NUREG-1410, Discusses NRC Concerns Re Operator Diligence While in Shutdown Conditions & Requests Quick & Appropriate Mgt Reactions to Generic Ltr 88-17.Supporting Documentation Encl
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
1 W A&MNGTON. D. C. 206El
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ncnenter 3, 1988 0b~l?O'fd f
TO:
ALL HOLDERS OF REACTOR OPERATOR AND SENIOR REACTOR OPERATOR LICENSES FOR PRESSURIZED WATER REACTOR $
SUBJECT:
OPERATOR DILIGENCE WHILE IN SHtfiDOWN CONDITIONS The NRC is issuing this generic letter to ensure that licensed operators at the controls of nuclear power plants are made aware tha.t serious accidents can occur while in shutdown conditions.
Enclosed is a copy of Generic Letter 88-17 that the NRC has just transmitted to all pressurized water reactor licensees. The NRC's concern is based on-technical evaluations and studies of operational events which have occurred when plants are in cold shutdown and have lost decay heat removal capability. We have found that loss of decay heat removal during cold shutdown conditions can lead to serious consequences sooner than previously recognized.
I am sending this information so that you are aware of our concerns. We are confident that your management will react quickly and appropriately to Generic Letter 88-17, but it will take some time to fully address the issues raised. Your awareness of these insights into non-power operation are particularly important during this interim period, b
Thomas E. Murley Office of Nuclear, Directot Reactor Regulation
Enclosure:
Generic Letter 88-17 cc w/ enc 1: NRC Regional Offices NRC Resident-inspectors cc w/o enc 1: Addresses of Generic Letter 88-17 S
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UNITE D STATES
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DEC 2 1983
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Docket Nos. 50-206 50-361 50-362 Pr. }ioward P. Allen Chairman of the Board Southern California Edison Company 2244 Walnut Grove Avenue P.O. Box 800 Rosemead, California 91770
Dear Mr. Allen:
SUBJECT:
LOSS Of DECAY llEAT REMOYAL We have just issued Generic Letter 88-17 which addresses loss of decay heat removal (DfiR)duringnonpoweroperation.
This letter was issued because of the potential serious consequence of loss of shutdown cooling concurrent with significant core decay heat.
Further, it is our belief that the industry as a whole has not aggressively responded to resolve the concern following its identification in our earlier Generic Letter 87-12.
In particular, the industry's response to the Generic Letter 87-12 was deficientintheareasof(1)preventionofaccidentinitiation,(2)mitig)a-tion of accidents before they potentially progress to core damage, and (3 control of radioactive material if a core damage accident should occur.
Generic Letter 88-17 prescribes expeditious actions which should immediately ease the concern, and parallel, but longer term, programmed enhancements which effectively aodress the root cause of the problems and permit greater flexi-bility in operation.
We consider this issue to be of high priority and request that you assure that your organization addresses it accoroingly.
Sincerely,
.AC Thomas E. Murley, Director Office of Nuclear Reactor Regulation cc: See next page bl gh k
w Mr. Kenneth P 3askin San Oncfre Nuclear Generating Sov hern Cal' srnia Edison Company Station, Unit No. 1 e
i CC Charles R. Kocher, Assistant Mr. Jack McGurk, Acting Chief General Counsel Radiological Health Branch J ac.E - ' vit.
o, Esquire State Department of Health h
So,. -
,fornia Edison Company Services
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'/14 P Street, Office hdg. 8
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>nia 91770 Sacramento, Californi:
95814 Mr. Hans Kaspar, Executive Director
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.an & Sutcliffe Marine Review Committee Inc.
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San Frt
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Mr. Robert G.
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Fhnager< NLcleu Sar Ciego Gas & Electric Company P. 6. ilox-1831 San tieso, California 92112 H.asiaent Inspector / San Onofre NPS U.S. t1RC P. O. Box 4329 San Clemente, California 92672 Mayor City of San C'de nente San Clemente, California 92672 y.
-Chairman Board of Supervisors County of San Diego 1600 Pacific Highway Room 335 San Diego, California 92101 Director Energy Facilities Siting Division Energy Resources Conservation b Development Commission 1516 - 9th Street Sacramento, California 95814 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Ma.in Lane, Suite 210 Walnut C sek, California 94596 1
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Mr. Kenneth P. Baskin San Onofre Nuclear Generating Southern California Edison Company S_tation, Units 2 and 3 cc:
Mr. Gary D. Cotton Mr. Hans Kaspar, Executive Director Senior Vice President Marine Review Committee, Inc.
Engineering and Operations 531 Encinitas Boulevard, Suite 105 San Diego Gas-& Electric Company Encinitas, California 92024 101 Ash Street Post Office Box 1831-San Diego, California 92112 Mr. Mark Medford Southern California Edison Company Charles R. Kocher, Esq.-
2244 Walnut Grove Avenue James A. Bcoletto, Esq.
P. O. Box 800 Southern Cal;tornia Edison Company Rosemead, California 91770 2244 Walnut Grove Avenue P. O. Box 800 Mr. Robert G. Lacy Rosemead, California 91770 Manager, Nuclear Department San Diego Gas & Electric Company Orrick, Herrington &_- Sutcliffe P. O. Box 1831 ATTN: David R. Pigott, Esq.
San Diego,-California s2112 600 Montgomery Street San Francisco, California 94111 Richard J. Wharton, Esq.
University of San Diego School of Alan R. Watts, Esq.
Law Rourke & Woodruff Environmental Law Clinic 701 S. Parker St. No. 7000 San Diego, California 92110 Orange, California 92668-4702 Charles E. McClung, Jr., Esq.
Attorney at Law Mr. S. McClusky 24012_Calle de la Plaza / Suite 330 Bechtel Power Corporation Laguna Hills, California 92653 P. O. Box 60860 Terminal Annex Los' Angeles, California 90060 Regional Administrator, Region V L'.S. Nuclear Regulatory Commission Mr. C. B. Brinkman 1450 Maria Lane / Suite 210 Cenbustion Engineering, Inc.
Walnut Creek, California 94596 7910'Woodmont Avenue, Suite 1310 Bethesda, Maryland 20S14 Resident Inspector, San Onofre NPS c/o U. S. Nuclear Regulatory Commission Mr. Dennis'F. Kirsh Post Office Box 4329 11.S. Nuclear Regulatory Commission San Clemente, California 92672 Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. Sherwin Harris Resource Project Manager Public Utilities Department City of Riverside City Hall 3900 Main Street Riverside, California 92522
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TASL INFORMAil0N SURV. TASK #:
14_210-103 ISSUE DATE:_ 03/10/90 EQUIP.I.D.#:11222U4026 11222U4027 APPL. MODE (S):
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14210-1 PROCEDURE TITLE :
CONTAINMENT BUILDING PEN 8T'ItATIONS VERIFICATION-REFUELING o..o...........................a........................s.....................
FOOTNOTES:
- DURING CORE ALTERATIONS OR MOVEMENT OF IRRADIATED FUEL IN CNTMT.
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TASKINFORMATIOR DATA REVISION 803/10/90 SURV.< TASK # : 14210-103 ISSUE DATE:
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CONTAINMENT BUILDING PENETRATIONS VERIFICATION - REFUELING 1.0 PURPOSE 1.1 The purpose of this procedure is to verify Containmenc Building Penetrations status pric. to and during refueling or core alterations or movement of irradiated fuel within the Containment.
1.2 This surveillance satisfies Technical Specification 4.9.4.
1.3 The irequency of this surveillance is within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once every seven days during core alterations or movement of irradiated fuel in the Containment Building.
2.0 APPLICABILITY This surveillance is required prior to and during core alterations or movement of irradiated fuel within the Containment Building.
3.0 PRECAUTIONS / LIMITATIONS Notify the Unit Shift Supervisor (USS) immediately 4.f any condition of this procedure is not satisfied.
INITIALS 4.0 PREREQUISITES / INITIAL CONDITIONS 4.1 The USS shall ensure this surveillance test does not affect other tests presently in progress or jeopardize plant operation prior to granting N
approval to perform this surveillance X
test.
PERUVAL 4.2 CONTACT Work Planning and ENSURE there are no outstanding Maintenance Work Orders (MW0s) which could affect Containment (CNMT) integrity and TAKE appropriate action, i.e.
clearance, on any penetration determined M provide a direct path from inside CNMT to outside environment,
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REWSloN PAGE No.
l, VEGP 14210-1 4
2 of 5 INITIALS 5.0 INSTRUCTIONS
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5.2 COMPLETE 14928-1, " Containment Ventilation Isolation Refueling".
ErnT 5.3 VERIFY that Steam Generator secondary manways are instelled or no direct access path from CNMT exists through main steam, feedwater or blowdown.
6.0 ACCEPTANCE CRITERIA
. 6.1 The Containment Equipment Door is closed and held in place by a minimum of four bolts.
6.2 Aminimumofonedoorgg,eachairlockisclosed.
'6.3 Each penetration providing direct access from the Containment atmosphere to the outside atmosphere shall be either:
Closed by an Isolation Valve, Blind Flange, or a.
Manual Valve, or:
b.
Be capable of being closed by an operable automatic Containment Ventilation Isolation Valve.
7.0 REFERENCES
7.1 P& ids 7.1.1-IX4DB110 Post Accident Sampling System
~7.1.2 IX4DB132 Miscellaneous Leak Detection System 7.1.3 IX4DB213-1,2 Containment Air Purification and Cleanup System 7.1.4 IX2D0lJ013 Containment Wall Liner Plate Penetration Schedule 7.2 PROCEDURES 14928-1,
" Containment Ventilation Isolation Refueling" END OF PROCEDURE TEXT
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Page No.
VEGP 14210-1 4
3 of 5 Sheet 1 of 3 DATA SHEET 1 CONTAINMENT BUILDING PENETRATIONS VERIFICATION - REFUELING REQUIRED COMPONENT DESCRIPTION PENETRATION STATUS BLDG /LVL INITIALS FLANGE MISC LEAK-DET FLANGE 64A INSTALLED FHB RA10
/8 UPPER MEZ FLANGE MISC LEAK DET FLANGE 64B INSTALLED FHB RA10 8
UPPER MEZ 1-1222-U4-051 MISC LEAK DET'CNMT TEST 68 LOCKED CLOSED AUX /B IN GAS FILL CONN INLET
& CAPPED ROOM B08 1-1222-U4-026 MISC LEAK DET CONTAINMENT 6 87 LOCKED CLOSED AtlX/B d
LEAK TEST ISOLATION ROOM B08 1-1505-U4-001 PREACCESS PURGE SPLY 83 LDCKED CLOSED EQUIP BLDG 8
TEST CONF
& CAPPED LEVEL 1 1-1506-U4-001 PREACCESS PURGE EXH 84 LOCKED CLOSED ORC BY 18 TEST CONN
& CAPPED PERSONNEL AIRLOCK
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'VEGP 14210-1 4
4 of 5 Sheet 2 of 3 DATA SHEET 1 CONTAINMENT EUILDING PENETRATIONS VERIFICATION - REFUELING REQUIRED COMPONENT DESCRIPTION PENETRATION
' STATUS BLDG /LVL INITIALS 1-HV-8212 PASS GAS SAMPLE RTN-ORC 86A CLOSED Zft' l
1-1222-U4-052 MISC LEAM DET CNMT TEST 87 LOCKED CLOSED AUX /B Iff-GAS FILL CONN INLET
& CAPPED ROOM B08 l
1-1222-U4-027 MISC LEAK DET CONTAINMENT' 87 LOCKED CLOSED AUX /B E
LEAK TEST ISOLATION 770M B08 l
1-15G8-U4-012 POST-LOCA EXH CTB PURGE 100 LOCKED CLOSED AUX /3 4?'
(Roof) 3 1-1508-U4-001 CAPCS POST-LOCA PURGE 10D LOCKED CLOSED AUX /3 2P<'
SUCTION TEST CONH ISO
& CAPPED (Roof) 1-HV-2791A H2 MONITOR B SPLY ISO ORC 70A CLOSED Z0' 1-HV-2791B H2 MONITOR A SPLY ISO ORC 71A CLOSED RY 1-HV-2793A 112 MONITOR B RTN ISO ORC 70B CLOSED AC' 1-HV-2793B H2 h0NITOR A RTN ISO ORC 71B CLOSED CI' CONTAINMENT EQUIPMEN1' HATCH CLOSED / HELD BY
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PERSONNEL AIRLOCK ONE DOOR CLOSCJ 43'T $
EMERGENCY AIRLOCK ONE DOOR CLOSED 4C' Verify position at QPCP
- Must be verified inside Containment
=
.PROCEDUAE No.
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-VEGP 14210-1 4
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_ CONTAINMENT BUILDING PENETRATIONS VERIFICATION - REFUEL EVALUATION AND REVIEW TEST PURPOSE
[y Surveillance
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gj Vogtb Electric Generating Pbnt Proc 40urc No.
14210-1
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NUCLEAR OPERATIONS g,,,,,,,, y,,
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CONTAINMENT BUILDING PENETRATIONS VERIFICATION - REFUELING 1.0 PURPOSE 1.1 The purpose of this procedure is to verify Containment Building Penetrations status pricr to and during refueling or core alterations or movement of irradiated fuel within the Containment.
1,2 This surveillance satisfies Technical Specification 4.9.4 1.3 The frequency of this surveillance is within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once every seven days during core alterations or movement of irradiated fuel in the Containment Building.
2.0 APPLICABILITY This surveillance is required prior to and during core alterations or movement of irradiated fuel within the Containment Building, 3.0 PRECAUTIONS / LIMITATIONS Notify the Unit Shift Supervisor (USS) immediately if any condition of this procedure is not satisfied.
INITIALS 4.0 PREREQUISITES / INITIAL CONDITIONS 4.1 The USS shall ensure this surveillance test does not affect other tests l
presently in progress or jeopardize plant operation prior to granting L
approval to perform this surveillance test.
CL. b USS APPROVAL 4.2 CONTACT Work Planning and ENSURE there are no outstanding Maintenance Work Orders (MW0s) which coul.d affect
)
Containment (CNMT) integrity and TAKE appropriate action, i.e.
clearance, on any penetration determined to provide a direct path from inside CNMT to outside environment.
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1 FRoCEDURE No.
REvtSloh PAGE No.
VEGP 14210-1 4
2 of 5 INITIALS 5.0 It1STRUCTIONS TEST STARTED
_3 - / 7-90 oo p
_ Mode (o
Date Time 5.1 COMPLETE Data Sheet 1 to verify 4
Containment Building penetration status.
K, ( '
5.2 COMPLETE 14928-1, " Containment O
Ventilation Isolation Refueling".
%7/7/U 5.3 VERIFY that Steam Generator secondary manways are installed or no direct access path from CNMT exists through main steam, feedwater or blowdown.
21_
6.0 ACCEPTANCE CRITERIA 6.1 The Containment Equipment Door is closed and held in place by a minimum of four bolts.
6.2 A minimum of one door in each airlock is closed.
6.3 Each penetration providing direct access from the Containment atmosphere to the outside atmosphere shall be either:
Closed by an Isolation Valve, Blind Flange, or a.
Manual Valve, or:
b.
Be capable of being closed by an operable automatic Containment Ventilation Isolation Valve.
7.0 REFERENCES
7.1 P& ids 7.1.1 1X4DB110 Pos t Accident Sampling System 7.1.2 1X4DB132 Miscellaneous Leak Detection System 7.1.3 1X4DB213-1,2 Containment Air Purification and Cleanup System 7.1. 4.
1X2D0lJ013 Containment Wall Liner Plate Penetration Schedule 7.2 PROCEDURES 14928-1,
" Containment Ventilation Isolation Refueling" END OF PROCEDURE TEXT wn
lPredadure Na Revisson -
Page No.
VEGP 14210-1 4L 3 of 5 cheet 1 of 3-DATA SHEET 1
. CONTAINMENT BUILC.NG PENETRATIONS VERIFICATION - REFUELING l
REQUIRED COMPONENT DESCRIPT10N PENETRATION.
STATUS.
BLDG /LVL
. INITIALS FLANCE' MISC LEAK-DET FLANGE 64A INSTALLED FHB RAl'0
)-
UPPER MEZ FLANGE MISC LEAK DET' FLANGE 64B INSTALLED FHB RAIO UPPER MEZ 1-1222-04-051 MISC LEAK DET CNMT TEST 68 LOCKED CLOSED AUX /B b
GAS FILL CONN INLET
& CAPPED ROOM B08 1-1222-U4-026 MISC LEAK DET CONTAINMENT 68
. LOCKED CLOSED
' AUX /B LEAK TEST ISOLATION ROOM B08
'3 LOCKED CLOSED EQUIP BLDG b
1 - 15I)S ;U4 -001 PREACCESS PURGE STLY 8
TEST CONN
& CAPPED LEVEL 1.
1-1506-U4-001 PREACCESS PURGE EXH 84 LOCKE0 CLOSED ORC BY C
TEST CONN
& CAPPED PERSONNEL 7
AIRLOCK L
e
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Procedure No Revision Page No.
VEGP 14210-1 4
4 of 5 Sheet 2 of 3 DATA SHEET 1 CONTAINMENT BUILDING PENETRATIONS VERIFICATION - REFUELING REQUIRED COMPONENT DESCRIPTION PENETRATION STATUS BLDG /LVL INITIALS l
1-HV-8212 PASS GAS SAMPLE RTN-ORC 86.A CLOSED 1-1222-U4-052 MISC LEAK DET CNMT TEST 87 LOCKED CLOSED AUX /B
[C.
l GAS FILL CONN INLET
& CAPPED ROOM B08 1-1222-U4-027 t1ISC LEAK DET CONTAINMENT 87 LOCKED CLOSED AUX /B LEAVs TEST ISOLATION ROOP B08 l
1-1508-U4-012 POST-LOCA EXH CTB PURGE 100 LOCKED CLOSED AUX /3 C
FILTER EXH ISO (Roof) 1-1508-U4-001 CAPCS POST-LOCA PURGE 100 LOCKED CLOSED AUX /3
[C_
SUCTION TEST CONN ISO
& CAPPED (Roof) b 1-HV-2791A H2 MONITOR B SPLY ISO ORC 70A CLOSED b
1-HV-2791B H2 MONITOR A SPLY ISO ORC 71A CLOSED 1-HV-2793A H2 MONITOR B RTN ISO ORC 70B CLOSED b
1-HV-2793B H2 MONITOR A RTN ISO ORC 71B CLOSED CONTAINMENT EQUIPMENT HATCH CLOSED / HELD BY MIN OF 4 BOLTS **
I PERSONNEL AIRLOCK ONE DOOR CLOSED EMERGENCY AIRLOCK ONE DOOR CLOSED b
. Verify position at.QPCP
- Must be verified inside Containment
s PROCEDURE NO.
REVISloM PAGE No.
VEGP 14210-1 4
5 of 5 Sheet 3cf3 DATA SHEET 1 CONTAI! MENT BUILDING PENETRATIONS VERITICATION REFUELING EVALUATION AND REVIEW TEST PURPOSE
[
Surveillance
[ ] Maintenance Retest
~
[ ] Ocher (explain)
Results obtain(d through performance of this procedure meet ACCEPTANCE CRITv.RIA of Section 6.0.
[
YES
[ ] NO If NO was checked, NOTIFY the Unit Shift Supervisor (USS) a.
and REFER to Technical Specification 3.9.4.
b.
Comments (include any abnormal conditions and corrective actions taken):
_ rO o rv8 USS notified of test completion and results.
c.
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/ 3'l? 90/ 6 f3 2 Ipitial Date Time Test Completed By
'IM hwa n
/ J-/ 7 pp / ON L
' Signaturd Date Time i
Supervisory Review
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/ 7- / 7 - Od / f J 7 6 Signature Date T'.me zu s
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