ML20062F112
| ML20062F112 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/15/1990 |
| From: | Dromerick A Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9011270092 | |
| Download: ML20062F112 (17) | |
Text
November 15, 1990 bocketfile50-219 DISTRIBUTION JPD1-4 File
./ Docket;fUe NRC & L PDRs JStolz FMiraglia ADromerick LICENSEE: GPU Nuclear Corporation JPartlow OGC Jersey Central Power & Light Company SVarga EJordan EGreenman ACRS(10)
FACILITY: Oystec Creek Nuclear Generating Station SNorris JCaldwell F0rr tilBJECT:
SUMMARY
OF NOVEMBER 7, 1990 MEETING WITH GPU NUCLEAR LPhillips CORPORATION (GPUN) TO DISCUSS MATTERS RELATED TO OYSTER HAbelson CREEK FUEL CHANNEL B0WlHG.
On Wednesday, November 7,1990, a meeting was held at the NRC, One White Flint North Rockville, Maryland with GPUN the licensee to discuss fuel channel bowing and reuse of fuel channels at the Oyster Creek Nuclear Generating Station. Enclosure 1 is the list of participants that attended the meeting. is the licensee's agenda. The following is a summary of the significant items discussed.
The licensee presented an overview of reuse of fuel channel at Oyster Creek.
GPUN also discussed in detail (1) fuel channel history, (2) fuel channel fabrication specification development, (3) reasons for channel bowing, (4) cycle 13 channel reuse strategy, (5) predicted end of cycle 13 channel bow, (6) methodology to adjust critical power ratio calculations to account
.for fuel channel bow, and (7) channel bow model revision.
Detailed discsssions were held on each of the above items. As a result of these discussions, GPUN indicated that they would submit a cycle 13 specific analysis of the affects of fuel channel bowing by December 1990.
The staff advised tne licensee to expedite GPUN's submittal to assure that the staff complete its review prior to start up of the reactor from the 13R refueling outage.
N Alexander W. Dromerick, Senior Project Manager Project Directorate I-4 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ enclosure:
See next page
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nog Mr. E. E. Fitzpatrick Oyster Creek Nuclear Oyster Creek Nuclear Generating Station Generating Station Cc:
Ernest L. Blake, Jr.
Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 2300 N Street, NW Post Office Box 445 Washington, D.C.
20037 Forked River, New Jersey 08731 Comissioner I. H. Jolles, Executive Vice President New Jersey Department of Energy GPU Service Corporation 101 Commerce Street 100 Interpace Parkway Newark, New Jersey 07102 Parsipanny, New Jersey 07054 Kent Tosch, Chief Regional Administrator, Region I New Jersey Department of Environmental
-U.S. Nuclear Regulatory Commission Protection 475 Allendale Road Bureau of Nuclear Engineering King of Prussia, Pennsylvania 19406 CN 415 Trenton, New Jersey 08625 BWR Licensing Manager
_ GPU Nuclear Corporation-i L
1 Upper Pond Road Parsippany, New Jersey 07054 Mayor Lacey Township l
818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager j
Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency. Bldg.
P. O. Box 388 Forked River, New Jersey '08731 l
L i
3; t.-
ENC _LOSURE'1 DOCKET _NO._50-219 MEETING - NOVEMBER 7,_1990 ATTENDANCE _LI_ST HAME OPGANIZATION A.W. Dromerick NRR-PDI-4 Larry' Phillips NRR/ DST /SRXB John F. Stolz-NRR/PDI-4 Robert C. Jones NRR/ DST /SRXB Tony Attard NRR/ DST /SRXB Harvey Abelson NRR/ DST /SRXB.
Gordon Bond GPUN-Director, Systems Engr.
i Ronald Furia GPUN-Mgr-OC Fuel Projects Phillip Kasik MPR Assoc.
John Rogers GPUN-Senior Licensing Engineer F. Orr NRR/PDI-4 7
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L OYSTER CREEK NUCLEAR GENERATING STATION REUSE OF FUEL CHANNELS l
GPUN/NRC
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l TECHNICAL MEETING L
NOVEMBER 7,1990 h
L
^*9 REUSE OF FUEL CHANNELE OVERVIEW GPU NUCLEAR CHANNEL MEASUREMENT HISTORY GPU NUCLEAR CHANNEL FABRICATION SPECIFICATION DEVELOPMENT REASONS FOR CHANNEL BOWING CYCLE 13 CHANNEL REUSE STRATEGY PREDICTED FOC 13 CHANNEL BOW METHODOLOGY TO ADJUST CPR CALCULATION TO ACCOUNT FOR FUEL CHANNEL BOW CHANNEL BOW MODEL REVISION CONCLUSION t
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M GPU NUCLEAR CHANNFL NEASUEntENT HISTORY EARLY IN PLANT LIFE POOR CHANNEL PERFORMANCE RECOGNIZED AS POTENTIAL PROBLEM BOW, CREEP, CORROSION OBSERVED RECOGNIZED NEED TO IMPROVE CHANNEL PERFORMANCE IN THESE AREAS 1977 (0YSTER CREEK CYCLE MEASURED FIRST CHANNELS l
l USING GPUN'S CHANNEL MEASUREMENT EQUIPMENT i
DESIGNED BY MPR ASSOCIATES AND GPUN FIRST AUTOMATED MEASUREMENT SYSTEM IN THIS COUNTRY LARGE FUEL CHANNEL BOWS MEASURED AT L
OYSTER CREEK-ONGOING CAMPAIGN OF CHANNEL MEASUREMENTS MEASUREMENT PROGRAM DEVELOPED TO MEASURE SELF.0TIVE CHANNELS:TO MONITOR CHANNEL-BOW BEHAVIOR DURING ONE AND-TWO FUEL BUNDLE LIFETIMES GPU-Ci!ANNEL MEASUREMENT PROGRAM DOCUMENTED IN GPU
-AND MPk DOCUMENTS 1
a l
2 1
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v-v
GPU NUCLEAR CHANNEL FAq;je idW SPECIFICATION DEVELOPMENT 1974 INITIAL CHANNEL FABRICATION SPECIFICATION DEVELOPED ANNEALED 14-DAY ~ CORROSION TEST MATCHED HALVES CHARACTERIZED TIGHTER AS-BUILT BOW TOLERANCES BOW ORIENTATION 1976 GPU CHANNEL MANAGEMENT PROGRAM DEVELOPED GOAL WAS ESTABLISHED TO DEVELOP AND JUSTIFY A:TWO-BUNDLE LIFETIME CHANNEL GOAL WAS TO BE ACHIEVED BY FABRICATION SPECIFICATION, MEASUREMENTS, AND ANALYSIS R & D FOR CHANNEL DEVF.LOPMENT ANODIZED CHEM-MILLED V. EAT TREATHENT ADVANCED DESIGN' CHANNEL'(1991).
ADVANCE r,ESIGN CHANNELS ARE EXPECTED.TO BOW-HALF-AS MUCH - AS THE-CURRENT CHANNELS' IN ALL REGIONS OF THE CORf-OYSTER CREEK WILL LOAD FOUR (4) OF THESE CHANNELS IN THE CENTRAL.AND ADJACENT REGIONS OF THE CORE THESE CHANNELS WILL BE EVALUATED AS PART OF THE CHANNEL MEASUREMENT PROGRAM CHANNEL FABRICATION SPECIFICATION BEING REVISED AS NEW MEASUREMENTS BECOME AVAILABLE
-... - - - ~
l REASONS FOR CHANNEL B0 WING MATERIAL DROPERTIES l
Un4 MATCHED HALVES HAVING DISSTMILAR ZIRCALOY PROPERTXES RESIDUAL STRESSES FROM COLD WORKING DIFFERENTIAL OXIDE GROWTH MATERIAL PROPERTIES COMPENSATED BY:
MATCHED CHANNEL HALVES OR THE USE OF SINGLE ZIRCALOY BLANKS ANNEALING p
BETTER CONTROL OF MATERIAL PROCESSING t
DIFFERENTIAL FAST NEUTROM FLUENCE CORE 1 EDGE EFFECTS
-PRESENCE OF CONTROL RODS.-
LOADING-PATTERNS DIFFERENTIALLFAST NEUTRON FLUENCE COMPENSATED BY:
CONTROLLING LOCATION OF CHANNELS
' CHANNELS RESIDING NEAR THE EDGE OF THE CORE ARE NOT CANDIDATES FOR REUSE
.<f L
L 1
1-1
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" *4 ACCELERATED GROWTH 1
TEST DATA SHOWS ACCELERATED GROWTH FOR ANNEALED ZIRCALOY-4 COMMENCES AT A FAST NEUTRON FLUENCE OF APPROXIMATELY 22
-2 1.5 x 10 CM OYSTER CREEK CHANNELS HAVING APPROXIMATELY 62 GWD/MTu HAVE A PEAK NEUTRON FLUENCE OF i
22
-2 APPROXIMATELY 1.3 x 10 CM l
ACCELERATED GROWTH NOT SEEN OR EXPECTED L
ACCELERATED GROWTH DOES NOT NECESSARILY MEAN ACCELERATED BOWING g.{.
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CYCLN 13 CHANNEL REUSE STRATEGY -
MEASUREMENT OF SELECTED CHANNELS AT EOC 12:
1)
- ADDITIONAL DATA FOR CENTRAL REGION BOW OgggiggPECIALLYIN THE HIGH 2)
WITH LARGE PREDICTED BOWS DISCHARGE REUSED CHANNELS THAT ARE EXCESSIVELY BOWED DUE TO REGULATORY UNCERTAINTIES LIMIT CYCLE 13 TO EIGHT (8t PREVIOU8LY INSTALLED REUSED CHANN ELS, ON RELOAD FUEL NOTE - WILL BE "C" HISTORY CHANNELS 4
PREDICTED EOC 13 CHANNEL BOW gYCLpNT PRglDESIGNCTIONS BASED UPON PRELIMINARY URR 13 CO l
L 118 CHANNELS SCHEDULED FOR REUSE IN CYCLE _13 (SEE FIGURE 1) l PROJECTED EOC 13 CORE AVERAGE BOW IS 51 MILS FIGURE 2 IDENTIFIED PREDICTED EOC 13 MAXIMUM CHANNEL BOWS
- REUSED CHANNELS ARE CIRCLED
- AVERAGE REUSED CHANNEL BOW IS 104 MILS TABLE 1 LISTS ALL CHANNELS HAVING PREDICTED EOC 13 BOWS GREATER THAN 150 MILS:
-NOTE-CHANNELS RESIDING IN THE' ADJACENT REGION DURING THElR INITIAL CYCLE ARE -
PREDICTED TO HAVE A LARGE BOW L
MODEL APPEARS TO BE CONSERVATIVE i
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d METHODOLOGY TO ADJUST CPR CALCULATION TO 1CCOUNT FOR FUEL CHANNEL BOW DESCRIBED IN DETAIL IN PAST SUBMITTALS l
FOR NON REUSED CHANNELL T. HE AVERAGE CORE i
CPR PENALTY IS SIMILAR TO THE GENERAL ELECTRIC METHODOLOGY
~
FOR LIMITING BUNDLES WITH REUSED CHANNELS CPR PENALTY BASED ON THE LARGER BOW OF EITHER:
- FUEL CELL AVERAGE OR LIMITING BUNDLE BOW LIMITING CPR BUNDLES AND MAXIMUM CHANNEL BOW IDENTIFIED BY GPUN CODES l
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CHANNEL BOW MODEL REVISION MEN %"NWuh'#aWP REVIEW WILL INCLUDE THE FOLLOWING:
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COMPARISON OF MEASURED TO PREDICTED DATA 2) ggTgF CENTRAL BOW MEASUREMENTS TO 3) g g g gC g g g O g ODELTO I
CONCLUSION THE GPU NUCLEAR CORPORATION HAS A COMPREHENSIVE PROGRAM TO CONTROL AND COMPENSATE FOR CHANNEL BOWING FROM ONE AND TWO FUEL bub'DLE LIFETIME CHANNELS.
THIS PROGRAM CONSISTS OF A DETAILED CHANNEL FABRICATION SPECIFICATION, CORE DESIGN, CONTROL OF CHANNEL USE AND A CYCLE SPECIFIC CPR PENALTY TO ACCOUNT FOR THE CHANNEL BOW OF ONE AND TWO BUNDLE LIFETIME CHANNELS.
IT IS CONCLUDED THAT THE RISK OF FUEL FAILURES DUE TO CHANNEL BOW 18 NEGLIGIBLE IN THE VERY UNLIKELY EVENT THAT FUEL FAILURE DOES OCCUR, THE FAILURES WOULD BE LIMITED, DETECTABLE AND WOULD NOT RESULT IN EXCEEDING EITHER REACTOR COOLANT OR RELEASE RATE TECHNICAL SPECIFICATIONS.
4
FIGURE 1
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s TABLE 1 NRC TECHNICAL MEETING WITH CPU NUCLEAR NOVEMBER 7.
1990 EOC,13 PREDICTED FUEL CHANNEL BOWS GREATER THAN 150 MILS OYSTER CREEK NGS CHANNEL-CORE EXPOSURE MAX. BOW S/N HISTORY GWD/MTU MILS 575C ACC-CCC 57.8 264
'138C ACCC-ACC 55.3 219 164C ACCC--CCC 57.0 218 166C ACCC-CCC 56.9 200
'121C ACCC--CCC 56.9 200 159C CCCC-ACC 64.9 198 2747E AC 23.1 171 2821E AC 23.1 171 9472D AC 23.0 171
- 6142D ACC 30.7 170 6101D ACC 30,7 170 60630 ACC 30.7 170 6171D-AACP 10.7 170
'7840D AC 23.0 170 7852D AC 23.0 170 2824E AC-23.0 170_
'8585C AACP 28.0 168-779D.
AACP 28.0 168 703D
.AACP 27.9 168 699D
-AACP 27.9 168 L
50009 ~
CCCC--AC 58.1 166 130C.
CCCC--ACC 57.4 163 50090-CCCC--CCC 59.2 162 50030 CCCC--CCC 59.1 162 711D AACP 28.3 161-8520C AACP 29.0 161'
.50062-CCCC--CCC 58.7 160
,. 408C.
CCC-ACC 56.5 160 50100 CCC--ACC 56.3 159 50024 CCCC--CCC 58.4 158'
'50086 CCCC--CCC 58.4 158 50059 CCCC--AC 56.1 158 50084 CCCC--CCC 58.0 155 215C' CCCC--CCC 57.6 153 192C CCCC--CCC 57.4 152
,