ML20093K991

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Responds to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves
ML20093K991
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 10/16/1995
From: Hill W
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-95-07, GL-95-7, NUDOCS 9510250134
Download: ML20093K991 (6)


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Northem States Power Company Monticello Nuclear Generating Plant 2807 West Hwy 75 Monticello, Minnesota 55362-9637 October 16,1995 NRC Generic Letter 95-07 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Response to Generic Letter 95-07: Pressure Locking and Thermal Bindina of Safetv-Related Power-Operated Gate Valves The purpose of this letter is to provide the 60 day response required by NRC Generic Letter 95-07 for the Monticello Nuclear Generating Plant.

Generic Letter 95-07 (dated August 17,1995) was issued by the NRC requesting licensees to provide information conceming (1) the evaluation of operational configurations of safety-related, power-operated gate valves for susceptibility to pressure locking and thermal binding; and (2) analyses, and needed corrective actions, to ensure that safety-related power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing the required safety function.

Generic Letter 95-07 contained the following required response:

Within 60 days from the date of(Generic Letter 95-07), a written response indicating whether ornot the addressee willimplement the action (s) requested (by the generic letter). If the addressee intends to implement the requested action (s), provide a schedule forcompleting implementation. If an addressee chooses not to take the requested action (s), provide a description of anyproposed attemative course of action, the schedule forcompleting the altemative course of action (if applicable), and the safety basis for determining the acceptability of the planned altemative course of action. to this letter provides our response.

This letter contains the following new NRC commitments:

1.

Monticello will implement the Generic Letter 95-07,90 day Requested Action items in accordance with the generic letter.

9510250134 951016 PDR ADOCK 05000263 M; [ i P

PDR i F I

USNRC NORTHERN STATES POWER COMPANY October 16,1995 Page 2 t

2.

Monticello will implement the Generic Letter 95-07,180 day Requested Action items. Completion of this activity is to coincide with the completion of our 1996 refueling outage. Should individual valves require a longer schedule, the appropriate schedule for completing any potential corrective action will be reported in our response to the Requested information of Generic Letter 95-07.

3.

Monticello will submit the information requested by Generic Letter 95-07 within 60 days after completion our 1996 refueling outage.

Please contact Mary Engen, Sr Licensing Engineer, at (612) 295-1291 if you require further information.

/kk/W

/E William J Hill Plant Manager Monticello Nuclear Generating Plant c:

Regional Administrator-lil, NRC NRR Project Manager, NRC l

Sr Resident inspector, NRC State of Minnesota, Attn: Kris Sanda Attachments: (1)

Monticello Nuclear Generating Plant,60 Day Response to Generic Letter 95-07 i

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UNITED STATES NUCLEAR REGULATORY COMMISSION s

NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 RESPONSE TO GENERIC LETTER 95-07:

PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES DATED October 16,1995 Northem States Power Company, a Minnesota corporation, hereby provides response to NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves. This letter contains no restricted or other defense information.

NORTHERN STATES POWER COMPANY

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By William J Hiti' Plant Manager Monticeho Nuclear Generating Plant On this I day of OCO 199f before me a notary public in and for said County, personally appeared William J Hill, Plant Manager, Monticello Nuclear Generating Plant, and being first duty swom acknowledged that he is authorized to execute this document on behalf of Northem States Power Company, that he knows the contents thereof, and that to the best of his knowledge, information, and belief the statements made in it are true and that it is not interposed for delay.

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klarvin R Engenf l l

  1. 0 M W Muusma Notary Public - Minnesota

-- _9_C8"_h8 888 Sherbume County My Commission Expires January 31,2000 l

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V Monticello Nuclear Generating Plant t

60 Day Resoonse to Generic Letter 95-07 i

Reauested Action.

Y Within 90 days of the date of(Generic Letter 95-07}, each addressee of(the} generic letteris requested to perform and complete the following actions:

1.

Perform a screening evaluation of the operational con 6gurations of all safety-related power-operated (i.e., motor-operated, air-operated, and hydraulically operated) gate valves to identify those valves that are potentially susceptible to pressure locking or thermalbinding; and 2.

Document a basis for the operability of the potential susceptible vains or, where operability cannot be supported, take action in accordance with individualplant Technical Specifications.

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Within 180 days of the date of(Generic Letter 95-07), each addressee of(the} generic letteris requested to implement and complete the guidance provided in Attachment 1 lof Generic Letter 95-07} to perform the followirnq actions:

1.

Evaluate the operational con 6gurations of safety-related power-operated (i.e., motor-operated, air-operated, and hydraulically operated) gate valves in its plant to identify valves that are susceptible to pressure locking or thermal binding; 2.

Perform further analyses as appropriate, and take needed conective actions (orjustify i

longer schedules), to ensure that the susceptible valves identi6 edin 1 are capable of performing theirintended safety function (s) under all modes of plant operation, including test con 6guration.

Monticello Response Monticello will implement the above Generic Letter 95-07, 90 day Requested Action items, as requested and in accordance with the generic letter. Monticello will implement the above Generic Letter 95-07,180 day Requested Action items, however; we are scheduling l

completion of this activity to coincide with the completion of our next scheduled refueling outage (currently scheduled for April /May 1996). This schedule will provide an opportunity to implement potential hardware modifications should such corrective actions be needed. Should a longer schedule be necessary for individual valves, the appropriate schedule justification and schedule dates for completing the potential corrective action will be reported in our response to the Requested information of Generic Letter 95 /.,7.

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i October 16,1995 Page 2 Reauested Information AII addressees, including those who han already satisfacionly addressed pressure locking and thermal binding for MOVs byimplementing the guidance in Supplement 6 to GL 89-10 (or i

equivalent industry methods), are requested to provide a summary descnption of the tbilowing:

1.

The susceptibility evaluation of operational con 6gurations performed in response to (or consistent with) 180-day Requested Action 1, and the further analyses performedin response to (orconsistent with) 180-day Requested Action 2, including the bases or cntena fordetermining that valves are orare not susceptible to pressure locking or thermalbinding; 4

2.

The results of the susceptibility evaluation and the further analyses referred to in 1 above, including a listing of the susceptible valves identi6ed; 1

1 3.

The corrective actions, or other dispositioning, for the valves identiRed as susceptible to pressure locking or thermal binding, including: (a) equipment or procedural modi 6 cations completed and planned (including the completion schedule for such l

actions): and (b) Justi6 cation for any determination that particular satiety-related power-operated gate valves susceptible to pressure locking or thermal binding are acceptable asis.

I Monticello Response l

Monticello will submit the above information requested by Generic Letter 95-07. The Generic Letter specifies that this information be submitted within 180 days from the date of the generic letter. As stated in our response to the requested actions, we foresee that some actions may not be completed until completion of our next scheduled refueling outage (April / May 1996),

4 and thus the requested information may not be available. Monticello will submit the requested information within 60 days after completion our next scheduled refueling outage.

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TRANSMITTAL MANIFEST NORTHERN STATES POWER COMPANY NUCLEAR LICENSING DEPARTMENT I

MONTICELLO NUCLEAR GENERATING PLANT Response to Generic Letter 95-07 Manifest Date:

October 16,1995 Correspondence Date: October 16,1995 Monticello Intemal Site Distribution Special Instructions Kaleen Hilsenhoff......USAR File.................Yes_x_ No Steve Ludders.......NRC Commitment.....Yes_x_ No Lila imholte..............Monti OC Sec...........Yes_x_ No

- 11, No dist to OC members below if YES Mil Opstad............... Monti SAC Sec..........Yes_x_ No

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  • Mail Room.............. Monti Posting............Yes No_x_ - 7 Monticello intemal Site Distribution:
  • Monti Document Control File J C Grubb, NGSS, OC W J Hill, Plant MGR, SAC, OC L L Nolan, GSSA, OC C A Schibonski, GSE, OC B D Day, MGR MTC, OC M F Hammer, GSM, OC Operating Experience Coord J E Windschill, GSRS, OC W A Shamla, NQD M W Onnen, GSO, OC Monti Site Lie File Tom Fallgren NRC Resident inspector's Office Keith Peterson NSP Intemal Distribution E L Watzl R O Anderson, Dir LMI, SAC T E Amundson, Dir NQD, SAC Communications Dept Yes No_x,__

Extemal NSP Distribution fl.PfDoc Control Desk, NRC '

Kris Sanda, State of Minn Regional Admin-lll,NRC J E Silberg T J Kim, NRR-PM, NRC

  • Advance Distribution made by Site Licensing 21CG33 a