ML20155H723
| ML20155H723 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/06/1998 |
| From: | Bateman W NRC (Affiliation Not Assigned) |
| To: | Gambhir S OMAHA PUBLIC POWER DISTRICT |
| References | |
| TAC-M95802, NUDOCS 9811100258 | |
| Download: ML20155H723 (3) | |
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20066-0001 o
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November 6, 1998 a
Mr. S. K. Gambhir Division Manager - Nuclear Operations Omaha Publia 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 (FCS), UNIT NO.1, RELIEF FROM ASME BOILER AND PRESSURE VESSEL CODE SECTiON ll!, OVERPRESSURE PROTECTION REQUIREMENTS (TAC NO M95802)
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Dear Mr. Gambhir:
By letter dated May 21,1996, Omaha Public Power District (OPPD) requested permanent relief 4
from the requirements of Article 9, Paragraph N-910.8 of the 1968 Edition of the ASME Code, Section Ill. The requirements pertain to the spent fuel pool and shut down heat exchangers which were constructed as Class C vessels per the 1968 Edition of the ASME Code, Section Ill.
The relief would allow OPPD to permanently retain the installation of a locked-open manual isolation valve (AC-140) located in series with overpressure protection relief devices in the chemical and volume control system and use specific administrative controls to verify its position.
In its May 21,1996, letter, OPPD requested that the NRC staff authorize the installed valve configuration at FCS as an attemative to the above ASME Code design requirements pursuant
.to 10 CFR 50.55a(a)(3). OPPD stated that the manualisolation valve and relief valve configuration provides an acceptable level of quality and safety because administrative controls (AC-10 is chained, locked in the open position, and verified) are in place to ensure that the
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manualisolation valve will remain in the open position. OPPD also indicated that comp!;ance
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with the above Code requirements would result in difficulties without a compensating !ncrease C
in the level of quality and safety.
The NRC staff has reviewed OPPD's request for the NRC staff to authorize its proposed f
altemative pursuant to 10 CFR 50.55a(a)(3). The NRC staff finds that ASME Code, Section lli Ch
-i requirements for Quality Group C components (ASME Code Class 3 components) such as the
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spent fuel pool and shut down heat exchangers, as stated in 10 CFR 50.55a(e), apply to nuclear power plants whose applications for construction permits (cps) were docketed after May 14,1984. The CP for FCS was docketed prior to May 14,1984; therefore, the regulations in 10 CFR 50.55a(e) concerning ASME Code, Section 111 design requirements for Class 3 components do not apply to FCS. Accordingly, authorization of an attemative to ASME Code, Lction 111 design requirements pursuant to 10 CFR 50.55a(a)(3)is unnecessary and inappropriate for FCS.
9811100258 981106 PDR ADOCK 05000285 P
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i Mr. S. K. Gambhir November 6, 1998 In its Updated Safety Analysis Report, OPPD committed to design and construct FCS in
- accordance with ASME Code, Section 111 design provisions. In its May 21,1996, letter, OPPD identified isolation valves installed in FCS that did not meet the design requirements of ASME Code for a Class 3 (or Class C) component. The NRC staff views the licensee's discovered condition of non-compliance with the ASME Code, Section ll1 design provisions as a deviation from plant licensing commitments. Accordingly, OPPD may either modify the plant to conform to the provisions of the current licensing and design basis information, or change the current licensing and design basis information to accurately reflect the existing plant design. Action may be taken pursuant to the provisions of 10 CFR 50.59, and depending on the results of l
. OPPD's evaluation, a license amendment may be required.
On the basis of the above evaluation, the NRC staff concludes that authorization of an alternative or relief from ASME Code, Section lli design provisions for ASME Code Class 3 components is unnecessary and inappropriate for FCS. OPPD may resolve the existing l
deviation by modifying the plant or by revising the licensing and design information.
j This completes our review for TAC No. M95802. Please contact L. Raynard Wharton at (301) l 415-1396 if you have any questions regarding this issue.
Sincerely, Original Signed By i
William H. Bateman, Director Project Directorate IV-2 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket No. 50-285 DISTRIBUTION:
Docket File EPeyton cc: See next page PUBLIC OGC l
PDIV-2 Reading ACRS EAdensam (EAG1)
RWessman WBateman PGwynn RWharton GHill(2)
DLange, EDO DOCUMENT NAME: FC95802.LTR l
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NAME hharton EP Y R h an Ijp4*4 Wbb' DATE 10/d /98 10/13/98 10/W/98 10/[k/98
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3-November 6, 1998 Mr. S. K. Gambhir
'cc:
I Winston & Strawn ATTN: Perry D. Robinson, Esq.
1400 L Street, N.W.
i 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 i
Fort Calhoun, Nebraska 68023 j
Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 3
611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Ms. Cheryl Rodgers, LLRW Program Manager Environmental Protection Section Nebraska Department of Health A
301 Centennial Mall, South i
P.O. Box 95007 Lincoln, Nebraska 68509-5007 4
Mr. J. M. Solymossy Manager-Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant Post Office Box 399 Hwy,75 - North of Fort Calhoun Fort Calhoun, Nebraska 68023 4-Mr. Mark T. Frans 4
Manager-Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 399 3
i Hwy. 75 - Nceth of Fort Calhoun
- Fort Calhoun, Nebraska 68023-0399 4
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