ML110050477
| 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
PSEG Internal Use Only HC.OP-AB.CONT-0002(Q)
PRIMARY CONTAINMENT Hope Creek Page 1 of 16 Rev. 9 Effective Date 5/3/10 CATEGORY II PRIMARY CONTAINMENT ALARMS
- DRYWELL PRESSURE HI/LO A7-E4
- NSSSS MSIV LOGIC INITIATED C8-A1,A2,A3,A4
- MN STM/ RWCU AREA LEAK TEMP HI D3-A3
- TIP SHEAR VALVE CLOSED/INOP D1-A3 INDICATIONS
- Drywell pressure lowering.
- Primary Containment Isolation 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: _____________________________
PSEG Internal Use Only HC.OP-AB.CONT-0002(Q)
PRIMARY CONTAINMENT Hope Creek Page 2 of 16 Rev. 9 This Page Intentionally Blank
PSEG Internal Use Only HC.OP-AB.CONT-0002(Q)
PRIMARY CONTAINMENT Hope Creek Page 3 of 16 Rev. 9 IMMEDIATE OPERATOR ACTIONS CONDITION ACTION PERFORM EITHER of the following:
CLOSE a redundant isolation valve Primary Containment Isolation Valve FAILS to automatically ISOLATE.
[T/S 3.6.1.1]
Date/Time:
CLOSE the valve manually.
AUTOMATIC ACTIONS Valves/ Dampers associated with Isolation 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.
PSEG Internal Use Only HC.OP-AB.CONT-0002(Q)
PRIMARY CONTAINMENT Hope Creek Page 4 of 16 Rev. 9 This Page Intentionally Blank
PSEG Internal Use Only HC.OP-AB.CONT-0002(Q)
PRIMARY CONTAINMENT Hope Creek Page 5 of 16 Rev. 9 LIST OF CONDITIONS A. Valid Containment Isolation Signal........................................................................ 7 B. System Isolation has occurred................................................................................. 7 C. Drywell Pressure Lowering....................................................................................... 9 D. Suppression Chamber/Drywell Vacuum 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 leakage......................... 11 G. TIP fails to retract................................................................................................... 11
PSEG Internal Use Only HC.OP-AB.CONT-0002(Q)
PRIMARY CONTAINMENT Hope Creek Page 6 of 16 Rev. 9 CAUTIONS:
- 1. Starting an idle RWCU pump with a pump seal cavity temperature > 200°F, will result in accelerated mechanical seal degradation.
- 2.
Prior to overriding interlocks, consideration should be given to the potential impact of changes in plant conditions since the time of isolation. Voids or high pressure conditions in isolated piping can result in equipment damage when isolation is restored. [PR 971015323]
Equipment Override may be used on equipment designed with this feature under the following conditions:
When the system is required to support performance of a step or steps in the Emergency Operating Procedures.
OR When the SM/CRS (person who has Command and Control Authority in the Control Room) determines that the systems, with which this equipment is associated, are necessary to mitigate the consequences of an accident. Refer to the appropriate System Operating, Abnormal Operating or Emergency Operating Procedure for guidance. Such a deviation should be logged in the CRS Narrative Log.
Equipment not designed with override features should not be overridden following an accident unless specifically directed by an Operating Procedure or as provided by 10CFR50.54x. For example, do not override the LOCA signal to the Service Water cooling to RACS valves by opening the breakers and manually opening the valves.
NOTES:
- 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.
ADDITIONAL INFORMATION:
Procedures:
- HC.CH-SA.RC-0002(Q)
Operation Of The Reactor Building/Rhr Sample Stations
- HC.OP-SO.SM-0001(Q)
Isolations System Operation
- HC.OP-SO.BG-0001(Q)
Reactor Water Cleanup System Operation
PSEG Internal Use Only HC.OP-AB.CONT-0002(Q)
PRIMARY CONTAINMENT Hope Creek Page 7 of 16 Rev. 9 SUBSEQUENT OPERATOR ACTIONS CONDITION ACTION
___ A.1 DETERMINE the source of the isolation signal.
A.2 ENSURE the isolation is effective by one OR more of the following:
- NOTE 1**
Trending room temperatures.
Trending Radiation levels.
Trending floor water levels.
A.
Valid Containment Isolation Signal Date/Time:
Visual verification [if possible].
- NOTE 3**
CAUTION 1
___ B.1 IF RWCU isolated, THEN RESTORE RWCU IAW Attachment 3.
___ B.2 IF 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 DIRECT Chemistry to ISOLATE the Cleanup Filter Demin Inlet sample AND the Mitigation Monitoring System.
___ B.3 IF the RWCU pump seal cavity temperature is > 200°F, ISOLATE AND DEPRESSURIZE A/B RWCU Pumps (BG).
B.4 IF the initiating condition clears, AND system restoration is desired, THEN PERFORM the following:
- a.
RESET the isolation. (SM)
- b.
RESTORE the system IAW the applicable SOP.
CAUTION 2
___ B.5 IF the isolation signal CANNOT be cleared, THEN OVERRIDE equipment as directed by the applicable Emergency Operating Procedure, Abnormal, or System Operating Procedure.
B.
System Isolation has occurred
[CD-341X]
[CD-771A]
[UFSAR 5.2.3.2.2.2]
[PR 970803103].
Date/Time:
___ B.6 IF an Equipment Override is used, AND it is NOT required to support a step in the Emergency Operating Procedures, THEN LOG the use in the CRS Narrative.
PSEG Internal Use Only HC.OP-AB.CONT-0002(Q)
PRIMARY CONTAINMENT Hope Creek Page 8 of 16 Rev. 9 ADDITIONAL INFORMATION:
Procedures:
HC.OP-SO.GS-0001(Q)
Containment Atmosphere Control System Operation.
HC.OP-ST.GS-0001(Q)
Drywell And Suppression Chamber Oxygen Concentration Verification - Weekly
PSEG Internal Use Only HC.OP-AB.CONT-0002(Q)
PRIMARY CONTAINMENT Hope Creek Page 9 of 16 Rev. 9 SUBSEQUENT OPERATOR ACTIONS (continued)
CONDITION ACTION C.1 PERFORM the following:
- a.
VERIFY proper Operation/Lineup of N2 makeup system. (GS)
- b.
VERIFY the following vacuum breakers CLOSED:
Suppression Chamber/Drywell.
Reactor Bldg/Suppression Chamber.
- c.
INSPECT Reactor Building/Drywell penetrations for potential leaks.
___ C.2 IF Drywell Pressure drops to 0.1 psig THEN PERFORM ST.GS-0001 to determine Drywell/Suppression Chamber O2 Concentration.
C.
Drywell Pressure Lowering
[T/S 3.6.6.2]
Date/Time:
___ C.3 IF Drywell O2 Concentration 4%
THEN REDUCE O2 Concentration by alternating between Containment Venting AND Containment Make-Up UNTIL Drywell O2 Concentration < 4%
(GS)
___ D.1 VERIFY proper operation of the respective Vacuum Breaker D.
Suppression Chamber/Drywell Vacuum Breaker NOT CLOSED.
[T/S 3.6.4.1]
Date/Time:
___ D.2 IF Vacuum Breaker misoperation is confirmed, CYCLE the valve using the TEST P.B.
E.
Reactor Bldg/Suppression Chamber Vacuum Breaker failed OPEN.
[T/S 3.6.4.2]
Date/Time:
___ E.1 IF Vacuum Breaker misoperation is confirmed, THEN ISOLATE the Vacuum Breaker MANUALLY.
PSEG Internal Use Only HC.OP-AB.CONT-0002(Q)
PRIMARY CONTAINMENT Hope Creek Page 10 of 16 Rev. 9 NOTES:
- 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 Instrumentation System Manual Tip Retraction
PSEG Internal Use Only HC.OP-AB.CONT-0002(Q)
PRIMARY CONTAINMENT Hope Creek Page 11 of 16 Rev. 9 SUBSEQUENT OPERATOR ACTIONS (continued)
CONDITION ACTION
- NOTE 2**
___ F.1 At the discretion of the SM/CRS, FIRE the shear valve.
F.2 VERIFY the following indications lit:
- SQUIB MONITOR
- SHEAR VALVE MONITOR F.
TIP CANNOT be isolated manually AND it is a source of leakage
[T/S 3.6.3]
[CD-118X]
Date/Time:
- TIP SHEAR VALVE CLOSED/ INOP G.
TIP fails to retract.
[T/S 3.6.3]
Date/Time:
___ G.1
___ G.2 RETRACT the TIP AND CLOSE the Ball Valve manually OR DIRECT I&C to manually retract the TIP IAW HC.IC-GP.SE-0005(Q).
PSEG Internal Use Only HC.OP-AB.CONT-0002(Q)
PRIMARY CONTAINMENT Hope Creek Page 12 of 16 Rev. 9 This Page Intentionally Blank
PSEG Internal Use Only ATTACHMENT 1 HC.OP-AB.CONT-0002(Q)
AUTOMATIC ISOLATIONS 10C650 PRIMARY CONTAINMENT Hope Creek Page 13 of 16 Rev. 9 SYSTEM COM PONENT 1.68
-129
+12.5 PCIG MAJOR KL-HV-5147, 5162, 5126A, 5126B, 5152A, 5152B, 5124A, 5124B, 5148 X X X
PCIG MINOR KL-HV-5155, 5154, 5156A, 5156B, SE-HV-5161 X
X X
PCIG XCONNECTS EG-HV-2453A, 2453B, 2321A, 2321B X X RHR A BC-HV-F024A, F027A, F010A X X RHR RW & SAMPLE BC-HV-F079A, F080A, F049, F040, F079B, F080B X
X RHR B BC-HV-F024B, F027B, F010B X X RHR SHUTDOWN CLG BC-HV-F015A, F009, F015B, F008 X
RCIC VAC BKR [ 64.5#]
FC-HVF062, F084 X
HPCI VAC BKR [100#]
FD-HVF079, F075 X
CS TEST RETURN BE-HV-F015A, F015B X X FPCC HX XCONNECT EG-HV-2317A, 2317B, 7922A, 7922B X X TIPS SE-SVJ004A1-5 X
X TWCU EE-HV-4652, 4679, 4680, 4681 X
X X
DW SUMPS HB-HV-F019, F020, F003, F004 X
X X
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 X
X X
PSEG Internal Use Only HC.OP-AB.CONT-0002(Q)
PRIMARY CONTAINMENT Hope Creek Page 14 of 16 Rev. 9 This Page Intentionally Left Blank
PSEG Internal Use Only ATTACHMENT 2 HC.OP-AB.CONT-0002(Q)
AUTOMATIC ISOLATIONS 10C651 PRIMARY CONTAINMENT Hope Creek Page 15 of 16 Rev. 9 SYSTEM COM PONENT 1.68
-129
-38 RB HI RAD 1X10-3 RF HI RAD 2X10-3 RBVS SUPPLY/EXH GU-HD-9370A, 9370B GR-HD-9414A, 9414B X
X X
X DW PURGE SUP/EXH GT-HD-9372A, 9372C X
X X
X CHILL WATER TO DRYWELL GB-HV-9531B1, 9531B2, 9531B3, 9531B4 9531A1, 9531A2, 9531A3, 9531A4 X X MSL DRAINS AB-HV-F016, F019 X
MSIVs AB-HV-F022A, F022B, F022C, F022D, F028A, F028B, F028C, F028D X
RECIRC SAMPLE BB-SV-4310, 4311 X
CRD TO RECIRC BF-HV-3800A, 3800B X X RWCU BG-HV-F001, F004 X
RACS RX BLDG ISOL ED-HV-2598, 2599 X X RACS TO RECIRC ED-HV-2553, 2554, 2555, 2556 X X TACS SUP/RET EG-HV-2522/2496A, 2522/2496C, 2522/2496B, 2522/2496D X X SW TO RACS EA-HV-2203, 2346, 2207, 2204 X X
PSEG Internal Use Only HC.OP-AB.CONT-0002(Q)
PRIMARY CONTAINMENT Hope Creek Page 16 of 16 Rev. 9 ATTACHMENT 3 PLACING RWCU IN SERVICE CAUTION RWCU pumps should be started immediately if possible to avoid thermal stresses to piping and associated components.
- 1. IF necessary, RESET NSSSS as follows:
- a. ENSURE conditions causing the Isolation have been corrected.
- b. PRESS 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. OPEN HV-F001 and HV-F004, RWCU suction valves.
- 2. ENSURE HV-F044, Filter Demin Bypass valve is CLOSED.
- 3. ENSURE HV-F104 HX Bypass valve is CLOSED.
NOTE 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. START A(B) P221, RWCU pump.
- 5. THROTTLE OPEN HV-F044, Filter Demin Bypass valve until computer point A2856, RWCU Outlet Flow indicates approximately 150 gpm.
- 6. START B(A) P221, RWCU pump.
- 7. THROTTLE OPEN HV-F044, Filter Demin Bypass valve until computer point A2856, RWCU Outlet Flow indicates approximately 300 gpm.
PSEG Internal Use Only HC.OP-AB.CONT-0002(Q)
PRIMARY CONTAINMENT Hope Creek Page 1 of 1 Rev. 9
- Packages and Affected Document Numbers incorporated into this revision:
CP No.
CP Rev.
AD No.
Rev No.
None 9
- The following OPEX were incorporated into this revision: None
- The following OTSCs were incorporated into this revision: None REVISION
SUMMARY
70102757-0010
- Moved interlocks, consideration in Caution #2. This change is editorial.
- Changed attachment number to 1 & 2 on Page 3. This change is editorial.
IMPLEMENTATION REQUIREMENTS None