ML110050477

Hope Creek, HC.OP-AB.CONT-0002(Q), Rev. 9, Containment

ML110050477
Person / Time
Site:	Salem, Hope Creek
Issue date:	05/03/2010
From:	Public Service Enterprise Group
To:	Office of Nuclear Reactor Regulation
References
LR-N10-0355 HC.OP-AB.CONT-0002(Q), Rev 9
Download: ML110050477 (17)

Text

DRYWELL PRESSURE HI/LO NSSSS MSIV LOGIC INITIATED HPCI STM LK ISLN TIMER INITIATED RCIC STM LK ISLN TIMER INITIATED RWCU STM LK ISLN TIMER INITIATED MN STM/ RWCU AREA LEAK TEMP HI TIP SHEAR VALVE CLOSED/INOP

Drywell pressure lowering. Primary Containment Isolati on Valve failure to isolate. React Bldg/ Suppression Chamber Vacuum Breaker inoperable. Drywell / Suppression Chamber Vacuum Breaker inoperable. Abnormal rise in Drywell makeup. Rising room temperature. Rising Radiation level. Rising room water level. TIP ball valve fails to close. Failure of the TIP mechanism to withdraw.

TERMINATED Date/Time: _____________________________

EITHER of the following:

___ a redundant isolation valve Primary Containment Isolation Valve FAILS to automatically

ISOLATE.

Date/Time:

___ the valve manually.

Valves/ Dampers associated with Isolat ion signal(s) close (Attachments 1 & 2) Drywell/Suppression Chamber Vacuum Breakers Auto Open @ 0.2 psid Rx Bldg/Suppression Chamber Vacuum Breakers Auto Open @ 0.25 psid.

A. Valid Containment Is olation Signal ........................................................................7 B. System Isolati on has occurred.................................................................................7 C. Drywell Pressu re Lowering.......................................................................................9 D. Suppression Chamber/Drywell Va cuum Breaker NOT CLOSED.............................9 E. Reactor Bldg/Suppression Chamber Vacuum Breaker failed OPEN........................9 F. TIP CANNOT be isolated manually AND it is a source of l eakage.........................11 G. TIP fails to retract...................................................................................................11

1. Torus room temperature can be trended on the HPCI/RCIC NUMACS in the Lower Relay Room. 3. At the SM/CRS direction, to prevent additional plant transient, OR to support recovery from a plant transient, RWCU pump isolation is not required. Procedures: HC.CH-SA.RC-0002(Q) O peration Of The Reactor Building/Rhr Sample Stations HC.OP-SO.SM-0001(Q) Isolations System Operation HC.OP-SO.BG-0001(Q) Reactor Wa ter Cleanup System Operation

___ A.1 the source of the isolation signal. A.2 the isolation is effective by one OR more of the following:

___ Trending room temperatures.

___ Trending Radiation levels.

___ Trending floor water levels. A. Valid Containment Isolation Signal Date/Time:

___ Visual verification [if possible].

___ ___ ___ B.1IF RWCU isolated, THEN RWCU IAW Attachment 3. ___ B.2IF RWCU isolated, AND will remain isolated for > 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, THEN Chemistry to ISOLATE the "Cleanup Filter Demin Inlet" sample AND the Mitigation Monitoring System. ___ B.3IF the RWCU pump seal cavity temperature is > 200°F, AND A/B RWCU Pumps (BG). B.4IF the initiating condition clears, AND system restoration is desired, THEN the following:

___ a.

the isolation. (SM)

___ b. the system IAW the applicable SOP. ___ ___ B.5IF the isolation signal CANNOT be cleared, THEN equipment as directed by the applicable Emergency Operating Procedure, Abnormal, or System Operating

Procedure. B. System Isolation has occurred

. Date/Time:

___ B.6IF an Equipment Override is used, AND it is NOT required to support a step in the Emergency Operating Procedures, THEN the use in the CRS Narrative.

Procedures: HC.OP-SO.GS-0001(Q) Containment Atmo sphere Control System Operation. HC.OP-ST.GS-0001(Q) Drywell And S uppression Chamber Oxygen Concentration Verification - Weekly

C.1 the following:

___ a.

proper Operation/Lineup of N 2 makeup system. (GS)

b.

the following vacuum breakers CLOSED:___ Suppression Chamber/Drywell.___ Reactor Bldg/Suppression Chamber. ___ c.

Reactor Building/Drywell penetrations for potential leaks. ___ C.2IF Drywell Pressure drops to 0.1 psig THEN ST.GS-0001 to determine Drywell/Suppression Chamber O 2 Concentration. C. Drywell Pressure Lowering Date/Time:

___ C.3IF Drywell O 2 Concentration 4% THEN O 2 Concentration by alternating between Containment Venting

AND Containment Make-Up UNTIL Drywell O 2 Concentration < 4% (GS) ___ D.1 proper operation of the respective Vacuum BreakerD. Suppression Chamber/Drywell Vacuum Breaker NOT

CLOSED.

Date/Time:

___ D.2IF Vacuum Breaker misoperation is confirmed, the valve using the TEST P.B. E. Reactor Bldg/Suppression Chamber Vacuum Breaker failed OPEN.

Date/Time:

___ E.1IF Vacuum Breaker misoperation is confirmed, THEN the Vacuum Breaker MANUALLY.

2. The TIP SHEAR VALVE CLOSED/ INOP annunciator will be energized if a TIP shear valve is closed or if there is no continuity in the shear valve circuit.

Procedures: HC.IC-GP.SE-0005(Q) Nuclear Instrument ation System Manual Tip Retraction

___ ___ F.1 At the discret ion of the SM/CRS, the shear valve.

F.2 the following indications lit:

___ SQUIB MONITOR

___ SHEAR VALVE MONITOR F. TIP CANNOT be isolated manually AND it is a source of leakage Date/Time:

___ TIP SHEAR VALVE CLOSED/ INOP G. TIP fails to retract.

Date/Time:

___ G.1

___ G.2 the TIP AND the Ball Valve manually OR I&C to manually retract the TIP IAW HC.IC-GP.SE-0005(Q).

PCIG MAJOR KL-HV-5147, 5162, 5126A, 5126B, 5152A, 5152B, 5124A, 5124B, 5148 PCIG MINOR KL-HV-5155, 5154, 5156A, 5156B, SE-HV-5161 PCIG XCONNECTS EG-HV-2453A, 2453B, 2321A, 2321B RHR A BC-HV-F024A, F027A, F010A RHR RW & SAMPLE BC-HV-F079A, F080A, F049, F040, F079B, F080B RHR B BC-HV-F024B, F027B, F010B RHR SHUTDOWN CLG BC-HV-F015A, F009, F015B, F008 RCIC VAC BKR [ 64.5#] FC-HVF062, F084 HPCI VAC BKR [100#] FD-HVF079, F075 CS TEST RETURN BE-HV-F015A, F015B FPCC HX XCONNECT EG-HV-2317A, 2317B, 7922A, 7922B TIPS SE-SVJ004A1-5 TWCU EE-HV-4652, 4679, 4680, 4681 DW SUMPS HB-HV-F019, F020, F003, F004 PRIMARY CONTAINMENT MIMIC GS-HV-4950, 4952, 4951, 4963, 4962, 4964, KL-HV-5172A,

GS-HV-5057A, 5055A, 5052A, 5050A, 5053A, 5054A, 5022A

GS-HV-4966A, 4965A, 4959A, 4983A, 4955A, 4984A, 5019A

SK-HV-5018, 4953, 4957, 4981,

GS-HV-4979, 4980, 4956, 4958, KL-HV-5172B

GS-HV-4978, 5055B, 5057B, 5050B, 5052B, 5054B, 5053B

GS-HV-5035, 4966B, 5022B, 4959B, 4965B, 4955B, 4983B

GS-HV-5019B, 4984B, 4974

RBVS SUPPLY/EXH GU-HD-9370A, 9370B GR-HD-9414A, 9414B DW PURGE SUP/EXH GT-HD-9372A, 9372C CHILL WATER TO DRYWELL GB-HV-9531B1, 9531B2, 9531B3, 9531B4 9531A1, 9531A2, 9531A3, 9531A4 MSL DRAINS AB-HV-F016, F019 MSIVs AB-HV-F022A, F022B, F022C, F022D, F028A, F028B, F028C, F028D RECIRC SAMPLE BB-SV-4310, 4311 CRD TO RECIRC BF-HV-3800A, 3800B RWCU BG-HV-F001, F004 RACS RX BLDG ISOL ED-HV-2598, 2599 RACS TO RECIRC ED-HV-2553, 2554, 2555, 2556 TACS SUP/RET EG-HV-2522/2496A, 2522/2496C, 2522/2496B, 2522/2496D SW TO RACS EA-HV-2203, 2346, 2207, 2204

1. IF necessary, NSSSS as follows:

a. conditions causing the Isolation have been corrected. ____

b.

the following PBs to reset NSSSS: NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM TRIP LOGIC A RESET. ____ NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM TRIP LOGIC B RESET. ____ NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM TRIP LOGIC C RESET. ____ NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM TRIP LOGIC D RESET. ____ c.

HV-F001 and HV-F004, RWCU suction valves. ____ 2.

HV-F044, Filter Demin Bypass valve is CLOSED. ____ 3.

HV-F104 HX Bypass valve is CLOSED. ____ RWCU pumps trip on low flow <70 gpm and after a time delay of 15 minutes. This trip will only occur if the common pump suction flowpath is <70 gpm.

4. A(B) P221, RWCU pump. ____

5. OPEN HV-F044, Filter Demin Bypass valve until computer point A2856, RWCU Outlet Flow indicates approximately 150 gpm. ____

6. B(A) P221, RWCU pump. ____

7. OPEN HV-F044, Filter Demin Bypass valve until computer point A2856, RWCU Outlet Flow indicates approximately 300 gpm. ____

Packages and Affected Document Numbers incorporated into this revision: CP No. CP Rev. AD No. Rev No. None The following OPEX were incorporated into this revision: None The following OTSCs were incorporated into this revision: None Moved "interlocks, consideration" in Caution #2. This change is editorial. Changed attachment number to 1 & 2 on Page 3. This change is editorial.

None