ML20206E096

Mgt Meeting Rept 50-293/86-60 on 860519.Major Areas Discussed:Util Response to Confirmatory Action Ltr 86-10 Per Items Listed in Encl to NRC 860510 Request for Addl Info

ML20206E096
Person / Time
Site:	Pilgrim
Issue date:	05/30/1986
From:	Euhrmeister R, Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20206E088	List: ML20206E083 ML20206E096
References
50-293-86-60-MM, CAL-86-10, NUDOCS 8606230089
Download: ML20206E096 (3)

See also: IR 05000293/1986060

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Meeting No.86-060

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l Docket No. 50-293

License No. DPR-35

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Licensee: Boston Edison Company M/C Nuclear

800 Boylston Street

Boston, Massachusetts

Facility Name: Pilgrim Nuclear Power Station

Meeting At: USNRC, Region 1, King of Prussia, PA

Meeting condtrcted: May 19, 986

Prepared by: l ndt 27 87/ml l#85

Ro LT uhrmeister, Reactor Engineer datdj

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I Approved by: zc e k[tes:4 c N30/84

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k R. Strosnider, Chief ~date -

P ojects Section 18, DRP

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Meeting Summary: A management meeting was held at NRC Region I on May 19, 1986

to discuss the Boston Edison Company (BECo) response to Confirmatory Action

l Letter (CAL) 86-10. The primary items discussed were those listed in the en-

closure to the May 16, 1986 NRC request for additional information. A separate

i discussion was held with regard to the labor situation in progress at the plant.

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8606230089 B60610

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Details

1. Participants

1.1 Boston Edison Company (BECo)

A. L. Oxsen Vice President - Nuclear Operations

A. E. Pederson Plant Manager

R. N. Swanson Nuclear Engineering Manager

S. D. Hudson Operations Section Manager

J. A. Seery Technical Section Head

R. V. Fairbank Deputy Manager - Nuclear Engineering

J. F. Crowder Senior Compliance Engineer

T. Benedeci Senior Modification Engineer

S. S. Wollman Onsite Safety and Performance Group Leader

B. Tucker Senior Nuclear Engineer

1.2 U.S. Nuclear Regulatory Commission (NRC)

T. E. Murley Regional Administrator

R. W. Starostecki Director, Division of Reactor Projects (DRP)

S. D. Ebneter Director, Division of Reactor Safety (DRS) ^

W. V. Johnston Deputy Director, DRS

W. F. Kane Deputy Director, DRP

H. B. Kister Chief, Projects Branch 1, DRP

L. H. Bettenhausen Chief, Operations Branch, DRS

J. R. Strosnider Chief, Projects Section 1B, DRP

M. H. McBride Senior Resident Inspector

P. H. Leech Project Manager, NRR

L. T. Doerflein Project Engineer, Projects Section IB, DRP

A. M. Overton Field Public Affairs Officer

S. V. Pullani Fire Protection Engineer, DRS

R. L. Fuhrmeister Reactor Engineer, Projects Section IB, DRP

S. M. Peleschak Summer Technical Intern, DRP

2.0 Purpose

The management conference was held at the request of NRC Region I, to

discuss BECo's response to CAL 85-10, dated May 15, 1986 and the NRC

request for additional information, dated May 16, 1986 (attached).

3.0 Presentation and Discussion

NRC Region I Regional Administrator, Dr. T. E. Murley, opened the con-

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ference by asking the licensee for a brief overview of the labor situation

at Pilgrim and any thoughts on how this would affect the restart schedule.

Following an introduction of the participants, Mr. A. L. Oxsen, Vice

President of Nuclear Operations of BECo gave a short talk on the labor

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situations (Strikes by the Utility Workers Union of America and by Bechtel

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Boston Edison Company 2

laborers) and the anticipated impact on the plant schedule. Af ter re-

sponding to several questions, Mr. Oxsen introduced Mr. Pedersen, the

recently appointed plant manager. Mr. Pedersen gave a presentation on the

events of April 4 and 11-12, 1986 at Pilgrim, some background information,

and several of the resultant changes in procedures. A detailed discussion

was conducted which resulted in identifying a need for additional infor-

mation. BECo representatives agreed to provide a written response for

each item.

Following these, a discussion was held on the BECo strike contingency

plan. Topics discussed included personnel training, shift manning, ex-

pected duration of strike, extra personnel available, fire protection, and

security. Several questions remained unresolved at the end of the session.

4.0 Concluding Statements

The meeting ended with the following issues being identified as needing

written responses prior to an NRC decision on restart of the plant:

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What is the final resolution of the controlled leakoff for RHR?

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What is the final resolution of leakage through valves 1001-288

and 298.

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What type of training is being given to licensed SR0's, with

regard to actual manipulation of reactor controls who are stand-

.ing watch during the strike and who have not recently performed

such operations?

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What training is being conducted for personnel acting as

auxiliary operators during the strike?

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How will the operations personnel be trained on the reasons for,

and significance of, procedure changes resulting from the April 4,

11-12, 1986 event?

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