ML20249C050
| ML20249C050 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/23/1998 |
| From: | Wharton L NRC (Affiliation Not Assigned) |
| To: | Gambhir S OMAHA PUBLIC POWER DISTRICT |
| References | |
| GL-92-01, GL-92-1, TAC-MA0545, TAC-MA545, NUDOCS 9806250228 | |
| Download: ML20249C050 (4) | |
Text
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June 23, 1998 Mr. S. K. Gambhir; Division Manager - Engineering & Operations Support Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 399 -
. Hwy. 75 - North of Fort Calhoun Fort Calhoun, Nebraska 68023-0399
SUBJECT:
FORT CALHOUN STATION, UNIT NO.1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO GL 92-01, REVISION 1, SUPPLEMENT 1,
" REACTOR VESSEL STRUCTURAL INTEGRITY" (TAC NO. MA0545)
Dear Mr. Gambhir,
By letter dated August 17,1995, Omaha Public Power District (OPPD) committed to participate in a Combustion Engineering Owners Group (CEOG) Reactor Vessel Working Group (RVWG)
. task performing a comprehensive evaluation of best estimate copper and nickel values for CE fabricated reactor vessel welds.. In July 1997, the CEOG issued the report that contains the results of this evaluation. By [[letter::LIC-97-0159, Forwards Revised FCS Reactor Vessel Weld Chemistry Values. Table Summarizes Original Values Submitted in OPPD for FCS Versus Revised Copper,Nickel & Chemistry Factors Resulting from Use of Rev 2 to CE-NPSD-1039|letter dated October 13,1997]], OPPD submitted revised Fort Calhoun Station reactor vessel weld chemistry values.
The staff requires further information to complete its review of the submittal. The information requested is listed in the enclosure. In order to maintain the staff's review schedule, please provide your response within 90 days' of receipt of this letter.
Sincerely,.
Original. Signed By
. L. Raynard Wharton, Project Manager Project Directorate IV-2:
Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket No. 50-285 DISTRIBUTION:
Docket OGC
Enclosure:
Request for AdditionalInformation' PUBLIC TSullivan PDIV-2 Reading Alee cc w/enci: See next page
' EAdensam (EGA1)
WBateman RWharton
- EPeyton PGwynn, Region IV WJohnson, Region IV ACRS DOCUMENT NAME: FC92-01.RAI' Kh il OFC JRDIV-2/PM PDIV-2/LA -
J NAME Mharton Eke ^9t$
DATE' I/d/98 '
foW/98 gg gp OFFICIAL RECORD COPY
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ccw/ encl:
Winston & Strewn ATTN. Perry D. Robinson, Esq.
- 1400 L Street, N.W.
Washington, DC 20005-3502 Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, Nebraska 68008 Mr. Wayne Walker, Resident inspector U.S. Nuclear Regulatory Commission Post Office Box 309
- Fort Calhoun, Nebraska 680?1 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Ms. Cheryl Rodgers, LLRW Program Manager Environmental Prc+1 ion Section Nebraska Departmerit of Health 301 Centennial Mall, South j
P.C. Box 95007 Lincoln, Nebraska 68509-5007 Mr. James W. Chase, Manager Fort Calhoun Station Post Omco Box 399 Fort Calhoun, Nebraska 68023 Mr. James W. Tills Manager-Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Omco Box 399
- Hwy. 75 - North of Fort Calhoun Fort Calhoun, Nebraska 68023-0399 c.
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OMAHA PUBLIC POWER DISTRICT l
FORT CALHGiRSTATION. UNIT NO.1 DOCKET MOM 245 REO' JEST FOR ADihi!O*Ff_ INFORMNON 1.
The limiting notorial for the Fort Calhoun RPV changed from the 3 410 tandem weld heat 27204/27204 to the tandem heat 27204/12008 as a result of the licensee's evaluation of the new CEOG RVWG data. The letter dateG October 13,1997, indicates that the RTn,
- value of the limiting materialincreased from 267'F to 269'F. The docketed information which the licensee supplied in response to GL 92-01, Revision 1 cited 249'F as the current RTm value for the limiting material. The docketed information received to date does not account for the change in the RTm value from 249'F to 267'F. In order to have accurate values for assessing RPV embrittlement, complete the attached Tabb for each RPV beltline weld material. Include a reference for the fluence value that was used in the new assessment. The information provided will be used in updating the Reactor Vessel integrity Database (RVID).
2.
Note that RPV integrity analyses Mlizing newly identified data could result in the need for license amendments in order to maintain compliance with 10 CFR Part 50.60,10 CFR 50.61 (pressurized thermal shock, PTS), and Appendices G and H to 10 CFR Part 50, and to address any potential impact on low temperature overpressure (LTOP) limits or pressure-temperature (P-T) limits. If additionallicense amendrrents or assessments are necessary, please provido a schedule for such submittals.
Attachment:
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