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Forwards Advance Submittal of FSAR & Tech Spec Changes Re Testing of Station Svc Water Recirculation Valves.Requests Expedited Review of Changes & Informs Util of Acceptability
	ML20247K599
Person / Time
Site:	Comanche Peak
Issue date:	07/25/1989
From:	William Cahill; TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	TXX-89515, NUDOCS 8908010006
	Download: ML20247K599 (17)
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July 25, 1989

.'J. S.. Nuclear Regulatory Commission Attn: Document Control Desk =

Washington, D. C..20555

SUBJECT:

CDMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445land 50-446 ADVANCE FSAR AND TECHNICAL SPECIFICATION SUBMITTAL STATION SERVICE WATER RECIRCULATION. VALVES Gentlemen:

The enclosures to this letter provides an advance submittal-of FSAR and.

Technical. Specification changes.related to testing of the station. service

-water. recirculation valves, along with.related supporting documentation.

These changes will be included in a future FSAR amendment and should also be reflected in;the CPSES. Unit 1 Technical Specification'when issued.

In order to' facilitate NRC staff review of these changes, information related

.to the FSAR change-(Enclosure 1) is organized as.follows:

1.

' Draft revised FSAR pages, with changed portions indicated by a bar' in the margin (denoted as " draft"), as they are to appear in a

' future amendment (additional pages immediately preceding and/or.

following the revised pages are provided if needed to understand the change).

-2.

A line-by-line description / justification of each revised FSAR

. item.

3.

A copy of related SER/SSER sections.

4.

The bold / overstrike version of the revised FSAR pcges referenced.

by the description / justification for each item identified above.

The' bold / overstrike version facilitates review of the revisions by highlighting each addition of new text in bold type font and overstriking with a slash (/) the portion of the text that is deleted.

In some cases, where the bold overstrike versien is unavailable, a hand marked-up version will be provided.

8908010006 890725 i j' PDR ADOCK'05000445 A

PDR w0 North Olive Street LB 81 Dallas, Taas 75201

___2-___

'i'

'TXX-89515

' July 25, 1989 Page 2 of 2'.

Information.related to the Technical Specification char,ye (Enclosure 2) is organized as follows:

1.

Draft revised Technical Specification pages, with changed port!ons indicated by a bar in the margin (denoted as " draft").

2.

A description / justification of the revised Technical Specification.

3.

~ A hand marked-up version of 'the Final Draft of the CP'SES. Unit 1 Technical Specifications as certified on April 14, 1989.

TV Electric requests that.the NRC perform an expedited review of the above FSAR' changes and. inform us as to their acceptability.

Sincerely, ty17h*

>h' William J. Cahill, Jr.

By:

M 1

Rog'er D'. Wal ker Manager.. Nuclear Licensing VPC/vpc.

Enclosures' c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) l l

~ J ;' '

+

JJ

, to TXX-89515-July-25, 1989

~Page 1 of 11 Advance FSAR Change Related to Station Service Water-Recirculation Valves and Supporting Documentation

Item 1 Draft Revised FSAR Pages pp. 2, 3 and 4 Iter 2-Line-by-line Description / Justification pp. 5 and 6 for FSAR Change

' Item 3 Related SER/SSER Pages

'pp. 7 and 8 Item'4 Bold / overstrike version of the pp. 9. 10 and 11-

.FSAR pages l

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Enclosure I to TXX-89515 July 25,,1989 L Pagd 2 of 11' l-I L

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Enclosure 1 to TXX-89515 July'25, 1989 CPSES/FSAR Page 3: of 11' 0032.17 66 safety-related instrumentation described in Section 7.5 (Table 7.5-7), the instruments and monitoring equipment are not required for safety.

Local indicators, plant computer i

11 points, plant annunciator and bypass monitoring systems, are not required for safety.

0032.17 11 1.

Control of System Components 0032.17 11 The SSW System is designed to operate with a constant DRAFT system pressure during normal operation.

Pump recirculation valves are provided to maintain pump minimum flow under abnormal system conditions.

0032.17 11 m.

Monitoring of System Operation

.0032.17 66 The SSW System is provided with monitoring instrumentation as described in Section 7.5.

In addition, each component 11 is provided with local temperature indication.

Sufficient local flow indication is provided to allow flow balancing of the system.

0032.17 11 Each power operated valve is supplied with a control switch and position indicating lights in the Control Room.

0032.17 11 Radiation monitors are provided with readout in the Control Room for each CCW Heat Exchanger discharge line.

0032.17

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Sequencing 0032.17 11 The sequencing of SSW pumps upon loss of offsite power concurrent with a LOCA is shown in Tables 8.3-1A and 8.3-IB.

Draft Version 7.3-42

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_ - _ - t'o TXX-89515 CPSES FSAR AMENDMENT 77-NJuiv25,,1989;

DETAILED DESCRIPTION Page-1.

Page' 5 of IT T FSAR'Page (as amended)-

Group Descriittign l-Table 3.98-10 2

See Sheet No(s):16 Station Service Water Pump Recirculation Valves l

Revision:

l' Revises FSAR. Table 3.9B-10 (Sheet 16) to include

- Station Service Water (SSW) pump recirculation.line control valves PV-4252 and PV-4253. Test Deficiency Deport (TDR) 5688 previously identified damage to the recirculation control valves caused by water hammer.

Consequently, removal of the recirculation lines was recommended to alleviate the water hammer prcblem.

Subsequent testing of the Station Service Water pump recirculation valves and assnciated piping has eliminated the necessity for component removal.

FSAR Change Request Number: 89-535.1 Related SER Section: 9.2.1 SER/SSER Impact: No

,:7.3 3 Instrumentation and Controls - Station Service Water Control of System Components Correction:

Clariffes purpose of SSW pump recirculation valves, FSAR Change Request Number: 09-535.2 Related SER Section: 9.2.1 SER/SSER Impact: No Tab h 7.3-4 2

See Sheet No(s):14 hstrumentation and Controls - Safety Injection Actuated Equipment List Revision:

Revises FSAR Table 7.3-4 (Sheet 14) to include Station Service Water (SSW). pump recirculation control valves PV-4252 and PV-4253.

(See additional just;. cation provided for SA-89-535.1)

FSAP Change Request Number: 89-535.3 Relrited SER Section: 9.2.1 SER/SSER Impact: Ho Figure 9.2-1 2

See Sheet No(s):1 of 3 Instrundntation and Controls - Station Service Water

System Description

Figure 9.2-1 (Sheet 1 of 3) Station Service Water System Flow Diagram Revision:

Revise Figure 9.2-1 (Sheet 1 of 3) to include Station Service Water System recirculation line control valves (PV-4252 & PV-4253), associated piping (10-SW-1-150-3

&10-SW-1-037-150-3), and orifices; but delete

,=

Enclosure;l' to,TXX-89515

CPSES FSAR AMENDMENT 77 g(($f7,-

I 9 4 DETAILED DESCRIPTION Page 2 iL

.s.

L, FSAR Page:

(as amended)

Group Deinriotion

-l respective blind flanges.

(See additional justification from SA-89-535.1 t

FSAR Change Request Number: 89-535.4 Related SER Section: 9.2.1

' ~

SER/SSERImpact: No 1

i A

1

._1___...

Enclosure'I to TXX-39515

- July 25,1989 Pags To'f 11'

-establish the extent to which heavy load ' handling operations satisfy the guide-l.

lines of NUREG-0612.

Further, the staff asked t w applicant to identify the

. changes and modifications that would be required to fully satisfy these guidelines.

Because this effort will extend over some period ~of time, certain measures that could be readily implemented, such as identifying safe load paths deve<1oping procedures, operator-training and crane inspections, and testing a,nd maintenance, were separately identified in Enclosure 2 to the December 22, 1960 generic letter.

The staff will require the applicant to implement these interim measures before the final implementation of NUREG-0612 guidelines.and before the issuance of Comanche Peak Operating License.

The s".aff will report on the resolution of this matter in a supplement to this report.

The staff finds that the fuel' hand 11ru system -is in conformance with the require-monts of GDC 2 and 61 as they relate <;a protectiots against natural phenomena and safe fuel handling and to the guidelines of Regulatory Guides 1.13 and 1.29 with respect to overhead crane interlock and ' main +,aining plant safety in a seismic event.

Based on the above and subject to the implementation of the interim measures in Enclosure 2 of the December 22, dequate and, therefore 1980 generic letter, the staff concludes that the fuel handifty system'is a subject to resolution of the sauter of NUREG;0612 described above., acceptable, 9.2 Water Systems 9.2.1 Station Service Water System The station service water system supplies cooling water to the plant from the -

safe-shutdown impoundment, which is the ultimate heat sink discussed in Sec-tion 9.2.5 of this report.

cooling water heat exchangers, eseThe station service water system cools the compone ncy diesel generators lube oil coolers forthesafetyinjectionandcentri.ugalchargingpumps,an,d?>earingcoolers J

for the containment spray pumps.

All of these cooling loads are required for plant shutdown and/or for mitigating the effects of a LOCA; no other cooling loads are serviced by this system.

The station service water system can also be used as a backup water supply for the auxiliary feedwater system and the fire protection booster pumps.

The station service water system consists of two separate and independent full-capacity trains for each reactor unit; cross-connections are provided between trains of the same unit for flexibility.

Cross-connections between units are isolated by two locked valves in series.

which can be supplied from a separate emergency diesel bus.Each train has one full-c One train is in operation at all times durine norsal operation to supply cooling for one train l

of the essential heat loads indicated above.

If the operating sintion service water pinp trips, the other pump automatically starts and is operative within 60 see to cool'the redundant train of essential equipment.

During normal unit cooldown and the post-LOCA recirculation phase both trains are normally used

)

although only one train need be operath:t.-During the post-LOCA injection phase,

)

only ono station service water system train is used.

Adequate isolation from nonessential systems is provided by normally shut Quality Group C, seismic Category I valves.

The design of the station service water system ensures that system function is not lost assuming a single active component failure coincident 1

with loss of offsite power.

Thus, the requirements of GDC 5 and 44 are met.

I 9-8

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

._ to TXX-89515 July 26,1989,

i 1

Page 8 of 11' l

The station service water system is designed to Quality Group C and seismic Category I requirements.

Connections to other nonessential systems are isolated by Quality Group C seismic Category I valves that are normally shut.

The valves to the fire protection system are locked closed. Components of the system are

.j located in seismic Category I structures, which provide protection against tornadoes, tornado generated missiles, and flooding (see Sections 3.4.1 and 3.5.2 of this SER).

Station service water system piping between the pumphouse and the auxiliary building and between the auxiliary building and the safe-shutdown impoundment is seismic Category I and is buried to protect the piping from tornado missiles.

Pump motors, valve operators, and controls are located above the postulated level of the probable maximum flood in the seismic Category I pumphouse, which also proviries tornado and tornado-missile protection for system components.

Thus, the requirements of GDC 2 and the guidelines of Regulatory Guides 1.26, 1.29, 3. 102, and 1.117 are met.

l i

l-The station service water systes is separated'from the effects of internally generated missiles and high-and moderate-energy pipe breaks (refer to Sec-tions 3.5.1.1 and 3.6.1 of this SER). Pumps and pump motors inside the pump-house are physically separated fmm each other by walls designed to preclude coincident damage to redundant equipment from pipe rupture, equipment failure, and missile generation.

Thus, the requirements of GDC 4 and the guidelines of BTP AS8 3-1 are met.

j The station service water system operates during normal operation; therefore, l

it does not require additional periodic tests and inspection of the system periodically to enable testing and ispection. peration are interchanged safety functions.

However, the components in o Recirculation loops are provided around the pumps for testing of these components.

Valves, controls, and instrumentation are also tested at regular intervals. The perfomance of the I

heat exchangers is monitored periodically to detect excessive scale formation.

The system s located in accessible areas to permit inservice inspection as required. Thus, the requirements of GDC 45 and 46 are met, i

Based on its review, the stsif concludes that the station service water systas I

meats (1) the requirements cf GDC 2,fssiles, and environmental effects sharing l

4, 5, 44, 45, and 46 with respect to pro-taction against natural phenomena, a i

ofessentialsystems;decayheatremovalcapability;interviceinspectIonand functional testing; and (2) the guidelines of Regulatory Guides 1.26, 1.29, 1.102 and 1.117 and BTP A$8 3-1 with respect to the systems quality group and 1

seismic classification and protection against flood, tornado-missile, and pipe break effect. Therefore, it is acceptable.

9.2.2 Reaci.orAuxiliariesCoolingWaterSystem(ComponentCoolingWaterSystem)

The component cooling water system (CCW5) >covides cooling water to various plant components and rejects the heat to tw station service water system (refer to Section 9.2.1 of this SER). The CCWS is an intermediate cooling loop between radioactive or potentially radioactive heat sources and the ultimate heat sink water. The CCWS provides cooling to the following essential plant auxiliary components dcring all modes of operetion including postulat.ed accidents (they are required for safe shutdown and accident mitigation):

containment sp. ray pump heat exchangers, residual heat removal (RNR) pump seal coolers, safety-chilled-water system condensers, and control room air conditioning condensers.

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r r

r e

v 7

C v 7 v v v 7

e u

w u

r r

r a r o v o s r

I x

x t

r r

F E E E u a E

w 7 s s s s lll lF l

L Enclosure 1 to IXX-89515^

E July.25., 1989 CPSES/FSAR Pagy I'0:o'f 11

C's12.17 6%

safety-related instrumentation described in Section 7.5 (Table 7.5-7), the instruments and monitoring equipment are not required for safety.

Local indicators.. plant computer 11 points, plant annunciator and bypass monitoring systems, are not required for safety.

0032.17 11 1.

Control of System Components 0032.17 11 The SSW System is designed to operate with a constant system pressure during normal operation. Pump recirculation valves are provided to maintain pump minimum flow distMd/dd Mddddt p/didd/d under abnormal s3 stem conditions.

0032.17 11 m.

Monitoring of System Operation 0032.17 66 The SSW System is provided with monitoring instrumentation as described in Section 7.5.

In addition, each component 11 is provided with local temperature inoication.

Sufficient i

local flow indication is provided to allow flow balancing of the system.

0032.17 11 Each power operated valve is supplied with a control switch and position indicating lights in the Control Room.

j i

0032.17 j

11 Radiation arsnitors are provided with readout in the Control

)

Room for each CCW Heat Exchanger discharge line.

0032.17 11 n.

Sequencing 0032.17 11 The sequencing *of SSW pumps upon loss of offsite power concurrent with a LOCA is shown in Tables 8.3-1A and 8.3-18.

7.3-42

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1..

. to TXXr89515 July 25,.1989 Page,1 of.4 l'

Advance Technical Specification Changes Related to f

Station Service Water Recirculation Valves and Supporting Documentation Item i Draft Revised Technical Specification

-p2 Pages Item 2 Description / Justifications of p3 Technical Specification Changes

' Item 3

. Mark-up of Certified Technical p4 Specifications

= _ - _ _ _

Enclosuro 2--to TXX-89515-

) July 25,,2989.

y-Page:2to7E4

. PLANT SYSTEMS I/4.7.4 ' STATION SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION l

3.7.4 At least two independent station service water loops shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

l

'With only one station' service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at'least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE0VIREMENTS

-4.7.4 Each station service water loop shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve e

(manual, power-operated, or automatic). servicing safety-related equipment that is not locked, sealed, or otherwise secured in position is in its correct position; and b.

- At least once per 18 months during shutdown, by verifying F

that:

1)

Each automatic valve servicing safety-related equipment F

actuates to its correct position on a safety injection test signal, and 2)

Each station service water pump starts automatically on F

a Safety Injection test signal.

COMANCHE PEAK - UNIT 1 3/4 7-14 DRAFT

= - - - - - - - - - - - - - -

_ to.TXX-89515

~

Jul y, 25. 1989.

CPSES TS REVISION F Page 3 of 4 "'

DETAILED DESCRIPTION Page1jl TS Pase Group Description

.3/4.7.4-14 2

Revision:

Adding the surveillance requirement to test each automatic valve servicing safety-related equipment that.

is actuated by a safety injection signal. This change returns T/S 3/4.7.4 back to the original Standard Technical Specification wording since the design modification previously indicated is no longer required. Successful testing of the Station Service Water recirculation valves and associated piping has been conducted which nullified the necessity for component removal.

TS Change Request Number: TS-89-089 Related SER Section: 9 '. 2.1 SER/SSER Impact: No

Myp'o.WS.

v uw w v

. ? h SYSTEMS Page 3f4.7.4 STATION SERVfCE WATER SYSTEM LIMITING CONDITION IOR OPERATION i

'I 3.7.4 At least two independent service water loops shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION-With only one service water loop OPERA 8LE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.4 Each service water loop shall be demonstrated OPERA 8LE:

At least once per 31 days by verifying that each valve (manual, a.

power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position is in its correct position; and b.

At least once per 18 months during shutdown, by verifying tha[

73 I) 1 r ch nt n :t;; ;;1y; ;;7,;;;,4 ;;;;; p s-t e :;f g a; :::.;;,,.-

g'p075 a

te ite :; r;;t ;;;;itien.6. as, ii :sjee;ter +==+

Maal eaW

([SafetyInjectiontestsignal.

ach station service water pump starts automatically on a STET Q EAcu Amo*Asse wave seevsemc sue, t-snuico e avsem eut Ae., vase s To s-rs coteeren Fe smew ou TS-A swew bac.,ww es, sscwAs.,*we 36 3,1 6 A t u vtAnsow SetNsce wArtet 9v% e vtAm. r 5 Tape,w L Jeessew AvioxA'sscAt.m ew A,

ve r1 swwat, COMANCHE PEAK - UNIT 1 3/4 7-14

l....

--

ML20247K599

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