IR 05000212/2003025
| ML20082S500 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick, 05000212  |
| Issue date: | 04/18/1995 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20082S491 | List: |
| References | |
| 50-333-95-06, 50-333-95-6, NUDOCS 9505030083 | |
| Download: ML20082S500 (2) | |
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NOTICE OF VIOLATION New York Power Authority Docket No. 50-333 l
James A. FitzPatrick Nuclear Power Plant License No. DPR-59 During an NRC inspection conducted from February 12 through March 25, 1995, two violations of NRC requirements were identified.
In accordance with the
" General Statement of Policy and Procedures for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C, the violations are listed below:
A.
Technical Specification 6.8(A) states, in part, that written procedures and administrative policies 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 5.1.2 states, in part, that procedures shall be followed, and the requirements for use of procedures shall be prescribed in writing.
Contrary to the above, three instances were identified where procedures were not followed. The following examples were cited.
1)
Surveillance Test (ST)-76J21, Smoke and Heat Detector Functional Test-Relay Room, Section 8.1, Step 8.1.1.D, requires entry into A0P-63, Relay Room CO, Discharge, if a system fault results in extended CO, discharge into the relay room. However, during performance of Section 8.1 on March 19, 1995, an unanticipated discharge of CO, in the relay room occurred and neither the test personnel or control room staff entered A0P-63.
2)
Administrative Procedure (AP)-07.20, Radiation Work Permit Program, Section 8.4, requires radiation workers to log in and out of radiation work permits (RWP) using the computer (or RWP entry log if the computer is inoperable) prior to entering and after exiting a radiologically controlled area (RCA). However, on January 24, 1995 a licensed operator entered the reactor building (RCA) to hang protective tags and did not log in and out of RWP 95-0008, Task 32, to conduct this work.
3)
Administrative Procedure (AP)-07.10, Radiological Requirements for Site Access and Egress, Section 8.2.5 requires a visitor to report to the dosimetry office for dosimetry issuance if they are required to be monitored inside the plant restricted area per Section 8.6 of AP-07.10. However, on March 7 and 8, 1995, an i
escorted visitor did not obtain dosimetry upon entering the l
restricted area.
This is a Severity Level IV Violation (Supplement-1).
0FFICIAL RECORD COPY 9505030083 95041s PDR ADOCK 05000333 D
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B.
Technical Specification 6.8(A) states, in part, procedures shall be established, implemented, and maintained for the Fire Protection Program 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 5.4 states, in part, that each procedure shall be reviewed prior to initial use, periodically, and following any modification to the affected system to reflect the condition of the
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system at that time and to provide the best possible instructions to the operators.
Contrary to the above, on March 19, 1995, Surveillance Test (ST)-76J21, Smoke and Heat Detector Functional Test-Relay Room, Revision 14, Section 8.1, was performed resulting in an unanticipated CO, discharge because a modification (No. F1-92-377) made to the CO, discharge initiation logic circuit during the 1994-95 refueling outage was not reflected in this surveillance test.
This is a Severity Level IV Violation-(Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, New York Power Authority is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region I, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a " Reply to a Notice of
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Violation" and should include for each violation:
(1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Your response may reference or
include previous docketed correspondence, if the correspondence adequately
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addresses the required response.
If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
Dated at King of Prussia, PA this 18thday of April 1995 l
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