ML18142A739
| ML18142A739 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/07/1977 |
| From: | White L Rochester Gas & Electric Corp |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18142A739 (4) | |
Text
U.S. NUCLEAR REGULATORY MISSION NRC FORM 195 (2'76)
,,- NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL r
DOCKET NUMBER PLY FILE NUMBER Mr. A. Schwencer FROM'G & E Rochester, N.Y.
14649 L D. White, Jr.
DATE OF DOCUMENT 12-7-77 DATE RECEIVED 12-9-77 BCRTTE R JUROR IGINAL Q.COP Y E3NOTORI2ED NCLASSIFIED PROP INPUT FORM NUMBER OF COPIES RECEIVED
) 5 (4,0@5 DESCRIPTION Request for an extension of time unti Mar. 1,
],978 to answer
& to respond to info on the generator
& reactor coolant pum support material.....lP ENCLOSU RE DISTRIBUTION FOR MATERIAL ON REACTOR VESSEL DATA PER R.
INGRAM 5-26-77 k
~ R.E. Ginna JCM SAFETY FOR ACTION/INFORMATION BRANCH CHIEF' R:
V'IETZIG INTERNALDISTRIBUTION PDR MIPC PANLICKI EISENHUT AO BUTLER GRDIES HAZELTON HOGE R'.
GAMBLE RANDALL EXTERNAL DISTR IBUTION CONTROL NUM ER III/Iia~5~
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89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE, JR.
VICE PREEI DENT December 7,
1977 Director of Nuclear Reactor Regulation Attention:
Mr. A. Schwencer, Chief Operating Reactors Branch Il U.S. Nuclear Regulatory Commission Washington, DC 20555 TEI.KPHONE ARE'A COOE TI8 546-2700 Q7 8
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Dear Mr. Schwencer:
On October 10, 1977 we received your letter requesting information on the steam generator and reactor coolant pump support material.
Since that time we have employed our NSSS Supplier, Westinghouse Electric Corporation, to help us develop the necessary information to answer your questions.
Westinghouse has informed us that they will require approxi-mately 90 additional days to provide the information due to the number of similar requests they have received and the man-power requirements to retrieve and evaluate the data.
There-
- fore, we request an extension of the response date to March 1, 1978.
The review of information in our possession, to date, has verified that ASTM A572 material was not used in the design and fabrication of Ginna Station's steam generator and reactor coolant pump supports.
Materials used include ASTM A36-63 and ASTM A514-64 which, based on our preliminary review of the design and fabrication of our supports, indicated that lamellar tearing should not be a problem.
Very truly yours,
~p.
L. D. White, Jr.
',977 DEC 9 AN 9