ML20038C811
| ML20038C811 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 08/25/1981 |
| From: | Parker W DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8112140150 | |
| Download: ML20038C811 (6) | |
Text
I DUKE POWEH COSHMY l'owru liciwiso 422 Sot: Tai Citructi STurnT, CliAug.oTTE, N.
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August 25, 1981 Mr. Jamer P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Re: McGuire Nuclear Station Unit 1 Docket iio. 50-369
Dear Mr. O'Reilly:
J Please find attached a Special Report submitted pursuant to Technical Specifi-cation 6.9.2.
This report concerns violation of T.S. 3.1.1.3, "The moderator temperature coefficient (MTC) shall be: a. less positive than 0 Delta K/K/ F for the all rods withdrawn, beginning of cycle life (BOL), hot zero thermal power condition..."
The actions taken described in the report will ensure the safe operation of the plant and that the health and safety of the public are not affected.
ARTS Very truly yours,
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William O. Parker, Jr.
PBN/php Attachment cc: Director Mr. Bill Lavallee ~
Office of Management and Program Analysis Nuclear Safety Analysis Center U. S. Nuclear Regulatory Commission P. O. Box 10412 Washington, D. C. 20555 Palo Alto, California 94303 Ms. M. J. Graham Resident Inspector-NRC McGuire Nuclear Station UFFICIAL COM' i
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i McGUIRE NUCLEAR STATION SPECIAL REPORT August 25, 1981 During zero power physics testing, the all rods withdrawn, isothermal temperature coefficient was measured as -0.56 PCM/0F. Since this corres-ponds to a moderator temperature coefficient (MTC) of +1.44 PCM/ F, purcuant to Technical Specification 3.1.1.3 the attached interim control rod with-drawal limits have been established for all Mode 1 or 2 operation not covered by special test exception 3.10.3.
These rod withdrawal limits are based on maintaining a negative moderator temperature coefficient at all times.
These limits will be placed in appropriate operating procedures and will remain in effect until such time that sufficient reactor poisons have built up to preclude a positive MTC. This will occur at approximately 40 EFPD.
Since the attached rod withdrawal limits will ensure a negative MTC during power operation, the health and safety of the public are not affected.
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Temporary Withdrawal Limits POWER LEVEL 0 - 9% F.P.
Cb C CB D Boron Steps ud Steps vd pym 180 66 1250 190 76 1225-a 204 90 1200 220 106 1175 228 138 1150 228 183 1125 228 228 1100 228 228 All boron conc.
less than 1100 s
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Temporary Withdrawal Limits POWER LEVEL 10 - 19% F.P.
CB C CB D Boron Steps wd Steps ud ppm 195 81 1250 205 91 1225 22S 118 1200 228 148 1175 228 200 1150 228 228 1125 228 228 All boron conc.
less than 1100 e
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Temporary Withdrawal Limits POWER LEVEL 20 - 29% F.P.
CB C CB D Boron' Steps vd Steps vd g
220 106 1250
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228 135 1225 228 178 1200 22S 228 1175 228 228 All boron conc.
less than 1175 i
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t Temporary Withdrawal Limits POWER LEVEL 30 - 39% F.P.
CB C CB D Boron-Steps ud Steps ud ppm s
228 152 1250 228 210 1225 228 228 1200 228 228 All boron conc.
less than.1200 NOTE:
Withdrawal limits do not apply at power levels in excess of 39% F.P.
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