ML20059K564

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Discusses GL-89-10,Suppl 5, Inaccuracy of Motor-Operated Valve Diagnostic Equipment
ML20059K564
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 01/27/1994
From: Steven Bloom
Office of Nuclear Reactor Regulation
To: Tira Patterson
OMAHA PUBLIC POWER DISTRICT
References
GL-89-10, TAC-M87950, NUDOCS 9402020161
Download: ML20059K564 (4)


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UNITED STATES (i((j NUCLEAR REGULATORY COMMISSION

' - g WASHINGTON. D C, 20555-0001 January 27, 1994 Docket No. 50-285 t

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 i

Dear Mr. Patterson:

SUBJECT:

GENERIC LETTER 89-10, SUPPLEMENT 5, " INACCURACY OF MOTOR-0PERATED VALVE DIAGNOSTIC EQUIPMENT" (TAC N0. M87950)

On June 28, 1993, the NRC staff issued Supplement 5, " Inaccuracy of Motor-Operated Valve Diagnostic Equipment," to Generic Letter (GL) 89-10, " Safety-Related Motor-Operated Valve Testing and Surveillance," requesting nuclear oower plant licensees and construction permit holders (1) to re-examine their tiOV programs and to identify measures taken to account for uncertainties in l

properly setting valve operating thrust _ to ensure operability, and (2) to ovaluate the schedule necessary to consider the new information on MOV diagnostic equipment inaccuracy and to take appropriate action in re~sponse to that information. Within 90 days of receipt of Supplement 5 to GL 89-10, i

licensees were required (1) to notify the NRC staff of the diagnostic equipment used to confirm the proper size, or to establish settings, for safety-related MOVs, and (2) to report whether they had taken actions or planned to take actions (including schedule) to address the new information on the accuracy of MOV diagnostic equipment.

The staff has reviewed the responses, and has found that, for the most part, licensees and permit holders have been actively addressing the uncertainties regarding the accuracy of MOV diagnostic equipment. The increased inaccuracy of MOV diagnostic equipment can raise questions regarding (1) the adequacy of torque switch settings to provide sufficient thrust while not exceeding thrust or torque structural limits and (2) the capability of actuator motors'at current settings.

In their responses, licensees;and permit holders indicated that many MOVs had the potential for underthrusting_ or overthrusting as a result of the higher than expected inaccuracy of M0V diagnostic ~ equipment. _ _

Consequently, some licensees reported that MOVs have been retested, adjusted, or modified to resolve the concerns regarding the accuracy of MOV diagnostic equipment.

In Fort Calhoun's response to Supplement 5 by letter dated September 30, 1993, it was stated that you use MOV diagnostic equipment manufactured by ITI-M0 VATS.

Fort Calhoun stated that the latest accuracy information had-been incorporated into your methodology in February 1992.

Fort Calhoun stated that it had evaluated 10 MOVs with close-direction safety functions.

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Mr. Terry L. Patterson stated that seven of those MOVs had been retested with direct measurement equipment; one MOV had been evaluated in accordance with ITI-MOVATS Engineering Report 5.2; and two MOVs were found to have 300% margin.

Fort Calhoun stated that it had revised its test procedures to provide for direct measurement equipment for the close-direction wherever possible.

During a future inspection, the NRC staff will discuss your resolution of the MOV diagnostic equipment accuracy issue.

Particularly, the staff will discuss your basis for the operability of the seven MOVs found to require retesting and whether Fort Calhoun considered overthrust / torque for the two MOVs said to have 300% margin.

This completes all efforts on TAC No. M87950.

If you have any questions regarding this issue, please call me at (301) 504-1313.

Sincerely, teven Bloom, Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation cc:

See next page

Mr. Terry L. Patterson Omaha Public Power District Fort Calhoun Station, Unit 1 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 Commission Post Office Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations Combustion Engineering, Inc.

12300 Twinbrook Parkway, Suite 330 i

Rockville, MD 20852 Regional Administrator, Region IV -

i U.S. Nuclear Regulatory Commission i

611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Harold Borchert, Director Division of Radiological Health Nebraska Department of Health 301 Centennial Mall, South 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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i Mr. Terry L. Patterson ]

I stated that seven of those MOVs had been retested with direct measurement equipment; one M0V had been evaluated in accordance with ITI-M0 VATS Engineering Report 5.2; and two MOVs were found to have 300% margin.

Fort Calhoun stated that it had revised its test procedures to provide for direct j

measurement equipment for the close-direction wherever possible. During a future inspection, the NRC staff will discuss your resolution of the MOV diagnostic equipment accuracy issue.

Particularly, the staff will discuss your basis for the operability of the seven MOVs found to require retesting and whether Fort Calhoun considered overthrust / torque for the two MOVs said to have 300% margin.

This completes all efforts on TAC No. M87950.

If you have any questions regarding this issue, please call me at (301) 504-1313.

l Sincerely, ORIGINAL SIGNED BY-Steven Bloom, Project Manager 4

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

See next page DISTRIBUTION:

Docket File NRC & Local PDRs PD4-1 Reading i

S. Bloom E. Adensam W. Beckner P. Noonan ACRS(10) (P-315)

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