ML20082G461
| ML20082G461 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/09/1991 |
| From: | Devine J GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 5000-91-2061, C321-91-2214, NUDOCS 9108190135 | |
| Download: ML20082G461 (5) | |
Text
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One Upper Pond Road M
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Parsippany, New Jersey 07054 3 '
201-316-7000 TE LEX 136-482 Wnters Direct Diat Number August 9, 1991 5000-91-2061 C321-9)-2214 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
0YSTER CREEK NUCLEAR GENERATING STATION (OCNGS)
DOCKET N0. 50-219, LICENSE NO. OPR-16 OYSTER CREEK FUEL CHANNEL BOWING
Reference:
(15 NRC letter, March 11, 1991, " Evaluation of Response to NRC Bulletin 90-02 for Oyster Creek Nuclear Generating Station, TAC No. 76342."
(2)
GPU Nuclear letter, April 10, 1991, agreement to Submit E0C 12 Measurements and Data Compo.ison."
Reference (1) provided the NRC Safety Evaluation and concluded that GPU Nucl:ar's response to NRC Bulletin 90-02 for the upcoming Cycle 13 was
, disfactory with the following condition:
Following End of Cycle (E00) 12, measured data from EOC 12 reused channels destined to te used in operating cycle 13, be compared to predicted E0C 12 calculated data for the purpose of verification and possible modification of the analytical channel box bow model.
The results of this comparison and any modifications to be made to the model, should Sa submitted to the NRC for review.
In addition, its application to any future channel reuse must be evaluated on a cycle specific basis.
In Reference (2), GPU Nuclear agreed to comply with the above condition and to submit to the NRC the required comparison and any required model modifications 60 days after the measured data is obtained.
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In compliance with this agreement, GPU Nuclear is submitting the results of the fuel channel measurements and bow model data following channel measurement at the end of cycle 12. The attached tables contain the EOC measurements and a comparison of predicted and measured data for those reused 5annels reinserted in cycle 13.
The attached figure shows the bcw model correlation including the new data from the E0C 12 measurements.
As can be seen there arc six (6) data points from three (3} channels at exposures greater than 50 GWD/MTV that are significantly greater than the calculated bows. This appears to be due to the effect of control rods, which is not accounted for in the current GPU Nuclear model, it was observed that these second lifetime channels resided in rodded cells of control cell core operation during cycle 12.
Although these bundles were discharged, it is expected that similar bows will be seen by some reused channels in cycle 13, GPU Nuclear has evaluated the impact of the higher than expecttd bows in the rodded locations for cycles 12 and 13.
The evaluation concluded that the magnitude of the higher average bow in the rodded cells would not make the fuel in that cell limiting.
Using the current bow model adjusted R factors, the fuel in the rodded control cells typically operate with greater than 15% margin to CPI limits due to the presence of control rods and high exposure fuel.
The decre, se in CPR for the high bow channels is 5%, leaving at least a 10% margin to CPR limits. The predicted bows in the limiting core locations for cycle 13 dre unCiTnged from What Was previously submitted.
GPU Nuclear is developing the revised bow model and evaluating its impact on the fuel channel reuse program. The NRC will be informed of any changes in the bow model or in the GPU Nuclear fuel channel reuse program when the evaluation is completed by December 31, 1991.
If you have any questions on this submittal, please contact Mr. Michael Laggart, Manager, Corporate Nuclear Licensing at (201) 316-7968.
Very trul yours, M
J. C. DeVine, Jr.
Vice President, Technical Functions JCD/RZ/plp Attachment cc:
Administrator, Region 1 NRC Resident Inspector NRC Oyster Creek Project Manager RZ.C3212214 LET
RESULTS OF THE OYSTER CREEK EOC 12 REUSED FUEL CHANNEL MEASUREMENTS CORE HISTORY TOTAL MEASURED MEASURED CHANNEL EXPOSURE EOC 12 EOC 12 111 AT EOC 12 MAX. X-DOW MAX. Y-BOW S/N 23456789012 GWD/MTU INCHES INCHES 248C D
ACCCCCC 61.5 0.346 122C D
CCCCCCC 61.2 0.299 0.398 50099 D
CCCCC AC 56.6 0.239 0.183 50039 D
CCCCCCCP 56.4 0.121 0.030 521C D
CCCCCC 54.2 0.321 0.242 159C D
CCCC AC 54.5 0.249 0.270 123C D
CCCC CCC 54.5 0.066 0.136 205C D
CCCC CCC 52.3 0.311 0.158 234C D
CCCC AA 50.1 0.180 0.238 2G6C CCcc CC 49.1 0.020
-0.061 50066 CCCC AC 48.6 0.113 0.173 575C D
ACC CC 46.5 0.011 0.242 138C D
ACCC AC 44.8 0.107 0.217 164C ACCC CC 46.2 0.119 0.060 121C ACCC CC 45.5
-0.021 0.068 166C ACCC CC 45.6 0.018 0.031 50009 CCCC AC 47.7 0.135 0.065 1300 CCCC AC 47.1 0.131 0.105 40BC CCC AC 46.0 0.096 0.050 50100 CCCC AC 45.9 0.165 0.200 50059 CCCC AC 45.5 0.132 0.080 50030 CCCC CC 47.8 0.040
-0.022 50090 CCCC CC 47.8 0.0u7
-0.092 50062 CCCC CC 47.3 0.0b3 0.205 50024 CCCC CC 47.6
-0.126 0.105 50084 CCCC CC 47.6 0.107 0.063 50086 CCCC CC 47.0 0.031
-0.060 192C CCCC CC 46.6 0.089 0.017 215C CCCC CC 46.2 0.047 0.040 50031 PPAP C
26.9
-0.011
-0.049 50011 D
ACC CCC 43.5 0.213 0.162 255C D
CAC ACC 40.7 0.103 0.173 1638C CCP C 34.7
-0.048
-0.025 1727C CCC C 39.5
-0.014
-0.014 50007 CCAPP A 32.0
-0.027 0.057 42 OOC CC C 31.5
-0.051 0.000 5602C CC C 30.7
-0.011 0.051 3294C CC A 29.4 0.011 0.076 50074 C CCC C 41.6 0.089 0.101 523C CCC C 38.8 0.066 0.041 144C D
CAPP CCP 38.2 0.131 0.173 1232C LCC 26.5 0.083 0.109
- HARWARE PROBLEMS, COULD NOT PROCESS MEASURMENT DATA a
D - DISCHARGED AT EOC 12 C - CENTERAL CORE REGION P - PERIPHERAL CORE REGION A - ADJACENT (ROW NEXT TO PERIPHERY) CORE REGION l
COMPARISION OF MEASUsED TO PREDICTED MAXIMUM BOW AT EOC 12 OF REUSED FUEL CHANNELS WHICH WERE REINSERTED IN THE CYCLE 13 TOTAL MAXIMUM MAXIMUM CHANNEL EXPOSURE-MEASURED PREDICTED S/N AT EOC 12 EOC 12 BOW EOC 12 BOW GWD/MTU INCHES INCHES 266C 49.1
-0.061 0.109 50066 48.6 0.173 0.129 164C 46.2 0.119 0.165 121C 45.5 0.068 0.144 166C 45.6 0.031 0.144 50009 47.7-0.135 0.126 130C 47 1
-0.131 0.124 4080 46.0 0.096 0.122 50100 45.9 0.200 0.122 50059 45.5 0.132 0.121.
50030 47.8 0.040 0.103 50090 47.8
-0.092-0.104 50062 47.3 0.205 0.101 50024 47.6
-0.126 0.102 50084 47.6 0.107 0.102
-50086 47.0
-0.060 0.100 192C 46.6 0.089-0.098 2150
.46.2 0.047 0.097 50031' 26.9
-0.019 0.085 1638C 34.7
-0.048 0.041 1727C.
39.5
.-0.014 0.071 50007 32.0 0.057 0.047 4200C 31.5
-0.051 0.048 5602C'
=30.7 0.051 0.046 3294C 29.4 0.076 0.063 50074 41.6' O.101.
0.078 523C. _
_38.8.
0.066 0.069 1232C 26.5 0.109 0.037
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