IR 05000333/1979010
| ML19210E413 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/09/1979 |
| From: | Feil R, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19210E411 | List: |
| References | |
| 50-333-79-10, NUDOCS 7912050010 | |
| Download: ML19210E413 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION /
ENFORCEMENT Regior i Report No.
79-10 Dockat No.
50-333 License No.
DP'l-59 Priority
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i cegory C
o Licensee:
ower Authority of the State of New York P.O. Box al Lycoming, New York 13093 Facility Name:
James A. Fitzoatrick Nuclear Power Plant Inspection at:
Scribu and New York City, New York Inspectior, conducted: July.30-Aug 3 and August 20-24, 1979 l
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Inspectors:
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R. Feil, Reactor Inspector date signed date signed cate signed Approved by:
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L. E. Tripp, Chief, Engineering Support Section No.1, RC&ES Branch Insoection Summary:
Inspection on July 30-August 3 and August 13-17, 1979 (Report No. 50-333/79-10)
Areas Inspected:
Routine unannounced inspection by a regional based inspector of the spent fuel rack mcdification including a review of procedures, audits & procurement specifications and of licensee action on previous inspection findings.
The inspection involved 48 inspector hours on site by one NRC regional based inspector.
Results:
No items of noncompliance were identified.
j d 014 (Rev. April 77)
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g g 182 0 5 0 M O Region I Form 12 3,
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DETAILS 1.
Persons Contacted W. Childs, Assistant to the Resident Manager M. Cosgrove, QA Site Engineer J. Hoddy, Reliability and Performance SLpervisor A. Klausman, Directcr, Quality Assurance
- J. Leonard, Resident Manager G. Nott, Assistant to the Superintendent of Power
- R. Pasternak,. Superintendent of Power J. Salek, QA Engineer W. Simpson, QA Project Engineer R. Swenson. Cognizant Project Engineer P. Swinburne, Assistant Plant Engineer The inspector conferred with other licensee and contractor personnel.
- denotes those present at exit interview.
2.
Licensae Action on Previous Inspection Items (Closed) Unresolved Item 50-333/78-25-01 Failure to Install Cables in Tray per Procedure The inspector examined cable pull tickets and the installation instructions for cables which wer; used during the construction of the facility by the A-E.
The " Installation Instructions for Cables" Revised May 2, 1972 paragraph IV A states in part "...it is permissable to install the cable in the raceway system to the terminal equipment location provided that the cable for the run to such terminal equipment is neatly coiled, tagged, securely fastened to the last raceway and protected against damage from other activities in such areas".
The cable pull tickets for the cables in question show that the cables were installed between December 1972 and July 1974 and that the cable run ends in a coil in accordance with the routing sequence.
(Closed) Unresolved Item 50-333/ 77-P.3-01.
Tcgqing Fire Fighting Equipment Following Inspection The inspector reviewed the Emergency Plan and Procedures, Revision 4, dated February 1979.
The procedure had been approved by the Plant Operations Review Committee on March 9, 1979.
The procedure provides for quarterly checking of the Emergency Survey Kits.
The inspector verified that Scott air packs and canister gas masks for Emergency Survey Kit #18 & #7 had been inspected within the last quarter and that the canister gas masks were checked to verify that the canister was within the shelf life expiration date.
Tags affiNed to the Scott air packs showed an inspection date of August 16, 1979.
1901015
(Closed) Unresolved Item 77-15-02, Containment Atmosphere Dilution System Modification The inspector verified that the preoperational test had been successfully completed for the containment atmosphere dilutution (CAD') system.
The Plant Operation Review Committee had reviewed arid accepted the results of the preoperational test.
The inspector verified that the modification had beca completed in accordance with 10 CFR 50.59 requirements.
The inspector verified that surveillance procedures had been prepared for the CAD system.
These procedures were:
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N1trogen System Pressure Sensor Functional Check.
F-ST-220 dated March 20, 1979.
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CAD System Operability Test.
F-ST-25 dated February 27, 1979.
Technical Specifications for the CAD system were submitted by PASNY.
NRR has not yet approved the submittal.
A pneumatic leak test was conducted on the CAD system and found acceptable on July 28, 1977.
The results of the test show that the system was leak tested at 330 PSIG for 35 minutes.
Test requirements stipulated a design pressure of 217 PSIG for 10 minutes.
No visible leaks were detected.
The inspector verified that the rust condition found in piping had beer removed.
The inspector reviewed Nonconformance and Disposition (N&D)
Report 991? dated July 27, 1977 which documented the rust and weld splatter in the stainless steel piping assemblies.
Tne disposition on the N&D shows that the rust was removed with Naval Jelly and the weld splatter removed with a wire stainless steel wheel.
The N&D was closed out on September 7, 1977.
3.
Tour of Facility The inspector toured the refueling floor and viewed the work in progress in the spent fuel pool.
Some items s2ch as sources and instrumentation chambers have been removed from the pool.
Clean up of sections of the pool is in progress.
No old spent fuel racks have been removed to date.
The new spent fuel racks are being held in storage at the manufacturer pending approval of the modification by NRR.
4.
Shent Fuel Rack Modification The licensee has submitted a proposed change to the spent fuel storage pool '.o increase the storage capacity of the pool.
The proposed modification consists of increasing the storage capacity from 760 fuel assemblies to 2,244 spent fuel assenblies by replacing the existing spent fuel racks with new high density fuel storage racks.
No changes will be made to the pool structure or the cooling systems.
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The new spent fuel storage racks are bolted anodized aluminum construction containing natural boron carbide B C (Boral) in an aluminum matrix
core clad with aluminum.
The Boral is sealed in two concentric square aluminum tubes.
The outer can of the tube is seal welded to the inner can to isolate the Boral from the spent fuel pool water.
The poison cans are placed alternately in egg crate fashion in the rack.
There will be 26 racks.
The racks contain cells in a matrix of 8X8, 8X10 and llX10.
Each spent fuel rack is free standing.
They are leveled by four stainless steel pads.
The stainless steel pads are separated from the aluminum racks by ABS plastic washers tc reduce galvanic corrosion.
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Procedures The inspector reviewed draft procedures covering preparation and receipt inspection, spent fuel rack and bracing ripout and removal, crane operation and rack installation.
The review consisted of assuring that the procedures:
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Would be reviewed and approved in accordance with the Technical Specifications, the modification application,10 CFR 50.59 and the licensees administrative controls.
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Were in conformance with the requirements of ANSI N 18.7-1972 " Administrative Controls for Nuclear Power Plants.
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Checklists, where applicable, were compatible with the step instructions in the procedures.
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Appropriate acceptance criteria (Technical Specification limitations and modification proposal criteria) were included in the procedures.
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Provided for temporary changes to be made in confomance with the Technical Specifications.
5.
Licensee Audits of Vendor The inspector reviewed audit reports of 8 audits conducted by Stone and Webster (S&W), subcontractor to the Power Authority of the State of New York (PASNY) for the spent fuel rack modification, of Programmed and Remote Systems Corporation (par), fabricator of the new high density spent fuel racks.
The QA program for S&W provides for control of nonconformances and disposition of the ncnconfonr.ar.ces. Documents reviewed by the inspector show that S&W is following up on nonconformances and deviations from the design and fabrication criteria by the vendor.
In addition the inspector reviewed audit reports of 5 audits conducted by PASNY.
Problems are identified in the audit report and corrective action is verified on a subsequent audit and documented in that report.
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6.
Exit Interview The inspector met with licensee representatives (danoted in paragraph 1)
at the conclusion of the inspection on August 2, 1979. The inspector sumarized the scope and findings of the inspection.
The licensee representatives acknowledged the inspector's coments.
After the exit interview the inspector telephoned the licensee representative and summarized his findings regarding the inspection of audits at the corporate headquarters conducted on August 23 and 24, 1977.
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