ML20057D168
| ML20057D168 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/27/1993 |
| From: | Fields M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9310010208 | |
| Download: ML20057D168 (20) | |
Text
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UNITED STATES j,,
NUCLEAR REGULATORY COMMISSION n
l W ASHINGTON, D. C. 20555 y
September 27, 1993
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Docket Nos. 50-361 and 50-362 LICENSEE: Southern California Edison Company (SCE)
FACILITY:
San Onofre Nuclear Generating Station, Unit Nos. 2 and 3
SUBJECT:
SUMMARY
OF MEETING WITH SCE HELD ON AUGUST 5, 1993, TO DISCUSS l
HARSH ENVIRONMENTAL EFFECTS ON INSTRUMENTS USED IN EMERGENCY OPERATING PROCEDURES i
A meeting was held on August 5,1993, between members of the NRC staff and SCE representat.ves to discuss methods of providing control room operators with I
optimal information on instrument accuracies under harsh environmental conditions.
A list of attendees is included as Enclosure 1 and a copy of the slides used by SCE is included as Enclosure 2.
The meeting was held at the request of the San Onofre licensee in order to present their approach for incorporating harsh environment-induced instrument errors into the emergency operating instructions (E01s) without degrading the operator's ability to properly interpret instrument readings and take appropriate actions.
SCE's operations philosophy is to maintain symptom-based E0Is utilizing realistic post-accident parameters and still include instrument inaccuracies in those setpoint numbers that are used as decision points by the operators. The method by whic;. SCE intends to establish the list of i
parameters in the E01s that should include ustrument inaccuracies due to harsh environmental conditions is illustrated by the flow chart in.
The first step is to estabiish those parameters that are used to validate safety functions.
Parameters /uses that are not impacted by instrument uncertainties are eliminated from consideration, as well as those parameters that are not used as operator decision points (e.g., trending or nominal control values).
The remaining parameters which have a significant I
safety function are identified, and inaccuracies due to harsh environmental effects are applied and included in the E01s. SCE is involving the Combustion Engineering Owner's Group in this effort and is participating in the Severe Accident Working Group evaluations. SCE expects to have this evaluation process completed by December 1994, and plans to implement the results into the E01s during cycles 8/9 (Unit 2 recently completed its cycle 7 refueling outage and Unit 3 will begin its cycle 7 refueling outage in October 1993).
The staff informed SCE that it considered the general approach presented during the meeting to be acceptable.
H. Garg of the Instrumentation and Control Branch indicated that Regulatory Guide 1.97, Revision 2,
" Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant kh k b d
9310010208 930927 PDR ADOCK 05000361 i N\\
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4 September-27, 1993 I
l Southern California Edison Company Conditions During and Following a Accident," should be considered when creating the list of parameters to be evaluated, which SCE agreed to do. The staff will examine, on a limited basis, a representative sample of E01s once the licensee has reached an appropriate stage in this program.
Original signed by:
Mel B. Fields, Project Manager Project Directorate V i
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation 1
Enclosures:
- 1. Attendance List
- 2. Viewgraphs i
cc w/ enclosures:
See next page DISTRIBUTION:
Docket: File NRC & Local ~'PDRs PDV Reading File MFields KPerkins, RV w/o enclosure 2:
TMurley/FMiraglia, 12G18 JPartlow, 12G18 JRoe EAdensam TQuay EBarnhill CDoutt, 8D24 SAthavale, 8D24 WMarsh, 8024 HGarg, 8D24 l
OGC, 15B18 EJordan, 3701 ACRS (10), P315 JMitchell,17G21 OFFICE PDV/LA PDV/PM _ _
HKB/BC HHFB/BCfEI' PDV/D NAME EBarnhi1Nb MFielY [
JWkm'ikl hiNarA[5 TQuay DATE 9 /c2/ /93 9 G //93 7/k2./93 67 /A//93 7/M/93 0FFICIAL RECORD COPY DOCUMENT NAME: SOMIGSUM.805 29005:1
I-Southern California Edison Company -
Conditions During and Following a Accident," should be considered when creating the list of parameters to be evaluated, which SCE agreed to do. The staff will examine, on a limited basis, a representative sample of E01s once the licensee has reached an appropriate stage in this program.
b Mel B. Fields, Project Manager Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosures:
1.
Attendance List 2.
Viewgraphs cc w/ enclosures:
See next page l
s J
i l
Southern California Edison Company San Onofre Nuclear Generating Station, Unit Nos. 2 and 3 cc:
T. E. Oubre, Esq.
Mr. Thomas E. Bostrom, Project Manager 1
Southern California Edison Company Bechtel Power Corporation Irvine Operations Center 12440 E. Imperial Highway 23 Parker Street Norwalk, California 90550 Irvine, California 92718 Mr. Robert G. Lacy Chairman, Board of Supervisors Manager, Nuclear Department County of San Diego San Diego Gas & Electric Company 1600 Pacific Highway, Room 335 P. O. Box 1831 San Diego, California 92101 San Diego, California 92112 s
Alan R. Watts, Esq.
Mr. Steve Hsu Rourke & Woodruff Radiologic Health Branch 701 S. Parker St. No. 7000 State Department of Health Services i
Orange, California 92668-4702 Post Office Box 942732 Sacremento, California 94234 Mr. Sherwin Harris Resource Project Manager Resident Inspector / San Onofre NPS Public Utilities Department c/o U.S. Nuclear Regulatory Commission City of Riverside Post Office Box 4329 3900 Main Street San Clemente, California 92674 Riverside, California 92522 Mayor L
Mr. Charles B. Brinkman, Manager City of San Clemente Washington Nuclear Operations 100 Avenida Presidio ABB Combustion Engineering Nuclear Power San Clemente, California 92672 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. R. W. Krieger, Vice President 1450 Maria Lane, Suite 210 Southern California Edison Company Walnut Creek, California 94596 San Onofre Nuclear Generating Station P. O. Box 128 Mr. Edwin A. Guiles San Clemente, California 92674-0128 Vice President Engineering and Operations Mr. Don J. Womeldorf San Diego Gas & Electric Company Chief, Environmental Management Branch 101 Ash Street i
California Department of Health Services San Diego, California 92112 714 P Street, Room 616 Sacramento, California 95814 Mr. Harold B. Ray Senior Vice President Southern California Edison Company 1rvine Operations Center 23 Parker Street Irvine, California 92718 l
MEETING ATTENDANCE AUGUST 5, 1993 EFFECIS OF HARSH ENVIRONMENT ON INSTRUMENT ACCURACIES I
HAME ORGANIZATION Mel Fields NRC/NRR/DRPW Cliff Doutt NRC/NRR/HICB
- 5. V. Athavale NRC/NRR/HICB Walter C. Marsh SCE Hukam Garg NRC/NRR/HICB Mike Wharton SCE Richard Bochorst SCE Brian Woods SCE i
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HARSH ENVIRONMENT EFFECTS ON INSTRUMENTS USED IN EOl's Overview Industry Group Activities Task Overview Scope of Task Task Plan Schedule E
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OVERVIEW - ACCEPTABILITY OF HARSH ENVIRONMENT EFFECTS ON CURRENT EMERGENCY OPERATING INSTRUCTIONS (EOl's) o San Onofre 2&3 Operations Philosophy: STRONG Desire and intent to maintain l
Symptom Based EOl's utilizing REALISTIC post-accident values o Generic validation by Combustion Engineering Owners Group (CEOG) Task 536 i
t l
o San Onofre 2&3 - specific application of CEOG Task 536 criteria I
o Validation by Operating crew simulator exercises:
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Safety Functions Status Check and the inherent safety in utilizing the f
Functional Recovery Procedure I
o Ongoing / Future Validation:
Current re-evaluation of harsh environment effects on instruments affecting EOl's San Onofre 2&3 participation in Severe Accident Working Group evaluations wi mm
o.
HARSH ENVIRONMENT EFFECTS ON INSTRUMENTS USED IN EOl's Industry Group Activities i
No clear industry guidance currently exists Instrument Society of America 67.04 Committee Approval of the Instrument Setpoint Methodology Standard is expected this year.
A technical paper addressing Emergency Operating Procedure values is being prepared.
Combustion Engineering Owners' Group SCE requested CEOG involvement in July,1992
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Technical planning seminar was held in December,1992 Phase 1 of task has been approved by the CEOG l
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HARSH ENVIRONMENT EFFECTS ON INSTRUMENTS USED IN EOl's Task Objective Improve the EOl's and/or the plant design through systematic evaluation of instrument performance, under post-accident conditions.
2
- EOl's should be integrated and focused on probable event sequences and not degraded nor complicated.by excessive consideration of low likelyhood conditions or events.
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-,z HARSH ENVIRONMENT EFFECTS ON INSTRUMENTS USED IN EOl's TASK OVERVIEW Establish parameter list Complete parameter evaluations Revise EOl's and/or implement design changes, as required Train op'erators on revised EOl's
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HARSH ENVIRONMENT EFFECTS ON INSTRUMENTS USED IN EOl's Scope o
The basis for the SONGS Units 2 & 3 EOl's is ABB C-E Emergency Procedure Guidelines, CEN-152, Revision 3 o
A strategy contained. in this document is continually checking safety functions o
History of CEN-152 Revision 0 initial response to June,1981 NUREG-0737, l.C.1 Revision 1 incorporated NRC November,1982 comments Revision 2 Addressed several May,1984 items identified in SER prepared for Revision 1 such as voiding, RCS heat removal, etc.
Revision 3 Addressed NRC concerns relative 1987 to Revision 2 B5
r HARSH ENVIRONMENT EFFECTS ON INSTRUMENTS USED IN EOl's a
Scope E
CEN - 152 SAFETY FUNCTION HIERARCHY r
REACTIVITY CONTROL
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MAINTENANCE OF VITAL AUXILIARIES (AC AND DC POWER)
RCS INVENTORY CONTROL RCS PRESSURE CONTROL CORE HEAT REMOVAL RCS HEAT REMOVAi_
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HARSH ENVIRONMENT EFFECTS ON INSTRUMENTS USED IN EOl's Scope CEN - 152 EVENTS / SONGS EOls CEN - 152 SONGS EVENTS EOls Standard Post-Trip Actions.
SO23-12-1 Diagnostic Actions Reactor Trip Safety Function Status Checks SO23-12-2 (Reactor Trip Recovery)
LOCA SO23-12-3 SGTR SO23-12-4 Excess Steam Demand SO23-12-5 Loss of Feedwater SO23-12-6 Loss of Offsite Power S 023-12-7
. Station Blackout SO23-12-8 Functional Recovery SO23-12-9 B7 U.
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CEN - 152 Safety Function Parameter List Parameters to be evaluated
-i Reactor power Vital AC bus power Non-vital AC bus power Vital AC instrument power DC bus power Pressurizer level RCS Subcooling S/G level S/G pressure RV voiding (RVLMS)
Safety injection flow (HPSI/LPSI/HPSI Hot Leg))
Charging flow CET temperature Pressurizer pressure Feedwater flow T-hot i
T-cold Containment pressure Containment ARMS Steam Plant RMs (MS/ Air Ejector)
Containment sump level Containment temperature CS flow i
Containment hydrogen 1
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HARSH ENVIRONMENT EFFECTS ON INSTRUMENTS USED IN EOl's scope 3
CEN - 152 Safety Function Parameter List Parameters not impacted by Instrument Uncertainties CEA position Contact operation -
Startup Rate Rate of change RCS Boron Chemistry analysis
. Turbine tripped Contact operation Generator breakers Contact operation RCP operation Contact operation CIAS Contact operation Process Radiation Monitor Not used at SONGS E
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... J HARSH ENVIRONMENT EFFECTS ON INSTRUMENTS USED IN EOl's Evaluation Process o From CEN - 152, establish parameters that are used to validate safety functions o Eliminate those parameters not impacted by instrument uncertainties
- Contact operation
- Chemistry analyses
- Rate of change indications j
- Not used at SONGS l
o identify the uses ass 6ciated with each remaining parameter o Document those parameter /uses not used as operator decision points-(ODPs)
- Trending
- Nominal control values o Document those parameter /uses which have no significant safety function o Apply instrument uncertainties to remaining parameter /uses B10-
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i HARSH ENVIRONMENT EFFECTS ON INSTRUMENTS USED IN EOl's Sample Evaluation Preliminary Results i
Steam Generator Pressure i
TABLE 2.2-1 EOI STEP VALUE ANALYSIS
SUMMARY
I current Calculated Calculated Step Para *eter Uses E01 Step Step value Value DC7 Value (PSIA)
(PSIA)
(YES/WO) to confirm LOTW diagnosis er to verify espected pcst trip S/G pressure response er to alert the cperator that an over cocting event is in progress
> 740 775 No and to initiate MSIS.
1000 1053 YES to ensure an operable S/G for controlled heat remeval by verifying $$CS operational and 1000 775 YES I
controtting at setpoint.
< $0 PSID fo verify PIR pressure is reduced to within 50 psi PZR Note 1 N/A of the isclated (ruptured) S/G pressure.
< 50 PS]D Wete 1 N/A P2R I
To monitor lowering RCS pressure to < S/G pressure
> P2R to restore the isolated S/G level to less than 80%
Pressure Note 1 N/A kR.
< MFP Disch.
To verify MFW pg operating ard feeding $/G.
Note 2 N/A fo verify the MSSVs are controtting S/G pressure
=1100 1104 YES in the event that S/G pressure can not be controtted using the ADVs.
=1100 1123 YES To permit the use of alterrate low pressure feed ster source.
< $0 Note 3 N/A To permit use of alternate low pressure feedwater source.
< 500 433.67 NO
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< Cond.
l To verify feedwater supply to S/Gs.
Pg Note 2 N/A Disch.
To verify adequate steam supply pressure for operation of steam driven AFV pep.
> 100 206 NO To ensure RCS pressure remains higher than ruptured S/G pressure in order to minimitt RCS
< PZR Note 1 N/A dilution due to backflow.
Pressure Note 1: No significant Safety Punction, see sections 5.5 & 8.5.1 Note 2 No significant safety Punction, see sections 5.5 & 8.5.2 Note 3: No significant Safety Punction, see sections 5.5 & 8.5.3 B12 l
HARSH ENVIRONMENT EFFECTS ON INSTRUMENTS USED-IN-EOl's
- i I
Schedule Start Date:
APRIL,1993
+
b Evalulations Complete: DECEMBER,1994 implementation Complete: CYCLE 8/9
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HARSH ENVIRONMENT EFFECTS ON INSTRUMENTS:USED IN EOl's Summary Previously completed evaluations have confirmed that current EOl's are satisfactory Scope of the task will address parameters that have a significant safety function Methods used will be generally consistent with industry methods (ISA & CEOG)
Completion of the task by Cycle 8/9 will allow prudent implementation of results
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814 i
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