ML20206E096
| 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: |
| 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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Docket No.
50-293
License No.
Licensee:
Boston Edison Company M/C Nuclear
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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:
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Ro LT uhrmeister, Reactor Engineer
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Approved by:
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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
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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
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discussion was held with regard to the labor situation in progress at the plant.
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8606230089 B60610
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ADOCK 05000293
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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
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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
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NRC Region I Regional Administrator, Dr. T.
E. Murley, opened the con-
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
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
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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:
--
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?
--
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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