ML18219D106
| ML18219D106 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/18/1978 |
| From: | Shaller D Indiana Michigan Power Co |
| To: | James Keppler NRC/RGN-III |
| References | |
| Download: ML18219D106 (9) | |
Text
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS >
DISTRIBUTION FOR INCOMING MATERIAL 50-316 REC:
KEPPLER J G
NRC ORG:
SHALLER D V IN Cc MI PNR DOCDATE: 05/18/78 DATE RCVD: 05/24/78 DOCTYPE:
LETTER NOTARIZED:
NO COPIES RECEIVED
SUBJECT:
LTR 1
ENCL" 0 CONFIRMlNG TELEPHONE CONVERSATION OF 05/17/78... ADVISING CONDENSER TEMPERAURE RlSE EXCEEDED THE TECH SPEC LIMIT BY APPROX ONE AND ONE-HALF DEGREES FOR A
TEN HOUR PERIOD AND A COMPLETE REPT OF THIS EVENT MILL BE SUBMITTED BY 05/26/78.
PLANT NAME: COOK UNIT 2 REVIEWER INITIAL:
XJM DISTRIBUTOR INITIAL:Q&
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOIJS NOTES:
i.
SEND 3 COPIES OF ALL MATERIAL TO IS.E ENVIRONMENTAL EVENT/ABNORMAL OCCURENCE
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FOR INFO:
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44neacsn NDIANA& MICIIIGANPDNER COMP N DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 May 18, 1978 Mr. J.G.
- Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Colission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-74 Docket No. 50-316
Dear Mr. Keppler:
This is to confirm our telephone report to Mr. Warnick, NRC, Chief of Reactor Projects,Section II, at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> on May 17, 1978.
At that time we reported that the condenser AT (temperature rise) exceeded the Technical Specification limit by approximately one and one-half degrees for a ten hour period.
A complete report of this event will be submitted by Nay 26,
- 1978, as required by Appendix B Technical Specifications Section 5.4.2. 1.
Sincerely, D.V. Shaller Plant Manager
/bab cc:
J.E.
Dolan R.W. Jurgensen R':F. Kroeger R. Kilburn R.J. Vollen BPI K.R. Baker-RO:III R.C. Callen MPSC P.W. Steketee,"Esq.
- Walsh, Esq.
G. Charnoff, Esq.
'.M.
Hennigan G. Olson PNSRC J.F. Stietzel Dir., IE (20 copies)
Dir., HIPC (2 copies)
Directorate of Licensing t'iAY 22 1S78
~
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS >
DISTRIBUTION FOR INCOMING MATERIAL 50-31 /316 REC:
CASE E
G NRC ORG:
TILLINGHAST J IN 5 MI PWR DOCDATE: 05/15/78 DATE RCVD: 05/22f78 DOCTYPE:
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YES COPIES RECEIVED
SUBJECT:
LTR 1
ENCL 0 FURNISHING INFO IN RESPONSE TO NRC LTR DTD,Oif25/78, CONCERNING THE SCHEDULE FOR PROVIDING THE EVALUATION OF THE OVERALL ASYMMETRIC LOADS DUE TO LOSS OF COOLANT ACCIDENTS FOR SYSTEMS AND COMPONENTS... NOTARIZED 05/15/78.
PLANT NAME: COOK -('UNIT.1 COOK 'UNIT 2-.,
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DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS NOTES:
I 8( E 3 CYS ALL MATERIAL FOR ACTION:
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GENERAL DISTRIBUTION FOR AFTER ISSUANCE (DISTRIBUTION CODF A001 >
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INDIANA fi MICHIGAN POWER COMPANY P, O. BOX 18 BO WL IN G G RE EN STATION NEW YORK, N. Y. 10004 May 15, 1978 Donald.C. Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 DPR Nos.
58 and 74 Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.. C.
20555
Dear Mr. Case:
This letter provides the response requested by Mr. Victor Stello's letter of January 25,
- 1978, concerning the schedule for providing the evaluation of the overall asymmetric loads due to. a loss of coolant accident, for systems and,cqmponents as described in the enclosures therein.
This submittal sets forth a realis'tic program of analytical evaluations that will, within the two-year time frame you have established,.
assess the safety of the plant.
Please be advised that condition C.3 (a) of the Donald C. Cook Nuclear Plant Unit 2 operating license DPR-74 requires submittal of this analysis by September 30, 1979 which is three months prior to the two-year time frame established in Mr. Stello's letter.
We will be working closely with Westinghouse Electric
.Corporation in order to attempt to meet the September 30, 1979 deadline.
If we find that it is not possible to meet this
~ deadline, we-will inform you by a formal request for modifi-cation to license DPR-74.
In any event, generic group analysis will be available by the end of the first quarter 1979.
As indicated in our letter of March 8,
- 1978, a task group. of utilities has been formed and, with the assistance of Westinghouse Electric Corporation, has outlined the steps necessary to complete an evaluation of the type you have requested.
The evaluation program prepared by the task group has been broken into three parts, or phases, to facilitate the work effort and to gain some advantage by performing generic analyses applicable to several plants of similar design.
I
Phase A, which is essentially
- complete, consists of a detailed examination of primary loop characteristics for each plant involved in the task group effort to categorize and group the plants for the analyses.
Plant groupings are based on plant characteristics such as reactor vessel diameter, steam generator
- type, steam generator,and reactor coolant pump support structures and primary loop temperatures.
Phase B will evaluate the postulated ruptures which have the greatest effect upon the steam generator and reactor coolant pump supports.
This evaluation will consist of generic scoping analyses for the plant groupings determined in Phase A of the.
project using standard. loop analysis procedures.
The breaks to be postulated for..the analyses are the hot leg at the reactor outlet nozzle, the crossover leg between the steam generator and the reactor coolant pump, and, the cold. leg at, either the pump discharge or the reactor vessel inlet nozzle.
The results of these-scoping analyses will be used to determine if specific analyses will be required to better assess the adequacy of the support systems.
During this phase
, bounding reactor coolant loop hydraulic forcing functions will be developed and generic subcompartment pressurization studies will be performed Phase C will address the reactor vessel response for postulated. pipe ruptures at the reactor vessel inlet and outlet nozzle Analyses will be performed on a group basis where asymmetric-cavity pressure loads, vessel internal hydraulic loads, and vessel support, characteristics are similar.
The need for specific plant analyses will be based on the results of the generic analyses.,
Prior to the initiation of the Phase C effort, studies will be performed to determine the effects of increased break opening times, more detailed downcomer annulus nodalization ancL structural damping on the NULTIFLEX calculations.
Also, certain reactor cavity pressurization studies and. the development of mechanistic crack opening analysis will be performed.
The anticipated, schedule for the program is presented below:
Pro ram Effort Com letion Date Phase A
Phase B Generic Group Analyses Phase B RCL Hydraulic Forcing Functions Phase B Subcompartment, Pressurization Complete June 15, 1978 June 30, 1978 November 1,
1978 Phase B Specific Plant Analyses Phase C Generic Group Analyses
- Early, 1979 First Quarter 1979
Pro ram Effort Com letion Date MULTIPLEX Modifications January 1,
1979 Reactor Cavity Pressurization Studies January 1,
1979 Mechanistic Pipe Break Analyses January 1,
1979 Phase C Specific Plant Analyses January 1,
1980 Should the generic analyses indicate that some corrective action is necessary, potential plant modifcations may be included in specific plant analyses which will be submitted to the Commission for review.
These modifications may be later incorporated in the plant, on a schedule acceptable to the Commission, or augmented in-service inspection or probability analyses may be proposed as. an alternate solution.
Xn either case, it is our intent to demonstrate the safety of long-term continuous operation of the Donald C. Cook Nuclear Plant.
We trust this information is suitable for your use.
Please inform us if you. have any additional questions concerning the program outlined above.
Very truly yours,
,JT:em gh st ce President Sworn and subscribed to before me on this I<
day of
Notary Public f4'iLLENBARRY NOTkRY tli"LiC, Slato of Naw York No. 42~6069')2 Quaiiiiou in Queens County Cartihccto iifed in Naw York County Cc,n<<>u.;in<<u,rros
'nurcn 30, L97 I cc:
(Attached)
cc:
R. C. Callen G. Charnoff P.
W. Steketee R. J. Vollen R. Walsh R.
W. Jurgensen D. V. Shaller-Bridgman