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{{#Wiki_filter: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 IG INAL 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 PLANT NAI'IE~R.E.Ginna JCM SAFETY FOR ACTION/INFORMATION BRANCH CHIEF'R: V'IETZIG INTERNAL DISTRIBUTION PDR MIPC PANLICKI EISENHUT AO BUTLER GRDIES HAZELTON HOGE R'.GAMBLE RANDALL EXTERNAL DISTR I BUTION CONTROL NUM ER III/Iia~5~
{{#Wiki_filter:NRC FORM 195                                          U.S. NUCLEAR REGULATORY     MISSION DOCKET NUMBER (2'76)                                                                                               PLY FILE NUMBER r
b~'h 0 gp J I (ZZl<nr rnid AHD~zrngri~<zzzzszr i~ll zzz8 I!>>uzzu ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y.14649 LEON D.WHITE, JR.VICE PREEI DENT December 7, 1977 Director of Nuclear Reactor Regulation Attention:
          ,,- NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL Mr. A. Schwencer                       FROM'G       & E                             DATE OF DOCUMENT Rochester, N.Y.       14649           12-7-77 L D. White, Jr.                     DATE RECEIVED 12-9-77 BCRTTE R                 E3NOTORI2ED         PROP                     INPUT FORM           NUMBER OF COPIES RECEIVED JUROR IG INAL            NCLASSIFIED Q.COP Y                                                                                        ) 5 (4,0@5 DESCRIPTION                                                     ENCLOSU RE 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 DISTRIBUTION FOR MATERIAL ON REACTOR VESSEL DATA PER R. INGRAM 5-26-77                           k PLANT NAI'IE     ~
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 ZPffjp, Dp~f~'b~%8 gD-8 II'f
R.E. Ginna JCM SAFETY                           FOR ACTION/INFORMATION BRANCH CHIEF' R:
V'IETZIG INTERNAL DISTRIBUTION PDR MIPC PANLICKI EISENHUT AO BUTLER GRDIES HAZELTON HOGE R'. GAMBLE RANDALL EXTERNAL DISTR I BUTION                                       CONTROL NUM ER 5~
III/Iia~


==Dear Mr.Schwencer:==
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                <zzzzszr i~ll zzz8 I!>>uzzu ROCHESTER GAS AND ELECTRIC CORPORATION              o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE, JR.                                                                TEI.KPHONE VICE PREEI DENT                                                    ARE'A COOE TI8  546-2700 December    7, 1977                          Q7 8
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Director of Nuclear Reactor Regulation                                'b Attention: Mr. A. Schwencer, Chief Operating Reactors Branch    Il                        ~ %8 U.S. Nuclear Regulatory Commission Washington, DC 20555 gD-8 II'f
 
==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.


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}}
',977 DEC 9 AN 9}}

Revision as of 01:30, 21 October 2019

Letter Requesting Information on the Steam Generator and Reactor Coolant Pump Support Material. Since That Time We Have Employed Our NSSS Supplier
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)
v • d • e


Text

NRC FORM 195 U.S. NUCLEAR REGULATORY MISSION DOCKET NUMBER (2'76) PLY FILE NUMBER r

,,- NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL Mr. A. Schwencer FROM'G & E DATE OF DOCUMENT Rochester, N.Y. 14649 12-7-77 L D. White, Jr. DATE RECEIVED 12-9-77 BCRTTE R E3NOTORI2ED PROP INPUT FORM NUMBER OF COPIES RECEIVED JUROR IG INAL NCLASSIFIED Q.COP Y ) 5 (4,0@5 DESCRIPTION ENCLOSU RE 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 DISTRIBUTION FOR MATERIAL ON REACTOR VESSEL DATA PER R. INGRAM 5-26-77 k PLANT NAI'IE ~

R.E. Ginna JCM SAFETY FOR ACTION/INFORMATION BRANCH CHIEF' R:

V'IETZIG INTERNAL DISTRIBUTION PDR MIPC PANLICKI EISENHUT AO BUTLER GRDIES HAZELTON HOGE R'. GAMBLE RANDALL EXTERNAL DISTR I BUTION CONTROL NUM ER 5~

III/Iia~

b

~'h 0

gp J

I (ZZl<nr AHD rnid

~ zrngri ~

<zzzzszr i~ll zzz8 I!>>uzzu ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE, JR. TEI.KPHONE VICE PREEI DENT ARE'A COOE TI8 546-2700 December 7, 1977 Q7 8

ZPffjp, Dp~

f~

Director of Nuclear Reactor Regulation 'b Attention: Mr. A. Schwencer, Chief Operating Reactors Branch Il ~ %8 U.S. Nuclear Regulatory Commission Washington, DC 20555 gD-8 II'f

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

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