ML20137Y096

Forwards Request for Addl Info Re Plan 12 Concerning Auxiliary Feedwater Sys Isolation Valves AF-599 & AF-608 & Other safety-related Motor Operated Valves & Main Steam Sys Valve MS-106.Response Requested by 860314

ML20137Y096
Person / Time
Site:	Davis Besse
Issue date:	03/04/1986
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Williams J TOLEDO EDISON CO.
References
TAC-59702, NUDOCS 8603120133
Download: ML20137Y096 (4)

Text

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fiarch 4,1986 g8 Ok y Docket No. 50-346 DISTRIBUTLON gocket FJf) JPartlow nut rux Ringram L PDR ADe Agazio Mr. Joe Williams, Jr. PSD#6 Rdg Gray File Senior Vice President, Nuclear FMiraglia EBrach Toledo Edison Company OELD H0rnstein Edison Plaza - Stop 712 ACRS GDick 300 Madison Avenue EJordan GEdison Toledo, Ohio 43652 BGrimes WPaulson WJohnston CYCheng

Dear Mr. Williams:

RWright JPage

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION: MOTOR OPERATED VALVES On.0ctober 30, 1986, the NRC issued a safety evaluation on Toledo Edison Company Action Plans 12 and 27 relating to motor operated valves AF 599, AF

'608 and MS 106. The safety evaluation indicated that additional information was required. Toledo' Edison Company responded in Revision 4 to the Course of Action. On December 16, 1985, a meeting in Bethesda was held to discuss additional issues related to the motor operated valve program. These issues were fomalized by a' Request for Additional Information (12 questions) dated January 2, 1986. Toledo Edison Company's response was issued January 3, 1986 as Revision 6 to the Course of Action.

The January ?,1986 submittal did not completely resolve our concerns with

regard to your program. These concerns were discussed February 13, 1986, in a meeting at the Davis-Besse site. The enclosed Request for Additional Information is a result of that meeting.

Since the motor operated valve program is an issue that must be resolved prior to restart, we urge you to respond as promptly as possible but not later than March 14, 1986, for us to support your most recent estimate for when the plant will be ready for restart.

! Sincerely,

%..as :iz am 5t 259],.120:2,*.>

John F. Stolz. Director PWR Project Directorate #6 Division of PWR Licensing-B 1

i

Enclosure:

l Request for Additional l Infomation cc w/ enclosure:

l See next page PBD-6 PBD- ^- P i ADeAg[z[io;cfCMcCr ken JStc 12 %

3/ y /86 3/ /86 3/4//86 l

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. Mr. J. Williams Davis-Besse Nuclear Power Station Toledo Edison Company Unit No. 1 CC*

Donald H. Hauser, Esq. Ohio Department of Health The Cleveland Electric ATTN: Radiological Health Illuminating Company Program Director P. 0. Box 5000 P. O. Box 118 i 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 Avenue Columbus, Ohio 43215 Toledo, Ohio 43652 Mr. James W. Harris, Director Gerald Charnoff, Esq. (Addressee Only) l Shaw, Pittman, Potts Division of Power Generation and Trowbridge Ohio Department of Industrial Relations l 1800 M Street, N.W. 2323 West 5th Avenue

! Washington, D.C. 20036 P. O. Box 825 i Columbus, Ohio 43216

! Mr. Paul M. Smart, President Mr. Harold Kohn, Staff Scientist The Toledo Edison Company Power Siting Commission I 300 Madison Avenue 361 East Broad Street l Toledo, Ohio 43652 Columbus, Ohio 43216 Mr. Robert B. Borsum President, Board of l

Babcock & Wilcox County Commissioners of Nuclear Power Generation Ottawa County

Division Port Clinton, Ohio 43452 l

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 Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 i

e-_________-___

F. .

s REQUEST FOR ADDITIONAL INFORMATION DAVIS-BESSE - DOCKET No. 50-346 DAVIS-BESSE ACTION PLAN #12-AUXILIARY FEEDWATER SYSTEM ISOLATION VALVES AF-599 AND AF-608 AND OTHER SAFETY RELATED MOTOR OPERATED V AND DAVIS-BESSE ACTION PLAN #27 - MAIN STEAM SYSTEM VALVE MS-106 t'

1.

Confirm that the most limiting opening and closing requirement (pressure differential and/or flow rate) for all nuclear safety related motor operated valves will be identified before restart and will meet present design requirements.

]

2. Confirm that the torque and limit switch adjustments for each nuclear safety relatedofmotor requirements Item 1operated above. valve take into account the limiting

3. Confirm that settings for the torque and limit switches do not exceed manufacturer's maximum recommended settings to preclude damage to the valve assemblies.

4. Confirm that all the threaded stem type NSR-MOVs utilize ACME General Purpose Screw Threads since that is the only type of thread design addressed in procedures provided.

5.

Confirm that the torque switch is bypassed for the first 20% to 25% of total disk travel on the opening cycle of a valve.

6.

Confirm that a clamp-on anneter and a dead-man switch are both used during a MOVATS test.

7. Provide the following information:

a. A list of nuclear safety related motor operated valves that identifies the valve number, actuator size, valve type, valve size, system purpose or function and safety function of valve.

b. A list of nuclear safety related motor operated valves, that in addition to MOVATS testing, will be tested against their most limiting operational requirement. The list should include the valve number, the operational limiting requirement, the test con-ditions (range), the vendor rating and when the test will occur (e.g., prior to restart). Some valves must be subject to closure testing under flow conditions.

E .

c. For each valve in Item 7.b above the rationale for. its selection and l why the tested. valves as a group should be considered a representative j sample of all the nuclear safety related torque seated valves. '

d. One valve information package that contains summary data for valve categorization and completed procedure HFEI-090.1 (copy of all data and documentation) for a valve greater than 2 inches in diameter included in Item 7.b above.