ML20100J110

Supplemental Response to Suppl 1 to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue USI A-46

ML20100J110
Person / Time
Site:	Monticello
Issue date:	02/19/1996
From:	Hill W NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, TAC-M69460, NUDOCS 9602280258
Download: ML20100J110 (6)

Text

Nonthem States Power Company Monticello Nuclear Generating Plant 2807 West Hwy 75 ,

Monticello. Minnesota 55362-9637 )

l February 19,1996 Generic Letter 87 02 l

US Nuclear Regulatory Commission i Attn: Document Control Desk l Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Supplemental Response to Supplement 1 to Generic Letter 87-02,

" Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors. Unresolved Safety issue USI A-46"(TAC M69460)

> On February 19,1987, the NRC issued Generic Letter 87-02, " Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety issue (USI) A-46". This Generic Letter encouraged utilities to participate in a generic program to resolve the seismic verification issues associated with USl A-46. As a result, the Seismic Quali'ication Utility Group (SQUG) developed the " Generic implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment".

On May 22,1992, the NRC Staff issued Generic Letter 87-02 Supplement 1, which constituted the NRC Staff's review of the GIP and which included Supplemental Safety Evaluation Report Number 2 (SSER-2) on tho GIP, Revisica 2, corrected on February 14,1992. By letters dated September 21,1992, and November 20,1995; Monticello responded to Generic Letter 87-02 Supplement 1.

In our November 20,1995 letter, Monticello committed to a follow-up response within 90 days providing our schedule for corrective actions to address components identified as outliers during the relay evaluation. These components were listed in Table 7-1 of our report USNRC A-46 Resolution. Seismic Evaluation Report. Monticello Nuclear Generatino Plant: the Monticello SQUG report. This letter satisfies that commitment. Attachment 1 to this letter restates the iisting of components provided in Table 7-1 of the Monticello SQUG report and provides our schedule for resolution of these outliers. .

This letter contains the following new NRC commitment:

1. Outlier components identified in Table 1-1 of Attachment 1 are to be evaluated and resolved in accordance with the SQUG Generic Imolementation Procedures (GIP). For Seismic Verification of Nuclear Plant Eouloment. Revision 2, Section I 5, " Outlier identification and Resolution." This action is to be completed prior to 2/16/96 NSP tt\ DATA \NRCCORR\GL9702RR. DOC

" 3602280258 960219 PDR ADOCK 05000263 p PDR

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USNRC NORTHERN STATES POWER COMPANY February 19,1996 Page 2 the end of the 1998 refueling outage, currently scheduled to commence in January 1998.

2. Outlier components identified in Table 1-2 of Attachment 1 are to be replaced with relays seismically qualified for their intended use during the Monticello 1996 refueling outage, scheduled for April 1996.

3. Outlier components identified in Table 1-3 of Attachment 1 are to be replaced with relays seismically qualified for their intended use during the Monticello 1998 refueling outage, currently scheduled to commence in January 1998.

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

h Einh W ,

William J Hill l Plant Manager l Monticello Nuclear Generating Plant c: Regional Administrator- 111, NRC NRR Project Manager, NRC Sr Resident inspector, NRC State of Minnesota, Attn: Kris Sanda Attachments: Affidavit to the US Nuclear Regulatory Commission l (1) Generic Letter 87-02, Supplement 1, Relay Evaluation Outlier Resolution l l

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UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 Supplemental Response Dated February 19,1996 to Supplement 1 to Generic Letter 87-02, Nerification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors. Unresolved Safety Issue USI A-46" frac M69460)

Northem States Power Company, a Minnesota corporation, hereby provides the information requested by Supplement 1 to Generic Letter 87-02, as committed to in our November 20, 1995, submittal.

This letter contains no restricted or other defense information.

NORTHERN STATES POWER COMPANY By / N*

William J Hf Plant Manager Monticello Nuclear Generating Plant l

On this day of [ebhv / 99h before me a notary public in and for a said County, personally appeared Vfilliam J Hill, Plant Manager, Monticello Nuclear Generating i Plant, and being first duly swom acknowledged that he is authorized to execute this document on beha!f of Northem States Power Company, that he knows the contents thereof, and that to i the best of his knowledge, information, and belief the statements made in it are true and that it is not interposed for delay.

. tuo M'drvin R Engen /

l Notary Public- Minnesota f '.$

Sherbume County nn/#

My Commission Expires January 31,2000 MARVIN SCHARD ENGEN ,

j h0TMtYPusuC IMedESOTA i  % N: E89: Jan. 31,2000; 1

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Attachment 1 Generic Letter 87-02. Supplement 1. Relav Evaluation Outlier Resolution The seismic capacity review performed using the Seismic Qualification User Group (SQUG) methodology identified a number of relays for which the Generic Equipment Ruggedness Spectra (GERS) or specific vendor qualification were not available. These relays are considered outliers and will require additional evaluation. The components listed in Table 1 1 below ere to be evaluated using the methodology for resolution of outliers contained in the SQUG Generic Implementation Procedures (GIPL For Seismic yp_riNeton of Nuclear Plant Eauipment. Revision 2, Section 5, " Outlier Identification and rb eJjution." This action is to be completed prior to the end of the 1998 refueling outage, c.urrently scheduled to commence in January 1998.

Table 1-1 Relay Outliers to be Further Evaluated Relay Designation and Panel Subsystem / Component used in ECRA (C91) G-3A (EDG 11)

ECRA (C92) G-3B (EDG 12)

ESR1 (C91) G-3A (EDG 11)

ESR1 (C92) G-3B (EDG 12)

ESR2 (C91) G-3A (EDG 11)

ESR2 (C92) G-3B (EDG 12)

ESRX1 (C91) P-111 A - 11 EDG-ESW pump, V-SF 11 EDG supply fan ESRX1 (C92) P-111B - 12 EDG-ESW pump, l V-SF 12 EDG supply fan l P-111 A - 11 EDG-ESW pump,  !

ESRX2 (C91)

- V-SF 11 EDG wpply fan ESRX2 (C92) P-1118 - 12 EDG-ESW pump, V-SF 12 EDG supply fan ESTR (C91) G-3A (EDG 11)

ESTR (C92) G-3B (EDG 12)

FFC (C91) G-3A (EDG 11)

FFC (C92) G-3B (EDG 12)

FFCO (C91) G-3A (EDG 11)

FFCO (C92) G-3B (EDG 12)

FPR (C91) EDG 11 FPM - motor driven fuel pump FPR (C92) EDG 12 FPM - motor driven fuel pump FSR1 (C91) G-3A (EDG 11)

FSR1 (C92) G-38 (EDG 12)

FSR2 (C91) G-3A (EDG 11)

FSR2 (C92) G-38 (EDG 12)

GV (C91) G-3A (EDG 11)

GV (C92) G-3B (EDG 12)

' Attachment 1 February 19,1996

• Page 2 Table 1-1 (continued)

Relay Designation and Panel - Subsystem / Component used in [

MSR1 (C91) G-3A (EDG 11) ,_

_MSR1 (C92) G-3B (EDG 12) _ l MSR2 (C91) G-3A (EDG 11) .

MSR2 (C92) G-38 (EDG 12)

NFLD (C93) G-3A (EDG 11)

NFLD (C94) G-38 (EDG 12)

NFLDA (C93) G-3A (EDG 11)

NFLDA (C94) G-3B (EDG 12)

OT (C93) G-3A (EDG 11) '

OT (C94) G-38 (EDG 12)

OTR (C91) G-3A (EDG 11)

OTR (C92) G-3B (EDG 12)

PFDA1 (C91) G-3A (EDG 11)

PFDA1 (C92) G-38 (EDG 12)

PFDA2 (C91) G-3A (EDG 11)

PFDA2 (C92) G-38 (EDG 12)

SFA (C93) - G-3A (EDG 11)

SFA (C94) G-3B (EDG 12)

STR1 (C91) G-3A (EDG 11),

11 EDG MVST1 - air start solenoid, 11 EDG BPM booster pump motor ,

STR1 (C92) G-3B (EDG 12),

12 EDG MVST1 - air start solenoid, 12 EDG BPM booster pump motor STR2 (C91) G-3A (EDG 11),

11 EDG MVST2 - air start solenoid, 11 EDG BPM booster pump motor STR2 (C92) G-3B (EDG 12),

12 EDG MVST2 - air start solenoid, 12 EDG BPM booster pump motor VSR1 (C91) G-3A (EDG 11)

VSR1 (C92) G-3B (EDG 12) .

VSR2 (C91) G-3A (EDG 11) l VSR2 (C92) G-3B (EDG 12)

ZSR1 (C91) G-3A (EDG 11)

ZSR1 (C92) G-38 (EDG 12)

ZSR2 (C91) G-3A (EDG 11)

ZSR2 (C92) G-3B (EDG 12) l l

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Attachment 1 February 19,1996 Page 3 The following relays identified as outliers per the methodology contained in the SQUG GIP are to be resolved by component replacement. These relays are to be replaced with relays seismically qualified for their intended use during the Monticello 1996 refueling j outage, scheduled for April 1998.

Table 1-2 PFD1 (C92) G-3B (EDG 12)

PFD2 (C92) G-3B (EDG 12)

SFB1 (C92) G-38 (EDG 12)

SFB2 (C92) G-3B (EDG 12)

SFD1 (C92) G-3B (EDG 12)

SFD2 (C92) G-3B (EDG 12)

SSP 1 (C92) G-3B (EDG 12)

SSP 2 (C92) G-38 (EDG 12)

The following relays identified as outliers per the methodology contained in the SQUG GIP are to be resolved by component replacement. These relays are to be replaced with relays seismically qualined for their intended use during the Monticello 1998 refueling outage, currently scheduled to commence in January 1998.

Table 1-3 PFD1 (C91) G-3A (EDG 11)

PFD2 (C91) G-3A (EDG 11)

SFB1 (C91) G-3A (EDG 11)

SFB2 (C91) G-3A (EDG 11)

SFD1 (C91) G-3A (EDG 11)

SFD2 (C91) G-3A (EDG 11)

SSP 1 (C91) G-3A (EDG 11)

SSP 2 (C91) G-3A (EDG 11)