ML20205T760

Forwards Request for Addl Info Re Review of Revised Responses to IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings

ML20205T760
Person / Time
Site:	Prairie Island
Issue date:	04/03/1987
From:	Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Larson C NORTHERN STATES POWER CO.
References
IEB-85-003, IEB-85-3, NUDOCS 8704070386
Download: ML20205T760 (6)

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APR 31987 Docket No. 50-282 Docket No. 50-306 Northern States Power Company ATTN: Mr. C. E. Larson Vice President, Nuclear Generation 414 Nicollet Mall Minneapolis, MN 55401 Gentlemen:

The preliminary review of your revised responses to IE Bulletin 85-03

Motor-0perated Valve Common Mode Failures During Plant Transients Due To Improper Switch Settings" indicates the need for additional information '

before the program to assure valve operability can be approved. The specific information necessary for the completion of our review is enclosed.

Additional information is requested within one month of receipt of this letter.

The written reports shall be submitted to the Regional Administrator, Region III, under oath or affirmation under provisions of Section 182a, Atomic Energy Act of 1954, as amended. Also, the original copy of the cover letters and a copy of the reports shall be transmitted to the U.S. Nuclear Regulatory Commission Document Control Desk, Washington, DC 20555 for reproduction and distribution.

Questions addressing this issue may be forwarded to Richard J. Kiessel, IE (301) 492-8119.

Sincerely, ORIOJNAL SIGNED BY C. E.190DET.mS Charles E. Norelius, Director Division of Reactor Pr /ojects

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Licensing Fee Management Branch Resident Inspector, RIII Prairie Island Resident Inspector, RIII Monticello John W. Ferman, Ph.D.,

Nuclear Engineer, MPCA State Liaison Officer, State of Minnesota Richard J. Kiessel, IE

• Enclosure 3 Page 1 of 2 REQUEST FOR ADDITIONAL INFORMATION (RAI) RE:

Review of Responses to Action Item e of IE Bulletin 85-03 Licensee: Unit (s): Prairie Island 1, 2 Northern States Power Company Date of Response: 05/12/86 414 Nicollet Mall 07/14/86 Minneapolis, MN 55401 09/12/86 11/26/86 Respondent:

C. E. Larson Vice President,-

Nuclear Generation The information provided in your responses to Action Item 3 of IE Bulletin 85-03 was found to be deficient in some areas. Please provide the additional information necessary to resolve the following comments and questions listed below. If any of the valves are locked in position and power is removed from

! the motor, please state this. Otherwise, the valves should be addressed in your revised response.

1. Unlisted MOV 32083 in the boric acid supply line of the safety injection system is shown normally open downstream of two normally closed MOVs in parallel. Although MOV 32083 is not identified in Table 1 of the response of July 14, 1986, it is shown in Zone J-6 of Drawing X-HIAW-1-45, Revision G. What controls are placed on this valve to ensure that it will be in I the proper position when needed? For example, how would suction of the boric acid tank be ensured if MOV 32083 were to be left closed inadver-tently? In accordance with the assumption of inadvertent equipment operations as required by Action Item a of the bulletin, revise Table 1 of the response to include this valve.

2. Unlisted MOVs 32071 and 32072 in discharge lines of the accumulator safety injection system are shown normally open on Drawing X-HIAW-1-44, Revision J. The possible problem that the system would be inoperable if the MOVs were left closed inadvertently should be addressed. Based on the assump-tion of inadvertent equipment operations as required by Action Item a of the bulletin, revise Table 1 of the response of July 14, 1986 to include these valves.

3. According to Item I.B.2 of the response dated July 14, 1986, " safety injection pump discharge to the cold leg valves are [ sic] not considered in the evaluation because Technical Specifications require these valves to be open with their associated motor contact center supply breakers locked open" .

. Revise drawing X-HIAW-1-44, Revision J for compliance with the above note.

Unlisted MOVs 32068, 32070 and 32073 are shown normally open and are affected by this comment.

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4. Has water hamer due to valve closure been considered in the determination of pressure differentials? If not, please explain.

Note: The above MOV numbers apply to Unit 1; Unit 2 is similar.

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APR 3 1987 l Docket No. 50-282 Docket No. 50-306 Northern States Power Company ATTN: Mr. C. E. Larson Vice President, Nuclear Generation 414 Nicollet Mall Minneapolis, MN 55401 Gentlemen:

The preliminary review of your revised responses to IE Bulletin 85-03

" Motor-0perated Valve Common Mode Failures During Plant Transients Due To Improper Switch Settings" indicates the need for additional information before the program to assure valve operability can be approved. The specific information necessary for the completion of our review is enclosed.

Additional information is requested within one month of receipt of this letter.

The written reports shall be submitted to the Regional Administrator, Region III, under oath or affirmation under provisions of Section 182a Atomic Energy Act of 1954, as amended. Also, the original copy of the cover letters and a copy of the reports shall be transmitted to the U.S. Nuclear Regulatory Comission Document Control Desk, Washington, DC 20555 for reproduction and distribution.

Questions addressing this issue may be forwarded to Richard J. Kiessel, IE (301) 492-8119.

Sincerely, i

ORIGINAL SIGNED BY C. E. MOmIUS j Charles E. Norelius, Director I Division of Reactor Projects

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E. L. Watzl, Plant Manager DCS/RSB (RIDS)

Licensing Fee Management Branch Resident Inspector, RIII Prairie Island Resident Inspector, RIII Monticello John W. Ferman, Ph.D.,

Nuclear Engineer, MPCA State Liaison Officer, State of Minnesota Richard J. Kiessel, IE l

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