IR 05000293/1980001
| ML19309B592 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/06/1980 |
| From: | Baunack W, Kehoe D, Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19309B591 | List: |
| References | |
| 50-293-80-01, 50-293-80-1, NUDOCS 8004040411 | |
| Download: ML19309B592 (8) | |
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O u s auc'e^a acco'^toar co""tssto" 0FF:CE OF INSPECTION AND ENFORCEMENT Region I 0-293/8401 Report No.
Docket No.
i 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, Unit 1 Inspection at: Plymouth, Massachusetts Inspection conducted:
January 8-11, 1980 Inspectors:
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2 RO&NS Branch 2/f[fo
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, Reactor Inspec or Approved by:
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T. bMartN Chief, Rdtor Projects Section #3, RO&NS Branch
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Inspection Summary:
Inspection on January 8-11,1980(ReportNo. 50-293/80-01)
Areas Inspected:
Routine, unannounced inspection by regional based inspectors of administrative controls for safety related maintenance; review of safety related maintenance activities; technician qualifications; organization and administration; preparation for refueling; new fuel receipt and inspection; witnessing of new fuel inspection and movement; jumper log review; and facility tours.
This inspection involved 88.5 inspector-hours on site by three NRC regional based inspectors.
Resul ts:
No items of noncompliance were identified during the conduct of this inspection.
Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted J. A. Abolton, Reactor Engineer J. Alukonis, Watch Engineer C. Anderson, Watch Engineer E. Cobb, Chief Operating Engineer M. Hensch, Chief Radiological Engineer E. Kearney, Operation and Construction Quality Control Group Leader R. Machon, Assistant Station Manager
- C. Mathis, Methods, Training and Compliance Group Leader
- P. McGuire, Station Manager R. Silva, Maintenance Engineer J. Sullivan, Quality Control Supervisor
- G. Whitney, Plant Engineer The inspectors also interviewed other licensee employees including members of tP technical and engineering staff and reactor operators.
- Denotes those present at the exit interview.
2.
Administrative Cor.trols for Safety Related Maintenance The inspector reviewed the licensee's program for administrative control of safety related maintenance activities, as described in the following administrative procedures-
Procedure 1.5.3, Revision 11, September 14, 1979, Maintenance
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Requests.
Procedure 1.3.4, Revision 20, May 22,1979, Procedures.
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Procedure 1.5.7, Revision 11, November 28, 1979, Unplanned
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Maintenance.
l Procedure 1.4.5, Revision 8, December 27, 1978, PNPS Tagging
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l Procedur.
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Procedure 1.5.5, Revision 10, October 10, 1979, Cutting and
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Welding.
Boston Edison Quality Assurance Manual, Volume II, Operation
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of Nuclear Power Plants, selected sections in the area of safety related maintenance.
This review was conducted as a familiarization with the licensee's procedural requirements in this area and as an audit with respect to Technical Specification, Section 6, Administra.tive Controls, Regulatory Guide 1.33, Quality Assurance Program Requirements, and ANSI N18.7, Administrative Controls for Nuclear Power Plants.
Based on this review, no items of noncompliance were identified.
3.
Review of Safety Related Maintenance Activities a.
The inspectors reviewed safety related maintenance conducted by the licensee on a sampling basis to verify that:
Limiting Conditions for operation were met while equipment
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was out of service.
Required administrative approvals were obtained to perform
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the work'.
An approved procedure was used where required.
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Required inspections were performed.
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QA/QC records were available to substantiate quality of
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work and parts used.
A Reportable Occurrence Report, if required, by Technical
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Specifications, was submitted based on review of circum-stances associated with the maintenance activity.
b.
The documentation associated with the following safety related maintenance activities was reviewed:
Maintenance Request (MR) 2774, Snubber on HPCI exhaust
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line.
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MR 2753, itaage HEPA filters on SGTS.
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MR 2704, Inner truck door lock inspection.
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MR 2592, Diesel Generator failed to shutdown.
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MR 2522, "C" SSW Pump high vibration.
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MR 2037, RHR discharge pressure gauge.
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MR 2036, Apply fire retardant coating to cable trays.
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MR 2085, RHR valve M0-1001-36B.
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MR 1697, "D" main steam RV.
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MR 1752, Torus level recorder.
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MR 1828, HPCI Snubber S-23-3-37.
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MR 2690, Rx truck lock.
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c.
No items of noncompliance were identified.
4.
Technician Qualifications The inspectors discussed the qualifications of selected individuals having responsibility for maintenance of safety related systems and components to verify that their experience level is in accordance with the guidelines set forth in ANSI N18.1, Selection and Training of Nuclear Power Plant personnel.
No unacceptable items were identified.
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5.
Organization and Administration The inspectors reviewed licensee organization charts and interviewed licensee personnel to ascertain whether the onsite organization and administration are in conformance with Technical Specification requirements. The following areas were examined.
Changes to the organizational structure have been reported to
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the NRC as required by the Technical Specifications.
The onsite organization is as described in the Technical
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Specifications.
Persons assigned to new or different positions since the last
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organization and administration inspection satisfy qualification requirements.
Authorities and responsibilities of personnel.
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Results of the above review show:
A change to the organization has been reported (LER 79-046/03L
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-0).
An apparent item of noncompliance related to organizational change reporting is addressed in IE Inspection Report 50-293/79-20.
The current onsite organization is as described in a letter to
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the commission dated September 27, 1979.
Personnel meet the qualification requirements for their assigned
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authorities and responsibilities.
No items of noncompliance were identified.
6.
Preparation for Refueling a.
Procedures i
The inspectors reviewed the following procedures to verify that approved procedures are available for fuel handling operations:
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Procedure 4.1, Revision 8, Receiving and Handling Un-
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irradiated Fuel Assemblies.
Procedure 4.2, Revision 14, Inspection and Channeling of
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Nuclear Fuel.
Procedure 4.3, Revision 14, Fuel Handling.
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During the inspectors review of station procedure 4.2 Inspection and Channeling of Nuclear Fuel, Revision 14, it was noted that none of the temporary measures taken due to the recent fuel handling errors (inadvertant lift of a spent fuel assembly ano dropped new un-irradiated fuel assembly) had been incorporated into the procedure.
The licensee stated that the temporary measures taken at the time were not intended to be permanent measures. Subsequent to the refueling outage an evaluation of new fuel handling procedures would be performed and the procedure revised as appropriate by September 1,1980.
The licensee further stated that the predominant proposal at this time is to move the new fuel from the inspection stand to the spent fuel preparation stand using the five ton overhead crane and to transfer this fuel from the preparation stand to the normal storage location within the spent fuel pool using the fuel grapple off the refueling bridge.
This item is unresolved (50-293/80-01).
b.
New Fuel Receipt and Inspection The inspectors performed the following examinations to verify that new fuel was received and inspected in accordance with approved procedures. The following documents were reviewed:
Material Receipt Inspection Report 80-006,184 8 x 8 Fuel
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Bundles.
Nuclear Material Transaction Reports.
Shipments 1-6 (184
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assemblies).
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Radioactive Materials Packaging Record for Shipment No.
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The inspector also witnessed the inspection, channeling and movement of new unirradiated fuel assemblies during inspection 50-293/79-22, perfomed December 13-14, 1979.
The following activities were witnessed:
Inspection of four (4) new fuel assemblies.
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Channeling of two (2) new fuel assemblies.
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Movement of two (2) new fuel assemblies from crate to new
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fuel inspection stand then to spent fuel pool pre-fueling storage location.
No items of noncompliance were identified.
7.
Jumper Log Review The inspectors reviewed the plant jumper log and associated procedure for compliance with 10 CFR 50.59 requirements.
The inspector noted that each jumper or lifted lead was to be evaluated by the Watch Engineer (SR0) to determine if it affected a technical specification related system.
If it did, the jumper / lifted lead was required to be approved by the Onsite Review Committee (ORC).
Further all active lifted leads / jumpers are reviewed periodically by the Chief
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Electrical Engineer.
The inspector verified that the above was being accomplished by perforMng a review of all active entries in the jumper log. The inspector detemined that the above controls satisfied the intent of 10 CFR 50.59.
No items of noncompliance were identified.
8.
Facility Tours On several occasions during the inspection, tours of the facility were conducted of the Turbine Building, Reactor Building, Refueling i
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Floor, Diesel Generator Rooms, Screen House, Relay and Cable Spreading Rooms, and portions of the Security Fence. During the tours, the inspectors discussed plant operations and observed housekeeping, radiation control measures, monitoring instrumentation, and controls for Technical Specification compliance.
In addition, the inspectors observed control room operations on both day and evening shifts for
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control room manning, shift turnovers, and facility operation in
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accordance with administrative and Technical Specification requirements.
No items of noncompliance were identified.
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Unresolved Items Unresolved items are findings about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. An unresolved item identified during this inspection is identified in Paragraph 6.a.
10.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on January 11, 1980. The purpose, scope, and findings of the inspection were summarized.
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