ML19210E475
| ML19210E475 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/18/1979 |
| From: | Leonard J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML19210E464 | List: |
| References | |
| JAFP-79-490, NUDOCS 7912050084 | |
| Download: ML19210E475 (2) | |
Text
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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FsTzPATRICK NUCLEAR POWER PLANT S
JOHN D. LEONARD, JR.
P.O. BOX 41 Resident Manager Lycoming. New York 13093 ais.aEase September 18, 1979 JAFP 79-490 Boyce H. Grier, Director United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA.
19406
SUBJECT:
DOCKET NO. 50-333 NRC I&E INSPECTION NO. 79-07
Dear Mr. Grier:
With reference to the inspection conducted by Mr. R. Zimmerman of your office on May 29-June 1,1979, at the James A. FitzPatrick Nuclear Power Plant, and in accordance with the provisions of Section 2.201 of Part II of Title 10 of the Code of Federal Regulations, we are submitting our response to Appendix A, Notice of Violation trans-mitted by your letter dated August 24,1Y79 as receTved by the under-signed on August 29, 1979.
APPENDIX A NOTICE OF VIOLATION Based on the results of an NRC inspection conducted May 29 through June 1,1979, it appears that one of your activities was not conducted in full compliance with conditions of your NRC Facility License No. DPR-59 as indicated below. This item has been categorized as a Deficiency.
Technical Specification 6.8.A states, in part, " Written Procedures...
shall be established, implemented, and maintained that meet or exceed the requirements and recommendations of Section 5, Facility Administrative Policies and Procedures of ANSI 18.7-1972..."
ANSI 18.7-1972, Section 5.3.6, Instrument Calibration and Test Procedures, states, in part, "The procedures shall have provisions for assuring measurement accuracies adequate to keep safety para-meters within operational and safety limits."
1561 244 79120 50 Dhh
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Boyce H. Grier, Director September 18, 1979 United States Nuclear Regulatory Commission JAFP 79-490
SUBJECT:
NRC I&E INSEECTION 79-07 Page Contrary to the above, surveillance calibration F-ISP-4-5, Drywell Suppression Chamber Differential Pressure, written in part to satisfy Technical Specification 3.2.c and performed May 2, 1979, did not contain acceptance criteria for assuring measurement accuracy for drywell pressure indicator PI-102B.
Further, the output data recorded fe: PI-102B did not correspond to the input signals from pressure transmitter PT-102B as would be expected.
This was found to be due to an incompatibility in operating ranges between PT-102B (10-20 PSIA) and PI-102B (0-20 PSIA).
The above calibration surveillance test had received secondary level review and approval with no discrepancies noted.
RESPONSE TO NOTICE OF VIOLATION The James A. FitzPatrick Nuclear Power Plant staff acknowledges the deficiency noted above and has reviewed the deficiency and this Response this date at PORC Meeting 79-056. The acknowledgement of this deficiency is further indicated by the submittal of Licensee Event Report No.79-034 on June 21, 1979.
As noted in the reference Licensee Event Report, Instrument Surveillance Procedure F-ISP-4.5 was revised to correct the discrepancy in the indicator scale for Instrument 27-PI-102B.
In addition, the temporary scale which was placed on the indicator during Inspection 79-07 has been replaced by a permanent scale.
During the PORC meeting referenced above, the Committee also discussed the responsibility of the plant's management personnel with respect to the requirements of Technical Specification, Appendix A, Paragraph 6.8.A.
The importance of the careful review of test data and procedural criteria was emphasized.
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Very truly;yliUrs,
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/ JOHN [i.'LE0ffARD, JR.
DISTRIBUTION RES DENT MANAGER b
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