ML20056H077

From kanterella
Jump to navigation Jump to search

Forwards Request for Addl Info Re Util 920706 & 930716 Responses to Rev 1 to GL 92-01, Reactor Vessel Structural Integrity. Response Requested within 60 Days
ML20056H077
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 08/20/1993
From: Steven Bloom
Office of Nuclear Reactor Regulation
To: Tira Patterson
OMAHA PUBLIC POWER DISTRICT
References
GL-92-01, GL-92-1, TAC-M83465, NUDOCS 9309080193
Download: ML20056H077 (4)


Text

Docket No. 50-285 August 20, 1993 l

4 Mr. Terry. L. Patterson Divisio: Manager - Nuclear Operations Omaha PLblic Power District Fort Cal.soun Station FC-2-4 Adm.

Post Office Box 399 Hwy. 75 - North of fort Calhoun Fort Calhoun, Nebraska 68023-0399

Dear Mr. Patterson:

SUBJECT:

RESPONSE TO GENERIC LETTER 92-01, REVISION 1, " REACTOR VESSEL STRUCTURAL INTEGRITY" - FORT CALHOUN STATION (TAC NO. M83465)

By letter dated July 6, 1992, as supplemented by letter dated July 16, 1993, you submitted your response to Generic Letter (GL) 92-01, Revision 1.

The purpose of GL 92-01 is to obtain information needed to assess compliance with requirements set forth in Appendices G and H to 10 CFR Part 50 and commitments made in response to GL 88-11 regarding reactor vessel structural integrity.

Other regulations requiring compliance are 10 CFR 50.60 and 10 CFR 50.61.

t The staff has completed the preliminary review and is transmitting a request for additional information (RAI) for Fort Calhoun Station.

The enclosed information question was discussed by the NRC staff and OPPD staff on August 17, 1993. As discussed during the telecon, we expect your response to our RAI to be submitted within 60 days.

If you have any questions about this 1

matter, please do not hesitate to call me at 301-504-1313.

This requirement i

affects fewer than 10 respondents and, therefore, is not subject to Office of Management and Budget review under Public Law 96-511.

Sincerely, ORIGINAL SIGNED BY:

f Steven D. Bloom, Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Enclosure:

RAI cc w/ enclosure:

1 See next page DISTRIBUTION:

Docket; file}

NRC & Local PDRs PD4-1 Reading i

S. Bloom E. Adensam H. Rood i

P.'Noonan ACRS(10) (P-315)

OGC (15818)

A. B. Beach, RIV J. Roe D. Mcdonald (14B2) 0FC LA:PD4 h PM:Pp4-1 D(A):PD4-J- )-

.i NAME PNoonhn Si}bpk HRood k 4

DATE hN/93

[/p/93 f?/?Cf93 YESk0) h0 YES/N0

{Ig

{

COPY OFFICIAL RECORD COPY Document Name:

FC83465.RAI 9309080193 930820

M 00 E.

1' PDR ADDCK 05000285 t

PDR,,

L P

pa Pico UNITED STATES

[

@,' t]

NUCLEAR REGULATORY COMMISSION

~ y WASHINGTON, D.C. 20555-0001 3

%9 *****

August 20, 1993 Docket No. 50-285 Mr. Terry. L. Patterson Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

Post Office Box 399 i

Hwy. 75 - North of Fort Calhoun Fort Calhoun, Nebraska 68023-0399

Dear Mr. Patterson:

SUBJECT:

RESPONSE TO GENERIC LETTER 92-01, REVISION 1, " REACTOR VESSEL STRUCTURAL INTEGRITY" - FORT CALHOUN STATION (TAC NO. M83465)

By letter dated July 6,1992, as supplemented by letter dated July 16, 1993, you submitted your response to Generic Letter (GL) 92-01, Revision 1.

The purpose of GL 92-01 is to obtain information needed to assess compliance with requirements set forth in Appendices G and H to 10 CFR Part 50 and commitments made in response to GL 88-11 regarding reactor vessel structural integrity.

Other regulations requiring compliance are 10 CFR 50.60 and 10 CFR 50.61.

The staff has completed the preliminary review and is transmitting a request for additional information (RAI) for Fort Calhoun Station.

The enclosed information question was discussed by the NRC staff and OPPD staff on August 17, 1993.

As discussed during the telecon, we expect your response to our RAI to be submitted within 60 days.

If you have any questions about this matter, please do not hesitate to call me at 301-504-1313. This requirement affects fewer than 10 respondents and, therefore, is not subject to Office of Management and Budget review under Public Law 96-511.

Sincerely,

=

Steven D. Bloom, Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Enclosure:

RAI cc w/ enclosure:

See next page

Mr. Terry L. Patterson Omaha Public Power District Fort Calhoun Station, Unit I cc:

Mr. Michael F. McBride, Esq.

LeBoeuf, Lamb, Leiby & MacRae 1875 Connecticut Avenue, NW Washington, D.C.

20009-5728 Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, Nebraska 68008 Mr. Raymond P. Mullikin, Resident Inspector U.S. Nuclear Regulatory Commis., ion Post Office Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations Combustion Engineering, Inc.

12300 Twinbrook Parkway, Suite 330 Rockville, MD 20852 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Harold Borchert, Director Division of Radiological Health l

Nebraska Department of Health 301 Centennial Hall, South Post Office Box 95007 tincoln, Nebraska 68509 Mr. James W. Chase, Manager Fort Calhoun Station Post Office Box 399 Fort Calhoun, Nebraska 68023 i

ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION REACTOR VESSEL STRUCTURAL INTEGRITY OHAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT I DOCKET NO. 50-285 Ouestion 2a in Generic letter 92-01 l

The response indicates that the initial upper-shelf energy (USE) values for all beltline welds, except for the surveillance weld, are not known.

Either provide the Charpy USE for each beltline weld with no documented initial USE value or provide the Charpy USE and analysis from welds that were fabricated using the same vendor, fabrication time frame, fabrication process, and material specification to demonstrate that all beltline welds with no documented initial USE values will meet the USE requirements of Appendix G, 10 CFR 50.

If this information 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.

l J

e

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _