ML20151A538

Forwards Request for Addl Info Re Util 860516,1120 & 870218 Responses to IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings, for Response within 30 Days

ML20151A538
Person / Time
Site:	McGuire
Issue date:	03/31/1988
From:	Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Tucker H DUKE POWER CO.
References
IEB-85-003, IEB-85-3, NUDOCS 8804070066
Download: ML20151A538 (3)

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Docket Nos. 50-369, 50-370 MAR 311988 License Nos. NPF-9, NPF-17 Duke Power Company ATTN: Mr. H. B. Tucker, Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION CONCERNING RESPONSE TO  ;

BULLETIN 85-03, MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 Duke Power Company's letters of May 16 and November 20, 1986, and February 18, 1987, pertaining to McGuire Units 1 and 2, contained responses to NRC ,

Bulletin 85-03, "Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings." Your letter of January 14, 1988, indicates responses for McGuire will be submitted at the end of fuel cycles 5 (Unit 1) and 4 (Unit 2). The review of these responses by the Nuclear Regulatory Commission indicates the need for additional information. identified by the enclosure, before the program to assure valve operability can be completed.

Please provide the additional information as stated in the enclosure. It is requested *. hat you submit the additional information within 30 days of the date of this letter. Should you have any questions concerning this letter, please contact S. Tingen at (404) 331-2603.

Sincerely, 4,

, )

p.- A Alan rdt,ThiF 3 Engineering Branch Division of Reactor Safety

Enclosure:

Request for Additional Information cc w/ enc 1:

l T. L. McConnell, Station Manager i

! Senior Resident Inspector - Catawba j i bec w/ enc 1:

B. Bonser, RII  %

D. Hood, NRP. 8804070066 080331 PDR ADOCK 05000369 R. Kiessel, NRR o PDR

NRC Resident Inspector DRS Technical Assistant Document Control Oesk RII RII RII' i m (d,:Y -

STingn:gb 03/n/88 j JJape

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MYk'b'les 1 f 03/M /88 03/&/88 l s ,

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ENCLOSURE sheet 1 of 2

1. E0llEST FOR ADDITIONAL INFORMATION REGARDING RESPONSES TO ACTION ITEM E OF NRC BULLETIN 85-03 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 By letters dated May 16 and November 20, 1986 and February 18, 1987 you responded to NRC Bulletin 85-03, "Motor-Operated Valve Comon Mode Failure During Plant Station, UnittTransients 1 and 2. Due ko Imoroper Switch Settings" for McGuire Nuclear Action Item e of NRC Bull'etin 85-03: Provide the following additional infomation regardin 1.

Clarf fy whe'her water hamer due to valve closure has been considered in the determination of pressure differentials. If not, explain.

2.

The following MOVs of the SI System are not ir, eluded in the response of 05-16-86; however, they are shown in the WOG Report of March 1986. Revise the response to include these MOVs, o* justify their exclusion. As required by Action Item a of the bulletin, assume inadvertent equipment operations.

(a) MOVs N!1448, N!115B and N!147A are shown normally open in the SI pump miniflow lines in zones G-9, H-9, and G-11 of Drawing MC-1562-3.0 Revision 9 (Unit 1). They are shown on Page 25 of the WOG Report, as HV-88148. HV-8814A and HV-8813, respectively.

NOTE:

Similarly located valves are used for Unit 2 also.

(b) POVs NY1508 and NY151A are shown normally open in the CCP miniflow lines on FSAR Figut a 9.3.4-2 (Unit 1). They are shown on Page 24 of the WOG Report, as HV-8111 and HV-8110, respectively.  :

NOTE:

Similarly located valves are use for Unit 2 a)so.

3.

The following MOVs in the AFW System are not included in the response of 05-16-86. Explain this exception to the Westinghouse recoernendation that "all MOVs within the AFW system should be included on the list of valves to be examined for maximum differential pressure", as stated on ea ge 5 of the WOG Report. Revise the response of 05-15-86 to include these MOVs, or justify their exclusion.

(a) MOVs CA162C and CA161C are shown normally closed in series in the AFW suction line from Nuclear Service Water Header IA in zones D-7 and 0-8 of Drawing MC-1592-1.1 Revision 6 (Unit 1).

(b) MOV CA6 is shown normally open in the AFV suction line from the AUX FDW Condensate Storage Tark in Zone C-10 of Draw!ng MC-1592-1.1.

Revision 6 (Unit 1).

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ENCLOSURE sheet 2 of 2 ,

(c) NOV CA4 is shown normally open in the AFW suction line from uoper surge tanks IA and 18 in Zone D-9 of Drawing MC-1592-1.1 Revision 6 (Unit 1). >

7 Note: Similarly located valves are used for Unit 2 also.

4 Clarify the response of 05-15-86 to indicate whether the tabulated P

differential pressure apply to opening the valve, closing the valve or  :

both opening and closing. '

5. Regarding the proposed (program fnr action items b, e and d of the bulletin, provide the>following as a minimum:

(a) a ccamitment to justify continued operation of a valve determined to be inoperable, and (b) consideration of pipe break conditions as required by the bulletin.

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