ML19257A517

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Summary of 791211 Meeting W/Util in Bethesda,Md Re Review of Electrical Design of Util Engineered Safety Feature Override Circuitry Pursuant to Criteria Provided by NRC
ML19257A517
Person / Time
Site: Pilgrim
Issue date: 12/13/1979
From: Hannon J
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8001040540
Download: ML19257A517 (8)
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Text

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UNITED STATES

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Mr. Carl Andognini Boston Edison Company M/C NUCLEAR 800 Boylston Street Boston, MA 02199 Mr. Paul J. McGuire 7

Pilgrim Station Acting Manager Boston Edison Company RFD #1, Rocky Hill Road Plymouth, Massachusetts 02360 Anthony Z. Roisman Natural Resources Defense Council 917 15th Street, N. W. ~

Washington, D. C.

20005 Henry Hernnann, Esquire Massachusetts Wildlife Federation 151 Tremont Street Boston, Massachusetts 02111 Plymouth Public Library North Street Plymouth, Massachusetts 02360 Docket File V. Noonan NRC PDR G. Knighton Local PDR D. Ziemann ORBi!3 Rdg P. Check NRR Rdg G. Lainas H. Denton D. Crutchfield E. Case F. Pagano D. Eisenhut-R. Clark

9. Grimes OELD W. Gammill OI&E (3)

R. Vollmer S. Sheopard L. Shao Project Manager J. Miller AC?.S (16) 1685 060 T.'Ipoolito

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R. Reid J. T 35$hanan A. Schwencer

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NUCLEAR REGULATORY COMMISSION gC WASHINGTO N, D. C. 20555

&ct%, ~# j#j December 13, 1979 Docket No. 50-293 FACILITY:

Pilgrim Nuclear Power Station LICENSEE: Boston Edison Company

SUBJECT:

MEETING

SUMMARY

A meeting was held with representatives from Boston Edison Company (BECo) in Bethesda, Maryland on December 11, 1979. The purpose of the meeting was to review the electrical design of Pilgrim ESF override circuitry pursuant to criteria provided by NRC letter dated November 28, 1979. A list of attendees, meeting agenda, and the electrical review criteria are attached.

The following letters were referred to during the background discussion:

(1) NRC letter regarding containment purging during nomal plant operation dated November 29, 1979, (2) BECo response dated January 9, 1979, (3) BECo supplemental response dated August 21, 1979, (4) NRC letter providing guidelines for valve operability dated September 29, 1979, (5) NRC letter providing " Interim Position for Containment Purge and Vent Valve Operation pending Resolution of Isolation Valve Oper-ability" dated October 22, 1979, (6) BECo response dated November 15, 1979, and (7) NRC letter requesting additional information in the systems /

mechanical area dated November 28, 1979.

BECo was advised that additional infomation would be necessary concerning valves and actuators before our review could be completed in the mechanical area. A handout was provided to BECo (copy attached) and they were requested to fill in the data and return it in the near future.

It was pointed out that their commitmert for in-situ valve testing documented in the November 1,5 1979 response should be supplemented by a description of the test program and acceptance criteria for early staff review.

1685 061

. In the August 21, 1979 response, BECo had discussed a radiological evaluation to support unlimited operation of 2" valves involved in maintaining con-tainment differential pressure. Certain infonnation including valve closure times was requested to assist the staff's confirmation of the dose calculation.

In the electrical area, BECo discussad proposed modifications to containment valve isolation circuitry intended to bring the Pilgrim design into confor-mance with staff criteria. With the following exceptions, no problems were identified during the initial electrical review:

(a) Criterion No. I was not met in all respects for 2" CAC valves used in containment differential pressure operation.

(b) Criterion No. 4 was not fulfilled since containment high radiation does not initiate isolation of containment.

(c) Criterion No. 6 was not met to the letter for certain groups of secondary containment isolation valves, although the intent was satisfied with the incorporation of keylock switches on the second level reset feature.

BECo agreed to provide justification for their position relative to (a) and (b) above. The staff tentatively agreed that the proposal for a key-lock switch on the second level reset function for the valve groups in item (c) above was acceptable. BECo was requested and agreed to provide the results of their analysis of the design of other safety actuation circuits employing a manual override feature in addition to the containment isolation circuits.

The staff indicated that our review schedule was consistent with the scheduled return to power operation of the Pilgrim unit after the spring 1980 refueling outage.

John N. Hannon, Project Manager Operating Reactors Branch #3 Division of Operating Reactors

Enclosures:

1.

Attendees of 12/11/79 meeting 2.

Agenda 3.

Electrical Review Criteria 4

Handout 1685 062

NRC MEETING WITH BOSTON EDISON ON PURGE VALVE (AND OTHER ESF's)

December 11, 1979 BOSTON EDIS0N COMPANY J. Fulton W. Deacon J. Coughlin EG&G/SR0 D. Hackett NRC E. Reeves J. Hannon R. Scholl J. Zudans F. Witt D. Verrelli 1685 063

AGENDA A.

Review background and the criteria being used in the evaluation B.

Discuss mechanical aspects and status

.C.

Discuss dose calculations, D.

Discuss Electrical Design 1.

Override Curcuits for ESF Systems 2.

Annunciation of override circuits 3.

Diversity of CI signals 4.

System level switches (manual) 5.

Equipment qualifications E.

Caucas F.

Summary of Electrical / Mechanical status for Pilgrim 1685 064

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ENCLOSURE 3 j

ELECTRICAL REVIE'e. CRITER:

The crimary inten cf tnis evaluation is to deter-ine if re fellowing NRC staff criteria are et for the safety sic, el-tc all ourge and ventilation isolation valves:

(1)

Criterion no.1 - The overriding

  • of one tyce of safety actuation signal (e.g., radiation)must not cause the blocking of any other type of safety actuation signal (e.g., pressure) to the isolation valves.

.( 2 )

Criterion no. 2 - Sufficient physical features (e.g., key lock switches) are orovided to facilitate adecuate actin #strative control s.

(3) Criterion no. 3 - The systen-level annunciation of the Overridden status is orovided for every safety system imoactec wner any override is active.

Incidental to this review, the following additional NRC sta" design criteria were used in the evaluation:

(i) Criterion no. 4 - Diverse signals should be provided to initiate isolation of the containment ventilation system.

Scecifically, containment high radiation, safety injection actuation, and containment high oressure should automatically initiate CVI.

Inis is 'n confomance with Branch Technical Position 6.4 of Section 6.2.4 of the Stancard Review Plan.

(2) Criterion no. 5 - The instrumentation and contml syste.s provided to initiate CVI should be designed and oualified as safety-grade equipment.

(3)

Criterion no. 5 - The overriding or resetting

  • of tne isolation actuation signal should not cause tne automatic recoening of any isolation / purge valve.

The folicwing definiticn is given for clarity of use in this evaluation:

Override:

The signal is still present, and it is blocked in order to oe-for a function contrary :: tne si nal, Ress::

-ne signal nas ccce and gone, and tne :#-:L'- is :eing cleared

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