ML17317A837
| ML17317A837 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/20/1978 |
| From: | Tillinghast J INDIANA MICHIGAN POWER CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:00108, AEP:NRC:108, NUDOCS 7812290179 | |
| Download: ML17317A837 (6) | |
Text
REGULATO INFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION NBR-7812290179 DOC.DATE: 78/12/20 NOTARIZFD~
NO FACIL:50-315 DONALD C COOK Nl, INDIANA R MICHIGAN ELECTRIC CO.
AUTH.NAME AUTHOR AFFILIATION TILLINGHAST,J.
IN 8 MI PNR RECIP.NAME RECIPIENT AFFILIATION DENTON,HER. 'FFICE OF NUCLEAR REACTOR REGULATI.ON SUBJECT-Provides prelim info re plans for next refueling outage of subj faci 1.Current operating cycle should end in late March or early April, 1979lstartup of next cycle is expected in May 1979.No Tech Spec changes foreseen.
DOCKET 4P 05 0003 15 N<>TESi M a E.
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DISTRIBUTION CODE:
A001S COPIES RECEI VEDtLTR 9 ENCL ~ SIZF.:~
TITLE: GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPFRATING LIC RFCI P I ENT ID,COD F/MAME ACTION-05 BC 0!78'~I INTERNAL-FG FILE 12 I8, 15 CORE PERF BR 17 ENGR BR 19 PLANT SYS BR 21 EFLT TRT SYS EXTERNAL: 03 LPDR 23 ACRS COPIES LTTR ENC 7
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TOTAL NUMBER OF COPIES REQUI RED-LTTR 38 ENCL
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INDIANA Ia MICHIGAN POWER COMPANY P. O. BOX 18 Bo WLI N G G R E EN STAT ION NEW YORK, N. Y. 10004 December 20, 1978 AEP: NRC: 00108 Donald C.
Cook Nuclear Plant Unit No.
1 Docket No. 50-315 License No.
DPR-58 Refueling Outage Plans Mr. Harold R.
Denton Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
This letter provides preliminary information concerning. the plans for the next refueling outage of the Donald C.
Cook Nuclear Plant Unit No.
1.
The current operating cycle (Cycle 3) is expected to end approximately in late March or early April, 1979.
The startup of Cycle 4 is expected in May, 1979.
The new fuel batch will consist of sixty-four fuel assemblies manufactured by the Exxon Nuclear Company and enriched to 2.90 w/o U-235.
Sixty-four fuel assemblies which were manufactured by the Westinghouse Electric Company and were part of the inital core will be removed.
The Cycle 4 core will consist entirely of Exxon fuel.
The reload fuel has the same mechanical and thermal hydraulic design parameters as the previous two Exxon reload fuel batches.
The performance analysis and safety analysis methods and procedures for the Cycle 4 reload are the same as for the Cycle 3 reload.
At this time, we do not foresee a need for any Technical Specification changes as a result of the refueling and the operation of Cycle 4 except for the removal of the part-length control rods as noted below.
We expect to review the reload core fuel design and safety analysis approximately three months prior to the startup of Cycle 4.
Activities other than refueling which are expected to take place during the outage are removal of the part-length control, rods and installation of anti-rotation devices on the part-length control rod drive
- shafts, and ice basket water addition.
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REGULQQRY DOCKET FILE COPY Q@ '0
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Denton December 20, 1978 AEP:NRC:00108 The removal of the part-length control rods will require amendments to the Final Safety Analysis Report and to the Technical Specifications.
This change has already been reviewed,
- approved, and accomplished in Unit 2, except that the installation of permanent anti-rotation devices in Unit 2 will be made during a future outage.
In order to satisfy the Surveillance Requirements of the ice condenser Technical Specifications, we expect that it will be necessary to increase the ice inventory in two or more row groups during the refueling outage.
This expectation is based on the ice weights and ice loss rates determined as a result of the last Unit 1
ice weighing program conducted in April and Nay, 1978.
We therefore plan to increase the ice inventory in the baskets in these sub-groups by means of the water addition method.
This method has previously been applied successfully to a small group of baskets in this ice condenser, as described in the report "Long Term Evaluation of the Ice Condenser System - Results of the January 1977 Ice Weighing Program", forty copies of which were transmitted to your office by oly letter of June 7, 1977.
JT/emc Sworn and suscribed to before me this-.i-'"hidey of.~ember, 1978 in New York County, New York Very truly yours, i
!((r'- ~
.'="'ohn Ti'1 1 i'nghast Vice President
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