ML20153E380

Forwards Response to 860128 Request for Addl Info on Containment Isolation Valve Closure Times.Closure Times for Various Valves Revised in FSAR Table 6.2-16,Amend 14.Closure Times Conservative Compared to Offsite Dose Evaluations

ML20153E380
Person / Time
Site:	Hope Creek
Issue date:	02/20/1986
From:	Corbin McNeil Public Service Enterprise Group
To:	Adensam E Office of Nuclear Reactor Regulation
References
NUDOCS 8602250020
Download: ML20153E380 (13)

Text

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Pue: c Service E:ectnc and Gas Company Corbin A. McNeill, Jr. Pubac Serece Elecinc and Gas Company P O Bon 236 Hancock s t4ndge NJ 0dO38 609 3314800 oce P es aent kCkdf February 20, 1986 l

l Directcr of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention: Ms. Elinor Adu. sam, Director Project Directorate 3 Division of BWR Licensing

Dear Ms. Adensam:

CONTAINMENT ISOLATION VALVE CLOSURE TIMES HOPE CREEK GENERATING STATION DOCKET NO. 50-354 The enclosed information provides the Public Service Electric and Gas Company (PSE&G) response to the request for additional information on containment isolation valve closure times as detailed in the telephone conference call between members of the Nuclear Regulatory Commission (NRC) staff and PSE&G staff on January 28, 1986. Closure times for various containment isolation valves have been revised in Final Safety Analysis Report (FSAR) Table 6.2-16, Amendment 14 (C.A. McNeill to E. Adensam dated February 4, 1986) as detailed in the attached Tables 1 and 2, while the justifications for the revisions are summarizen in Attachment 1. This summary concludes that the closure times for the containment isolation valves listed in the Amendnent 14 version of Table 6.2-16 are conservative revisions when compared to the results of offsite dose evaluations and are consistent with Technical Specification Table 3.6.3-1.

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

Sincerely,

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0602250020 860220 g0 PDR ADOCK 05000354 $

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Director of Nuclear 2 2-20-86 Reactor Regulation Attachments C D.H. Wagner USNRC Licensing Project Manager R.W. Borchardt USNRC Senior Resident Inspector

ATTACHMENT 1 In support of revisions made in Amendment 14 to Table 6.2-16, the following detailed justification addresses the valve closure times which were either changed in an apparently non-conservative direction, or deleted.

As indicated in SRP 6.2.4 Secticns II.n and III and SRP 15.6.5 Appendix A, containment isolation valve closure times should be limited to one minute or less. Therefore, the containment isolation valve closure times that were increased in Amendment 14 but that did not exceed one minute are justified. Accident consequences have been calculated for lines which can potentially release radioactivity to the environment if it takes over one minute to isolate the line, or if the line communicates directly with the atmosphere and takes more than 5 seconds to isolate.

As indicated in Table 1 the only valves which isolate lines in over one minute serve the RHR and Core Spray Systems, which constitute closed loops outside containment, and are designed to be operated (i.e. opened) during the course of the accident but at times much later than containment isolation. The only potential for radioactive releases from these lines is from system leakage which is already included in the DBA LOCA dose analysis in FSAR Section 15.6.5. While faster valve closure would reduce the dose consequences from system leakage, the reduction would be negligible when compared to the long-term dose consequences.

Therefore, the containment isolation valve closure times that exceed one minute in Amendment 14 are also justified.

The deletion of closure times (see Table 2) and use of NA (not applicable) for various valves has been employed in both the FSAR and Technical Specifications to clearly indicate which valves do not automatically reposition at the onset of an accident for the purposes of containment isolation. Valves in this category include: ECCS pump suction and injection valves which remain open during an accident to provide the necessary coolant to the reactor, check valves which close on reverse flow, ECCS pump minimum flow valves which operate in response to system flow and pressure signals, and valves which have been intentionally placed out of service and are administratively controlled in the closed position. The justification for each valve is detailed on Table 2. For the poacr-operated valves

2 listed, a maximum stroke time will be included in the itCGS Inservice Testing Program (IST) since the operability of the valves is more closely tied to system operability than to containment isolation. The IST program imposes stringent testing requirements on valves and includes retest and repair requirements for valves which exceed predetermined maximum stroke times.

s Based ot, the above two arguments and the justifications provideo in Table 2, the closure times for containment isolation valves identified in FSAR Table 6.2-16, Amendment 14 and Technical Specification Table 3.6.3-1 are consistent and accurately reflect plant operability.

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TABLE 1 CONTAINMENT ISOLATION VALVE'S WITH INCREASED CLOSURE TIMES FSAR TABLE 6.2-16, AMENDMENT 14 REVISIONS LINE, PENETRATION (S), AND VALVE (S) AMENDMENT 14 PREVIOUSLY Main Steam (P-1A,B,C,D)

AB-V059, AB-V060 45 29 AB-V061, AB-V062 KP-V010, KP-V009 KP-V008, KP-V007 RHR Shutdown Cooling (P-3:4A,B)

BC-V071, BC-V164 45 29 BC-V013, BC-V110 DW Cooler Chilled Water (P-8A,B;38A,B)

GB-V046, GB-V070 60 51 GB-V048, GB-V071 GB-V081, GB-V083 GB-V082, GB-V084 RWCU Supply (P-9)

BG-V001, BG-V002 45 35 RHR Head Spray (P-10)

BC-V020, BC-V021 60 35 Main Steam Drain (P-12)

AB-V039, AB-V040 30 19 Reactor Recirculation Water Sample (P-17)

BB-SV-4310 15 <10 BB-SV-4311 Recirculation Pump Seal Water (P-19,20)

BF-V098, BF-V099 45 29 Drywell Purge Vent (P-22,23)

GS-V009, GS-V023 15 3-9 GS-V021, GS-V020 GS-V024, GS-V026 GS-V004, GS-V005 45 28 GS-V002, GS-V003 DW Floor and Equipment Drain Sump Discharge (P-25,26)

HB-V005, HB-V006 30 21 HB-V045, HB-V046

2 LINE, PENETRATION (S), AND VALVE (S) AMENDMENT 14 PREVIOUSLY Instrument Gas (P-28A,B;39)

KL-V001, KL-V002 45 29 KL-V025, KL-V026 KL-V027, KL-V028 KL-V049 RACS (P-29,30)

ED-V019, ED-V020 45 28 ED-V021, ED-V022 TIP Probe Guide Tube (P-34A,B,C,D,E)

SE-V026, SE-V027 15 <0.5 SE-V028, SE-V029 SE-V030 TIP Purge System (P-34F)

SE-V004 15 10 RHR To Suppression Chamber Spray Header (P-214A,B)

BC-V015, BC-V112 75 65 Core Spray Test to Suppression Pool (P-217A,B)

BE-V025, BE-V026 80 72 Suppression Chamber Purge & Vacuum Relief (P-219,220)

GS-V006, GS-V007 45 39 GS-V010, GS-V008 GS-V028, GS-V027 15 3-9 GS-V022 15 5 Torus Water Cleanup (P-222,223)

EE-V001, EE-V002 45 39 EE-V003, EE-V004 i

H 2 /02 Gas Analyzer (J-3B,7D,9E,10C)

GS-V031, GS-V032 45 29 GS-V033, GS-V034 GS-V047, GS-V048 GS-V045, GS-V046 GS-V053 RCPB Leakage Radioactive Gas Sampler (J-5A)

SK-V008, SK-V009 45 29

3 LINE, PENETRATION (S), AND VALVE (S) AMENDMENT 14 PREVIOUSLY RCPB Leak Detection (J-8C)

SK-V005, SK-V006 45 29 Suppression Chamber Outlet / Inlet To/From H2/02 Analyzer (J-201,202,210,212)

GS-V051, GS-V052 45 29 GS-V042, GS-V043 GS-V040, GS-V041 GS-V049, GS-V050 Instrument Air to Torus (J-211)

KL-V018, KL-V019 15 10

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TABLE 2 i

i CONTAINMENT ISOLATION VALVE'S WITH DELETED CLOSURE TIMES FSAR TABLE 6.2-16, AMENDMENT 14 REVISIONS SYSTEM / PENETRATION (S) VALVE (S) AMENDMENT 14 PREVIOUSLY JUSTIFICATION FOR "NA"

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j Feedwater AE-V002 NA 5 These check valves do not

) P-2A,B AE-V006 receive containment iso-j lation signals.

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i RHR Shutdown Cooling BC-Vll7 NA 10 These normally closed / fail P-4A,B BC-Vll8 closed valves are used by.

the operator to equalize the.

pressure across the testable check valves during_ testing.

The valves are opened by de-pressing the control push-button. Once released, the valve closes.

Core Spray to Reactor BE-V071 NA 10 See justification for valves P-5A,B BE-V072 BC-Vll7 and BC-Vll8'above.

BE-V003 NA 12 These ECCS injection valves BE-V007 do not receive containment isolation signals thus permit-BJ-V001 NA 20 ting the systems to. function during a LOCA.

J O SYSTEM / PENETRATION (S) VALVE (S) AMENDMENT 14 PREVIOUSLY JUSTIFICATION FOR "NA" LPCI BC-V119 NA 10 See justification for valves P-6A,B,C,D BC-V120 BC-V117 and BC-Vll8 above.

BC-V121 1 BC-V122 BC-V004 NA 24 See justification for valves

BC-V016 BE-V003 and BE-V007 above.

BC-V101 ~

BC-Vll3 HPCI Turbine Steam FD-V001 NA 36 These valves do not receive Supply FD-V002 a containment isolation signal P-7 thus permitting the system FD-V051 NA 29 to perform its safety function.

These valves do receive a system isolation signal.

RCIC Turbine FC-V001 NA 12 These valves do not receive Steam Supply FC-V002 a containment isolation signal P-ll FC-V048 thus permitting the system to perform its safety function.

I These valves do not receive a system isolation signal.

Standby Liquid Control BH-V028 NA 27 These valves do not receive P-18 BH-V054 a containment isolation signal.

These are remote manual stsp check valves that do not receive any automatic open or close 4

signal.

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SYSTEM / PENETRATION (S) VALVE (S) AMENDMENT 14 PREVIOUSLY JUSTIFICATION FOR "NAd RUR Containment Spray BC-V018 NA 12 These normally closed. valves P-24A,B BC-V019 do not receive a containment BC-Vll5 isolation signal. Only one BC-V116 valve (there are two in series in each containment spray line) can be opened at a time unless a accident signal is l

present and LPCI flow is purpose-fully being diverted by the operator to the containment for pressure control purposes.

HPCI Vacuum FD-V006 NA 120 See justification for valves Breaker Network FD-V001, FD-V002, and FD-V051 P-201,204 FD-VOL7 NA 21 above.

FD-V010 HPCI Pump Suction BJ-V009 NA 96 This valve does not receive P-202 a containment isolation signal thus permitting the system to perform its safety function.

The valve does receive a system isolation signal.

HrCI Minimum Return BJ-V016 NA 10 This valve does not receive P-203 a containment isolation signal.

The valve opens and closes depending upon HPCI pump dis-charge flow and pressure.

The valve also closes upon system isolation' signals which indicate the HPCI steam supply valves are closed.

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RCIC Vacuum Breaker FC-V005 NA 66 See justification for valves Network FC-V001, FC-V002 and FC-V048 P-207 FC-V006 NA 21 above.

RCIC Pump Saction BD-V003 NA 30 This valve does not receive P-208 a containment isolation signal.

This valve is normally closed, receives no automatic close signals and opens upon receipt of low CST level signals.

RCIC Mir.imum Flow BD-SV-F019 NA 0.250 This valve does not receive P-209 a containment isolation signal, instead it opens and closes depending upon HPCI flow and pressure. This valve also closes upon signals which indicates the RCIC steam supply valves are closed.

RCIC Vacuum Pump FC-V0ll NA 26 This is a remote manual valve Discharge which does not receive any P-210 automatic open or close signals.

RHR Pump Suctirn BC-V001 NA 132 These are remote manual P-211A,B,C,D BC-V006 valves which do not receive BC-V098 any automatic open or close BC-V103 signals.

SYSTEM / PENETRATION (S) VALVE (S) AMENDMENT 14 PREVIOUSLY JUSTIFICATION FOR "NA" RHR Suppression Pool BC-V031 NA 27 These valves do not receive Cooling & System BC-V034 containment isolation signals, Test (Minimum Flow BC-V128 instead they open and close Valves) BC-V131 depending upon RHR flow.

P-212A,B l RHR Suppression Pool BC-V026 NA 27 These valves are permanently Cooling & System BC-V126 out of service as electrical Test (Steam Condensing power has been disconnected, Valves) the manual override is chain P-212A,B locked in the closed position, i

and the valve is tagged out of service.

Core Spray Pump BE-V017 NA 96 These remote manual valves Suction BE-V018 do not receive any automatic P-216A,B,C,D BE-V019 open or close signals.

, BE-V020 1

Core Spray Test BE-V035 NA 36 These valves do not receive to Suppression Pool BE-V036 containment isolatien signals.

(Minimum Flow Valves) The valves open and close P-217A,B depending upon core spray flow.

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• SYSTEM / PENETRATION (S) VALVE (S) AMENDMENT 14 PREVIOUSLY JUSTIFICATION FOR "NA" Suppression Chamber GS-V038 NA 3-9 These valves do not receive Purge and Vacuum GS-V080 containment isolation signals.

Relief The valves open and close P-219,220 depending upon reactor building to suppression chamber differ-rential pressure.

Post Accident RC-SV-0643A&B NA <5 These remote manual valves Sampling System RC-SV-0707A&B do not receive any automatic P-227 RC-SV-0729A&B open or close signals. Admini-J-7E, 10E, 50 RC-SV-0730A&B strative procedures prevent J-220,221 RC-SV-0731A&B the valves from being inadvert-RC-SV-8903A&B antly opened by ensuring that power is not supplied to the valves until the system is required to be operable.

Suppression Pool BJ-V500 NA 29 These are remote manual valves Water Level BJ-V501 that do not receive any auto-P-228 matic open or close signals.

J-209,217,219 BJ-V502 NA 30 BJ-V503