detection of fires. This capahility is required In order to detect

and locate fires In their early stages. Prompt

detection of fires will reduce the potential

for damage to safety related equipment. and is

an integral element In the overall facility fire

protection program. In the event that a portion

of the fire detection Instrumentation Is Inoperable,

j the establishment of frequent fire Inspections in the

affected areas Is required to provide detection

capability until the Inoperable Instrumentation

is returned to service.

The operability of the fire suppression systems

ensures that adequate fire suppression capability

is available to confine and extinguish fires

occurring in any portion of the facility where

safety related equipment Is located. The fire

suppression system consists of the water system,

sprinklers, CO, systems, tialon system, and tire hoqw stations, and is adequate to minimize potential

damage to safety related equi-went, and is a major element In the facility fire protection proqram.

In the event that portions of the fire suppression

system are Inoperable, alternate backup fire

fighting equipment Is required to be made available

in the affected areas until the affected equipment

can be restored to service.

A fire suppression water system shall consist of

a water source, pumps, and distribution piping

with associated valves. Such valves shall include sectional control valves, and the first valve ahead

of the water flow alarm device on each sprinkler or

hose standpipe riser.

In the event that the fire suppression water system becomes Inoperable, Immediate corrective measures must be taken since this system provides the major fire suppression capability

of the plant. The requirement for a 24-hour report of the Cum)tssion.provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.

The functional Integrity of the penetration fire barriers ensures that fires will be

:confined or adequately retarded fro spreading

to adjacent portions.of the facility. This design feature minimizes the possibility of a single fire rapidly Involving several areas of the facility prior to detection bnd extinguishment. The penetration fire hN.rrlers are a passive element In the facility fire protection program and are subject to periodic Inspections.

Wuring periods of time when the barriers are not functional, a fire watch Is required to be maintained In the vicinity of thb affected barrier until the barrier Is restored to

,functional status.

1561

Aý.^nrmn+n Nn

442

Onp"-19

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IJ"Hl- j9.

TABLE 3.12-1

FIRE DETECTION INSTRU14ENTS

INSTRUIlENT LOCATION

1. tla In Control Room 34 Smoke. Detectors

2. Untit 213 Aux. Elect. Equip. Room 12 Smoke Detectors

3. Unit 2/3 Computer Room 8 Smoke Detectors

4. Unit 2 Battery Room 10 Smoke Detectors

S. Unit 2 Turb Bldg. 480Y MCC 17 Smoke Detectors

6. Unit 2 Turb Bldg. 4KV Swttchgear 10 Smoke Detectors

7. Unit 2/3 Diesel Generator Area 4 Ileat Detectors

8. Unit 2 Diesel Generator Area 3 Heat Detectors

9. Unit 2 Rx Bldg. 480v MCC (570') 3 Smoke Detectors

10. Unit 2 Rx Bldg. 480v MCC (517') 7 Smoke Detectors

)1. Unit 2 Rx Bldg. 4KV Swttchgear 4 Smoke Detectors

12. Unit 2 Standby Liquid Control 1 Smpke Detector

MINIII.H INSTRtIMEITIS OPERABLE

24

"8

7

12

7

3

2

2

3

Area

156 m

, Amendpient., No. 36<,

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niP"-19 TABLE 3.12-2

SPRINKLER SYSTEMS

I.

2.

3.

4. 5.

6.

7.

a.' 9.

10.

11.

12.

. . .. . . .I

unit 2 Emergency Diesel Oil Day Tank

Unit 2/3 Turbine Mezzanine 538' Elevation

thiIt .2/3 Emergency Diesel Ol Day Tank

Ihit 2 Reactor Feed Pump Area

(hUit 2 Hydroqen Seal Oil Area'

Unilt 2 Condensate Feed Puwp Area

hilt 2 HPCI Area

Uhit 2 Turbine Building East Mezzanine Area Unit 2 EHC Area

2/3 Fire Pump Area

Unit 2 Trackway

Unit 2 Instrument Air Compressor Area IIAmendment No._,a, 639

K

(

156n

Page 18: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

I,-'

flpR-19 TABL.E 3.12-3

COZ SYSTIMS

1.Unit I Emergency Dismal Canarstor

*2. Unit 21) Eauergency, llaesl Gjenerator

MOO

Amendment No. 3K', G 9

Page 19: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

NO.

F21

F54

E55

F56

FS1

F58

F59

F60

F61

F61IA

LOCATION

Cribhouse517-ft., by Bus 20

Reactor Building 589-ft., North East Wall at Elevator

Reactor Building 589-ft., South of Standby Liquid Tank

Reactor Building 589-ft., South East of Isolation Condenser

Reactor Building 589-ft., South West Stairway

Reactor Building 570-ft., North Wall at Elevator

Reactor Building 570-ft., Across from Cleanup Demineralizer P.C. Tank

Reactor Buildihg 570-ft., C.R.D. Repair Room

Reactor Building 570-ft., West Wall Hear RBCCW Tank

Reactor Building 570-ft,, by South Stairs

1Pw-19 TABLE 3.12-4

FIRE HOSE STATIONS

NO.

F62

F63

F65

F66

P67

F68

F73

F74

F8OA

F80B

I 156p

Amendment No. p u 9

LOCATION

Reactor Building 545-ft., North Wall Hear Elevator

Reactor Building.545-ft.5 South Wail at RBCCW Heat Exchanger

Reactor building

545-ft., South West Stairway

Reactor Building 545-ft., North of bus 23

Reactor Building

517-ft., at Elevator

Reactor building 517-ft., South Eant Wall

Reactor Bvilding .17-ft., South Enat Stairway

Reactor Building 476-ft.. 20 LPCI Pump

Reactor Building 476-ft., 2C Core Sproy Pump

Turbine Building 549-ft., Iforth WallJUnit 2 Battery Room

Turbine Building 549-ft., Outnide of, Passenger Elevator

Im

Page 20: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

DI'Il-19 TAB1LE 3.12-4

FIRE NOSE STATIONS

HO. LOCATION NO. LOCATION

F82 Turbine Building ! 538-ft,, Stator Cooling Pump

F62A Turbine Building 538-ft., East of Trackvay Equipment Hatch

F82B Turbine Building 334-ft., Across from Svitchgear 23 and 24

F84 Turbine Building 334-ft., East of Itandby Gas System

F85 Turbine Building 517-ft., Near U-2 Transformer Valve

F86 Turbine Building 517-ft., at U-2 Emergency Diesel

F87 Turbine Building 517-ft., Across from 20 RFP West Walk

F88 Turbine Building 495-ft., at C.R.D. Pumps

F89 Turbine Building 469-ft., Across from 2D

, Condensate Pump

156q

Amendment No.A, ci9

Page 21: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

, R EREG&

44, 0

A lu

UNITED STATES NUC&AR REGULATORY COMMISSION

WASHINGTON, D. C. 20555

COMMONWEALTH EDISON COMPANY

DOCKET NO. 50-249

DRESDEN STATION UNIT NO. 3

AMENDMENT TO FACILITY OPERATING LICENSE

Amendment No. 61 License No. DPR-25

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Commonwealth Edison Company (the licensee) dated October 22, 1980, as supplemented June 12, 1981: and Feb rary 17, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;

B. The facility will operate in conformity with the application, the provisions .of the Act, and the rules and regulations of the Commission;

C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations;

D. The issuance of this amendment will not be inimical to the common defense and security or-to the health and safety of the public; and

E. The issuance of this arendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

Page 22: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

-2-

2. Accordingly, the license is Specifications as indicated amendment and Paragraph 3.B No. DPR- 25is hereby amended

amended by changes to the Technial in the attachment to this license of Facility Operating License to read as follows:

Technical Specifications

The Technical Specifications contained in Appendix A as revised through Amendment No. 61 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is

Attachment: Changes to the Technical

Specifications

effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

bominici B. Vassallo Operating Reactors Branch #2 Division of Licensing

Date of Issuance: April 12, 1982

Page 23: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

ATTACHMENT TO LICENSE AMENDMENT NO. 61

FACIITY OPERATING LICENSE NO. DPR-25

DOCKET NO. 50-249

Change the Appendix A Technical Specifications by removing the pages described below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating' the area of change.

REMOVE INSERT

156d 156d 156e 156e 156f 156f 156g 156g 156h 156h 156i 156i 156j 156j 156k - 156k 1561 1561 156m 156m 156n 156n 156o 156o 156p 156p

-- 156q

Page 24: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

3.12..........Cowrntmnu a- 4M

3.12 FIRE PunlrTrI SySvmr

•Pplicahutltvg~

Applies to the fire protection systems "Whenever the equipment or systems be!in protected are required to be operable.

Objective:

To ensure that adequate protection against fire* is maintalned during all modes of: facility operation.

Srpcification:

A. Fire Detection Instrumentation

1. As a minimum, the fire detection instrumentation for each fire detection.zone shown in Table 3.12-1 shall be operable at all times when equipment in that fire detection zone is required to be operable.

2. With the number of operable fire detection Instruments less than required by Table 3.12-1;

a. Perform an inspection of the affected zone, if accessible, within 1 hour. Perform additional Inspections at least once per hour, except it inaccessible areas.

b. Restore the inoperable instruient(s) to operable status within 14 days, or prepare-and submit n report to the Commission pursuant to Specificastion 6.6nB.2 within the next 156 30 days outlining the cauge of the malfunction and the plans for restoring the Instrument(s) to opprable status.

Co- Vie provalon,; of spreircaticon 3.0.A are not applicable#

,DPR-25 .12 stmvzMLtAICg RqItVlYMNT~S i 4.12 LaC 4. 12 FIRE, rPýTECTMM, TSU

OPp"hs to the Periodic tetOa ,, requireMenr of the fire Protection systems whenever the iire protection systems are required to be operable .. ... .. ..

"be o-erabl.

To verity operability of the fire "I Protection system..

A. Firs Detection

. Each of the fire detection instru. sent. Riven by Table 3.17-1 ahall be demonstrated OPERABLE at leant every 6 months by a channel functional test.

Amendment No. 51,

�6

.

(

I

;d

. LIMITING MUNDITtoll-I IMM ,,., . .

0

Page 25: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

3.12 LINPR.

3.12 LItITiflG CONDITION• sni, nnrna.~'.., -

ni .fun, 4.12 SURVEILLANCF REQUIREfIIEHTS . Fire uppres erSupPr n @, te 1. The FSu <, -ippresslon Hater Systen

1. The Fire Suppression Rater-System shall be shall _,' nerable at all times with: " a. A 'k,, path capable of ta'ktng suctionh a $ At least o nce-pr 31 days by ver ifying the 2/3 Intake Canal for Unit 2/3 ,.

.t 4!m b At least once per 12 months by cycling

b. A fow path capable of taking suction each testable valve in the 1`1 path

frul, the Unit I Intake Canal for Unit I throuqh one complete cycle. f; •" P UM P " c . A t least once per ye hr by ierfonna nce c. Thi, Unit 2/3 fire pump (2000 GIM) with of a slest e r fu h. itt discharge aligned to the fire sup- donce er operating cycle: pI":sion header (from Unit 2/3 Intake a once Perfo pang cyle : d. Siric ture).

1 Till' UntuIfre) pum BY perfonuinq a system d. Tue Unit t fire pump ( th00 Cr1) with

functional test which inIts discharge aligned to the fire sup

cludes simulated automatic pression header- (from Unit 1 Ine.n

__ .actuation of the system throughout its operating sequence and verifying that each automatic valve in the flow path actuates to Its correct Position.

2) By verifying that the Unit 2/3 fire pump develops at least 2000 gpm, at a 'system head of 238 feet. 3) By verifying that the Unit I fire pump starts and develops at least 2000 gpm at a system head of 238 ft. 4) Cycling each valve in the flow path that is not testable during plant operation through at least, one complete cycle of full travel. e. At least once per 3 years by performing. flow tests of the iystem in accordance with' the "Test of Water Supplies" Chapter in the NFPA Fire. Protection Handbook.

Struc thre). " e. Automatic initiation logic for each ftire pomp. f. Fire suppression header piping with sectional control valves to:

IS~

1) The yard loop. 2) The front valve ahead of the

water flow alam device on each sprinkler or water spray system.

3) The standpipe system.

2. Wi1th an inoperable fire pump or associated water supply, restore the inoperable equipment to operable status within 7 days, or prepare and sunmit a report to the Commission litrsuant to Specification 6.6.0.2 within the next 30 days outlining the plans and procedures to he used to provide for the loss of redundancy In this system.

I 1

I

Amendment. No.3-5 6.

I,

I.

/ I

I

Page 26: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

r)PR-3.12 LIMITING CONDITIONS FOR OPERATION

4.12 SURVEILLANCF RFAhItDnArMrc�

Amendment No. 3•,

**��.U LIII 3

*

61

is56

3. with no rire Suppression Water System operable, within 24 hours;

a. Estahlish a backup Fire Suppression Water System..

b. Notify the Commission pursuant to Specification 6.6.0.1 outlninq the actions taken and the plans and schedule for restoring the system to operable status.

4. If the requirements of 3.12.0.3.a cannot be met, an orderly shutdown shall be Initiated, and the reactor shall be in cold shutdown condition within 24 hours.

SDr"-?5'

(

4.12 SURIVEILLANCE: grnQiRAtrureIII w•l U. I L III | J

I I

Page 27: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

3.12 LIMITIIIG.CONDITIONS 1OR OPERATION 4.12 SURVEILLANCE REIUIREMENTS

~~~~~~~t I &A , ,_ ,._ • u-4 b a- efnm .

C.. Spr InK ler 3y5Lems

1. The sprinkler systems given in Table 3.12-2 shall be operable at all times when equipment in the area that s. sprinkler protected is required to be operable.

2. With a sprinkler fire inspections equipment within

system inoperable, establish with backup fire suppression

1 hour.

a. In the Unit 2/3 turbine mezzanine 538' elevation area or Unit 2 hydrogen seal oil area, a continuous fire watch is to be established.

b. In all other-areas given in Table 3.12-2 perform inspection hourly.

3. Restore the system to operable status within 14 days, or prepare and submit a report to the Connisslon pursuant to Specification 6.6.B.2 within the next 30 days outlining the cause of inoperability, action taken and the plans for restoring the system to operable status.

4. The provinirnn of Spnciftcntion 3.O.A are not ap1licables

D. CO,, Sys tem

1. The CO2 Storage Tank shall have a minimum standby level of SO percent and a minimum pressure of 250 psig.

2. The CO System given In Table 3.12-3 shall he operable.

* I

At least once per 31 days by verifying that each valve, manual,- power-operated, or-- .-.

automatic, in the flow path is in its correct position.

2. At least once per 12 months by cycling each testable valve in the flow path: through at least one complete cycle of full travel.

3. At least once per operating cycle:

a. A system functional test shall be performed which includes simulated automatic actuation of the system and verifying that the automatic valves in the flow path actuate to their correct positions.

b. The sprinkler headers shall be inspected to verify' their integrity.

c. Each nozzle's spray area shall be inspected to verify no blockage of the spray pattern.

:4. At least every other operating cycle, a flow test will be performed to verify that each open head spray nozzle is unobstructed.

D. CO2 System

1. At least once per 7 days the CO2 Storage Tank level and pressure will be verified;

2. At least Once per 31 da'.s .by verifying tha.t. "*each valve, manual, power-operated, or automatic, in toe iiow path is in the correct position.

3. At least once per operating cycle, the system valves and associated dampers will be verified

I

5 P In 1 " t~ ,X • ,gr

I. S.9

I

oI

(

Page 28: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

3 . 1 2 L I NI T I I NG fr N hi I T M n U r fn l nD r IO A T tI a I H I-z-.*

E. Fire Hose Stations

I. The Fire Hose Stations given In Table 3.12-4 shall be operable at all times when the equipment In the area Is required to be operable.

2. With a hose st'tion Inoperable route an additional equivalent capacity hose to the unprotected area from an operable hose station within I hour.

3. When a hose station becomes inoperable, restore to operable status within 14 days or report to the Commission pursuant to specification 6.6.8.2 within the next'30 days outl Ining the cause of InoperabilIty and plans for restorinq the hose station to ope rab I I I ty.

4. The provlstons of onpccificntion 3.O.A ore not npplicable.

3. Specifications 3.12.0.1 and 3.12.D.2 above apply when the equipment in the areas given in Table 3.12-3 is required to he operable.

4. With a CO. System inoperable,.establish fire inspection with backup fire suppression equipment In unprotected areas within I hour,'and perform Insleacticn at least hourly.

5. Restore the system to operable status within 14 days, or prepare and submit a report to the Commission pursuant to Specification 6.6.8.2 within the next 30 days outlining the cause of Inoperability, action taken and the plans and schedule for restoring the system to operable status.

8o The provtalono of Specification 3.O.A are not opplIcablee

q.Ie )UIiVI�ILLRIYLL KLIJUIRUItNIS

* 1*

C

Fire Rose Stations

1. At least once per 31 days, a visual inspection of each fire hose station shall be made to assure all equipment is available at the. station.

2. At least once per operating cycle, the hose will be removed for Inspection and repacked. Degraded gaskets In the couplings will be replaced.

3. At least once per 3 years, each hose station valve will be partially opened to verify valve operability and no blockage.

4. At least once per 3 years a hydrostatic test will be conducted on each hose at.. a pressure at least 50 psig above line pressure at that station.

Amendment No.

I

I

E.

,It* 14 3 KILILLUIftt M(IUIKI:MEIS

G1156h

Page 29: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

A 17 �iInvrIIiA1rr IZFOIIIRFIIENTS

F.3.12 LIMITIN.G CONDITIONS FOR OJPERATION

F. - Penetration Fire Barriers

1. All penetration fire barriers (including fire doors and fire'dampers) protecting safety related areas shall be intact, .except as stated in specification 3.12.F.2 below.

2. With one or more of the required penetration fire barriers not Intact, establish a continuous fire watch on at least one side or the affected-penetration within I hour when the area on either side of the affected ~netration con t.ins equipment required to

3. Tho provisions of "Specification 3.0.A are niot applicableio

4. Restore the non-functional fire barrier penetrations to operable status within 7 days or prepare and submit a report to the' Commission pursuant to Specification 6.6.B.2. within the

next 30 days outlining the cause of inopera

bility~action taken and the plans and schedule

for restoring the penetration fire barriers

to operable status.

G. See 3.12.B.

I1561

Penetration Fire. Barriers

1. Each of the required penetration fire barriers shall be verified to be Intact by a visual 'Inspection: .

a... At least once-per 10-months, and -,

b. Prior to dclarig a penetration fire barrier Intact flollpwinq repairs or maintenance.

G.- Fire Pump Diesel Engine

1. The fire pump diesel engine shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying:

1) The fuel storage day tank contains at least 150 gallons of fuel, and

2) The diesel starts for ambient conditionis and operates for at least 30

- 1 minutes.

I 3) The fuel transfer pump starts and transfers fuel from the storage ta( to the day tank.

b. At least once per 92 days 'a sample of diesel fuel shall be checked for viscosity, water and-sediment. Theprocedure used shall be consistent with existing station procedures used to check diesel fuel in the main storage tanks.

Amendment No. 05, 6 1

Page 30: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

3912 LIMITING CONDITIONS FOR OPERATION 4.12 SURVEILLANCE REQ•tl•ETN.ITS

| c. At least once per 18 months, Lt':

1) SubJecting the diesel to an inspec, tion In accordance with procedures -prepared In cnnJunction with Its:' manufacturer's reconimendatIons for -the class of service, and

2) Verifying the diesel starts from ambient copditions on the auto-, start signal and operates' for ?'* 30minutes while loaded with the -fire pump.

2. The fire pump diesel enxslne batteries sh( be demonstrated operable:

a. At least once per 7 days by verifying that:

1) The electroylyte level of each battery Is above the plates, and

2) The overall battery voltage ts' 24 volts.

b. At least once per 92 days by verifying that the specific gravity is appropriate for continued service of the Iattery.

c. At least once per 18 months by verifyint that:

1) The batteries and battery racks show no visual Indl(a.tion. of physical damage or abnotme deterioration, and

2) The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anticorrosion material.

156j

Amendment No. .•6,

.- -.-- ý1•r

I

61Z

Page 31: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

3.12 I.XIITINE awNMITIOc FM OPFRATION 4.12 .9JRMU/AWE. RQIRFMENMS

H. Ifalon System .

1 . The following ialon system shall 6e OPflMAfl with the storage tanks havingrat least 95% of fullcharqe weight and 901 of full charge pressure.

a. Auxiliary Electrical uiprent Rom

2. With one or more of the above required l1alon systems inoperable, establish a continuous fire watch with backup fire suppression equipment for the unprotected area'(s) within 1 houri restore the system to OPfEBLE .status within 14 days or, prepare and submit a report to the Commission pursuant to Specification-6.6.E within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPFjMLEU status.

i'bkI

I W. Ilalon system . .

1. At least once per 31 days, ye.rify.that. each valve. in'the flow path is in the correct position.

2. At least once per 6 months, the Halon storage tank weight and pressure will be verified.

3. At least once per operating cycle, the system, including associated ventilation dampers, will be verified to actuate manually and automatically. A flow test shall be made through headers and nozzles to assure no blockage.

Amendm'erit No.._X,

, j.-, . - i.

(

6 11.'

vs

°*

Page 32: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

½,? �

* -. 1-� I

oases: Fire Protection Systems

OperabilitY of the fire detection instriunentation

ensures that adequate warning capability Is

available for the prompt detection of fires.

This capability is required In order to detect

and locate fires in their early stages. Prompt

detection of fires will reduce the potential

for damage to safety related equipment, and is

an integral element in the overall facility fire

protection program. In the event that a portion

of the fire detection instrumentation Is inoperable,

the establishment of frequent fire inspections in the

affected areas Is required to provide detection

capability until the inoperable instrumentation

Is returned to service.

The operability of the fire suppression systems

ensures that adequate fire suppression capability

is available to confine and extinguish fires

occurring In any portion of the facility where

safety related equipment Is located. The fire

suppression system consists of the water system,

sprinklers, CO2 systems, Halon system, and fire hmop

stations, and is adequate to minimize potential

damage to safety related equl[tnent, and is a major

element in the facility fire protection proqram.

In the event that portions of the fire suppression

system are inoperable, alternate backup fire

fighting equlpient Is required to be made available

In the affected areas until the affected equipment

can be restored to service.

A fire suppression water system shall consist of

a water source, pumps, and distribution piping

with associated valves. Such valves shall Include

sectional control valves, and the first valve ahead

of the water flow alarm device on each sprinkler or

hose standpipe riser.

In the event that the fire suppression water system becomes Inoperable. Immediate corrective

measures must be taken since this ;ystem

provides the major fire suppression capability

of the plant. The requirement for a 24-hour

report of the Commission. provides for prompt

evaluation of the acceptability of the corrective

measures to provide adequate fire .svppression

thpahility for the continued protection of the

nuclear plant.

The functional 'Integrity of the penetration ,fire barriers ensures that fires will be

"-confined or adequately retarded from spreading

to adjacent portions.of the facility. This

desiqn feature minimizes the possibility of

a single fire rapidly involving several areas

of the facility prior to detection and extin

guishment. The penetration fire barriers are

a passive element In the facility fire pro

tection program and are subject to periodic

inspections.

During periods of time when the barriers are

not functional, a fire watch Is required to

be maintained in the vicinity of thPe affected

barrier until the barrier Is restored to

functional status.

156 1

Amonnnma~nt N . 331ý '-3 1

4

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IWl- 25 TABLE 3.12-1

FIRE DETECTION INSTRUMENTS

INSTR LN( LOCATION MINIIILM INSTRUNEITS oPERAWL" 1. Main Control Room

24 34 Smoke. Detectors

2. Unit 2/3 Aux. Elect. Equip. Room 12 Smoke Detectors

3. UnIt 2/3 Computer Room 6 8 Smoke Detectors

4. Unit 2 Battery Room 7 10 Smoke Detectors (

5. Unit 2 Turb Bldg. 480v MCC 17 Smoke Detectors 12

6. Unit 2 Turb Bldg. 4KV Swltchgear I 10 Smoke Detectors

7. Unit 2/3 Diesel Generator Area 3 4' fleat Detectors

8. Unit 2 Diesel Generator Area 2 3 Hoat Detectors

9. Unit 2 Rx Bldg. 480v MCC (570'). 2 3 Smoke Detectors

10. Unit 2 Rx Bldg. 480v M1CC (517) 5 7 Smoke Detectors

11. Unit 2 Rx Bldg. 4KV Swltchgear 3. 4 Smoke Detectors

12. Unil 2 Standby Liquid.Control Area 1 Sirn-:ke Detector

156m

Amendment No.)•, 6 1

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n•P-25 • , t

TABLE 3.12-2

SPRINKLER SYSTEMS

I.

2.

3.

4.

5.

6.

7.'

8.

9.

10.

11.

12.

156n

Amendment No..3', 6 1

thit 2 Emergency Diesel Oil Day Tank

Unit 2/3 Turbine Mezzanine 5381 Elevation

Unit .2/3 Emergency Diesel Oil Day Tank

UnIt 2 Reactor Feed Pump Area

Unit 2 Hydrogen Seal Oil Area

Unit 2 Condensate Feed Pump Area

Unit 2 HPCI Area

Unit 2 Turbine Building East Mezzanine Area

Unit 2 EHC Area

2/3 Fire Pump Area

Unit 2 Trackway

Unit 2 Instrument Air Compressor Area

S" - .. . .. 4.

(

V

I

Page 35: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

* *

I

W~-20~

CO? SISTII4S

to Unit 2 Emergency D~iesel Cu.rrator

*2. Unit 2/3 Emergency Diesel Cemerstor

f.

V

I sc,4, I

(

T', "Pv

Page 36: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

A"

H6.

F21

F54

F'

LOCATION

Cribhouse 517-ft., by Duo 20

Reactor Building 589-ft., North Bast Wall at Elevator

Reactor Building 589-ft., South of Standby Liquid Tank

Reactor Building 589-ft., South Edst of Isolation Condenser

Reactor Building 589-ft., South West Stsirv&y

Reactor Building 570-ft., North Wall at Elevator

Reactor Building 570-ft., Across from Cleanup Demineralizer P.C. Tank

Reactor Building 570-ft., C.R.D. Repair Room

Reactor Building 570-ft., West Wall Hear RBCCW Tank

Reactor Building .570-ftb, by South Stairs I

FSOO

I. 156p

DPR- 2 5 TABLE 3.12-4

RE ROSE STATIONS

NO.

F62

F64

F65

F66

P67

F68

F73

F74

F78A

LOCATION

Reactor Building 545-ft., North Wall Hear Elevator

Reactor Building 545-ft., South Wail at RBCCW Heat Exchanger

Reactor Building 545-ft., South West Stairway

Reactor Building 545-ft., North of Due 23

Reactor Building 517-ft., at Elevator

Reactor Builditg517-ft., South East Wall

Reactor beiiding.17-ft., South East Stairway

Reactor Building 476-ft., 2B LPCI Pump

Reactor Building 476-ft.', 2C'Core Sproy Pump

Turbine, Biilding 549-ft., North Wall Unit 2 Battery Room

Turbine Building549-ft.,' Outnide of Passenger Elevator

dn 33'% f 1

-

I'

F56

F51

F58

F59

F60

F61

F6 IA

Page 37: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

Di I'I 4- 2 5 •. TAKiLE 3.12-4

FIRE HOSE STATIONS NO. LOCATION

.... NO. LOCATION"

Fe2 Turbine Building 538-ft., Stator Copling Pump

Fe2A Turbine Building 538-ft.. East of Trackvay Equipment Hatch

F828 Turbine Building 534-ft., Across from Suitchgeor 23 and 24

F84 Turbine Building 534-ft., East of Standby Gas System

FOS Turbine Building 517-ft., Hear U-2 Transformer Valve

F86 Turbine Building 517-ft., at U-2 Emergency Diesel

F07 Turbine Building 517-ft., Across from 20 RFP West Walk

F8e Turbine Building 495-ft., at C.R.D. Pumps

F89 Turbine Building 469-ft., Across from 2D Condensate Pump

156q

Amendment No. 6 1

Page 38: 0 NUCLAR REGULATORY COMMISSION Q ,WASHINGTON, D. C. …

UNITED STATES NUCLEAR REGULATORY COMMISSION.

DOCKET NOS. 50-237 AND 50-249

COMMONWEALTH EDISON COMPANY

NOTICE OF ISSUANCE OF AMENDMENTS TO OPERATING LICENSES

The U. S. Nuclear Regulatory Commission (the Commission) has issued

Amendment No. 69 to Provisional Operating License No. DPR-19 and Amendment

No. 6 1 to Facility Operating License No. DPR-25, to Commonwealth Edison

Company, which revised the Technical Specifications for operation of the.

Dresden Nuclear Power Station, Unit Nos. 2 and 3, respectively, located in

Grundy County, Illinois. The amendments are effective as of their date of

issuance.

The amendments modify the Technical Specifications to incorporate

Limiting Conditions for Operati-on-and Surveillance Requirements related

to modifications to the fire protection system required by the March 22,

1978 Safety Evaluation Report by the Commission's staff.

The application for amendments complies with the standards and require

ments of the Atomic Energy Act of 1954, as amended (the Act), and the

Commission's rules and regulations. The Commission has made appropriate

findings as required by the Act and the Commission's rules and regulations

in 10 CFR Chapter 1, which are set forth in the license amendments. Prior

public notice of these amendments was not required since the amendments do

not involve a significant hazards consideration.

The Commission has determined that the issuance of these amendments

will not result in any significant environmental impact and that pursuant

to 10 CFR Section 51.5(d)(4) and environmental impact statement or negative

declaration and environmental impact appraisal need not be prepared in

connection with issuance of these amendments.

8204260 I

7920-01

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For further details with respect to this action, see (1) the application

for amendments dated" October 21, 1980, and its supplements dated

June 12, 1981 and February 17, 1982, (2) Amendment No. 69 to Provisional

Operating License No. DPR-19 and Amendment No. 61 to Facility Operating

License No. DPR-25, and (3) the Commission's related Safety Evaluation

published on March 22, 1978. All of these items are available for

inspection at the Commission's Public Document Room, 1717 H Street, N. W.,

Washington, D. C., and at the Morris Public Library, 604 Liberty Street,

Morris, Illinois. A copy of items (2) and (3) may be obtained upon

request addressed to the U. S. Nuclear Regulatory Commission, Washington,

D. C. 20555, Attention: Director Division of Licensing.

Dated at Bethesda, Maryland, this 12th day of April, 1982.

FOR THE NUCLEAR REGULATORY COMMISSION

Dennis M. Crutchfield, C Operating Reactors Branch #5 Division of Licensing