ML20137W584

Forwards Info Re Valve Classifications & Testing Requirements for Feedwater Lines.Withdraws 851212 Exemption Request 3.Marked-up Revs to FSAR & Tech Specs Encl

ML20137W584
Person / Time
Site:	Hope Creek
Issue date:	02/18/1986
From:	Corbin McNeil Public Service Enterprise Group
To:	Adensam E Office of Nuclear Reactor Regulation
References
NUDOCS 8602200229
Download: ML20137W584 (23)

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e Pubhc Service Electric and Gas Company Carbin A. McNeill, Jr.

Pubhc Serwce Electnc and Gas Company P O Box 226. Hancocks Bndge.NJ 08038 609 339-4800 Vice Presiaent-Nuclear FEB 23 ges Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:

Ms. Elinor Adensam, Director Project Directorate 3 Division of BWR Licensing r

Dear Ms. Adensam:

FEEDWATER VALVE CLASSIFICATION AND TESTING HOPE CREEK GENERATING STATION i

DOCKET NO. 50-354 As a result of discussions with the Nuclear Regulatory Commission (NRC) Statf, Public Service Electric and Gas Company (PSE&G) is providing specific information to detail the valve classifications and testing requirements for the feedwater lines.

In summary, the major points of discussion include:

1.

Classification of the third check valve in each feedwater I

line ( AE-V001 and AE-V005) as a containment isolation l

valve and therefore, inclusion of these valves in FSAR Table 6.2-16 and Technical Specification Table 3.6.3-1.

i 2.

Appendix J Type C testing of these third valves with water at 1.10 Pa and identification of the leakage criteria in i

Technical Specification 3.4.6.1.

I 3.

Inclusion of the Appendix J Type C leakage for the first two check valves in each feedwater line ( A E-V00 2, A E-V00 3, and AE-V006, AE-V007) in the 0.60 La acceptance criteria of Appendix J.

8602200229 860219 ~

l PDR ADOCM 05000354 i

A P,DR I \\

Director of Nuclear 2

Reactor Regulation With regard to the first point of discussion, in addition to classifying valves AE-V001 and AE-V005 as containment isolation valves, the first valve in each branch line between the second and third feedwater check valves will also be classified as containment isolation valves.

The lines between the second and third check valves are from the RCIC system (BD-V005), the HPCI system (BJ-V059) and the RWCU system (AE-V021).

Hence, these valves, as well as those in the feedwater lines, will be included in FSAR Tables 6.2-16 and 24 (see Attachment 1) and Technical Specification Table 3.6.3-1 (see Attachment 2).

With regard to the second point of discussion, the additional containment isolation valves identified above form the long-term containment boundary for the feedwater system by establishing a water seal on the third feedwater check valves.

Since the leakage past valves BD-V005, BJ-V059 and AE-V021 will be into the RCIC, HPCI and RWCU systems, respectively, which are seismically qualified, water-filled, closed systems outside containment, there is no requirement to identify their specific leakage in the Technical Specifications.

Therefore, leakage through the valves which form the long term seal boundary of the feedwater lines will be limited to 10 gpm as specified in the Technical Specifications (see Attachment 2).

Finally, regarding the third point of discussion, PSE&G previously submitted six 10CFR50 Appendix J Exemption Requests (letter from C.A.

McNeill, Jr. to E.

Adensam on December 12, 1985) in which Exemption Request 3 discussed feedwater valves AE-V002, AE-V003, AE-V006 and AE-V007.

Specifically, deviation from paragraph III.C.3, which requires all penetrations and valves subject to Type B and C tests (except those sealed with fluid from a seal system) to have their combined leakage maintained less than 0.60 La, was requested on the basis of the response to Safety Evaluation Report (SER)

Confirmatory Item #13 (Short-Term Feedwater System Analysis).

However, the staff has concluded that since valve stem leakage may occur from the air-operators on valves AE-V002 and AE-V006 during the short-te rm feedwater system line-up, the leakage determined from the Type C air test on valves AE-V002, AE-V003, AE-V006 and AE-V007, should be appropriately included in the 0.60 La criteria.

PSE&G will modify the Technical

Director of Nuclear

?

4 Reactor Regulation Specifications accordingly (see Attachment 2).

As a result, Exemption Request 3, transmitted in the December 12, 1985 PSE&G letter to NRC, is withdrawn.

Finally, Attachment 1 to this letter reflects the necessary revisions to the FSAR in support of the items summarized above while Attachment 2 provides a draft copy of the necessary revisions to the Technical Specifications.

I Should you have any questions on the subject filing, please do not hesitate to call us, Sincerely, hl

'~

Attachments (2)

C D.H.

Wagner USNRC Licensing Project Manager R.W.

Borchardt USNRC Senior Resident Inspector

9:

e ATTACHMENT 1

HCGS FSAR 01/86 The MSIV sealing system is divided into two independent subsystems.

The inboard subsystem maintains a seal between the two MSIVs, and the redundant outboard subsystem maintains a seal between the outboard MSIV and the MSSV.

Sealing is accomplished by maintaining a higher pressure in the main steam lines than in the containment.

The operation of the MSIV sealing system is discussed.in Section 6.7.

A main steam drain line connects to the main steam lines between the two MSIVs on each main steam line outside of the primary containment.

Isolation of this line is.provided by the inboard MSIV and by a motor-operated globe valve in the drain line that automatically closes upon receipt of a containment isolation signal.

6.2.4.3.1.2 Feedwater Lines The portion of the feedwater system that forms part of the RCPB 1sE-2WDwHag and penetrates the primary containment has threetvalves(

The U4F nounto first valve, a check valve, is classified as a containment isolation valve and located inside the primary containment.

The second valve, a positive-acting check valve, is classified as a containment isolation valve and located outside the primary containment as close as possible to the primary containment penetration.

Upon a loss of water flow into the RPV, these valves close as normal check valves, and, in addition, the main control room operator can assist in starting the outboard valve closure by sending a signal to open two fail-open solenoid valves arranged in parallel, releasing air pressure from the operator cylinder.

If a break occurs in the feedwater line, the two containment isolation valves prevent significant loss of inventory and offer immediate isolation.

During the postulated LOCA, it is desirable to maintain reactor coolant makeup from all sources of supply.

For this reason, the feedwater containment isolition valves do not automatically close on a primary containment isolation signal.

A third valve in the feedwater line is a motor-operated check valve located outside primary containmentpand is capable of being remotely closed from the main control room.

This valve provides redundant isolation and long-term leakage protection upon operator judgment that continued makeup through the feedwater line is unavailable.

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WLVG 6.2-45 Amendment 14

HCGS FSAR 01/86 C*

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After observing indication of low feedwater flow, the operator may close the third valve within 20 minutes after a postulated LOCA.

WAIAftENT IWAlkW[

In addition to the third valve, there arefvalves on the high l

pressure coolant injection (HPCI) and reactor core isolation cooling (RCIC) discharge lines, and on the reactor water cleanup system (RWCU) return lines that connect to the feedwater lines between the4outside containment isolation valves.:nd the third (

tv:1:0.

Those valves can be closed by operator action from the main control room. f See Section 5.4.9 for a further discussion of the design of the main steam lines and the feedwater lines.

6.2.4.3.1.3 Residual Heat Removal Shutdown Cooling Suction Line The residual heat removal (RHR) shutdown cooling suction line penetrates primary containment and taps into one of the two recirculation loops.

Isolation is provided by two normally closed motor-operated gate valves

6. hat are interlocked closed by

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a reactor high pressure signal during normal operation and are

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maintained closed during an accident by a low water level isolation signal.

One containment isolation valve is located inside primary containment, and the second valve is located outside primary containment.

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HCGS FSAR 01/86 t

instrumentation, and those lines containing excess flow check valves, will have their leak tightness verified during the Type A test.

These instrument lines were designed on an "other defined basis" of GDC 56 (see Sections 6.2.4.3.2.21 and 6.2.4.3.5) and hence are not capable of being Type C tested.

Instrument lines are provided with a manual isolation valve outside containment for greater reliability.

The systems they serve are closed systems outside containment, thereby providing reliable boundaries against containment leakage.

The Type A test that.

will be conducted on these instrument lines serves to adequately assure integrity.

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HCGS FSAR 01/86 9 leakage of radicactive cent-am-inants-tar-ough the i eclat-ion-valves-9 during-appro::imate1y a ' - heu r-per4ed-af-ter-the-asei den t,

i4e.,

c-until the water ceal ic reestab14-shedHhurrr-no-bypass--leakage-of-9 the f eedwater cyster is expected to occur.

Y 0 A Typ-; C watcr test will bc perforncd ci

1. i OPa on the-outermoeb-mchecP valve and its leakase-included with all other-hrcstatically tected-va-ivec.

Once tha -water real-syster is--

9 activated, any external leakage-would-be-through thic boundary 9unlua via tha een1 fluid.

The Type C uater-tect will be 7 suf ficient tc assur-e-proper-1eakage-ver-i-f-ieaticn.

Alec 3ec

? Sectionc 5.4.0, 6.2.3.2.3, and 6.2.4.3.1.2.

6.2.4.4.4 Main Steam Isolation Valves l

10CFR50, Appendix J, Paragraph III.C.2(b) requires valves that are sealed with fluid from a system to be pressurized with that fluid to a test pressure not less than 1.10Pa.

The main steam isolation valves (MSIVs) will be leakrate tested by pressurizing between the inboard and outboard MSIVs and between the outboard MSIV and the main steam stop valve (MSSV) at a reduced pressure of 5 psig.

The main steam isolation valve sealing system (MSIVSS) (see Section 6.7) is initiated manually approximately 20 minutes after the onset of a LOCA and only after main steam line pressure is below 20 psig.

This latter restriction is necessary since the MSIVSS maintains the pressure between the valves at reactor vessel pressure plus 5 psig and because a back pressure differential of 25 psi will lift the HSIV disk, unseating the valve.

Therefore, testing of the two MSIVs simultaneously, between the valves, at 1.10Pa would lift the disk at the inboard valve and result in a meaningless test.

A test will be conducted at 5 psig (the seal system differential pressure) with the total observed leakage through both the outboard MSIV and the MSSV conservatively assigned to that penetration and_ limited to 11.5 scf per hour for any one main steam line.

6.2.4.4.5 Containment Air Locks l

10CFR50, Appendix J, Paragraph III.D.2(b)(ii) requires air locks that have been used during periods when containment integrity is not required by the plant's Technical Specifications to be tested at the end of such periods at not less than Pa.

In addition to the 6-month intervals, air locks will be subjected to an overall air lock leakage integrity test only when maintenance on the air lock has been performed that could affect the air lock's sealing capability.

This is an exemption to Paragraph III.D.2(b)(ii) 6.2-62c Amendment 14 m

HCGS FSAR 8/84

(.

All valves that are exposed to the primary containment atmosphere

(

after a DBA are tested with air or nitrogen at primary containment peak accident pressure, P,, as defined in Table 6.2-22.

All valves in lines designed to be filled with a liquid for a minimum of 30 days after a DBA are leakage-rate-tested with the 1

same liquid at a minimum pressure of P -

l a

Liquid leakage is not converted to equivalent air leakage, or added to the Type C testing total, but is reported separately as

" liquid leakage" and included in the Technical Specifications.

All the valves tested with liquid are identified in Table 6.2-24.

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The Total Allowable Leakage acceptance criteria for penetrations and isolation valves subject to Type B and C tests are given in Chapter 16.

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6.2.6.4 Schedulino and Reportino of Periodic Tests

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The periodic leakage rate test schedules for Type A, B, and C 4

testing are given in Chapter 16.

Type B and C tests are performed prior to initial criticality and periodically thereafter, during shutdown periods or normal plant operations.

The preoperational Type A test follows the preoperational ASME Section III pressure test.

A primary containment isolation system functional test and Type B and C leakage tests are completed prior to the preoperational Type A test.

The procedure for reporting test results is given in Chapter 16.

6.2-94 Amendment 7

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I' Containment isolation of the feedwater lines. represents a unique situation which requires a combination of air and water testing and therefore merits further' discussion.

During the short-term feedwater system line-up, isolation of the feedwater-lines is provided by valves AE-V002, AE-V003, AE-V006 and AE-V007 and the water seal upstream of the third feedwater heaters (see Section 6.2.3.2.3).

Hence, a Type C air test will be performed on these valves with their leakage appropriately included in the 0.60 La criteria.

During the long-term feedwater system line-up, isolation of the feedwater lines is provided by a water seal on the third feedwater check valves, AE-V001, and AE-V005.

Identifi-cation of these valves as containment isolation valves requires a similar classification for the first valve in each branch line between the second and third feedwater check valves, BD-V005, BJ-V059, and AE-V021.

Since the

-leakage past these valves will be into the RCIC, HPCI and l

RWCU systems, respectively, which arc seismically qualified, l

water-filled, closed systems outside containment, there is no requirement to identify their specific leakage in the Technical Specifications.

However, leakage through the valves which form the long-term seal boundary of the feedwater lines (i.e., AE-V001, AE-V005, AE-V021, BD-V005 and BJ-V059) will be determined by a Type C water test and will be limited to 10 gpm as specified in the Technical Specifications.

Since these valves are scaled with water,

[

the leakage determined from their Type C test need not l

be included in the 0.60 La criteria per 10CFR50 Appendix l

J paragraph III.C.3.

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Page 33 of 33 HCGS - FSAR TABLE 6.2-16 (Cont'd)

(9)

Post-Accident valve position (open or closed) is the position during the initial 10 minutes after an accident.

(10) Shutdown valve position (open or closed) is the position beyond the initial 10 minutes after an accident.

(11) Tne ESF System designation is applied to primary containment penetrations that are a part of an ESF System and where that part of the system provides or aids a function that is characteristic of an ESF System.

Although re-activity control systems are not usually characterized as being ESF Systems, in this table reactivity control system penetrations are given the ESF system designation.

(12) Manual indicates remote manual initiation of valve CMsure from the main control room.

(13) The secondary mode of operation is AC motor.

(14) Operation is by local manual hand wheel.

(15) Deleted l

(16) The valve actuator is only used to exercise the valve disk during testing.

(

(17) This is a spring loaded piston-actuated check valve.

When the valve operator is in the open position, it will not resist valve closure, in this position the valve will function much like a simple check valve.

In the de-energized position, the spring-loaded piston will assist in closing the valve.

However, it will not close the valve against flow from the normal direction.

(18) The isolation signals for his valve are generated to provide proper system alignment for ECCS injection.

By assuming the ECCS injection position, the valves also provide a containment isolation function.

(tci)

Tee vac*s Ape uso tarru n'R % A w e:x ue s cc Pa. 4Jo THe lenkpGs 15 incuax=O in Tue o.Mla. cRcrePA cv Autescox 3 (ao) Tie:s t4tvss hat Tas tauuey r<A Tus tees-Twa-i sea. cr THe FEEL %#Tt96 Un6S A@ HOX6 Aki TGSTED lorrn v> amp AT

l. IO Pr. l.EAVMs From Au VN seS l3 LJmnel:> TO }6 GC+t,

i

?

l T1002775 Anendment 14, 01/86

A, s

r s

RCt3 FSAR 07/M5 l

TABLE 6.2-24 Page 1 of 17 l

CONTAINMENT PENETPATIDMS/IS3LATIDM VALVE COMPLIANCE WITH 10 CFR 50, APPENDIX J Inboard Isolation outboar$ Isolation Penet PEID Test Barrier Description /

Barrier Description /

Jeuzber Number

System Description

Type, Valve Number Notes Valve Number Notes P 1A M-41 Main steam line A AB V028 6

AB-V032, AB-V059, 6

FP-V010 P 19 M-41 Main steam line B AB V029 6

AB-V033, AB-V060 6

FP-V009 P 1C M-41 Main steam line C AB V030 6

AB-V034, AB-V061, 6

FP-V008 P 1D M-41 Main steam line D AB-V0 31 6

AB-V035, AR-V062 6

FP-V007 P 2A M-41 Feedwater C

AE-V003 AE-V00 2, Bo-w:cs-AG-6tx>l l

E-Voze, P 2B M-41 Feedwater C

AE-V007 AE-V006, AE-l hG-1bli, BT-VC P3 M-51 RRR shutdown cooling C

BC-V071 BO-V164 14 suction A,C PC-PSV-4425 7,17 P 4A M-51 RRR shutdown cooling return C

PC-V014 PO-v013 C

PC-V118 P es M-51 RHR shutdown cooling return C

BC-Vill 80-V110 C

BC-V117 P 5A M-52 Core spray to reactor C

B E-V002 BE-V003 l

C BE-V072 P 55 M-52 Core spray to reactor C

BE-V006 BE-V007 C

B E-V 071 BJ-V001 P 6A M-51 LPCI C

BC-V005, BC-V122 B0-V004 l

P 6B LPCI C

BC-V017, BC-v12G PC-V016 P 6C LPCI C

BC-V114, BC-V119 PO-V113 l

P 6D LPCI C

PC-7102, BC-V121 80-V101 l

P7 M-55 RPCI turbine C

FD-V001 9

TD-V002 e

stean supply FD-V051 Amendment 11 3

O BD V046

+M

(

PRIMARY rq BD-V013 l '

RPV CONTAINMENT

1. BD V047 1 P J m i r AE-V015 y

j FROM

- m

-- ;g,g-

1. AE-V016 BD V005 (TYPICAL AO FOR HPCI)

O M

%, )>

h

)>

FEEDWATER v

w

---

tine AE V0os AE V003 AE-V002 AE V001

\\

3 -

3 p l P-2A l k

AE V139 J

AE V020 4

r - a AE V140 ]

EVm 1

P J

L i AE V019 i

L J

AE V138 ISOLATION VALVES AE-V127 lAE V141 y

s P-2A P.28

' ['; ((]

AE V003 AE V007 AE.V142 AE V021 AE V002 l AE V006 fD AE V021 AE V021 i > BG V071 TO THE OTHER FEEDWATER LINE J i BD V005 BJ V059 7 7 AE V001 l AE V005 l [ BG B072 J k TEST / DRAIN VALVES i

AE V128 l

P-2A P 28 DETAll 2 l

AE V020 AE V018 AE V019 l AE V017 M

l AE VOIS l AE V014

,,,,[,,,,,,,,,,,!,,,,,,,,,

)!,,,,

.f AE V013 AE V008

[**.,

AE =V005 AE V016 BG v072 l rROM i

L.S.2.9.,

1 BG V071 RWCU AE V075 AE V074.-

HOPE CREEK BD V047 ! BJ V018 CENER ATING STAflON BD Vodo l BJ V017

1. ' "^ ^

U" AE V001 1 AE V008 AE V127 j AE V128 FEEDWATER LINES

• (SEE LEGEND) 7launE 6 2 2a SHEL T 2 OF 48 Amendment 14,01/86

I e

ATTACHMENT 2

Ic n r p,-

r. - -- f

\\

CONTAINMENT SYSTEMS 1 1.w o.","-.1 ',- ),

a o

PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION

3. 6.1. 2 Primary containment leakage rates shall be limited to:

An overall integrated leakage rate of less than or equal to L,481 a.

, 0.5 percent by weignt of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,,

psig.

b.

A combined leakage rate of less than or equal to 0.60 L for all VAUFS U)#/C#

"'"'t"*ti "5 *"O

• II ** I" Ii 5 t*d i n Tabl e 3. 6. 3-1, ex2eo t for mai n

\\

N RK?H THF B2/NI427 steam line isolation valves"fandivalves which are hydrostatically N

tested per Table 3.6.3-1, subject to Type B and C tests when M R 716 M 7 &Il pressurized to P, 48.1 psig.

• Less than or eq al to 11.5 scf per hour for any one main steam line c.

NVM l16 through the isolation valves when tested at 5 psig (seal system.1P).

/e.

A combined leakage rate of less than or equal to 10 gpm for all :

M g

A containment isolation valves in hydrostatically tested lines in 7,33, 3,s 3 1,nien pen,te,t, sn, primary contain,,nt, onen test.e at 1.10 Pa, 52.9 psig.

b APPLICABILITY: When PRIMARY CONTAINMENT INTEGRITY is required per

-(

Specification 3.6.1.1.

ACTION:

With:

The measured overall integrated primary containment leakage rate a.

exceeding 0.75 L, or b.

The measured combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves",tand# valves which are hydrostatically tested per Table 3.6.3-1, N N subject to Type 8 and C tests exceeding 0.60 L,, or The measured leakage rate exceeding 11.5 scf per hour for any one c.

gg main steam line isolation valves, or g

g8 The measured combined leaxage rate for all/ containment isolation valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment exceeding 10 gpm, restore:

a.

The overall integrated leakage rate (s) to less than or equal to 0.75 L,, and

" Exemption to Appendix J" of 10 CFR 50.

(.,>

m ;. w HOPE CREEK 3/4 6-2

I-h~.-

/"A.'f.'.3.M G y l i

CONTAINMENT SYSTEMS

- - - -- '.. I LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued)

- W1LES WHICH '

The combined leakaae rate for all cenetrations and all valves listed i

b.

in Table 3.6.3-1, except for main steam line isolation valves",iand+-onee l

Nil 6[DM valves which are hydrostatically tested per Table 3.6.3-1, subject i

fBR DE LCNG-to Type B and C tests to less than or equal to 0.60 L,,

and O N6 The leakage rate to less than or equal to 11.5 scf per hour for any c.

tee one main steam line through the isolation valve (s), and g

c

_ f.

The combined leakage rate for all/ containment isolation valves in ODER j

Te hydrostatically tested lines in Table 3.6.3-1 which pentrate the i

gg primary containment to less than or equal to 10 gpm, C

prior to increasing reactor coolant system temperature above 200*F.

A SURVEILLANCE REOUIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 - 1972:

?

Three Type A Overall Integrated Containment Leakage Rate tests shall a.

be conducted at 40 + 10 month intervals during shutdown at P,,

48.1 psig, during each 10 year service period. The third test of each set shall be conducted during the shutdown for the 10 year plant t

j inservice inspection, If any periodic Type A test fails to meet 0.75 L,, the test schedule j

b.

i for subsequent Type A tests shall be reviewed and approved by the

]

Commission.

It two consecutive Type A tests fail to meet 0.75 L,,

a j

Type A test shall be perforNed at least every 18 months until two j

consecutive Type A tests meet 0.75 L,, at which time the above test schedule may be resumed.

The accuracy of each Type A test shall be verified by a supplemental c.

j test which:

i 1.

Confirms the accuracy of the test by verifying that the difference i

between the supplemental data and the Type A test data is within

0. 25 L,.

l 2.

Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.

I 3.

Requires the quantity of gas injected into the cont 41nment or bled from the containment during the supplemental test to be between 0.75 L, and 1.25 L,.

i

(

SD a0.%

i j

HOPE CREEK 3/4 6-3 f

---

-..-- -.-- n n -

INSERT A d.

A combined leakage rate of less than or equal to 10 gpm for all containment isolation valves which f orm the boundary for the long-term seal of the feedwater lines in Table 3. 6.3-1, when tested a t 1.10 Pa, 52.9 psig.

INSERT B d.

The measured combined leakage rate for all containment isolation valves which form the boundary for the long-term seal of the feedwater lines in Table 3.6.3-1 exceeding 10 gpm, or INSERT C d.

The combined leakage rate for all containment isolation valves which form the boundary for the.long-term seal of the feedwater lines in Table 3.6.3-1 to less than or equal to 10 gpm, and e n

TA8lE 3.6.3-1 (Continued) 5 i

y PRIMARY CONTAINHENT ISOLATION VALVES MAX 1 HUM N

PENETRATION ISOLATION TIME VALVC FUNCTION ANO NUMBER HUMBER (Seconds)

NOIE(S)

P&IO (b) DLO-RMS Return Isolation Valves M-25-1 Outside:

IIV-4957 (SK-V008)

JSA 45 3

llV-4981 (SK-V009)

J5A 45 3

J b.

Manual Isolation Valves i

1.

Group 21 - feedwater System (a) Fee & vater Isolation Valves M-41-1 M

Outside:

HV-R:G2B Check Valves

]

(/s-m :5 FV-F0748 (AE-V002) 2A 3

pg _

28 e

i k-F074A (AE-V006) g,, g p

3 4

(N -trc&

Group 22 - liigh Pressure Coolant Injection (llPCI) System 4.

i 1

(a) Core Spray Discharge Valve JNTERT p

Outside:

ilV-F006 (BJ-V001)

P58

_T3 4

H-55-1

-J (b) Turbine Exhaust Valve

,9]

Outside:

• • 1 i

e ilV-F071 (FO-V006)

P201 I?

• 5 H-55-1 4NST'r N'

"8 (c) IIPCI Minimum Return Line Valve (f

D J

[b a

Outside:

'O IIV-F012 (BJ-v016)

P203

-4 5

H-55-1

'd 3.

Group 23 - Reactor Core Isolation Cooling (RCIC) System

[*

h, (a) RCIC Turhine Exhaust Valve Outside.

j IIV-F059 (FC-V005)

P207 5

H-49-1

TABLE 3.6.3-1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES 2

MAXIHtM 01 PENETRATION ISOLATION TIME

^

VALVE FUNCTION ANO NilHBER NUMBER (Seconds)

ET_E(_S}

P&Ill Outside:

1 (b) RCIC Pump Suction Isolation Valve IIV-F031 (BD-V003)

P208 5

H-49-1 i

Outside:

(c) RCIC Minimum Return Line Isolation Valve SV-F019 (BO-V007)

P209 5

H-49-1 Outside:

j (d) RCIC Vacuum Pump Discharge

]

1NS-RT HV-F060 (FC-V011)

P210 5

M-49-1 i

E

~

j!

4.

Group 25 - Core Spray System U

l (a) Core Spray injection Valves M-52-1 T

Outside:

g Loop A&C llV-V005A (DE-V007)

P5B 4

Loop B&D llV-F0058 (BE-V003)

P5A

~4 (b) Core Spray Suppression Pool Suction Valves M-52-1 Outside:

g.,

I Loop A llV-f001A (BE-V017)

P2160

J 5

Loop B IIV-F0018 (BE-V019)

P216A 5

Loop C HV-f001C (BE-V018)

P216C vi 5

Loop D llV-F001D (8E-V020)

P2168 g y3 5

f (c) Core Spray Minimum Flow Valves ff M-52-1

• • • 'j Outside:

lt '

Loop A&C llV-F031 A (BE-V035)

P217B

?.. M 5

Loop B&D IIV-F0310 (BE-V036)

P217A M

5 c2 j

(d) Core Spray injection Line Bypass Valves f]

M-52-1 Inside.

1

<a IIV-F039A (BE-V071)

P58 4

PSA 4

IIV-F0398 (BE-V072) i 4e

o i

INSERT D (d)

Feedwater Line Discharge Valve Outside:

HV-8278 (BJ-V059)

P2B 2

M-55-1 INSERT E (e)

Feedwater Line Discharge Valve Outside:

HV-F013 ( B D-V00 5 )

P2A 2

M-49-1 INSERT F (b)

Reactor Water Cleanup System Return Outside HV-F039 (AE-V021)

P2A&B 2

M-44-1

e 4

o W T: 7..

j i

d(-'

'" -~ ~'~

I TABLE 3.6.3-1 i I*d> D'

' T :'t )'./

f PRIMARY CONTAINMENT ISOLATION VALVES NOTES NOTATION 1.

Main Steam Isolation Valves are sealed with a seal system that main-tains a positive pressure of 5 PSIG above reactor pressure.

Leakage is in-leakage and is not acced to 0.60 La allowable leakage.

ComWH9)T

2. ;F::: :::r Isolation Valves are sealed with a water seal from the HPCI AND42 v

D N

paed RCIC systemt h:htica vehes er; ;;; type C teste ts evel ete f D

pch;/:::t k3;;c c:acitica.

Leewege H net ;; :d t 0.50 L: : hu: tier NY

h

h:g:.

The,-....

___. ___....., valves are tested with water stipa.

E

@ If6 b' 840-1f osig, to ensurefseal boundary will prevent by pass leakage.

W/4492 l>Nf?5 Seal boundary liquid leakage will basedd;d :: th; Typ; 0, w;ter testf 52,q 1h l^ 2 A blJlhtTED To 50 GRn.

3.

Containment Isolation Valve, Type C gas test at Pa, 48.1 psig.

Leak-age added to 0.60La allowable leakage.

4.

ECCS Isolation Valve, Type C gas test.

Leakage test to determine valve leakage condition.

Leakage is not added to 0.60La allowable leakage.

5.

Containment Isolation Valve, Type C water test at Pa, 48.1 psig a P.

Leakage added to 10 gpm allowable leakage.

6.

Containment isolation is discharge no:Ile or relief valve, leakage testea during Type A test.

7.

Drywell and suppression chammer pressure and level instrument root valves, leakage tested during Type A.

8.

Explosive shear valves (SE-V021 through SE-V025) not Type C tested.

9.

Surveillances to be performed per Specification 4.6.1.8.1.

10. All valve I.D. numbers are preceded by a numeral 1 which represents a'n Unit 1 valve.

a:

1

.(

'. ' 't 0li"3 HOPE CREEK 3/4 6-a2

.,,,.--,,,,.,v---

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-w-,-

--,,,-,a-.,

_