ML17317B516
| ML17317B516 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/30/1979 |
| From: | Dolan J INDIANA MICHIGAN POWER CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 00075, 75, NUDOCS 7909050348 | |
| Download: ML17317B516 (5) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIBS)
ACCESSION NBR:7909050300 DOC,DATE: 79/00/30 NOTARIZED:
YES DOCKET 0'
A C I L : 5 0 "3 1 6 Donald C,
Cook Nuclear Power P
1 a n t F U n i t 2 F Indiana 8
0 5 0 0 0 3 1 6 AU T H N AME AUTHOR AFFILIATION DOLANFJ,ED Indiana 8 Michigan Power Co, REC IP ~ NAME RECIPIENT AfFILIATION DENTONEH ~ R9 Office of Nuclear Reactor Regulation COPIES 4TTR ENCL-7
SUBJECT:
Notifies that review of Nestinghouse fracture mechanics analysis verifies acceptability of reactor operation beyond four effective full years, Review serves as addi Justification for use of installed Barton transmitters, DISTRIBUTION'ODE: A001S COPIES RECEIVED:LTR g ENCL Q SIZE:
TITLE: General Distribution for After Issuance of Operating Lic ES Se&S W Cum d/-
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INDIANA R MICHIGAN POWER COMPANY P. O. BOX 18 BO WL IN G G R E EN STAT ION NEW YORK, N. Y. 10004 August 30,1979 AEP:NRC:00192 Donald C.
Cook Nuclear Plant Unit 2 Docket No. 50-316 License No.
DPR-74 Supplement to AEP:NRC:00075 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Reference:
AEP:NRC:00075 Dated Au ust 18 1978
Dear Mr. Denton:
In the attachment to our above referenced letter we presented additional justification for continued operation of Unit 2 of the Donald C.
Cook Nuclear Plant with the installed Barton transmitters.
The argument used was based on a Westinghouse performed fracture mechanics analysis that insured reactor vessel integrity at the safety valve setpoint for in excess of one effective full power year.
This period of time was then assumed to be sufficient to resolve the issue of environmental in-accuracies of the transmitters.
On flay 15, 1979 the NRC Staff completed the review of the environ-mental qualification results and determined that additional testing would be required to demonstrate the adequacy of the transmitters during long term post accident cooling.
Westinghouse Electric Corporation, in their letter No.
NS-TMA-2103 dated June 21, 1979, provided a schedule to the commission indicating that the results of the required additional tests will be submitted by September 1979.
It is our understanding that the Westinghouse Electric Corporation has already completed the supple-mental test for lot 1 and'ot 2 transmitters and that tests reports are being drafted.
V90S 05O Z<8',
Nr. Harold R. Denton, Di:rector AEP'NRC:00192 In light of the above and of the fact that one effective full power year of operation wi'll be reached approximately during the third week of September<',
we requested the Westinghouse Electric Corporation to review the fracture mechanics analysis for the reactor vessel for its application and vali'dity for time periods beyond one effective full power year.
In response to this request Westinghouse Electric Corporation has completed their review and advised us that the re-sults of the said analysis remain indeed acceptable for a period up to and beyond four effective full power years of operation.
JED:em Very truly yours, John E, Dolan Vice President Sworn and subscribed to before me this>>'ay of August, 1979 in New York County, New York Notary Public ICATIILl's;KBARRY NOTARY lUM.IC, 't tu cf t4cxv York 1%0 '"I-"50i'~'I/2 Qusiih
~ in Queens Ccunty Cortificrto tii.d in Now York County t.i nun, i;on.;.inrus rAorch 30, 1987 cc:
R.
C. Callen G. Charnoff W. Sugnet - Westinghouse D. V. Shaller - Bridgman R.
S.
Hunter R.
W. Jurgensen
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