ML20215H796
| ML20215H796 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/01/1987 |
| From: | Marlone Davis Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8705070057 | |
| Download: ML20215H796 (28) | |
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1 MAY DS7 -
Docket Nos. 50-528 and 50-529 Licensee: Arizona Public Service Company Facility: Palo Verde, Units 1 and 2
Subject:
Sumary of Meeting on Units 1 and 2 Cycle 2 Reloads A meeting was held in Bethesda, Maryland on April 22, 1987, with representatives of the licensee. The purpose of the meeting was to discuss schedules for the Unit 1 Cycle 2 and Unit 2 Cycle 2 core reloads. The meeting was a follow-up to the September 24, 1986 meeting on the same subject.
(see Meeting Summary, dated October 6,1986). Enclosure 1 lists the meeting attendees and the meeting is sumarized as follows:
Sumary:
The licensee's presentation was based on the viewgraphs provided as Enclosure-2.
The points made during the presentation included the following:
1.
In order to develop a staggered fall / spring refueling outage schedule the Unit 1 Cycle 2 reload is planned for a 15 month cycle; and Unit 2 Cycle 2 reload is planned for an 18 nonth cycle.
2.
The schedule and scope of submittals to the NRC was discussed, including the reload analysis report, the modifications to the Statistical Combina-tions of Uncertanties (SCU) methodology, and Technical Specifications changes.
The staff expressed concern about the availability of technical review resources and recommended that the licensee identify the priority items required to be reviewed by the NRC for the reload analysis.
The staff also expressed concern about the problem encountered during the Waterford reload with the Moderator Temperature Coefficient (MTC) initially being positive. The licensee stated that they shared this concern and had reverified their calculations to ensure that the MTC following reload would be significantly more negative than Waterford.
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The staff reminded the licensee that the reload analysis is needed 120 days prior to restart. This assumes that all referenced topical reports and any sifnificant revisions in previously accepted methodology have been reviewed prior to receipt'of the reload analysis.
Grisinal siped W Michael J. Davis, Project Manager Project Directorate No. V Division of Reactor Projects-III/IV/V and Special Projects
Enclosures:
l 1.
Meeting Attendees 2.
Licensee's Presentation DISTRIBUTION 6
NRC PDR Local PDR GKnighton MDavis OGC - Bethesda JPartlow EJordan ACRS (10)
NRC Participants PDS Reading l
k 0:PD5 DRSP/PD5 M /
MJDavis:cdd ghton 04/ As /87 Of/f /87 l
OFFICIAL RECORD COPY
Mr. E. E. Van Brunt, Jr.
Arizona Nuclear Power Project Palo Verde cc:
Arthur C. Gehr. Esq.
Kenneth Berlin, Esq.
Snell & Wilmer Winston & Strawn 3100 Valley Center Suite 500
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Phoenix, Arizona 85073 2550 M Street, NW Washington, DC 20037 Mr. James M. Flenner, Chief Counsel Arizona Corporation Commission Ms. Lynne Bernabei 1200 West Washington Government Accountability Project Phoenix, Arizona 85007 of the Institute for Policy Studies 1901 Que Street, NW Charles R. Kocher, Esq. Assistant Washington, DC 20009 Council James A. Boeletto Esq.
Southern California Edison Company Mr. Ron Rayner P. O. Box 800 P. O. Box 1509 Rosemead, California 91770
" Goodyear, AZ 85338 Mr. Mark %insberg Mr. Charles B. Brinkman, Manager Energy Director Washington Nuclear Operations Office of Economic Planning Combustion Engineering, Inc.
and Development 7910 Woodmont Avenue Suite 1310 1700 West Washington - 5th Floor Bethesda, Maryland 20814 Phoenix, Arizona 85007 Mr. Wayne Shirley Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 Mr. Roy Zimmennan U.S. Nuclear Regulatory Comission P. O. Box 239 Arlington, Arizona 85322 Ms. Patricia Lee Hourihan 6413 S. 26th Street Phoenix, Arizona 85040 Regional Administrator, Region V U. S. Nuclear Regulatory Comission 1450 Maria Lane Suite 210 Walnut Creek, California 94596
s MEETING ATTENDEES Palo Verde 182 Reload Analyses
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NAME AFFILIATION Mike Davis NRC/NRR/PDS
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Larry Kopp NRC/NRR/RSB Paul Crawley APS - Nuclear Fuel Bill Quinn APS - Mgr. Licensing Ron Land APS - Nuclear Fuel Janet Roth APS - Licensing *
- Wayne Hodges
!!RC/NRR/RSB George Knighton NRC/NRP/PDV Manny Licitra NRC/NRR/PDV J. F. Church CE Project Mgr. Reload Fuel Vick Nazareth CE Fuels Michael A Book CE Fuel Engineering Mark R. Kulwich CE Fuel Engineering Bruce Miller APS - Nuclear Fuel
STATUS UPDATE OF PVNGS UNIT 1, CYCLE 2 RELOAD f
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PRESENTED BY l
l ARIZONA NUCLEAR POWER PROJECT AND COMBUSTION ENGINEERING ON APRIL 22, 1987 CEN. 344(V)-NP SUPPLEMENT 1-NP PALO VERDE NUCLEAR GENERATING STATION
s ANPP-NRC-CE MEET)G OUTLINE
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(APRI. 22,
.587) 0 INTRODUCTION 0
RECAP OF LAST MEETING 0
UNIT 1, CYCLE 2 AND UNIT 2, CYCLE 2 OPERATING SCHEDULES 0
0VERVIEW 0F PREVIOUSLY APPROVED NEW METHODOLOGY 0
DETAll.ED CONCEPTUAL PRESENTATION OF SCU METHODOLOGY 0
TECHNICAL SPECIFICATION CHANGES 0
ENVIRONMENTAL REPORT ISSUE O
UNIT 2, CYCLE 2 RELOAD 0
UNITS 2 AND 3 NEW METHODOLOGY IMPLEMENTATION PLAN 0
DESCRIPTION OF CYCLE 1 CPC SOFTWARE REVISION 0
UNIT 1, CYCLE 2 SCHEDULE 0
ANPP ACTION ITEMS / COMMITMENTS
i PVNGS UNIT 1 CYCLE 2 RELOAD MEETING SEPTEMBER 24, 1986
- TOPICS DISCUSSED
- SCHEDULE
- CPC IMPROVEMENT PROGRAM
- MODIFICATION TO STATISTICAL COMBINATION OF UNCERTAINTIES (SCU)
METHODOLOGY
- LARGE BREAK LOCA EVALUATION MODEL
- WESTINGHOUSE FUEL ASSEMBLY DEMONSTRATION PROGRAM
- TECHNICAL SPECIFICATION CHANGES
- OPEN ITEMS
- IDENTIFY TYPE OF VARIABLE OVERPOWER TRIP UTILIZED
- VERIFY PVNGS UNIT 1, CYCLE 2 IS B0UNDED BY OLD LOCA EVALUATION MODEL
- PROVIDE A LIST OF TECHNICAL SPECIFICATION CHANGES
- PROVIDE DRAFT SCU TOPICAL (WITHOUT NUMERICAL DETAIL)
PVNGS UNIT 1 AND UNIT 2 OPERATING SCHEDULES
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END OF PVNGS UNIT 1, CYCLE 1 SEPTEMBER 12, 1987 STARTUP 0F PVNGS UNIT 1, CYCLE 2 NOVEMBER 10, 1987 END OF PVNGS UNIT 2, CYCLE 1 FEBRUARY 21, 1988 STARTUP 0F PVNGS UNIT 2, CYCLE 2 MAY 1, 1988 G
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OVERVIEW 0F NEW METHODOLOGY FOR PVNGS UNIT 1 CYCLE-2 THAT HAS BEEN PREVIOUSLY APPROVED BY THE NRC aC
CLADCOLLAPSEANALYSISAND AUGMENTATION FACTORS o
CYCLE 1 - CLAD COLLAPSE ANALYSIS PERFORMED PER REGULATORY REQUIREMENTS
- AUGMENTATION FACTORS DEVELOPED AND APPLIED FOR INTERPELLET GAP-RELATED POWER PEAKING l
0 EPRI REPORT NP-3966-CCM VOLUME F (APRIL, 1985)
PROVIDES A BASIS TO ELIMINATE CLAD COLLAPSE ANALYSIS FOR CYCLE 2 FUEL INDICATES THAT GAPS AND AUGMENTATION FACTORS FOR CE FUEL TYPE ARE NEGLIGIBLE RELATIVE TO OTHER DESIGN UNCERTAINTIES l
0 NRCSTAFFACCEPTEDTHISCONCLUSION'FORTHEFOLLOWINGREL0hDREVIEWS CALVERT CLIFFS UNIT 1 CYCLE 8 (SER SUPPORTING TECH SPEC AMENDMENT 104 FOR CALVERT CLIFFS DOCKET N0. 50-317)
SONGS UNITS 2 AND 3 CYCLE 3 i
(SER SUPPORTING TECH SPEC AMENDMENT 47 TO OL NPF-10 DOCKE'T NO. 50-361 AND TECH SPEC AMENDMENT 36 TO OL NPF-15 DOCKET NO. 50-362)
ANO UNIT 2 CYCLE 6 WSES UNIT 3 CYCLE 2
CPC IMPROVEMENT PROGRAM O
CYCLE 2 WILL USE CPC AND CEAC SOFTWARE MODIFICATIONS DEVELOPED AS A PART OF THE CPC IMPROVEMENT PROGRAM (CIP)
SOFTWARE MODIFICATIONS IMPROVE PLANT RELIABILITY BY REDUCING INCIDENCE OF SPURIOUS
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TRIPS NRC HAS CONCLUDED THAT CIP RESULTED IN LITTLE NET CHANGE TO PLANT SAFETY t
o CIP SOFTWARE AND METHODOLOGY CHANGES ACCEPTED BY NRC IN " ACCEPTANCE FOR REFERENCING 0F LICENSING TOPICAL REPORT CEN-308-P AND CEN-310-P", DATED MARCH 12, 1986 I
O CIP SOFTWARE IS CURRENTLY IN USE AT SONGS UNITS 2 AND 3, ANO UNIT 2, AND WSES UNIT 3
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RELOAD DATA BLOCK -
O CYCLE 2 WILL EMPLOY RELOAD DATA BLOCK (RDB) CPC AND CEAC CONSTANTS RDB USE ALLOWS CONSTANT CHANGES WITHOUT REQUIRING SOFTWARE CHANGES IN FUTURE CYCLES RDB USE ACCEPTED BY NRC FOR WSES UNIT 3 CYCLE 2 0
GENERIC ACCEPTANCE OF RDB USE IN " ACCEPTANCE FOR REFERENCING 0F LICENSING TOPICAL REPORT t
CEN-330-P REV. 00-P", DATED AUGUST 12, 1986 e
TRANSIENT ANALYSIS - CIP TRIPS O
CYCLE 1 - HARDWARE V0PT CREDITED FOR CEA EJECTION, CEA WITHDRAWAL, SETP0 INT ANALYSIS 1
- FLOW PROJECTED DNBR TRIP IN CPC l
0 CYCLE 2 - CPC SOFTWARE V0PT WILL BE CREDITED FOR ANY EVENT REANALYZED FOR THE RAR I
- 95% (ADDRESSABLE) PUMP SPEED TRIP'IN CPC l
0 IN ITS REVIEW 0F ALL EVENTS REANALYZED FOR THE RELOAD SUBMITTALS FOR SONGS UNITS 2 AND 3 CYCLE 3 AND FOR WSES UNIT 3 CYCLE 2, THE NRC ACCEPTED THE CPC'V0PT AND PUMP SPEED TRIPS l
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- SONGS UNITS 2 AND 3 - SER SUPPORTING TECH SPEC AMENDMENT 47 TO OL NPF-10 DOCKET j
50-361 AND TECH SPEC AMENDMENT 36 TO OL NPF-15 DOCKET 50-362 1
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TRANSIENT ANALYSIS - CREDITS O
CYCLE 1 - STATISTICAL CONVOLUTION OF DNBR WITH DNB PROBABILITY USED TO CALCULATE FUEL FAILURE
- HERMITE SPACE-TIME NEUTRONICS CODE USED FOR SELECTED EVENTS
- OTHER EVENTS USED THE CESEC AND STRIKIN POINT KINETICS CODES AND TOOK NO CREDIT FOR SPACE-TIME SCRAM EFFECTS t
o CYCLE 2 - NRC POSITION ON SONGS UNITS 2 AND 3 CYCLE 3 AND WSES UNIT 3 CYCLE 2 WAS THAT DNBR CONVOLUTION SHOULD NOT BE USED EXCEPT FOR SEIZED ROTOR AND SHEARED SHAFT ANALYSES.
CURRENhPLANFORPVNGS-1 CYCLE 2ISTO CONFORM TO THIS POSITION.
- HERMITE SPACE-TIME CODE WILL AGAIN BE USED FOR SELECTED EVENTS
- POINT KINETICS CALCULATIONS WILL TAKE SOME CREDIT FOR SPACE-TIME EFFECTS ON THE CYCLE 2 SCRAM CURVE TO AVOID UNNECESSARY REANALYSES' e
TRANSIENT ANALYSIS - CREDITS (CONT'D)
O IN ITS REVIEW 0F THE ST. LUCIE-1 CYCLE 4 AND THE CALVERT CLIFFS-1 CYCLE 5 RELOAD SUBMITTALS, THE NRC ACCEPTED PARTIAL SPACE-TIME SCRAM CREDIT FOR STRIKIN ANALYSIS OF LOSS
. OF FLOW o.
THESE ST. LUCIE AND CALVERT CLIFFS SUBMITTALS REFERENCED CEN-123(F)P AND CEN-124(B)P WHICH DESCRIBED STATISTICAL COMBINATION OF UNCERTAINTIES (SCU) METHODS TO BE APPLIED TO SAFETY ANALYSES AND THE USE OF SPACE-TIME SCRAM CREDITS IN ACCORDANCE WITH CEN-122(F) o IN ITS REVIEW 0F THE SONGS UNIT 2 CYCLE 2 RELOAD SUBMITTAL, THE NRC ACCEPTED THE USE OF SPACE-TIME METHODS FOR CALCULATION OF SCRAM CURVES FOR ALL EVENTS (CEN-122(F)),
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l CECOR LIBRARY FOR INCORE MEASUREMENTS 1
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THE CECOR LIBRARY FOR CYCLE 2 WILL BE GENERATED USING THE MC CODE, PREVIOUSLY ACCEPTED FOR i
THE FOLLOWING RELOAD SUBMITTALS 1
I SONGS UNITS 2 AND 3 CYCLES 2 AND 3 l
j ANO UNIT 2 CYCLE 4 j
0 GENERIC ACCEPTANCE OF THE USE OF ROCS AND~DIT CODES WITH THE MC MODULE FOR THIS.
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APPLICATION WAS PROVIDED BY THE NRC IN " ACCEPTANCE FOR REFERENCING OF LICENSING TOPICAL i
REPORT CENPD-266-P, CENPD-266-NP", DATED APRIL 4, 1983 i
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FATES 3A FUEL EVALUATION MODEL o
FUEL PERFORMANCE ANALYSIS FOR CYCLE 2 WILL USE THE FATES 3A CODE WITH THE NRC GRAIN SIZE RESTRICTION PREVIOUSLY ACCEPTED FOR THE FOLLOWING RELOAD SUBMITTALS SONGS UNITS 2 AND 3 CYCLES 2 AND 3 WSES UNIT 3 CYCLE 2 o
GENERIC ACCEPTANCE OF THE FATES 3A CODE WAS PROVIDED BY THE NRC IN LETTER FROM R. A. CLARK (NRC) TO A. E. LUNDVALL (BG8E), " SAFETY EVALUATION OF CEN-161 (FATES 3)", DATED MARCH, 1983 9
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DETAll FD CONCEPTUAL PRESENTATION OF STATISTICAL COMBINATION OF UNCERTAINTIES METHODOLOGY O
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CURRENT SCU PROGRAM DOCUMENTATION
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PALO VERDE
- ENCLOSURE 1-P TO LD-82-054
- SYSTEM PARAMETER SCU
- ENCLOSURE 1-P TO LD-83-010
- STATE PARAMETER SCU FOR LSSS
- ENCLOSURE 2-P TO LD-83-010
- STATE PARAMETER SCU FOR LCO -
WATERFORD - 3
- CEN-343 (C) - P
- STATISTICAL COMBINATION OF UNCERTAINTIES FOR WATERFORD-3 4
- EXPLANATION OF MODIFICATIONS TO SCU FOR CPC IMPROVEMENT PROGRAM
- LETTER FROM J. H. WILSON (NRC) TO J. G. DEWEASE (LP8L),
" RELOAD ANALYSIS REPORT FOR CYCLE 2 AT WATERFORD 3",
DOCKET NO. 50-382
- NRC APPROVAL OF WATERFORD-3 SCU METHODS
TECHNICAL SPECIFICATION CHANGES / PRIORITY TECHNICAL SPECIFICATION NUMBER WILL IT CHANGE?"
REASON 3.1.2.7 M
3.9.1 M
3.10.7 M
l 5.3.1 W
C2 3.3.2 W
C2 2.2.1 8 BASES W
C2/SCU/CII 1
3.1.3.3 M
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l 3.5.2 M
3.3.1 W
SCU 3.1.1.1 W
C2 3.10.1 M
3.10.8 M
2.1.1 & BASES W
C2/SCU 3.1.1.3 W
C2 3.1.3.1 W
C2 l
3.1.3.2 M
3.1.3.5 M
I 3.1.3.6 W
C2 3.2.6 M
1 l
3.2.8 W
C2
" M - AS OF THIS TIME THERE IS A POSSIBILITY OF CHANGE W - THERE WILL BE A CHANGE CIP - CPC IMPROVEMENT PROGRAM SCU - STATISTICAL COMBINATION OF UNCERTAINTIES C2 - CYCLE 2 RELOAD ANALYSIS i
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TECHNICAL SPECIFICATIONS CHANGES / PRIORITY (CONT'D)
TECHNICAL SPECIFICATION NUMBER WILL IT CHANGE 7" REASON 3.10.2 M
3.10.4 M
3.10.5 M
3.10.3 M' '
3.2.1 W
C2 3.2.4 8 BASES W
CIP/C2 3.2.5 W
C2 3.2.7 W
CIP 3.3.3.2 M
M - AS OF THIS TIME THERE IS A POSSIBILITY OF CHANGE W - THERE WILL BE A CHANGE CIP - CPC IMPROVEMENT PROGRAM SCU - STATISTICAL COMBINATION OF UNCERTAINTIES C2 - CYCLE 2 RELOAD ANALYSIS i
)
PVNGS ENVIRONMENTAL REPORT ISSUE
- 10CFR51 TABL'ES S-3 AND S-4 LIMITS THE ALLOWABLE ENRICHMENT AND BURNUP TO 4.0 W/0 U-235 AND 33,000 MWD /MTU RESPECTIVELY ANPP ACTION PLAN
- ANPP WILL USE A MAXIMUM PIN ENRICHMENT OF 4.05 W/0 U-235 IN UNIT 1, CYCLE 2
- AIF-NESP-0.32 STUDY. COMPLETED IN JUNE OF 1985 SHOWS THERE IS NO SIGNIFICANT INCREASE IN ENVIRONMENTAL IMPACT FOR BURNUPS UP TO 45,000 MWD /MTU WITH AN ENRICHMENT OF 4.36 W/0 U-235
- ANPP WILL RELICENSE THE SPENT FUEL POOL AND FUEL HANDLING EQUIPMENT TO 4.3 W/0 U-235 AS SUPPORTED BY EXISTING CRITICALITY STUDIES
- PREVIOUS CONVERSATIONS WITH THE NRC STAFF CONCLUDING WITH A TELEPHONE CONVERSATION ON JANUARY 9, 1987 INDICATED THAT EXCEEDING THE 10CFR51 LIMITS WITH RESPECT TO E.NRICHMENT BY +,05 W/0 U-235 IS ACCEPTABLE
- INFORMATION TO DATE INDICATES THAT THE NRC IS CURRENTLY WORKING IN-HOUSE TO INCREASE THE 10CFR51 LIMITS IN SUPPORT OF EXTENDED CYCLES
PVNGS UNIT 2, CYCLE 2 RELOAD LICENSING SCHEDULE FORECASTED DATE PVNGS UNIT 2, CYCLE 2 KICKOFF MEETING APRIL 22, 1987 SUBMIT NEW METHODOLOGY TO NRC, IF ANY NOVEMBER 16, 1987 SUBMIT ALL TECHNICAL SPECIFICATION CHANGE DECEMBER 28, 1987
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PACKAGES ON COMPUT'ER DISK SUBMIT RELOAD ANALYSIS REPORT DECEMBER 28, 1987 END OF PVNGS UNIT 2, CYCLE 1 FEBRUARY 21, 1988 STARTUP 0F PVNGS UNIT 2, CYCLE 2 MAY 1, 1988 L
NEW METHODOLOGY FOR PVNGS UNIT 2, CYCLE 2 NO ADDITIONAL METHODOLOGY CHANGES OTHER THAN THOSE PROPOSED FOR PVNGS UNIT 1, CYCLE 2
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RR0 GRAM IMPLEMENTATION IN UNITS 2 AND 3
- CPC IMPROVEMENT PROGRAM CURRENTLY SCHEDULED FOR IMPLEMENTATION IN UNIT 2, CYCLE 2 AND UNIT 3, CYCLE 2
- MODIFIED STATISTICAL COMBINATION.0F UNCERTAINTIES PROGRAM
' CURRENTLY SCHEDULED FOR IMPLEMENTATION IN UNIT 2, CYCLE 2 AND UNIT 3, CYCLE 2 Y
CYCLE 1 CORE PROTECTION CALCULATOR SOFTWARE REVISION PURPOSE
- TO REVISE THE CPC SOFTWARE SUCH THAT THE PALO VERDE UNITS DO NOT TRIP DURING A FAST BUS TRANSFER EVENT
- TO ENABLE RELIABLE OPERATION.0F THE PALO VERDE UNITS
..,0FF 0F THE AUXILIARY TRANSFORMERS DESCRIPTION "ZERO OUT" THE CONSTANTS UTILIZED BY THE FLOW PROJECTED DNBR TRIP IN THE FLOW ALGORITHM
- UTILIZE A TRIP BASED ON REACTOR COOLANT PUMP SPEED FOR PROTECTION AGAINST A LOSS OF FLOW TRANSIENT
- SOFTWARE REVISION PREVIOUSLY REVIEWED AND APPROVED BY THE NRC FOR SONGS 2 AND 3 (CEN-284 (S-P), DATED JUNE 1984)
CYCLE 1 CORE PROTECTION CALCULATOR SOFTWARE REVISION (CONT'D)
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ANTICIPATED TECHNICAL SPECIFICATION CHANGES
- NO TECHNICAL SPECIFICATION CHANGE NEEDED
- CURRENT CPC PRIMARY COOLANT PUMP SPEED RESPONSE TIME
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TEST ACCEPTANCE CRITERION IS MORE RESTRICTIVE THAN THE VALUE IN TECHNIC'AL SPECIFlCATION TABLE 3.3-2
- NEED TO REVISE RESPONSE TIME TEST ACCEPTANCE CRITERION TO MAKE IT CONSISTENT WITH THE NEW LOSS OF FLOW ANALYSIS SCHEDULE
- SAFETY EVALUATION TO NRC ON OR ABOUT MAY 15, 1987
- IMPLEMENTATION TARGET DATE - JUNE 15, 1987 APPLICABILITY
- PVNGS UNITS 1, 2, AND 3
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PVNGS UNIT 1 CYCLE 2 RELOAD LICENSING SCHEDULE FORECASTED DATE DETAILED PRESENTATION TO THE NRC ON NEW APRIL 22, 1987 METHODOLOGY l
SUBMIT REV. O TOPICAL REPORT ON REVISED SCU MAY 15, 1987 METHODOLOGY (WITHOUT NUMERICAL DETAIL)
SUBMIT ALL TECHNICAL SPECIFICATION C ANGE JULY 1, 1987 PACKAGES ON COMPUTER DISK l
SUBMIT RELOAD ANALYSIS REPORT JULY 1, 1987 SUBMIT REV. 1 TOPICAL REPORT ON REVISED SCU JULY 15, 1987 METHODOLOGY (WITH NUMERICAL DETAIL) f END OF PVNGS UNIT 1, CYCLE 1 SEPTEMBER 12, 1987 STARTUP OF PVNGS UNIT 1, CYCLE 2 NOVEMBER 10, 1987 l
MK2/NJG l
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