ML20097J054

Amend 76 to License NPF-57,adding New Note to Table 3.6.3-1 Re Isolation Valves

ML20097J054
Person / Time
Site:	Hope Creek
Issue date:	08/01/1995
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Public Service Electric & Gas Co, Atlantic City Electric Co
Shared Package
ML20097J056	List: ML20097J054 ML20097J060
References
NPF-57-A-076 NUDOCS 9602010023
Download: ML20097J054 (11)

Text

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UNITED STATES j

j NUCLEAR REGULATORY COMMISSION o

WASHINoTON, o.C. - *1 i

4, PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION MENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 License No. NPF-57 1.

The Nuclear Ragulatory Comission (the Comission or the NRC) has found that:

A.

The application for amendment filed by the Public Service Electric

& Gas Company (PSE&G) dated April 25, 1994, as supplemented July 24, 1995, complies with the standards and requirements of the i

Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; 8.

The facility will operate in conformity with the application, the i

provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance:

(1) 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 set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-57 is hereby amended to read as follows:

(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 76, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license.

PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

9602010023 950801 PDR ADOCK 05000354

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. 3.

The license am ndment is effective as of its date of issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMISSION 9h4 Jopn. Stolz, Dir'ector P o act Directorate I-2 D ision of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 1, 1995 i

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4 ATTACHMENT TO LICENSE AMENDMENT NO. 76 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert 3/4 6-20 3/4 6-20 3/4 6-21 3/4 6-21 3/4 6-29 3/4 6-29 a

3/4 6-30 3/4 6-30 3/4 6-31 3/4 6-31 3/4 6-35 3/4 6-35 3/4 6-36 3/4 6-36 3/4 6-42 3/4 6-42 eeee

TABLE 3.6.3-1 (Continued)

PRIMARY COffrAIl#8.ENT ISOLATION VALVES MAXIMUM PENETRATION ISOLATION TIME VALVE FUNCTION AND NUMBER WUMBER (Seconds)

NOTE (S) FEID (c) MSIV Sealing System Isolation Valveg M-72-1 Outside:

Line A KV-5834A (KP-V010)

PLA 45 1

Line B HV-5835A (KP-VOO9)

PIB 45 1

Line C KV-5836A (KP-V008)

PIC 45 1

Line D HV-5837A (KP-V007)

P1D 45 1

2. Group 2 - Reactor Recirculation Water Sample System (a) Reactor Pecirculation Water Sample Line Isolation Valves M-43-1 Inside:

BB-SV-4310 P17 15 3

Outside: BB-SV-4311 P17 15 3

3. Group 3 - Residual Heat Removal (RHR) System (a) RHR Suppression Pool Cooling Water

t. System Test Isolation Valves Outside:

M-51-1 Loop A: HV-F024A (BC-V124)

P212B 180 11 KV-F010A (BC-V125)

P212B 180 11 l

Outside:

Imp B : HV-F024B (BC-V028)

P212A 180 11 KV-F010B (BC-V027)

P212A 180 11 (b) RHR to Supp'ression Chamber Spray Header Isolation Valves Outside:

M-51-1 Loop A: HV-F027A (BC-V112)

P214B 75 3

Loop B: HV-F027B (BC-VOIS)

P214A 75 3

HOPE CREEK 3/4 6-20 Amendment No. 76

~ - -

TABLE 3.6.3-1 (Conti'1ed)

PRIMARY CONTAINMElfT ISOLATION VALVES MAXIMUM PENETRATION ISOLATION TIME VALVE FUNCTION AND NUMBER NUMBER (Seconds)

NOTE (S)

E11Q (c) RHR Shutdown Cooling Suction Isolation valves M-51-1 Inside: HV-F009 (BC-V071)

P3 45 3

Outside: HV-F009 (BC-V164)

P3 45 3

(d) RHR Head Spray Isola. ion Valves M-51-1 Inside: HV-F022 (BC-V021)

P10 60 3

Outside: HV-F023 (BC-V020)

P10 60 3

(e) RHR Shutdown Cooling Return Isolation Valves M-51-1 Outside:

Loop A: HV-F015A (BC-V110)

P4B 45 3

Loop B: HV-F015B (BC-V013)

P4A-45 3

4.

Group 4 - Core Spray System Outside:

(a) Core Spray Test to Suppression Pool Isolation valves M-52-1 Loop A:

HV-F015A (BE-V025)

P217B 80 11 Loop B:

HV-F015B (BE-V026)

P217A 80 11 5.

Group 5 - High Pressure Coolant Injection (HPCI) System (a) HPCI Turbine Steam Supply Isolation Valves M-55-1 Inside:

HV-F002 (FD-V001)

P7 NA 3

HV-F100 (FD-V051)

P7 NA 3

Outside: HV-F003 (FD-V002)

P7 NA 3

(1-) HPCI Pump Suction Isolation Valve M-55-1 Outside:

HV-F042 (BJ-V009)

P202 NA 11 HOPE CPEEK 3/4 6-21 Amendment No. 76 m

]

l TABLE 3.6.3-1 (Continued)

PRIMARY COFTAINMENT ISOLATION VALVES MAXIMLDt PENETRATION ISOLATION TIME VALVE FUNCTION AND NUMBER NUMBER (Seconds)

IE7TE (S)

P&ID (b) DLD-RMS Return Isolation Valves M-25-1 Outside:

HU-4957 (SK-V008)

J5A 45 3

HV-4981 (SK-V009)

J5A 45 3

B. Remote Manual icolation Valves 1.

Group 21 - Feedwater System (a)

Feedwater Isolation Valves M-41-1 Outside Check Valves HV-F032B (AE-V001)

P2A NA 2

HV-F032A (AE-V005)

P2B NA 2

(b)

Reactor Water Cleanup System Return Outside:

HV-F039 (AE-V021)

P2ALB NA 2

M-44-1 2.

Group 22 - High Pressure Coolant Injection (HPCI) System (a)

Core Snray Discharge Valve Outside:

HV-F006 (BJ-V001)

PSB NA 3

M-55-1 (b)

Turbine Exhaust Vaive Outside:

HV-F071 (FD-V006)

P201 NA 4

M-55-1 (c)

HPCI Minimum Return Line Valve Outside:

HV-F012 (BJ-V016)

P203 NA 11 M-55-1 (d)

Feedwater Line Discharge Valve Outside:

MV-8278 (BJ-V059, P2B NA 2

M-55-1 3.

Group 23 Reac* ot Core Isoletion Cooling (RCIC) System (a)

RCIC Turbine Exhaust Valve Outside:

KV-F059 (FC-VOOS)

P707 NA 4

M-49-1 HOPE CREEK 3/4 6-29 Amendment No. 76

I l

IABLE 3.6.3-1 (Continutd)

PRIMARY CONTAINMENT ISOLATION VALVES l

MAXIMUM PENETRATION ISOLATION TIME VALVE FUNCTION AND NUMBER NUMBER (Seconds)

NOTE (S)

P&ID outside:

(b)

RCIC Pump Suction Isolation Valve KV-F031 (BD-V003)

P208 NA 11 M-49-1 Outside:

(c)

RCIC Minimum Return Line Isolation Valve SV-F019 P209 NA 11 M-49-1 Outside:

(d)

RCIC Vacuum Pump Discharge KV-F060 (FC-V0ll)

P210 NA 4

M-49-1 (e)

Feedwater Line Discharge Valve outside:

KV-F013 (BD-V005)

P2A NA 2

M-49-1 4.

Group 25 - Core Spray System fa)

Core Spray injection Valves M-52-1 Outside:

Loop A&C KV-F005A (BE-V007)

PSB NA 3

Loop B&D KV-F005B (BE-V003)

PSA NA 3

(b)

Core Spray Suppression Pool Suction Valves M-52-1 Outside:

Loop A KV-F001A (BE-V017)

P216D NA 11 Loop B KV-F001B (BE-V019)-

P216A NA 11 Loop C KV-F001C (BE-V018)

P216C NA 11 Loop D KV-F001D (BE-V020)

P216B NA 11 (c)

Core Spray Minimum Flow Valves M-52-1 Outside:

Loop A&C KV-F031A (BE-V035)

P217B NA 11 Loop B&D KV-F03.B (BE-V036)

P217A NA 11 (d)

Core Spray Injection Line Bypass Valves M-52-1 Inside:

KV-F039A (BE-VO71)

PSB NA 3

KV-F039B (BE-V072)

PSA NA 3

HOPE CREEK 3/4 6-30 Amendment No. 76 4

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TABLE 3.6.3-1 (Continued)

PRIMARY N AINMENT ISOLATION VALVES MAXIMUM PENETRATION ISOLATION TIME VALVE F11NCTION AND NUMBER NUMBER (Seconds)

NOTE (S)

PGID 5.

Group 26 - Residual Heat Removal System (a)

Low Pressure Coolant Injection valves M-51-1 Outside:

Loop A: HV-F017A (BC-V113)

P6C NA 3

Loop B: HV-F017B (BC-V016)

P6B NA 3

loop C-HV-F017C (BC-V101)

P6D NA 3

Loop D: HV-F017D (BC-V004)

P6A NA 3

(b)

RHR Containment Spray Outside:

M-51-1 Loop A: HV-F021A (BC-V116)

P24B NA 3

HV-F016A (BC-V115)

P24B NA 3

Loop B: HV-F021B (BC-V019)

P24A NA 3

HV-F016B (BC-V018)

P24A NA 3

s (c)

RHR Suppression Pool Suction Outside:

M-51-1 Loop A: HV-F004A (BC-V103)

P211C NA 11 Loop B: HV-F004B (BC-V006)

P211B NA 11 Loop C: HV-F004C (BC-V098)

P211D NA 11 Loop D: HV-F004D (BC-V001)

P211A NA 11 L

(d)

RHR Minimum Flow Isolation valves Outside:

M-51-1 Loop A: HV-F007A (BC-V128)

P212B NA 11 Loop B: RV-F007B (BC-V031)

P212A NA 11 Loop C: HV-F007C (BC-V131)

P212B NA 11 Loop D: HV-FOO7D (BC-V034)

P212A NA 11 HOPE CREEK 3/4 6-31 Amendment No. 76

TABLE 3.6.3-1 (Continued)

PRIMARY COtrTAINMENT ISOLATION VALVES 1

MAXIMUM PENETRETION ISOLATION TIME VALVE FUNCTION AND NUMBER NUMBER (Second'd.

NOTE (S)

P6ID 5.

Group 35 - Breathing Air System M-15-1 Inside KG-V016 P31 NA 3

I Outside KG-V034 P31 NA 3

6.

Group 36 - TIP Purge System Inside:

Check Valve: SE-V006 P34F NA 3

M-59-1 7

Group 37 - HPCI System Outside:

HPCI Turbine Exhaust: FD-V004 P201 NA 4

M-55-1 8.

Group 38 - RCIC System Outside:

RCIC Turbine Exhaust:

FC-V003 P207 NA 4

M-49-1 Vacuum Pump Dideharge: FC-V010 P210 NA 4

M-49-1 9.

Group 39 - RHK System (a)

Thermal Relief Valves Outside:

M-51-1 Loop A:

BC-PSV-F02 5A P212B NA 5

Loop B:

BC-PSV-F025B P212A NA 5

Loop C:

BC-PSV-F025C P212B NA 5

Loop D:

BC-PSV-F025D P212A NA 5

(b)

Jockey Pump Discharge Check Valves Outside:

M-51-1 Loops A &'C: (BC-V206)

P212B NA 11 Loops B& D: (BC-V260)

P212A NA 11 (c)

RHR heat Exchanger Thermal Relief Valves Outside:

M-51-1 BC-PSV-4431A P213B NA 5

BC-PSV-4431B P213A NA 5

HOPE CREEK 3/4 6-35 Amendment No. 76 l

i

l TABLE :.6.3-1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM l

PENETRATION ISOLATION TIME VALVE FUNCTION AND NUMBER NUMBER (Seconds)

NOTEfS)

P6ID (d)

RHR Shutdown Cooling Suction Thermal Relief Valve l

Inside:

M-51-1 BC-PSV-4425 l

P3 NA 3

l (e)

LPCI Injection Line Check valves M-51-1 Inside:

HV-F041A (BC-V114)

P6C NA 3

HV-F041B (BC-V017)

P6B NA 3

HV-F041C (BC-V102)

P6D NA 3

HV-F041D (BC-V005)

P6A NA 3

(f)

Shutdown Cooling Return I.ine Check Valves Inside:

M-51-1 HV-F050A (BC-V111)

P4B NA 3

HV-F050B (BC-V014)

P4A NA 3

(g)

RHR Suppression Pool Return Valves Outside:

M-51-1 H"-F011A (BC-V126)

P212B NA 11 FV-F0118 (BC-V026)

P212A NA 11 10.

Group 40 - Core Spray System (a)

The rma l Relief Valves Outside:

M-52-1 Loop ALC:

BE-PSV-F012A I

P217B NA 5

Loop B&D:

BE-PSV-F012B I

P217A NA 5

(b)

Core Spray Injection Line Check Valves Inside:

M-52-1 HV-F006A (BE-V006)

PSB NA 3

HV-F006B (BE-V002)

PSA NA 3

11.

Group 11 - Drywell Pressure Instrumentation Outside:

M-42-1 BB-V563 J6A NA 6

BB-V564 J8D NA 6

BB-V565 J7A NA 6

BB-V566 J10D NA 6

HOPE CREER 3/4 6-16 Amendment No. 76

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TABLE PR!v.ARY CO*:T A !':w E? - !5-*.ATION '/ A L Y E S NOTES

• 0TATION 1.

Main steam : solation.'a;ves are sealed we:n a seal system that maintatna a post:tve pressure of 5 pstg accve reactor pressure.

Leakage as enleakage and as not added :: 0.60 La allowable leakage.'

2.

Contatnment Isolatten Valves are sealed witn a water seal from the HPCI and/or RCIC system to f:rm the long-term seal boundary of the feedwater lines. The valves are tested with water at 1.10 Pa, 52.9 patg, to ensure the seal boundary will prevent by-pass leakage. 5641 Doundary itquid leakage wt11 be itmated to lo gpm.

3.

Containment Isolation valve. Type C gas test at Pa, 48.1 peng.

Leakage l

added to entare system 'eaxage.

A;;owacle leaxage for ent:re system l

Itmated to 0.60La.

4.

Containmen: Is:;ati:n '.'a ; v e. Type C -ater test a: 1.10 Pa, 52.9 pstg celta P. Leskage actes :: ent.re s,ste- ;es4 age.

Al'0-aole leakage for f

entire syste....;e: ::.; ;p.

5.

C:nts;n ent ::.n: arf

.3

. s:* arge..:::.e :f re..ef va.ve, leakage tested 3.r.ng Tjpe A tes:

6.

Crywe;; an:

s. press.-. :r a. :er press.re an: ;evel instrument root valves an: entess

e:4

<a..es.

.eanage teste: 2 ring Type A.*

Exp;cseve srear ea;ves S I '. ; ; :.- - :. ;

SE-V;;5, n:: Type C tested.*

8.

Survea;;an:es t: ce pert:r e3 per spe:.f.:at.:n 3.6.1.8.

9.

All valve :.0

n. rers are ;re:ede: ef a n.cera; wntch represents an Unit i va.ve.

j i

10.

The reart r vesse. F.e a d sea..eas dete::. n

...e (per.e:ratacn J5C) l excess !;os One:. e s.' v e.BS-XV-3649)

.s n:: s.c;e:: to OPERASILITY l

testang. Tn.s es; e

.... n: ce expcse: :: pr; ary systen pressure em:ept.tser tre. n.. <. e. f ::nd;;.:cs :f a sea. faalare -nere it could ce partes;.y press.r.:e: :: reart:r cress.re. A r. ; ;eagage path is i

restr;:te: a: ne a:.rre:

neref:re,

.s

<a..e nee: n:: ce OPERABIL:TY tested.

. Centa;n.ent

s

.at.:-

Ja..e 5,

are n::

~ pe 0 estem.

C:n t a i r. men t cy-f pass ;eaxage

.s prevente: s.r :e ne

..ne terr. nates tel:w :ne ntnamum water level in :ne s.ppresseen er.areer an: tre system as a : : sed system :. s.:e Pr..ari ::nta.r. cent 9efer :: Spe:.f.:at.:n 4.0.5.

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• Exemption tc Appendix Of 1; 0FR Part i;.

HOPE CREEK 34 6-42 A.? e r.:m e r '

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