ML17285A199

Summary of 881215 Meeting W/Util at Site Re Surveillance of Degraded Voltage Protection Circuitry at Facility

ML17285A199
Person / Time
Site:	Columbia
Issue date:	01/05/1989
From:	Samworth R Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-71445, NUDOCS 8901230218
Download: ML17285A199 (10)

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UNITHDSTATES NUCLEAR REGULATORYCCNMtsSION NASHIHO'JON, D, C,20555 January 3, 1989 A

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I Docket No.:

50-397 LICENSEE:

FACILITY:

SUMECT:

WASHINGTON PNLIC POWER SUPPLY SYSTEH itASHINGTON NUCLEAR PROJECT NO. 2 itPPSS

- SitlNARY QF DECKHBER 15 1988 MEETING ON SURVEILLANCE OF THE DEGSSED VOLTAGE ItROTECTION CIRCUITRY AT kNP-2 On December lS, l988 representatives of MNP-2 set wfth representatives of the NRC staff to discuss surveillance of the degraded voltage protection circuitry at itNP-2.

The list of attendees at the meeting is enclosed.

The fol'lowing are the salient points discussed at the aeeting.

l.

The licensee fs not complying with surveillance requirements in Technical Specifications Section 4.3.3.1

2. If the licensee ran satisfactorily demonstrate in a safety analysis that relfabflfty of the undervoltage protection circuitry is adequately ensured by doing so, and that component drift is not a prob'lem the staff can accept functiona'l testing of the three second delay reiays (in Divisions 1 5 2) as part of the calibration at frequenter "R".

3.

The undervoltage protection system on Division 3 is not tested fn accordance with the Technical Specfficatfons.

The license will argue that based on reliability and drift experfence with the components, testing on schedule 'R'dequately ensures relfabil5 and accuracy.

4.

The lfcensee has a large number of logic systems not testable at power.

The 15censee will amend FSAR Chapter 7 to show portions of the protection system requirements for which exceptions to IEEK testabflftg-at-power standards are IIadeo 5.

The licensee will Ale a license amendment applfcatfon ear ly next week to

<<odffy the Technical Specifications to specify an achievable survefl)ance schedule.

6.

The licensee will need relfef before January 12, therefore the Tech Spec amendment application will be submitted as an e!Mrgenqy, 7.

In reviewing their testing procedure submitted with the December 7 letter, Fred Burrow noted that the setpoints in the procedure differ from those in the Tech Specs.

The licensee will submit a separate Tech Spec asendment requesting new setpofnts.

This part will not be an emergenci.

The licensee has reperformed calculations and has computed new setpoints which are more 8901230218 890105 l PDR ADOCK 05000397 Sp ZB'd SBBE Ct'6 STt' 6t"BT 686TrTTgyB

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January 5, 1ggg different from those in the existing Tech Specs.

According to Tom Dunning the existing Tech Specs let the licensee adjust the setpo$ nt to any value w)thin the specified setpu/nt rang>>.

Therefore, the licensee can use the setpo$ nts shown in the test)ng procedure is they fall within the existing Tech Specs.

8.

The licensee advised that they believe that the action statement in Table 3.3.3-l (page 3/4 3-28) for degraded voltage does not address the circumstance of two channels inoperable and therefore should be changed.

They are going to propose a Tech Spec change on this.

Me advised that we do not want to review th)s request on an emergency basis and so they agreed to submit it separately.

9.

R. Saworth commented for the record that the staff has not completed its review of the MPPSS submittal dated December 7, 1988 {G02-88-26l) and that MPPSS staff should not infer that IIRR

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$ n agreement with statements aIde

$ n that submittal at this time.

5 tnce MPPSS will be submitting a license amendment application regarding th>> degraded voltage protection survefllances, NRC w)11 not respond separately ro the Decetiber 7 submittal.

Enclosuree ec w/enclosure:

See next page lg;Pp

~gohera B, gawoiah, Senior Progeca Hanager Pro)ei:t fl)recto> ate Dkv)sion of Reactor Projects Qffkc>> of ttuclear Reactor Regulat)on 03'd SGBE Dr6 GTtr

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ENCLOSURE 1

NRC-MPPSS MEETING On Surrveillance of te degraded voltage protection circuitry at MNP-2 December 15, 1988 NAMES R. Samworth G. Knighton J. Bradfute D. Tondi F. Burrows T. Dunning P. Johnson P. Powell M. Muestefeld T. Neade Region 5 (on phone)

ORGANIZATION NRC NRC NRC NRC NRC NRC NRC MPPSS MPPSS MPPSS

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8r. G. C. Sorensen, Manager Mashington Public Power Supply System WPPSS Nuclear Project No. 2 (MNP-2)

CC'icholas S. Reynolds, Esq.

Bishop, Cook, Purcell 3 Reynolds 1400 L Street NM Mashington, D.C.

20005-3502 Nr. G. E. Doupe, Esquire'ashington Public Power Supply System P. 0. Box 968 3000 George Mashington May Richland, Washington 99532 Mr.'Curtis Eschels, Chafrman Energy Facility Site Evaluatfon Council Nail Stop PY-11 Olympia, Washington 98504 Mr. Alan G. Hosier, Licensing Manager Washington Public Power Supply System Pi 0.

Box 968, ND 956B Richland, Mashington 99352 Nr. A. Lee Oxsen Assistant Managing Director for Operations Washington Public Power Supply System P. 0. Box 968, ND 1023

Richland, MA 99352 Mr. Gary D. Bouchey, Dfrector Licensing and Assurance Washington Public Power Supply System P. 0.

Box 968, ND 280 Rfchland, Washington 99352 Nr. C. N. Powers MNP-2 Plant Manager Washington Public Power Supply System P. 0.

Box ND 927M Richland, Mashington 99352 Regional Administrator, Region V

U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Chafrman Benton County Board of:Coaefssfoners

Prosser, Mashfngton 99350 Nr. Christian Bosted U. S. Nuclear Regulatory Commission P. 0. Box 69 Richland, Mashington 99352

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January 5,

1989 different from those in the existing Tech Specs.

According to Tom Dunning the existing Tech Specs let the licensee adjust the setpoint to any valtfe within the specified setpoint range.

Therefore, the licensee can use the setpoints shown in the testing procedure is they fall within the existing Tech Specs.

8.

The licensee advised that they believe that the action statement in Table 3.3.3-1 (page 3/4 3-28) for degraded voltage does not address the circumstance of two channels inoperable and therefore should be changed.

They are going to propose a Tech Spec change on this.,

We advised that we do not want to review this request on an emergency basis and so they agreed to submit it separately.

9.

R. Samworth commented for the record that the staff has not completed its review of the WPPSS submittal dated December 7, 1988 (G02-88-261) and that WPPSS staff should not infer that NRR is in agreement with statements made in that submittal at this time.

Since WPPSS will be submitting a license amendment application regarding the degraded voltage protection surveillances, NRC will not respond separately to the December 7 submittal.

Enclosure:

As stated Robert B. Samworth, Senior Project Hanager Project Directorate Division of Reactor Projects Office of Nuclear Reactor Regulation cc w/enclosure:

See next page RBSamu th:dr DISTRIBUTION j'ooa NRC f LPDRs PD5 Reading NVirgilio RSamworth OGC EJordan BGrimes NRC Participants ACRS (10)

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