IR 05000293/1978029
| ML19281A403 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 01/16/1979 |
| From: | Feil R, Mcgaughy R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19281A396 | List: |
| References | |
| 50-293-78-29, NUDOCS 7903130167 | |
| Download: ML19281A403 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-293/78-29 Docket No. 50-293 License No. DPR-35 Priority
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Category C
Licensee:
Boston Edison Comoany 800 Boylston Street Boston, Massachusetts Facility Name:
Pilgrim Nuclear Power Station Inspection at:
Boston and Plymouth, Massachusetts Inspection conducted:
December 18-21, 1978 Inspectors:
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k H. A. Fell, Reactor inspector date signed date signed
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f date signed
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j Approved by:
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R. W. McGaugtjy, Chief, Construction Project Section, RCaES Branch
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Inspection Summary:
Inspection on December 18-21,1978 (Report No. 50-293/78-29)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector of the spent fuel rack modification including inspection, installation and procedural control. The inspection involved 27 inspector hcurs onsite by one NRC inspector.
Results:
No items of noncompliance were identified.
790313016'l Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted Mr. J. Aboltine, Senior Reactor Engineer Mr. J. Ashkar, Project Engineer
- Mr. E. Cobb, Acting Station Manager
- Mr. M. Hensch, Chief Radiological Engineer Mr. J. Jeffries, Mechanical Engineer
- Mr. J. Keyes, Licensing Engineer
- Mr. C. Mathis, Senior Plant Engineer
- Mr. V. Stagliola, Senior Waste Management Engineer Mr. R. Trudeau, Radiation Protection Manager The inspector interviewed other licensee as;d contractor personnel.
- denotes those present at exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (50-293/78-12-03):
No material certificates for ABS plastic washers.
The vendor has forwarded to the licensee a certificate of conformance for the plastic washers.
(Closed) Unresolved Item (50-293/78-12-04):
No study verifying compatibility of ABS plastic washer with fuel pool environment.
Documentation provided to the inspector shows that compatibility was checked by Yankee Atomic Electric Company and the vendor, Program and Remote Systems Corporation.
NRR, during the licensing review for spent fuel racks.#or Vermont Yankee NPS, considered the use of ABS plastic in the fuel pool environment and concluded that the pool water would not have any significant effect on the ABS plastic.
In addition, the Atomic Safety and Licensing Board, during hearings for similar racks at Vermont Yankee NPS, questioned the use of ABS plastic in their application and subsequently approved the application with the use of ABS plastic washer.
3.
Facility Tour The inspector observed the work which has been done on the installation of the spent fuel racks.
Half of the old spent fuel racks have been removed and eight of the twenty-seven new spent fuel rack modules have been installed. These are presently housing spent fuel.
The spent fuel pool water was clear and visibility was good.
Water level is being monitored by shift personnel who verify that the water level is at least within 5' cf the refueling floor.
No items of noncompliance were identified.
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Spent Fuel Storage Racks a.
Inspection The licensee has committed to an in situ test oroaram for insnactinn
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the new spent fuel racks.
Verification of adequate boral sheets in the fuel racks is being accomplished by a random sampling program. A neutron source and neutron detector is being utilized
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at multiple levels in selected cavities to determine the presence of boral. A sample size of 106 was selected for use in the inspec-tion.
The individual cavities selected for inspection were chosen by a random number system.
The selection of the individual cavities by a random number system produced at least one sample from each module except module 12.
Because of this disparity in the simple random sampling method, in that every module did not have a cavity tested, the licensee has agreed to utilize a systematic random sampling method measuring 5% of the cavities in each module.
Three cavities did not have boral in one side of the cavity.
These were among cavities which were intentionally absent of boral and are on the periphery of the module.
b.
Installation After installation of the fuel racks, dimensional checks were made on 10% of the cavities in each module.
These tests were made uith a single blade guide or channe.-
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The rack position was verified to be within 1/8" of specified dimensions.
Racks on the outer periphery were placed in direct contact with adjacent racks.
Interlocking buttons on each rack are used to laterally locate adjacent racks.
c.
Procedural Control Procedures for the removal of the old spent fuel racks and the installation of new fuel racks were reviewed.
The procedures had been reviewed by the On Site Review Committee.
Minor dis-crepancies were noted in the procedures, but did not affect any safety aspects of the operation.
The procedures provided for precautionary measures regarding movement of any racks or fuel over the new spent fuel racks.
The licensee plans to follow the Vermont Yankee NPS program regarding the checking for swelling in the cavity walls.
In the event that Vermont Yankee develops a problem in this area, the licensee will then take appropriate action to check the racks for swelling or any other degradation.
No items of noncompliance were identified.
5.
Exit Interview The inspector met with the licensee representatives (denoted in Parearaph 1) at the conclusion of the inspection on December 21, 1978 The inspector summarized the scope and findings of the insp';ction.
The licensee representatives acknowledged the inspector's findings.