i

..*

i,

PAGE 1 OF 3 Ii

,

i

;.,

. |

|

FACILITY CHANGE SAFETY ANALYSIS

ECN R-0775 REY. 1 AND LOG NO. 807 E, GSUBS R-0775 A-I REY. O

Descrintion:

Perform excavation for a new sump, a new Regenerant H.oldup Tank(RHUT), and buried piping and conduit required to implement allthe changes. Backfill and pave as, required.

'

Add a make-up demineralizer waste sump, two sump pumps, anddischarge header from the pumps. Make-up demineraliserregenerant wastes and other non-radioactive wastes will berouted to the new sump. The new make-up demineraliser will belined with High Density Polyethylene (HDPE).

Upgrade existing RHUT 'A' & 'B' transfer pump impeller and add aparallel pump to improve water movement capabilities of REUTs 'A'& 'B'. Install a third pump for the new REUT ('C').

Provide foundations for the new RHUT, new pumps, demineraliserskids, and effluent strainer skid.

Add a ~100,000 gallon REUT and designate it the 'C' RHUT (T-9500).Tank will be lined with HDPE and will have a mixing agitator,

"sampling pump, level indication, and acid and caustic supply forneutralization.

Add an off-line oil separation / filtering system that connectsbetween the condenser pit sump and polisher sump.

Install a new sluiceable demineraliser system which will functionto clean up RHUT 'A' & 'B' water prior to transfer to theretention basins.

Install all interconnecting piping required to accommodate thechanges specified in ECN R-0775 Rev. 1 (See sketch ofinterconnecting piping, Attachment I).

Reroute secondary sample waste discharge to the polisher sumpwhere a sampling basin will be provided. Reroute secondary samplecooler service water to the new make-up sump. Reroute otherpotentially contaminated secondary drains to the polisher sump.

Provide all necessary wiring needed to connect the new pumps, RHUTequipment, sluiceable demineraliser equipment, and effluentstrainer to plant power sources and local control panel H4RH..

I Replace the existing H4RH panel with a new H4RH human factoredcontrol panel that integrates new and old controls (See ECN R-0775

i Major Rev. 1, Sub ECNs A through I Rev. O, and DBR)|

$[S4 SOS 0!$$Sohfha;P

PAGE 2 OF 3.,

.

.

.

Reason ing Channe:

ECN R-0775 Rev. 1 and sub ECNs A through I provide modificationsnecessary to separate potentially contaminated from non-contaminated secondary waste water, increase the plant'sprocessing capability and flexibility, and provide additionalcleanup components which will be used to maintain off-site liquideffluent discharges within 10 CFR 50 Appendix I limits. Also, themodifications will improve the plant's ability to safely processand dispose of waste water following an OTSG tube leak. Thechanges represent an operational enhancement and an improvement inradiological safety and control. -

Evaluation and Basis 12I Safety Findinas:

All the new mechanical equipment, piping, valves, and powerscurces are non QA and Seismic Class I and are designed inaccordance with project specifications and required codes of theeffected systems. The new Make-up Demineralizer Sump and the new'C' RHUT will not contain radioactive wastes and thus will notbe controlled by radioactive waste management systems designrequirements (Reference DBR for ECN R-0775).

The make-up demineraliser sump and pumps collect non-radioactivewastes separate from polisher and condenser pit sump wastes which

- become radioactive following OTSG tube leaks. The new 'C' RHUTwill be used to store and neutralise waste water from the make-upsump. The existing 'A' & *B' RHUTs will be used to store andneutralise condenser pit and polisher sump wastes. Also, excesstritiated Demineralized Reactor Coolant Storage Tank (DRCST) watercan be transferred to the 'A' and 'B' RHUTs. A new sluiceabledemineraliser system will clean up A & B RHUT waste water prior tadischarge to the retention basins.

The non-radioactive 'C' RHUT waste water is neutralised prior torelease. The discharge will not be through the sluiceabledemineraliser, the effluent strainer, or radiation monitor R-15020. In contrast RHUT 'A' & 'B' waste water is alwaysmonitored by R-15020 when discharged to the retention basins.

The 'A' & 'B' RHUTs cannot be discharged at the same time. One ofthe two tanks will always be maintained as.a receiver at alltimes. The new 'C' RHUT' water,can be transferred to the 'A' or'B' tank, but 'A' or 'B' tank contents will not be transferred to'C' to avoid contaminating 'C' waste water.

Hydrostatic testing, leak testing, and testing against componentspecifications are required. New equipment will be similar to theexisting equipment to optimise maintenance procedures and spaieparts inventories. Plant operating procedures will be revised toinclude the operation of the new ccmponents and their interactionswith the existing systems.

. - , -- - . . . - -. . _ _ _ . . .- - -

_ _ = _ _ _ -. . . - - - - -

. .

PAGE 3 OF 3*

-

,.2

t .

Use of HDPE affects the Fire Protection Program. HDPE is aflammable material. The sump and tank being installed are locatedoutside the south side of the turbine building. The FHAR and theCombustible Loading Calc. will be revised to include the HDPEbeing added by this change (See Attachment II).-

! USAR Chapter 11 " Radioactive Waste and Radiation Protection" willbe reviewed against the changes being made and a complete rewritei

of Chapter 11 submitted for the next FSAR update. Tech Specsection 6.17 does apply to the change. A detailed discussion ofthe major changes to the radioactive waste management system willbe included in the next FSAR update. The discussion will include

,

the topics outlines in Tech Spec section 6.17.2A.1 a through h*

! (See Tech Spec 6.17, Attachment III). No other Tech Specs are

,

affected by the change.!

The changes do not alter Rancho Seco's design basis. Release of. radioactive liquids is expected following the abnormal operatingcondition of primary to secondary leaks. The modifications willincrease the possible amount of radioactivity entering into the'A' & 'B' RHUTs by ~40%, but the volume of radioactive water being

i processed is reduced sharply. Also, the new processing equipmentbeing installed works to remove significantly more radioactivity

j than the previous system. Ultimately, the total amount ofradioactivity released annually is controlled by the ALARA limits!

of 10CFR50 Appendix I. The change will not cause the amount ofi radioactivity being released off-site as liquid effluent to

increase. A rupture of either tank and subsequent release ofradioactivity will not result in a release above 10CFR50 AppendixI limits.

The changes act to give Operations better control of theradioactive waste water systems. Management of waste water isimproved and thus nuclear safety is also improved. Themodifications will not affect,previously analyzed plant faliuremodes, and no new failures are intr'oduced by the changes.

.

I

~ . _ _ _ _ - _ _ _ _ _ _ - _ . - _ _ _ _ . _ . . _ - . . . - _ . _ _ _ _ ..._...-_._._ _ _ ____.___ __-

.. . . _ . _ . _ _

,.

' '

.

)-

.

Fl&UR E I'

_S ECON DA RY W A STEJFlow DI A GR A M

. .

-n,* 1;us~c I F44c-r ' '

#1 6 y4 p7 j.,

E E O [{ {E F i,

,

y .. _.- ..

-i ii s '. i s. g a i u* ~

Pou. Men s P po,nur :Sapac PSam? - ,

.

- - ;..

I ! ., .

,,

II ] I

')k

IT 4 .U y4 y

Zi197~ RHdT & MJ7' .

'

T9SD ~T'TSO 7~950I.

.

h 8 c. :.

! :-

.I| I .

T,, rv v .-'/-pgy/ %

'

co A 6&.ve7/ 'o'

An p/,/, . .

l ).

w2'

;- ,

'Y i

fdb.5f$'s'

w 'a / ,; .

's u, -'v' -

//wa-v w ;t w a| '' A ' ' L %- L F 3

7.sce husrrP6b3 s %r, m-'-

g.,

| b4 1 t,Y ;><:1-+ 4_veu'

R* I 5'Q 2 WwM MisL- -

N 'd w2a r m &w r.

~'v,

w nan ei ,wA A w !"F A . .z "p u. - T& A 9 yh

t 2&~ sw.17"fran I.A 4 L r, a t-94 (snueur-r. 6 mever W<.sg EoJ44%

o0 Sc wsy*-- w FuG- (2)'uceprv. -

se u ,, ..

,

$

_

O m id

( =- )s- - - - - - - - .. .. _ _ - .

[.-

-,

- . ...,.

Attachment Jr1:30 Daoe 1 of i*

FIRE PR ION CONTROL REPORT._____________________________.______________________________________________.,_________,,,,,,-

8NEFPCR No.L-no433 -NE Revision c2. Date Received __ -l V- M

beI -

Part I - Descriotion: , hR/2 m sin MA/ c 2- nel' A wed r 3 /Mthv('

ihrrm M hukrx as bests iners:o T-o '~wtr A st OTSG-AeiuN m

Th w im

O Documents attached

Part II - Evaluation: WE RM e: m AMA tw evj waats:-

feria;A vuMt 79ct2 Av is | At m zer,ws 'ns r

ho&se 2%surrFV f6t.v rBhin nAir isum1.& u ti f ar)v M r A trr we,

c n

kn% .$ 4t7b/EM h6 *n/E0f d PtAr_h r~s fr $W [MT/M _ _A

; McMAkM x M 27th -

| __

'

.

*.

|- Conclusion: The evaluation abo've jndicates:

,

t

O No effect on the fire protection program.

M ire Protection Program affected as follows:

F*tM Auf r+Ainm c uurx/G Carr att HA'Vf lb-

16~ f.Sttrit-y

Affected FP documents: FtrM. w6Londrs T M il d- ek

(doproved Notappr$ved. Note reasons in above etion.

Prepared by: d/ 'mia 9-// -tK NEFPC Concurrence: f-//ds

C , g ' d g ,f,g (Date) GV (Cate;i

C NOFPC - plant cerations concerns

Part *!: - Cicsure: C:=cletec/Date N/A Precarer/Date(Initiais)

31an: Changes: [] [[ /

F3 Jocument Changes-: [] [] /_ _

_ '.70:acortins ir.t::._ UFH AR:_ _ _ R _, __ [] __/

.- _ . - -.

-'.

G,| Attackt ni w usPANCHO SECO UNIT 1

TECHNICAL SPECIFICATIONS

Administrative Controls

6.17 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (LIQUID,GAbr.Uu3, ANU 5ULID)

6.17.1 Function,

The radioactive waste treatment system (if quid, gaseour, and solid)are those systems described in the facility Final Safety AnalysisReport or Hazards Summary Report, and amendments thereto, which areused to maintain that contro1 over radioactive materials in gaseousand liquid effluents and in solid waste packaged for offsite shipment

i required to meet the LCO's set forth in these Specifications.

6.17.2 Major changes to the radioactive waste systems (liquid, gaseous, andsolid) shall be made by either of the following methods. For thepurpose of this specification, " major changes" is defined inSpecification 6.17.3, below.

A. Licensee-initiated changes:

1. The Commission shall be infomed of all changes by the| inclusion of a suitable discussion of each change in the'

|Annual FSAR Update for. the period in which the changes were

. made. The discussion of each change shall contain:'

-=- t,

,

a. A sumusary .of the evaluation that led to the-

determination that the change could be made (in'

accordance.with 10 CFR 50.59);

b. Sufficient detailed information to totally support thereason for the change without benefit of additional orsupplemental information;

c. A detailed description of the equipment, components,and processes involved, and the interfaces with otherplant systems;

d. An evaluation of the change which show:s the predicted| releases of radioactive materials in liquid and

gaseous effluents and/or quantity of solid waste fromthose previously predicted in the license applicationand amendments thereto;

e. An evaluation of the change which shows the expectedmaximum exposures to individuals at or beyond the SITEBOUNDARY and to the general population from thosepreviously estimated in the license application andamencments thereto;4

Amendment No. 535 '9

-. _._. _ _ _. _ _ _ _ _ _ _ _ __ _ _ .__ _ __-

__ _ _ _ _ . . _ .- _ _ ___._ __ _ __ _

- -

.

,.

.

.. .,

.

p%e a a 353>

RANCHO SECO UNIT 1TECHNICAL SPECIFICATIONS .

Administrative Controls

6.17.2 (Continued) .

f. A compaH son of the predicted releases of radioactivemateMals in liquid and gaseous affluents and in solidwaste to the actual releases for the peM od in whichthe changes were made;

g. An estimate of the exposure to plant operatingpersonnel as a msult of the change; and

h. Documentation of the fact that the change was reviewedand found acceptable by both the PRC and MSRC.

2. The Change shall become effective upon review andacceptance by both the PRC and MSRC.

6.17.3 Background and definition of what constitutes " major changes" toradioactive waste systems (liquid, gaseous, and solid).

A. Background

1. 10CFRPart50[Section50'.34a(a)requiresthateach -

..gapplication to construct a nuclear power reactor provide a ,e'

descMption of -the equipment installed to maintain controlover. radioactive mateMal in gaseous and liquid effluentsproduced duMng nomal reactor operations, includingoperational occurrences.

2. 10 CFR Part 50, Section 50.34a (b) (2) requires that eachapplication to construct a nuclear power reactor provide anestimate of the quantity of radionuclides expected to be'

released annt. ally to unrestricted areas in liquid andgaseous effluents produced during nomal recctor operation.-

3. 10 CFR Part 50, Section 50.34a (b) (3) requires that eachapplication to construct a nuclear power reactor provide adescription of the provisions for packaging, storage, andshipment offsite of solid waste containing radioactivematerials resulting from treatment of gaseous and liquideffluents and from other sources.

4. 10 CFR Part 50, Section $0.34a (c) requires that eachapplication to operate a nuclear power reactor shallinclude (1) a description of the equipment and proceduresfor the contro' of gaseous and liqui 1 effluents and for themaintenance and use of equipment ins:alled in radioactivewaste systems, and (2) a revised estimate of theinfomation required in (b)(2) if th: expected releases ancexcosures aiffer significantly from tne estimate sucaittacin :ne :onstruction gemit.*

ameacent Nom 52

-_ ~ -

_

..

,

..,

-

,,

[RANCHO SECO UNIT 1'

- TECHNICAL SPECIFICATIONS.

Administrative Controls,

6.17.3 (Continued) -

5. The NRC's Safety Evaluation Report and Amendments theretoissued prior to the issuance af an operating license-

contains a description of the radioactive waste systemsinstalled,in the nuclear power reactor and a detailed

- evaluation (including estimated releases of radioactive'

materials in liquid and gaseous waste and quantities ofsolid waste produced from nomal operation, estimatedannual maximum exposures to an individual in theunrestricted area and estimated exposures to the general

.

population) which shows the capability of these systems to'

meet the appropMate regulations.

6. The NRC's Final Environmental ^ Statement issued prior to theissuance of an operating license contains a detailedevaluation as to the expected environmental iapact from theestimated releases of radioactive mateHal in liquid and,

'

gaseous effluents.

B. Definition - -

" Major Changes" to cadioactive wasta systems (liquid, gaseou's,and solid) shall inplude the following:

's1. Major changes in process equipment, components, structures,

|and effluent monitoHng instrumentation from those

,

!described in the Final Safety Analysis Report (FSAR) or theHazards Summary Report and evaluated in the NRC's SafetyEvaluation Report (SER) (e.g., deletion of evaporators andinstallation of demineralizers; use of fluidized bedcalciner/ incineration in place of cement solidificationsystems);

2. Major changes in the design of radwaste treatment systems(liquid, gaseous, and solid) that could significantly alterthe characteristics and/or quantities of effluents releasedor volumes of solid waste stored or shipped offsite fromthose previously considered in the FSAR and SIR (e.g., useof asphalt system in place of cement);

3. Changes in system design which may invalidate the accidentanalysis as described in the SER (e.g., changes in tankcapacity that would alter the curies released); and

4. Changes in system design that could potentially result in asignificant increase in occupational exposure of operatingperson 1el (e.g., use of skid-mounted equipment, use of.

< mobile processing equipment).

Amendment No. 536-21

_ _ _ , . _.___ _ ______--. _ _ _ ..____ _ _._ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

__ _

.,% f . * *

-%

0.*

*-. . . ,,

,

OESIGN BA' SIS RE PQRT ~

0 August- 11, 1986.

-os. .sv earsasecteune ruas one is sasso om aca woes esou st n.

Nuclear / Mechanical**" ** I ~

530 incLuos asy n.'.moo. m.

L PURPOSE OF QESIGN CH ANGE:.

See Attached.

11. DESIGN CRITERI A USED:

See Attached. -

,

*.

111. CALCULATIQNS & QESIGN INFORM ATION:

See Attached..

IV. FAILUR E MODES:Q' rues eseamos ones not appset coastnet moon sustavesentarsom

O rues cuasses.aarsets cosernoc moons asestnuasaar.irion. ::: amatises,,

.

V. SPECIAL MAINTENANCE REQUIREMENTS ,

See Attached. 3F.

.

V I. SPECI AL QPERATING REQUIREMENTS:

| See Attached.|

.

Vll. VERIFICATION. CRITERI A

See Attached. -

Vill. COMMENTS :

See Attached.

lx. APPROVALS :.

See Attached.,

1*

| A' '

m a a c e - w a c /s m n "-"; d;%g,

ELEcTalCAL Days' /

CivsLf/ aycTumak A%i 8(/h47s/FsMJ s1LL z, eeo Ltns

l)| . , , . . . . . . . .ars ... . ..c ( s -. ...f%dl~L &&Qf&c.i Yu.3,s'

7 idf6 \ii . %

-co.. p r .. .. . . - ..t. .. 2.r..

| %._ 4. M/['i., .T -c <c ;' b. . . . . ...o u9c,dbh $/M!il~c4 4. .y wiu , .. . ..cc n... m . 2.n v.- ewou 2 ri ,

_

_ _ _ . . _ ._

m _.. _ _ ___ . . _ - - _ _ . _ . - - . . - - - _ . - - - - - - - - -- - - - - - - - --- - ---

~ _ _

,,

w ,., ,

.

*.

6 -g

DESIGN BASIS REPORT.

gust 11, 1986DBR Rev. No. 0 This DBR is Based on: Date:

ECN R-0775 A 'through I, Rev. O

MOD No. 530 Work Order No. 108530 NCR No.

I. PURPOSE OF DESIGN CHANGE:i

10CFR50 Appendix I establishes the limits on total annual dose to thepublic from normal plant release points. The lower limits ofdetection (LLD) for radioactivity and the volume of contaminated waterdischarged are prime factors in determining the offsite dose. Bysegregating potentially. radioactive sources from non-radioactivesources", the differential between actual radioactive concentration andthe LLD is reduced.

- This design change will provide Leproved facilities for segregating,processing, and disposing of potentially radioactive waste water.

;

i

II. DESIGN CRITERIA:'

.

A. S_ummary of Change,

A new sump (seke-up domineralizer. sump) and pumps shall be a

provided to collect make-up desineraliser regenerant wastes andother non-radioactive wastes separately from the polishing

e domineraliser regenerant wastes and the condenser pit sump wasteswhich become radioactive following once through steam generator

(OTSG) tube leaks.|

| A'new make-up domineralizer regenerant hold up tank (RHUT) T950Cwill be provided to store and neutralize the waste water'

transftrred from the make-up desineralizer sump prior to transferto the retention basins or the bypass line for off-site discharge.

The two existing RHUTs T950A and T950B shall be used to store andneutralize wastes from the condenser pit sump and the polishingdemineralizer system sump. Also, excess demineralized(triciated) reactor coolant can be transferred from storage tankT621 to these RHUT's for discharge.

A new regenerant waste transfer pump shall be provided for thenew regenerant hold up tank. Also a new regenerant wastetransfer pump shall be provided as a spare to the existing pump,servicing RHUT's T950A and T9508.

A sluiceable demineralizer system shall be provided to processcontaminated waste water held in RHUT's T950A and T950B prior todischarge to the retention basins.

| 3231V 1

f ._ _ _ -

. .

-.___ _

- - -s, ,

.

.

DESIGN BASIS REPORT

Oily . wastes will te reecvec primartiy at sne concenser pit sump oy meansof an off line pump that will transfer surface oil to a disposal crum.The first exchange vessel in the sluicing demineralizer system willcontain an activateo charcoal cec for capture of emulsified oil thatescaped from the condenser pic sump.

Piping additions and modifications shall be made as required for the newequipment and waste stream segregation.

The available system flow naths (Figure 1 attacheq) are as follows:

1. Flow may be from the makeup deminerait:er surp through sump pumpsP966A and 6 to RHUT TS50C. Optionally, the f1cu path can be to RHUTT950A or RHUT T9508.

2. Flow may be from RHUT ToSOC through regenerant waste transfer pumpP683C via the sotra drains to the north or south retention basins orthe bypass line to Hadselville Creek. Optionally, the tank cay begravity drained through the pump bypass 1 ne. The discharge flowfrom RHUT'T950C will be never be through the sluiceable demineralizerand will never be through the effluent strainer. The discharge flowfrom RHUT T950C will not be monitored by radiation monitor R-15020.

..'

3. Flow may be from the polishing dominerlizer sump (polisher sump)through sump pumps P965A and B to.RHUT T950A or RHUT T9508. The

'.. polisher sump discharge flow will never be to RHUT T950C. -

| 4. Flow may be from RHUT T950A through the effluent strainer (gravity .

drain), through the sluiceable demineralizer booster pump, throughthe sluiceable demineralize.r to RHUT T9508 This flow path can alsobe frcr RHUT T9508 to RHUT T950A. The demir.iralized waste flow pathwill be from RHUT T950A or RHUT T950B through transfer pumps P683A orP6838 to the north or south retention basin. The discharge from RHUT7950A or T9508 to the retention basins is always monitored byradiation monitor R-15020.

5. ' Flow may be from RHUT T950A or RHUT T950B through the regenerant: transfer. pump P683A or P6838 through the effluent strainer to the

north or south retention basins. the discharge flow is alwaysj

monitored by radiation monitor R-15020. RHUT T950A and RHUT T9508cannot be discharged simultaneously since one tank must be maintainedas a received at all times. The effluent strainer may be bypassedwith flow through pump P683A or P6838 to the north or south retentionbasins.

,

1

i

h

2

. . . - - _ _ _ _ - _ - - _ _ - _ - . _ - - - - _ _ _ - _ _ _ _ _ _ , - . . _ - _ _ _ _ _ - _ _ . _ _ _ _ _ _ _

. ._ _ _ . _ ._. .. .. _ ___

.*-

. ., ,

~.

-4

DESIGN BASIS REPORT

6. Flow may be from RHUT T950A or RHUT T950B through the effluentstrainer through the domineralizer booster pumps to the spentregenerant tank T689A or T6895.

] 7. Flow s.ay be from the domineralized reactor coolant scorage tank: T621 to RHUT T950A or RHUT T9508 but never to RNUT T950C.

B. Desian Basis

The design will be in accordance with project specifications, andstandards for the effected systems.

Regulatory Guide 1.143, Revision 1, Design Guidance for RadioactiveWaste Management Systems Structures, and, Components Installed inLight Water Cooled Nuclear Power Plants is applicable to those nEsystems containing/ processing radioactive waste. The make-updomineral:.zer sump and the new RHUT T-950-C do not containradioactive waste and therefore are not designated per R.G. 1.143.

C. S.s.sna

The scope of this change includes the clean drain system, the,

secondary waste water disposal system, the domineralized reactorcoolant st:srage system, the make-up water domineralization system, .

the polishing domineralizer system, and the secondary sample system.

.' Plant operating procedures for the above systems that are affected'bythis change will be revised.as necessary.

D. Eauinment ': lass and Power Requirements

' The equipment classifications and power requirements are sunnarizedj below:

i Mechanical Equipment Proiect Class Codes|

1. RHUT, T950C 339 API 650

2. Regenerant Waste 337 Hydraulic Institute

Transfer Pump, P683A,B,C

3. Make-Up Domineralizer 337 Hydraulic Institute

Sump PumpsI

! 4 RHUT T950C Waste 337 Hydraulic Institute

Samp1e Pump

5. RHUT, T950C Agitator 339 --

3

-. - _ . - . . , _ . . __ -_._-.. -_ - - __.-._-___.-_ - -..._ _ _. - _ . _ - - , _ . - _ . . .

._.- - - _ - . - _ - _ . .. . .. -

- -

.,. ,

,*-

.,

.

DESIGN BASIS REPORT

.

f. ' Slui : b!: 02:' :ra!':er ^25 ASPE Sectica VIIISysten

.

01c*r- and ve.1vne

The transfer piping ano valves from domineralized reactor coolant-

storage tank to RHUT's T-950A and B is Project Class 22 and'abricated cer ANSI S31.1.. NOTE: The existing system is 22N3, yhichper current standsrds is treated as 22.' ,

.

All otner piping ano valves for these enanges are Project Class 2391

and fabricated per ANSI 331.1.

'

Power Source Project-Class

1. 480 V,.vCC S2CS, Cub. 2CS03 for makeup 22-domineralizer sump pump P966Ai

,

2. 480 Y MCC S2El, Cub. 2E1:S for makeup ??-domineralizer sump pump P5668

3. 480 V MCC S2E1, Cub. 2E112 for RHUT, T950C 22-agitator '

,,

4. 480 V, MCC S2C1, Cub. 2C110 for regenerant 22-*

waste transfer pump P6838,

5. 480 V, MCC S2C5, Cub. 2C505 for regenerant 22-waste transfer pump P683C<

6. 480 V, MCC 52CS, Cub. 2C528 for RHUT, T950C 22-.

regenerant holdup tank sample pump P941 -

7. 48G V, MCC S2C2, Cub. 2C232 for the sluicing 22-demineralizer booster pump

:

8. 480 V, MCC S2C2, Cub. 2C209 for upgraded 22-regenerant transfer pump P683A (relocated,

| from Cub. 2C201) -

!

9. 480 V MCC S2C2, Cub. 2C214 for effluent strainer 22-;'

pump P602A

10. 480 V. MCC S2C2, Cub. 2C215 for effluent strainer 22-pump P6028

'

|11. 480 Y, MCC 252C, cub. 2C226 for effluent strainer 22-

pump P602

I 12.120 V power supply for caustic piping heat tracing 22-i

1 4-. - ._.- - - - _ - - - - - - . . - _ _ _ _ -

~s s

*.

,

DESIGN BASIS REPORT

..

E. Testina

Shop hydrostatic testing is required for the sluiceable.

desineralizer pressure vessels and hoses. A leak test of thesystem is required after field installation is complete.

The regenerant waste transfer pumps and the make up domineralizersump pump shall be tested per the pump specification.

Control panel H4RH shall be shop tested per the panelspecification.

III. CALCULATIONS AND DESIGN INFORMATION

A. Desian Information

1. Make-up Domineralizer Sump and Sump Pumps

A new sump will be provided to collect non-radioactivewastes including the make-up domineralizer regenerant wastesand area draina and the sentry cooler drains. The existing

piping from these sources to the polishing domineralisersump will be capped off.

The sump is sized to limit the pump starts to about threestarts per hour with an influent flow of about 150 gpm whichyields a sump working volume of about 1200 gallons. Thesump will be constructed of reinforced concrete and linedwith 80 mil high density polyethylene (HDPE).

Two sump pumps (one dupiex set) will be provided to transferthe non-contaminated waste water to RHUT T950C. Each pumpis sized for 250 spe flow, equivalent to the maximum make-updominera11:er cation backwash flow of 144 spm plus 83 gymanion backwash flow plus a 10% design allowance. Other sumpinfluent streams are 150 spa maximum from five sentrycoolers. Both pumps will operate when the influent flowexceeds 150 spm.

2. Make-up Domineralizer Regenerant Hold Up Tank (RRUT) T950C

The new make-up domineralizer RHUT will have the samecapacity, 100,000 gallons, as existing RHUT T950A. RHUTT9508 has a 200,000 gallon capacity. The tank will befabricated of carbon steel, lined with high density

polyethylene, and equipped with a side nozzle mountedagitator. Acid and caustic for tank neutralization will beprovided from the existing storage facilities through newpiping. The caustic piping will be heat traced to preventfreezing.

-. .

3231V 5 --

_- __

..

._

. . ~.',.

*.

*

DESIGN BASIS REPORT

Piping will be provided to direct RHUT T950C influent toREUT's T950A or T9508 if necessary. RHUT's T950A and T-9508will not be transferable to RHUT T950C.

3. Regenerant Waste Transfer Pumps (P683C)

A new regenerant waste transfer pump will be provided forREUT T9 SOC and will be dedicated to transfer only from thistank to offsite disposal via the retention basins or thebypass line.

.

.

A new regenerant waste transfer pump (P6835) will be .

provided as an in line spare pump to existing pump P683A.These two pumps will be dedicated to transfer only fromREUTs T950A and T9508 to the retention basins via the neweffluent strainer provided under ECN A 4954.

The two new pumps will be sized for 1000 spa capacity, topermit transfer of 100,000 gallons from an RHUT in about1.7 hours with flow through the effluent strainer.

Pump P683A may require upgrading to overcome the pressuredrop across the effluent strainer.

The tank agitator and the two new transfer pumps will be thesame as the existing equipment.to optimise meintenanceprocedures and spare parts inventories for these items.

4. Control Panel H4RH

A new control panel will be provided to replace the existingpanel and integrate the new and old controls with theemphasis on human factors and ease of operation. The newcontrol scheme will include a graphic presentation of-equipment on the panel, a programmable logic control systemwith remote inputs and outputs, and indication of status forperipheral equipment such as the acid and caustic day tanks.

5. Sluiceable Demineralizer System

A sluiceable demineralizee system consisting of two boosterpumps and two demineralizer skids will be provided toprocess radioactive wastes prior to discharge to theretention basins.

Each demineralizer train will have a 50 gpm capacity whichis adequate for processing the flow f rom equipment drains tothe condenser pit sump. The polishing demineralizer systemwill be operated in the throw away mode during theseperiods. RHUTs T950A and T950B will.be utilized forprocessing radioactive wastes with flow from one RHUTthrough the sluicing demineralizer to the second RHUT.

' . i : '?

. . _ _ - _ . _ _ _ _ ._ _ . _ _ _ _ _ _ _. -- - .- _ __. .

- - s, ,

O' .

h .,

i.

DESIGN BASIS REPORT

. The domineralizer skid will be a Duratek system utilizing! either their proprietary Durasil ion exchange media or

conventional ion ' exchange media or a combination of both. They'

system will be a booster pump to overcome the system pressure,

! drop, five exchange pressure vessels, a mechanical filter and-

shield, interconnecting piping and valves, instrumentation, and'

control pene1.

8. Design Calculations

calculations will be performed 'to support the design of the sump| pumps, transfer pumps, sump and foundations, piping and hangers.j The calculations will be completed prior to final closure of the-

ECN. The DBR will be revised to reflect the calculation numbers and'

,titles.

)

| IV. FAILURE MODES -.

:

This change does not affect control room instrumentation.

The modifications made under the ECN will not affect previously analyzed, ,

! plant failure modes. This modification, by segregation clean wastes fromi potentially contaminated wastes provides two benefits. First, it

| . decreases the total quantity of radioactive discharge, by discharging theclean wastes from its own system. Second, it increases the concentrationof radioactivity in a RHUT by not prediluting with clean wastes. This

! increased concentration, does increase the total contained activity inthe tank, however, increases the efficiency of the domineralizers to-

remove activity. The' captured activity at the maximum expected D.F. andthrough put does not pose a personnel exposure concern, less than 1mrem /hr at 18 inches. Even the 200K gallon RHUT with maximum expectedconcentration does.not create an exposure concern. Even following thecompletion of the modification with release concentrations 100 times less.

than previous concentrations, our limitation on quantity of effluent andoffsite exposure remains controlled by 10CFR50 Appendix I of 9.62 meiCs-137 (No H-3) or 3 mrem exposure. The decreased volume andconcentration ensure our comp 11ance with regulatory guidelines, whileoperating with an operable OTSG tube leak. Release procedures will haveto be revised to account accurately for the cumulative activity aftereach discharge. Technical Specifications 3.15, Radioactive LiquidEffluent Instrumentation and 3.17, Liquid Effluents, are not affected bythese revisions.

Figure 11.1-4 Sheet 5 of 5 (ABK248) " Coolant Radwaste System", in USARYolume V. Section 11 will be revised to show the new transfer piping fromthe Demineralized Reactor Coolant Tank to RHUTS T950A and B.

.

.[.

-

. -. . s

. . ..'

, ,* -

.,-

.

V. SPECIAL MAINTENANCE REOGIREMENTS

Equipment seals throughout the Turbine Building must be maintained tominimize the leakage flow rate and oil content in equipment drains to thecondenser pit sump.

VI. SPECIAL OPERATING REQUIREMENTS

During operation with failed fuel plus OTSG tube leaks, the polishingdemineralizer regeneration will be performed in the throw away mode andthe contents of regeneration holdup tanks T950A and T950B will beprocessed through the sluiceable demineralizer system prior to dischargeto the offsite retention ponds.

_

VII. VERIFICATION CRITERIA '

None.

VIII. COMENTS

The new RHUT. T950C, will not contain radioactive liquid wastes anddischarge from this tank will not be monitored. TechnicalSpecifications 3.15. Radioactive Liquid Effluent Instrumentation

. . and 3.17. Liquid Effluents, will not apply to discharge from RHUTT950C.

r.

'

*-

.

E

I

.

6

i

1

i

1,

|

6

-8-_ _ __ _ . _-_ _._ _ _ _ _ __ _____ ___ _ _.____ _ - - -_ _ ___. __ _

-.

.6

,.j 'S-

Fl&UR E I

S ECoM DA RY W A STESFlow DI A GR A M

.

A

hE F ' 5

Mdi y y . M4 C -" -

<

@ @ O @ {E 7} i

,. .. .,y, .

'. I * L._r '-4 i L_}-4 ii s~

g PS.;m? Pos tMcx sc.)+AP ps, w.g ur! gaps ,,.,

. ...

.

!"-

.i i-i .y i"

L

'I Y 9 y 4v

Eiktr RHd 12MdT'

7 9sD 7 950 D50cA 8

.I .

v -

{ . 'c"/ A [~ '

v"" "

.

w2 .-

'

.Ym

Y )

ff8.5 A \r-

'-w>:

s24' -r,' - -

if E 2 _. LJ.

u 2VA Ak V3[ |

FM'

= {n*1 %WPLb3 e %r, m-,

H { W&'

. R * ' 5* gerw'- nd MirL-

M hw# M -

LTs IV N'd6 coa A:.E / se4 a M2~A z "eu. Tw n y

| Y: udTa/7-# -

.4 JL '

f' preenr'g emueur-S n u i n e' r ,M 7 m~ n s

(e.

Eo)44%e.u-u - r a gy-

iu' M pI*vSSIjg ;

Su.)ICACU" -

,

CEmid

i2)_ _ . ._ . . -- + - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _