ML20057E345

Forwards Safety Evaluation Advising That Based on Determination That Alternative Testing Consistent w/OM-10, Paragraph 4.3.2.2 Requirements,No Relief Required

ML20057E345
Person / Time
Site:	Fort Calhoun
Issue date:	10/01/1993
From:	Steven Bloom Office of Nuclear Reactor Regulation
To:	Tira Patterson OMAHA PUBLIC POWER DISTRICT
Shared Package
ML20057E346	List: ML20057E345 ML20057E347
References
TAC-M84503, NUDOCS 9310120048
Download: ML20057E345 (5)

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION a

WASHINGTON, D.C. 205E6 0001

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October 1, 1993

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

SUBJECT:

EVALUATION OF INSERVICE TESTING PROGRAM RELIEF REQUEST FOR SAFETY INJECTION TANK CHECK VALVES - FORT CALHOUN STATION (TAC NO. M84503)

The enclosed safety evaluation (SE) provides the result of the NRC review of l

information relating to valve relief request E4 in the Fort Calhoun Station third 10-year pump and valve inservice testing (IST) program.

This information was provided by Omaha Public Power District (the licensee) in letters dated September 3 and November 13, 1992, as supplemented by letters dated June 11 and July 13, 1993. The SE for other relief requests submitted i

for the third 10-year interval will be provided at a later date.

Relief request E4, which concerns stroke testing of safety injection tank (SIT) check valves, is an updated version of relief request E19 for the second 10-year interval ending September 15, 1993. The NRC SE dated March 26, 1992, granted relief for E19 on an interim basis pending completion of staff's detailed evaluation of the licensee's valve exercising methodology. The enclosed SE for E4 completes this detailed evaluation and the review of E19.

The NRC, with technical assistance from Oak Ridge National Laboratory (ORNL),

i has reviewed the information provided by the licensee for E4. As explained in i

the enclosed SE, the staff adopts the analysis and conclusions contained in the enclosed report, ORNL/NRC/LTR-93/16, " Analysis of Proposed Testing of Safety Injection Tank Discharge Check Valves Using a Flow Resistance Methodology," prepared by ORNL.

Based on the determination that the alternative testing is consistent with OM-10, Paragraph 4.3.2.2 requirements, the staff finds that no relief is required provided the licensee documents the justification for deferral of stroke testing in accordance with OM-10, Paragraph 6.2(d), and follows the recommendations specified in the enclosed

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9310120048 931001 NE PDR ADOCK 05000285 P

PDR

c Hr. Terry L. Patterson.

ORNL report.

If the licensee cannot meet these provisions, a submittal with the revised relief request should be made within 90 days of the date of this SE.

Sinccrely, ORIGINAL SIGNED BY:

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

Enclosures:

1.

Safety Evaluation 1

2.

ORflL/NRC/LTR-93/16 cc w/o Enclosure 2:

4 See next page DISTRIBUTION w/ Enclosure 2:

i Docket File NRC & Local PDRs S. Bloom A. B. Beach, RIV l

PD4-1 Reading w/o Enclosure 2:

J. Roe j

E. Adensam W. Beckner K. Dempsey P. Noonan ACRS (10) (P-315)

OGC (15B18) 0FC LA:PD4rd ht,.

PM;PD4-1 D(A):PD4-1 P Mfskpk NAME PNoon WBeckner DATE h/$93 ih/93 l0 l /93

/

COPY

$0

/[YES/hD YES[fiO) 0FFICIAL RECORD COPY Document Name:

FC84503.ltr 1

Mr. Terry L. Patterson,

ORNL report.

If the licensee cannot meet these provisions, a submittal with i

the revised relief request should be made within 90 days of the date of this SE.

Sincerely, Steven Bloom, Project Manager i

Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Enclosures:

1.

Safety Evaluation 2.

ORNL/NRC/LTR-93/16 cc w/o Enclosure 2:

j See next page 1

l

Mr. Terry L. Patterson I ORNL report.

If the licensee cannot meet these provisions, a submittal with the revised relief request should be made within 90 days of the date of i

this SE.

i Sincerely, I

ORIGINAL SIGNED BY:

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

Enclosures.

1.

Safety Evaluation 2.

ORNL/NRC/LTR-93/16 cc w/o Enclosure 2:

See next page DISTRIBUTION w/ Enclosure 2:

1 Docket File NRC & Local PDRs S. Bloom A. B. Beach, RIV

-i PD4-1 Reading j

w/o Enclosure 2:

J. Roe E. Adensam W. Beckner K. Dempsey l

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

OGC (15818) 0FC LA:PD4, O la PM;PD4-1 D(A):PD4-1

' ddkdkpk WBeckner NAME PNoon DATE' 9/$93 YkO 93 l0/l/93

/

COPY

/NO

([YES/)0 YES[ tid) 0FFICIAL RECORD COPY Document Name:

FC84503.ltr 05^043 3Fo t i

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

Mr. Michael F. McBride, Esq.

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

20009-5728 i

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

l 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 i

Harold Borchert, Director Division of Radiological Health Nebraska Department of Health 301 Centennial Mall, South l

Post Office Box 95007 Lincoln, Nebraska 68509 Mr. James W. Chase, Manager Fort Calhoun Station Post Office Box 399 Fort Calhoun, Nebraska 68023 i

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