ML17321A127
| ML17321A127 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/06/1984 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:0878, AEP:NRC:878, NUDOCS 8407120339 | |
| Download: ML17321A127 (6) | |
Text
REGUI.ATORY NFORMATION DISTRIBUTION SY l'EM (RIDS)
ACCESSION NBR:8407120339 DOC ~ DATE: 84/07/06 NOTARIZED: YES DOCKETACIL:50>>316 Donald C,
Cook Nuclear Power Plantr Unit 2< -Indiana 8
05000316 AUTHRNAME AUTHOR AFFILIATION ALEXICH<M,P.
Indiana 8 Michigan Electric Co, RECIP ~ NAME RECIPIENT AFFILIATION DENTON,H.R, Office of Nuclear Reactor Regulationg Director
SUBJECT:
Advises that application for amend to License DPR 74J requesting plant operation w/nuclear enthalpy rise hot channel factor larger, than value currently in effect~may be made on or about 840731
~
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INDIANA8 NICHIGAN ELECTRIC CONPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 July 6, 1984 AEP:NRC:0878 Donald C.
Cook Nuclear Plant Unit No.
2 Docket No. 50-316 License No. DPR-74, ANTICIPATED APPLICATION FOR UNIT 2 TECHNICAL SPECIFICATION CHANGES Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
This letter constitutes notice that an application for amendment to the Donald C.
Cook Nuclear Plant Unit No.
2 Appendix A Technical Specifications (T/S) may be made on or about July 31, 1984.
We anticipate that the proposed amendment Pll request plant operation with a nuclear enthalpy rise hot channel factor (FA
) larger than the value currently in effect.
The proposed amendment is based on a new LOCA analysis being performed by our fuel vendor, Exxon Nuclear Company.
Since final calculations are not yet complete, the applioation can not be made at this time.
When the final calculations become available, there is a probability that the applicatiog will be made on an emergency basis.
This is the case because the curr ent F A H limit specified in the T/S is so restriotive that power deratings may be required early in the cycle.
The plant is expected to begin power escalation within the next week.
Ther efore, we expeot to make comparisons between measured F> H and the existing T/S limit. If the comparisons obtained during power escalation testing show that a derating early in the cycle will be required, an emergency T/S change will be requested.
If the comparisons show that a derating will not be needed, the application for T/S change will request normal processing.
As indicated
- above, the calculational support for the T/S change is not yet available.
However, in order to expedite this matter, my staff has held several discussions and meetings with Exxon during the revisions to Exxon's EXEM/PWR/ECCS model and will continue to do so.
As information becomes available, it will be promptly supplied to you for your review. In particular, on July 6,
- 1984, Exxon Nuclear Company will have submitted for your review:
1)
A preliminary description of the proposed changes to the EXEM/PWR/ECCS model to account for the difference between the axial power distribution used in the Donald C.
Cook Nuclear Plant Unit No. 2 analysis and that employed in the FLECHT SEASET tests.
The FLECHT SEASET test data has been used by Exxon Nuclear Company in the reflood heat transfer correlation in EXEM/PWR ECCS evaluation model.
8407120339 840706 PDR ADOCK'5000316 P
~ '
Mr. Harold R. Denton 2)
Benchmark analyses of EXEM/PWR ECCS model changes relative to the FLECHT skewed tests.
3)
Preliminary results from the application of EXEM/PWR ECCS model changes to the Donald C.
Cook Nuclear Plant Unit No. 2.
The final submission, including the ECCS/LOCA results and the draft T/S changes, is planned for or near July 31, 1984.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, M.. Ale ch iVice President MPA/bJs cc: John E. Dolan W.G. Smith, Jr. - Bridgman R.C. Callen G. Charnoff E.R.
- Swanson, NRC Resident Inspector - Bridgman
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