ML20137B512

Forwards Request for Addl Info Re motor-operated Valves AF-599,AF-608 & MS-106 & Other safety-related motor-operated Valves,Based on course-of-action Rept Through Rev 4.Response Expected by 860107

ML20137B512
Person / Time
Site:	Davis Besse
Issue date:	01/02/1986
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Williams J TOLEDO EDISON CO.
References
TAC-59702, NUDOCS 8601150524
Download: ML20137B512 (3)

Text

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January 2,1986 '

D Ok Docket No. 50-346 A STRTRITION WPaulson Q ocket :ile 3 JPartlow NRC PDR Ringram L PDR ADe Agazio Mr. Joe Williams, Jr.

PBD-6 CMcCracken Vice President, Nuclear FMiraglia Gray File Toledo Edison Company OELD EBrach Edison Plaza - Stop 712 ACRS-10 H0rnstein 300 Madison Avenue EJordan GEdison Toledo, Ohio 43652 BGrimes GDick

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - MOTOR OPERATED VALVES The staff has reviewed the information submitted with your Davis-Besse Course-of-Action report up through Revision 4 We find that we require additional information in order to complete our review with regard to your program relating to motor operated valves AF599, AF 608, and MS 106 and other safety related motor operated valves. The information required is identified in the Enclosure to this letter.

Should you have any questions regarding the scope of your response required or need clarification, please contact your NRR Project Manager, Al De Agazio (301-492-8945). To avoid delay in preparation of our evaluation related to Davis-Besse restart, you should provide your response no later than January 7, 1986.

The information requested in this letter affects fewer than 10 respondents; therefore, OMB clearance under P.L.96-511 is nt required.

Sincerely,

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. JOISI F. 530E4%)'

John F. Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-B i

cc: See next page PBD-6 PRD-6

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1/g/86 1/J_186 1/ JE fMA %s

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Mr. J. Williams Davis-Besse Nuclear Power Station Toledo Edison Company-Unit No. I s

CC:

Donald H. Hauser, Esq.

Ohio Department of Health The Cleveland Electric ATTN: Radiological Health Illuminating Company Program Director P. O. Box 5000 P. O. Box 118 Cleveland, Ohio 44101 Columbus, Ohio 43216 Mr. Robert F. Peters Attorney General Manager, Nuclear Licensing Department of Attorney Toledo Edison Company General Edison Plaza 30 East Broad Street 300 Madison Asenue Columbus, Ohio 43215 Toledo, Ohio 43652 Mr. James W. Harris, Director Gerald Charnoff, Esc.

Shaw, Pittman, Pottsi Division of Power Generation Ohio Department of Industrial Relations and Trowbridge 2323 West 5th Avenue 1800 M Street, N.W.

P. O. Box 825 Washington, D.C. 20036 Columbus, Ohio 43216 Mr. Paul M. Smart, President The Toledo Edison Company Mr. Harold Kohn, Staff Scientist 300 Madison Avenue' Power Siting Comission 361 East Broad Street Toledo, Ohio 43652 Columbus, Ohio 43216 Mr. Robert B. Borsum President, Board of Babcock t, Wilcox Nuclear Power Generation Ottawa County Division Port Clinton, Ohio 43452 Suite 200, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident Inspector U.S. Nuclear Regulatory Commission 5503 N. State Route 2 Oak Harbor, Ohio 43449 Regional Administrator, Region III U.S. Nuclear Regulatory Comission 799 Roosevelt Road Glen Ellyn, Illinois 60137 S

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Enclosure QUESTIONS RELATING TO DAVIS-BESSE VALVES AF-39, AF-608 AND MS-106 i

AND OTHER SAFETY RELATED VALVES 1.

Identify all valve operating conditions and expected intervals for those that are known (i.e., test, normal, transients, limiting conditions).

Is the use of a single open and close torque switch setting in each direction of valve travel adeouate for all conditions?

2.

Specify, the max delta P that was experienced by AF-599 and -608 during the event. Will it be expected that delta Ps in excess of 1050 psid will be experienced in the future.

If not, why not?

3.

Explain in detail the methodology used to set A.

Bypass _ limit switches B.

Torque switches C.

Limit switches for both directions of valve travel.

4.

Explain in detail how stem stresses are calculated and are determined to be acceptable. Do the new switch settings have any negative effects on the qualified life of the valve / actuator assembly?

5.

Submit a single description of the in-situ tests that will be performed prior to restart; refer to specific procedures where appropriate.

6.

Are any in-situ tests planned prior to restart utilzing line fluid ficw(s) in which the valve (s) must close?

7.

Are any in-situ tests utilizing delta Ps and/or fluid flow planned on an ongoing basis? Ongoing MOVATs, etc? Corrective / preventive maintenance procedures, LCTS Nos. 1251 and 1257. How many delta Ps will be used for single valve assembly?

For'7, above; how many of these actions will be applied to all 8.

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safety-related valves?

9.

Should LCTS Nos.1261 and 1273 also state"to preclude damage to the. valve?"

10. How often are these valves tested and what types of tests are performed? (IST Program, Technical specifications, other)

- 11. Are packing problems considered in adjusting the toroue switches?

(i.e., dried out packing, etc.).

12. Does exclusion of thermal over19:ds have any negative effect on the qualified life of the valve / actuator?

(i.e., motor burnouts, etc.)

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