ML20214K318
| ML20214K318 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/11/1986 |
| From: | Kister H, Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20214K310 | List: |
| References | |
| 50-293-86-14, NUDOCS 8608210033 | |
| Download: ML20214K318 (1) | |
See also: IR 05000293/1986014
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U.S. NUCLEAR REGULATORY COMMISSION
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REGION I~
Docket / Report No. 50-293/86-14
License: DPR-35
Licensee:
' Boston Edison Company
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800 Boylston Street
Boston, Massachusetts 02199
Facility:
Pilgrim Nuclear Power Station
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Location:
Plymouth, Massachusetts
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Dates:
April 19, 1986 - June 2, 1986
Inspectors:
M. McBride, Senior Resident Inspector
J. Lyash, Resident Inspector
Reviewed by:
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J. Strosn'ider, Chief, Reactor Projects
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Approved by:
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H'. Ki(tgr, Chief, Reactor Projects
Branch No. 1
Summary: April 19, 1986 - June 2, 1986 (Inspection Report 50-293/86-14)
A_reas Inspected:
Routine resident inspection of the control room, accessible
parts of plant structures, plant operations, radiation protection, physical
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. security, plant operating records, plant events, maintenance, surveillance,
and reports to the NRC. The inspectors also reviewed actions taken to resolve
concerns documented in Confirmatory Action Letter 86-10 and licensee performance
under strike conditions. A total of 224.5 inspection hours were expended during
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this inspection period.
Results: Two violations were identified concerning failure to take prompt
corrective action in response to quality assurance findings (Section 7), and
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failure to control calibration of measuring and test equipment (Section 4). Of
particular concern is the licensee's failure to take timely corrective action
in response to safety significant problems identified by the quality assurance
staff. This weakness appears to be programmatic in nature. Also of concern
is the licensee philosophy regarding performance of safety evaluations. The
failure to complete corrective actions for a previous NRC violation is
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discussed in Section 2. The lack of a documented conversion factor for radia-
tion survey equipment is discussed in Section 6. Problems with independent
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verification during the replacement of the reactor mode switch are discussed in
Section 8.
Actions addressed in response to CAL 86-10 were generally well
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planned and executed.
Licensee response to labor action was thorough.
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