ML20056E197

From kanterella
Jump to navigation Jump to search

Forwards Corrected Superseding 930620 Document Re Response to GL 92-01,rev 1
ML20056E197
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 08/04/1993
From: Olshan L
Office of Nuclear Reactor Regulation
To: Donnelly P
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
GL-92-01, GL-92-1, TAC-M83435, NUDOCS 9308200247
Download: ML20056E197 (3)


Text

1

]

s l

August 4, 1993 Docket No. 50-155 i

Mr. Patrick M. Donnelly, Plant Man iger Big Rock Point Plant Consumers Power Company 10269 U.S. 31 North Charlevoix, Michigan 49201

Dear Mr. Donnelly:

SUBJECT:

BIG ROCK POINT PLANT - CORRECTION LETTER RE:

RESPONSE TO GENERIC LETTER (GL) 92-01, REVISION 1, " REACTOR VESSEL STRUCTURAL INTEGRITY, 10 CFR 50.54(f)" (TAC NO. M83435)

On June 30, 1993, the staff issued the subject letter with an incorrect date of June 20, 1993. A corrected copy of tne June 30, 1993, letter is enclosed.

The enclosed letter supersedes the June 20, 1993 document.

We regret any i uonvenience this error may have caused.

Sincerely, ORIGINAL SIGNED BY Leonard N. Olshan, Project Manager Project Directorate III-l Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Enclosure:

June 30, 1993 letter l

cc:

See next page DISTRIBUTION:

Docket File NRC & Local PDRs j

PD3-1 Reading JRoe JZwolinski WDean CJamerson L01shan 1

OGC ACRS (10) j WShafer, RIII BElliott NBC FIE CBfTER CSPY 9308200247 930804 PDR ADDCK 0500 5

0FFICE LA:PDIII-1 s EpH:PDIII-l (A)PD:PDIII-l CJamerson h/' l'blshan WDean N f,s NAME DATE 6/ 3/93 h

6/ h 93 3/4/bb I

/

hN0

' MJO YES/NO COPY G:

P OCS\\BIGROE4TBRP83435.00R

' ORIGINAL OFFICE COPY

)

0041 3r=oi s

ui

Mr. Patrick H. Donnelly, Plant Manager Big Rock Point Nuclear Plant cc:

Mr. Thomas A. McNish, Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Jane E. Brannon, County Clerk County Building Annex 203 Antrim Street Charlevoix, Michigan 49720 Office of the Governor Room 1 - Capitol Building Lansing, Michigan 48913 i

Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3423 N. Logan Street P. O. Box 30195 Lansing, Michigan 4B909 U.S. Nuclear Regulatory Commission Resident Inspector Office Big Rock Point Plant 10253 U.S. 31 North Charlevoix, Michigan 49720 Mr. David P. Hoffman, Vice President Nuclear Operations Big Rock Point Plant Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 i

u,,,ma I

e

pn eu c i.

g..

O I 5 (

E UNITED STATES Q

j NUCLEAR REGULATORY COMMISSION g

g WASHINGTON. D.C. 20555-0001 June 30, 1993 Docket No. 50-155 Mr. Patrick M. Donnelly, Plant Manager Big Rock Point Plant Consumers Power Company 10269 U.S. 31 North Charlevoix, Michigan 49201

Dear Mr. Donnelly:

SUBJECT:

BIG ROCK POINT PLANT - RESPONSE TO GENERIC LETTER (GL) 92-01, REVISION 1, " REACTOR VESSEL STRUCTURAL INTEGRITY, 10 CFR 50.54(f)"

(TAC NO. M83435)

Your previous responses dated July 1,1992, and February 25, 1993, to questions 2a & 2b in GL 92-01 indicate that the initial upper-shelf energy (USE) and chemistry data for all beltline welds, except for the surveillance i

weld, are not known.

Either provide the data (initial Charpy USE and chemistry data) for each beltline weld or provide the data and analysis from welds that were fabricated using the same vendor, fabrication time frame, fabrication process, and material specification to demonstrate that the surveillance weld is indeed representative of all beltline welds, and all beltline welds will meet the USE requirements of Appendix G,10 CFR Part 50.

(Your response dated February 25, 1993, indicates that the surveillance weld is only representative of the lower shell longitudinal weld.)

If this cannot be provided, then submit an analysis which demonstrates that lower values of USE will provide margins of safety against fracture equivalent to those required by Appendix G of the ASME Code.

Please provide a response within 60 days of receipt of this letter.

The information requested by this letter is within the scope of the overall burden estimated in Generic Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity, 10 CFR 50.54(f)." The estimated average number of burden hours is 200 person hours for each addressee's response. This estimate pertains only to the identified response-related matters and does not include the time required to implement actions required by the regulations. This action is covered by the Office of Management and Budget Clearance Number 3150-001), which expires June 30, 1994.

Sincerely, hJub r

Leonard N. Olshan, Project Manager Project Directorate 111-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation cc:

See next page j#

fi

)

xtu2--