ML17318A549

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Discusses Peaking Factor Limits in Light of Revised ECCS Analysis.Peak Factor Limit Administratively Reduced to Value of 1.99 from 2.11.Forwards Revision to Tech Specs Incorporating Reduced Limits
ML17318A549
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 01/09/1980
From: Dolan J
INDIANA MICHIGAN POWER CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML17318A550 List:
References
RTR-NUREG-0630, RTR-NUREG-630 NUDOCS 8001140461
Download: ML17318A549 (7)


Text

REGUI.A1'0 INFORMATION DISTRIBUTION STEM (RIDS)

ACCESSION NBR:8001100461 DOC,OATEN'0/01/09 NOTARIZED! NO DOCKET FABRIC 50 316 Dona)8 C ~ Cook Nucl'ear Power Pl anti" Onit 2g "Indiana 8 05000316 AOTH, NAME AU1 HOA AFF EL I

~ ED Indiana 8 Hichigan Power Co.

ATION'OLAAiJ HECIP,NAME RECIPIENT AFFILIATION DNTONeH ~ RE Office of NucTear Reactor Regulatian

SUBJECT:

Discusses peaking factor limits in light of revised ECCS ana'lysis,Peak factor limit administi atively reduced to valve of 1 '9 fram 2.liiForwards revision to Tech Specs incorporating reduced limits, CODE: A039S COPIES RECEIVEDeLTR g ENCL

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INDIANA II'MICHIGAN ELECTRIC COMPANY P. O. BOX 18 BOWLING GR E EN STATION NEW YORK, N. Y. 10004 January 9, 1980 AEP:NRC:003228 Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74

Subject:

Peaking Factor Limits at Unit 2 in Light of Revised ECCS Analysis Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr.'Denton:

As a result of the revised ECCS analysis performed for Donald C. Cook Nuclear Plant Unit 2 by Westinghouse Electric Corporation using their February 1978 evaluation model and in-.

corporating into the analysis the potential impact of the clad behavior data presented in draft NUREG-0630, we have discovered that our current limit on Fq of 2; ll should be reduced to a value of 1.99. A discussion'f the basis for this change is enclosed as Attachment A. Upon the discovery of this reduction we informed the NRC staff and stated in our letter of January 8, 1980 (AEP:NRC:00322A} that we would administratively limit the Fq of Unit 2 to 1.99. Further, unti 1 the NRC staff approves the Technical Specification changes- discussed below, we, will not operate Unit 2 in any mode in which the new Fq limits apply.

The Fq limit affects numerous Technical Specifications. In our letter of November 2, 1979 (AEP:NRC:00297}, we submitted Technical Specification change requests related to Fg .limits along with the required license:.',amendment fee. At that time, our moti-vation was to bring the actual Technical Specifications in line with the administrative limits which resulted from the discovery of a calculational'error in Westinghouse's October 1975 evaluation model and subsequent issuance of the NRC order. In light of the latest 0

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Mr. Harold R. Denton, Director AEP:NRC:003228 e

results, we wish to update the outstanding Technical Specification change requests to incorporate the F limit of 1.99. A detailed description of the changes involved 3re presented in Attachment B to this letter.

Since the change requests of interest have already been formally requested and paid for as a Class III License Amendment for Unit 2, payment of additional fees is deemed unwarranted.

Very truly yours, JED:em John E. Dolan

. Vice President cc: R. C. Callen G. Charnoff R. W. Jurgensen R. S. Hunter D. V. Shaller -Bridgman

Mr. Harold,R. Denton, Director AEP:NRC:00322B bc: S. J. Milioti/J. I. Castresana/V. P. Manno J. G. Del Percio/K. J. Vehstedt H. L. Sobel/J. J. Heiss R. F." Hering/S. H. Steinhart/J. A. Kobyra R. F. Kroeger H. N. Scherer, Jr./S.H. Horowitz/J. M. Intrabartola E. A. Smarrella/V. VanderBurg-Bridgman J. F. Stietzel-Bridgman D. Pligginton-NRC Cook Plant Resident NRC Inspector DC-N-6015.1 DC-N-6665.7 AEP:NRC:00322 AEP:NRC:00322A AEP:NRC:00322B

ATTACHMENT A TO AEP:NRC:00322B DONALD C. COOK NUCLEAR PLANT UNIT NO. 2 DOCKET NO. SO-316 LICENSE NO. DPR-74