ML20206N364

Forwards Rev 8 to Inservice Testing Program,Callaway Nuclear Program & Description of Changes.Changes Will Be Fully Implemented by End of Refueling Outage 2

ML20206N364
Person / Time
Site:	Callaway
Issue date:	04/14/1987
From:	Schnell D UNION ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20206N370	List: ML20206N364 ML20206N478
References
ULNRC-1484, NUDOCS 8704200467
Download: ML20206N364 (4)

Text

r Union Etscraic a

1901 Gratiot Street, St. Louis Donald F. Schnell April 14, 1987

%ce President ULNRC-1484 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

CALLAWAY PLANT DOCKET NUMBER 50-483 CALLAWAY PUMP AND VALVE INSERVICE TESTING PROGRAM REFS: 1) ULNRC-738 dated January 31, 1984

2) ULNRC-833 dated May 29, 1984

3) ULNRC-1039 dated February 11, 1985

4) ULNRC-1127 dated June 23, 1985

5) ULNRC-1152 dated August 9, 1985

6) ULNRC-1267 dated June 28, 1986

7) P. W. O' Conner letter to D. F. Schnell dated July 10, 1986

8) ULNRC-1426 dated January 14, 1987 Reference 1 transmitted the Callaway Pump and Valve Inservice Testing Program.

References 2 through 6 and 8 transmitted updates to this same p'rogram.

Included as an attachment to this letter is a further update to the Callaway Testing Program. Attachment 1 is a brief description of the changes and Attach- '

ment 2 contains a copy of revised pages which should be inserted into the existing program. The changes to testing resulting from these program changes will be fully implemented by the end of the Refuel 2 Outage.

If you have any additional questions, please contact me.

Very truly yours, Donald F. Schnell DFS/WEK/lrj Attachments

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l Mailing Address: P.O. Box 149. St. Louis, MO 63166

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cc: Gerald Charnoff, Esq.

Shaw, Pittman, Pott s & Trowbridge 1800 M. Street, N.W.

Washington, D.C. 20036 Dr. J. O. Cermak CFA, Inc.

3356 Tanterra Circle Brookeville, MD 20833 W. L. Forney Division of Projects and Resident Programs, Chief, Section lA U.S. Nuclear. Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn,-Illinois 60137 Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission RRil Steedman, Missouri 65077 Paul O'Connor (2)

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 316 7920' Norfolk Avenue Bethesda, MD 20014 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102

Attachment 1 Page 1 of 2 CHANGES TO CALLAWAY NUCLEAR PLANT INSERVICE TESTING PROGRAM ITEM 1: CHANGE: Delete relief request AP-1 and valve AP-V-0033 from the test program.

BASIS FOR CHANGE

Per meeting with EG&G in September 1986, the NRC requested that AP-V-0033 be investigated with respect to.its safety related function. Initial investigation could not substantiate keeping the valve from the test program so it was added in revision seven in January 1987. Later, a more in-depth review revealed that AP-V-0033 serves no safety related function and need not be added to the test program.

ITEM 2: CHANGE: Add additional basis for relief to relief request BG-8.

BASIS FOR CHANGE: Per telecon with EG&G, the NRC requests a more de-tailed justification for not testing BG-V-0147, BG-V-0165, and BG-V-0174 on a power operations fre-quency.

ITEM 3: CHANGE: Increase test frequency from refueling to cold shutdown for valves EJ-HV-8811A and B as addressed by relief request EJ-6.

i BASIS FOR CHANGE: Per telecon with EG&G, the NRC requests that the frequency of testing for these valves be increased from refueling to cold shutdown.

ITEM 4: CHANGE: Add measurement of differential pressure to relief request P02.

BASIS FOR CHANGE: Per telecon with EG&G, the NRC requests that the inlet pressure during normal testing and differen-tial pressure for P-JE-01A and B be measured to assess pump degradation.

ITEM 5: CHANGE: Clarify the alternate testing statement on relief requests 4

AE-1, AL-2, BB-1, EN-1, EN-2, EN-3, and EP-2.

BASIS FOR CHANGE: Per telecon with EG&G, the NRC requested that these relief requests be modified to clarify the group of valves addressed by these individual relief requests. i l

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Attachment 1 Page 2 of 2 ITEM 6: CHANGE: Add further basis for relief for relief request EN-4.

BASIS FOR CHANGE: Per telecon with EG&G, the NRC requests a more technical justification for not testing EN-HV-1 and EN-HV-7 on a power operation quarterly fre-quency.

ITEM 7: CHANGE: Add additional basis for relief to relief request EP-4.

BASIS FOR CHANGE: Per telecon with EG&G, the NRC requests a more technical justification for not testing EP-HV-8950A, B, C, D, E, and F on a quarterly power op-erations frequency. -

ITEM 8: CHANGE: Add additional basis for relief to relief request KA-1 BASIS FOR CHANGE: Per telecon with EG&G, the NRC requests a more in depth justification for not exercising KA-FV-29 on a quarterly power operation frequency.

ITEM 9: CHANGE: Add additional basis for relief to relief request KJ-2.

BASIS FOR CHANGE: Per telecon with EG&G, the NRC requests a more clear and technical justification fo r not ex-ercising KJ-V-711A and B and KJ-V-712A and B on a quarterly power operations frequency.

ITEM 10: CHANGE: Change testing on relief request FC-1 from stroking closed at cold shutdown to valve disassembly at refueling to demon-strate operability.

BASIS FOR CHANGE: Further review of system design has determined that both valves in each Main steam supply line to the Auxiliary Feedwater Pump Turbine are re-quired for accident analysis. This results in needing to verify the closure capability of each of the four valves. Since there are no vents, drains, or connections between the two check valves on a line to allow for pressurization, depressurization, or flow, the valves must be disassembled and inspected to verify closure capability I