ML19330A416
| ML19330A416 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/16/1980 |
| From: | Ebneter S, Finkel A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19330A415 | List: |
| References | |
| 50-333-80-10, IEB-79-01B, IEB-79-1B, NUDOCS 8007280080 | |
| Download: ML19330A416 (3) | |
See also: IR 05000333/1980010
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
Region I
Report No.
80-10
Docket No.
50-333
License No. DPR-59
Priority
Category
C
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Licensee:
Power Authority of the State of New York
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James A. FitzPatrick Nuclear Power Plant
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P.O. Box 41
Lycomina. New York 13093
Facility Name:
James A. FitzPatrick Nuclear Power Plant
Inspection at:
Lycoming, New York 13093
Inspection conducted:
May 14, 1980
Inspectors:
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A. E. Finkel, Refactor Inspector
date' signed
date signed
date signed
Approved by: ,$
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S. D.'Ebneter, Chief, Engineering Support
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Section #2. RC&ES Branch
Inspection Summary:
Inspection on May 14, 1980 (Report No. 50-333/80-10)
Area Inspected: Routine, announced inspection by . regional inspector of licensee
RHR system components as identified in the May 1980 document entitled " Response
to NRC IE Bulletin 79-01B for James A. FitzPatrick Nuclear Power Plant". The
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inspection involved 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> on site by one regional based inspector.
Results:
No items of noncompliance were identified.
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Region I Form 12
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(Rev. April 77)
8.0872 80
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DETAILS
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Persons Contacted
Power Authority of the State of New York
- V. Childs, Assistant to the Resident Manager
R. Pasternak, Resident Manager
- Mr. V. Childs represented Mr. Pasternak at the exit interivew.
2.
Residual Heat Removal System (RHR)
The inspector verified that the RHR system inside containment which comprised
the following components, Motor Operated Valves, Junction Boxes, Cables
and Penetrations, as listed in the May 1980 response to IE Bulletin 79-01B,
were in accordance with the documentation at the site.
The inspector
reviewed the following site documentation.
Limitorque Wiring Diagram, No. 15-476-1192-3
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Wiring Diagram Electrical Penetration X-100B, JB0 and I 575/120V
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Power, No. 11825-FE-36H-5
System 23 Element Diagrams - 600 Volt Circuits - MOV, No. 11825-ESK-
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6MAV
600 Volt Wiring Diagram 23 MOV-015, System 23. No.11825-SE-9LL
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Wiring Diagram Control and Indication Penetration Junction Box X-111B,
JBO, No. 11825-FE-36T-7
Wiring Diagram Control and Indication Penetration Junction Box X-1118,
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JBI, No. 11825-FE-36U-T
600 Volt Wiring Diagram 10 MOV-108 System 10, No. 11825-SE-96Q
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Conduit Drawing, No. 11825-FE-46AA
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General Notes and References, No. 11825-FE-36R
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No items of noncompliance or deviation were identified.
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2.
IE Bulletin 79-01B 90 Day Response
The inspector reviewed the " Response to U.S. Nuclear Regulatory Commission
IE Bulletin 79-01B for James A. FitzPatrick Nuclear Power Plant", dated May
1980. Areas where clarification of the report is required was identified
to the licensee during the exit interview.
The licensee has stated in a letter dated May 23, 1980, No. JAFP-80-436,
that a revision to the report will be made answering the question identified
in NRC letter to the licensee dated May 23, 1980.
The revised 90 day report will be reviewed by tha Region I Principal Reviewer.
A data verification inspection is scheduled during the month of September,
1980.
No items of noncompliance or deviation were identified.
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Exit Interview
At the conclusion of the inspection on May 14, 1980 a meeting was held at
the James A. FitzPatrick Nuclear Power Plant site with a representative of
the licensee. Attendees at this meeting included personnel whose names are
indicated by notation (*) in Paragraph 1.
The inspector summarized the
results of the inspection as described in this report.
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