IR 05000333/1981017
| ML20031C084 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/10/1981 |
| From: | Ebneter S, Finkel A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20031C081 | List: |
| References | |
| 50-333-81-17, NUDOCS 8110060528 | |
| Download: ML20031C084 (5) | |
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i U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-333/81-17 Docket No. 50-333
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License No. DPR-59 Priority Category C
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Licensee:
Power Authority of the State of New York P.O. Box 41 Lycoming2 New York 13093 Facility Name:
James A. FitzPatrick Nucle., Power Plant Inspection At:
Lycoming, New York Inspection Conducted:
August 17-21, 1981 k
Inspectors:
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A.E. Finkel, Reactor Inspector date signed Approved By:
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S.J. Ebnetbr, Chief, Plant System Section dite' signed DETI Inspection Summary:
Inspection on August 17-21, 1981 (Report No. 50-333/81-17)
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Areas Inspected:
Routine, uncnnounced inspection of Design Changes / Mod-ifications, and previously identified items.
The inspection involved 30 inspector-hours onsite by one NRC region-based inspector.
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Results: No items of noncompliance were identified.
Region I Form 12
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(Rev. April 77)
8110060528 8109147 PDR-ADOCK 05000333 G
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DETAILS
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1.
Persons Contacted
- B. Baker, Superintendent of Power
- P. Bayne, Senicr Vice President, Nuclear Generation M. Cosgrove, Quality Assurance
- W. Fernandez, Technical Services Superintendent
- R. Pasternak, Resident Manager E. Zufelt, Technical Services
- S. Zulla, Manager, Nuclear Technical Services NRC Personnel
- L.
Doerflein, Resident Inspector The inspector also contacted other licensee employees during the course of the inspection including engineering, maintenance, office, operating plant technical support, quality assurance and stores personnel.
- denotes those present at the exit interview.
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Licensee, Action on Previous Inspection Items
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(0 pen) Noncompliance (50-333/81-04-Ci): Drawings do not reflect the. ;
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as-built plant ccnfiguration. The drawings were corrected and the f
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packages forwardet' to central file. This noncompliance remains open f
pending acceptance of li:ensee's long term corrective action.
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(0 pen) Noncompliance (50-333/81-04-02): Modification packages not complete. The design modification packages were completed and for-warded to central file.
This noncompliance remains open pending acceptance of licensee's long term corrective action.
3.
Design Changes /Modificattorg a.
References WACP 10.1.5, Control and Identification of Purchased Materials
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and Services, Revision 4,
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WACP 10.1.6, Control of Modification, Revis?on 5,
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WACP 10.1,8, Automated Records Management System, Revision
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0, QAP 10.1, Inspection of Quality Related Activities, Revision
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N/A, QAP 11.1, Test Control, Revision N/A,
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Drasing 11825-FM-39A, Figure 9.11-1 Sheets 1 and 2, " Breathing
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Instrument and 3ervice Air, General Electric E-LAB Technical Services Report No. EH-79-
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80, " Analysis of Radiation Protection Breathing Air System."
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b.
Review Modification documentation packages were reviewed on a sampling basis to verify that the following requirements have been implemented
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as applicable.
10 CFR 50.59 rev1ews were performed and documented.
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Design changes / modifications were reviewed in accordance
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with the requirements of tha Technical Specifications and
the QA Program.
Design changes / modifications were accomplished in accordance
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with written procedures.
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. Acceptance testing was acccmplished and deemed satisfactory.
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Procedures and drawings required to be changed or generated as a result of a :iesign change / modification were updated or
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generated (sample).
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Tiie design change / modification package has been transmitted to the records retrieval department for incorporation as a
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plant record.
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They were:
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.-- 75-262, Add Keep Full Instrumentation to Core Spray System,
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76-90, CAD System Installation, 78-30, Drywell Equipment Drain Sump,
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18-45, CAD System,
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78-48, Target Rock Safety Felief Valve Topworks Changeout,
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and, 79-17, Target Rock Relief Valve Change (Topworks).
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These work packages have been completed and are part of the 403 closed items discussed in paragraph c. below.
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c.
Modification Review Status The status of the modification packages reviewed and closecut by the licensee is as follows:
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690 Modification packages have been identified since 1974.
392 modification packages have been closed and 11 are in process of being closed for a total of 403. The remaining
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287 identitied modification packaces are being scheduled for work tz the licensee.
The licensee responded to the finding identified in IE Inspection
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Report 50-333/81-04 with letter dated May 29, 1981 Code No. (JAFP 81-0551). The letter states that "...by September i981 a plan will be provided to the NRC that will provide information with respect to the schedule for implementation of the plan." The inspector discussed this response with licensea management.
It appears that the proposed answer.will address the specific
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problem identified in the noncompliance 50-333/81-04-02 and not the systematic problem. The inspector communicated his concerns to the licensee during the inspection and at the exit. The licensee acknowledged the inspector's statements.
No items of noncompliance were identified.
s 4;
Reactor Protection System Cable Damage On August 4,1981, the licensee was removing a flexible cable conduit from wall penetration IWC078U17. During the process of removing the flexible conduit, sharp edges of the flexible conduit cut into cable IRPSCUC156 causing it to short. The licensee conducted a normal reactor shutdown in order to repair the damaged cable.
Approximately 96 feet of #10 Two conductarcable was used to mak< a splice in the IRPSCUC156 cable. One conductor of the two conductor splice cable was cut back and sealed leaving one of the conductors for making the splice connection. The cable was from a 1972 qualified cable order from the Okonite Company.
Cable / coil No.76-263 was the
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cable reel from which the splice cable was taken. The re-installation, splicing and testino of the splice cable was verified by quality control on August 7, 1981.
During the re-installation of.the flexible
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cable conduit IWC078U17, the licensee cleared and broke the sharp edge of the flexible conduit as defined in Paragraph 4.2 of MP 57.9.
The IRPSCUC156 -cable is scheduled to be replaced during the October 1981 outage.
An inspection of other flexible conduits in the plant by the inspector noted that many of the installations did not have end seals on the end of the flexible conduits. The licensee noted this item and plans to add additional caution notes to paragraph 7.1.3.2 of MP 57.5.
This item is unresolved.
(50-333/81-17-01)
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Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable, items of noncompliance or deviations. Unresolved items are discussed in paragraph 4.
Exit Interview
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A meeting was held with licensee management representatives (identified in Paragraph 1) on August 20, 1981. The purpose, scope and findings of this inspection were preser.ted and discussed. The licensee acknowledged the inspector's findings.
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