IR 05000293/1980013
| ML19310A481 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 04/18/1980 |
| From: | Kehoe D, Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19310A480 | List: |
| References | |
| 50-293-80-13, NUDOCS 8006170805 | |
| Download: ML19310A481 (4) | |
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U. S. NUCLEAR REGULATORY COMISSION
.mC OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report No.
50-293/80-13 Docket No.
50-293
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License No.
DPR-35 Priority Category C
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Licensee:
Boston Edison Company M/C Nuclear 800 Boylston Street Boston, Massachusetts 02199 Facility Name:
Pilgrim Nuclear Power Station Inspection At:
Plymouth, Massachusetts Inspection Conducted:
March 31-April 1, 1980 Inspectors:
di 4-17-FC David V. Kehoe, Reactor Inspector date date date Approved by:
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f'd T. T. Martin, Chief RPS #3, Ra&NS Branch dath
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Inspection Summary:
Inspection on March 31-April 1, 1980 (Report No. 50-293/80-13)
Areas Inspected:
Routine unannounced inspection by one regional base inspector of refueling activities.
Facility tours were conducted.
The inspection involved 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> onsite by one NRC regional based inspector.
Results:
No items of noncompliance were identified.
8006170 Y Region I Form 167 (August 1979)
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a.
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DETAILS 1.
Persons Contacted
- E. Cobb, Chief Operating Engineer
- C. Mathis, Methods, Training,and Compliance Group Leader
- P. McGuire, Station Manager K. Taylor, Watch Engineer The inspector also interviewed other licensee employees during the inspec-tion, including operations, health physics and staff personnel.
- Denotes those present at the exit interview.
2.
Refueling Activities a.
References 8.M.1-1, IRM Functional / Calibration, Revision 5
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8.M.1-3.1, APRM Set Down Functional, Revision 10
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8.M.1-21, RPS Channel Test Switch, Revision 2
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8.M.1-23, Reactor Manual Scram, Revision 2
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8.9.1, Manually Start and Load Each Diesel Once Per Month,
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Revision 3 8.7.3, Secondary Containment Leak Rate Test, Revision 7
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8.10.1, Refueling Platform Interlocks Weekly Functional Test,
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Revision 1 8.10.2, Refueling Platform and Reactor Manual Control System,
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Revision 3 8.10.5, Refueling Platform Main Mast Interlock Functional Test,
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Revision 3 Temporary Procedure 80-35, Core Spray Operability Check While
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A111gned to the CST b.
The inspector reviewed the above procedures to verify that surveil-lance testing involving Technical Specification requirements, refuel-ing involving Technical Specification requirements, refueling inter-locks, refueling bridge operation, and communications were properly addressed.
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No items of noncompliance were identified, however, one unresolved item is discussed below.
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During the course of the inspection the inspector monitored the per-formance of procedure 8.10.5.
At two points during the course of the procedure temporary changes were required to make the procedure work.
The inspe,ctor reviewed the procedure and agreed that the changes were necessary and the procedure could not be completed as written.
The inspector questioned the plant staff as to how this procedure was completed one week earlier as a prerequisite to refueling without the required changes.
The licensee acknowledged the inspector's comment and stated that this item would require review before responding.
This item is unresolved pending licensee review of the inspector's request.
(50-293/80-13-01)
c.
The inspector verified by direct observation of refueling activities, including actual fuel movement,that the following requirements were being complied with.
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Core monitoring during refueling operations..
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Containment integrity during refueling is in accordance with
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Technical 5pecifications.
Fuel movement and accountability is in accordance with established
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procedures.
Refuel floor housekeeping is acceptable.
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Refuel floor and control room licensed operator manning is in
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accordance with Technical Specification requirements.
Vessel water level is in accordance with Technical Specification
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requirements.
Mode switch. positioned in accordance with Technical Specification
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requirements.
Control blade checks are in accordance with established procedures.
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The refueling floor supervisor holds an SRO license and is
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directly supervising fuel movement that could effect reactivity.
When ac+1vities which could effect reactivity era being conducted
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on the refuel floor the licensed operator in the control room is in direct communications with the fuel handling crew.
No items of noncompliance were identified.
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3.
Facility Tours The inspector conducted tours of the accessible areas listed belew at various times to observe the status of plant systems and conditions and to observe activities in progress.
The plant areas inspected included the Battery Rooms, 4160V Room, Switchyard, Control Room, Secondary Control Station, Auxiliary Bay, Refueling Floor and accessible areas of the Reactor Building.
The following were among the items observed:
Radiation controls properly established
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Housekeeping, including the attention to the elimination of fire
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hazards No significant fluid leaks
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Status of pre-selected valves
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Status of Battery Room Modifications
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Inspection tags on fire extinguishers, no obstruction of fire hoses
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Extent of insulator arcing due to salt contamination, etc.
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No items of noncompliance were identified.
4.
Unresolved Items Unresolved items are items about which more information is needed to deter-mine if the item is acceptable, an item of noncompliance or a deviation.
An unresolved item is discussed in paragraph 2.b.
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5.
Exit Interview The inspector met with the licensee representatives at the conclusion of the inspection on April 1, 1980.
At this meeting the inspector identified the scope and findings of this inspection.
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