ML18101A357
| ML18101A357 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/28/1994 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18101A356 | List: |
| References | |
| 50-272-94-24, 50-311-94-24, NUDOCS 9412060120 | |
| Download: ML18101A357 (2) | |
Text
APPENDIX A NOTICE OF VIOLATION Public Service Electric and Gas Company Salem Nuclear Generating Statton Docket Nos:
50-272 50-311 Units 1 and 2 License Nos:
DPR-70 DPR-75 During an NRC inspection (investigation) conducted on September 18, 1994 -
November 5, 1994, violations of NRC requirements were identified.
In accordance with the 11General Statement of Policy and Procedure for NRC Enforcement Actions, 11 10 CFR Part 2, Appendix C, the violations are listed below:
.A.
10 CFR 50, Appendix B, Criterion XVI requires, in part, that licensees establish measures to assure that conditions adverse to quality are promptly identified and corrected. The Facility Operating License for Salem Nuclear Generating Station, Unit No. 2, requires that PSE&G operate the facility at steady state reactor core power levels not in excess of 3411 megawatts (thermal).
Contrary to the above, from July 23, 1993 until January 19, 1994, the licensee failed to promptly identify and correct sustained periods of steady state reactor core power levels of up to 3499 megawatts (thermal).
This is a Severity Level IV violation (Supplement I)
B.
Technical Specification 4.3.1.1.1 for Salem Unit 2 requires that each reactor trip system instrumentation channel shall be demonstr~ed operable by the performance of the channel calibration as shown in Table 4.3-1. Table 4.3-1 specifies that the power range neutron flux functional unit shall be calibrated by heat balance daily for power operation above 15%.
Technical Specification 1.13 defines daily as at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Technical Specification 4.0.2 requires that each surveillance requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.
Contrary to the above, with power above 15%, on October 12, the licensee failed to perform the required daily calorimetric of the NIS within the variance allowed by the Technical Specification.
This is a Severity Level IV violation (Supplement I)
- c.
Technical.Specification 3.9.4 for Salem Unit 2 requires that during core alterations or movement of irradiated fuel within the containment the containment building penetrations, providing direct access from the containment atmosphere to the outside atmosphere, shall be either (1) 9412060120 941128 PDR ADOCK 05000272 Q
2 closed by an isolation valve, blind flange, or manual valve, or (2) be capable of being closed by an operable automatic containment isolation valve.
Contrary to the above, the licensee moved irradiated fuel from 11:38 p.m. on October 24, 1994, to 1:10 a.m. on October 25, 1994, with a release pathway from open service water vent valves in containment to open service water drain valves outside of containment.
This is a Severity Level IV violation (Supplement I).
D.
The NRG-Approved Artificial Island Security plan section 5.6 requires measures to insure control of access to vital areas at Salem Unit 2.
Post orders to control access to the Salem Unit 2 no. 2C Emergency Diesel Generator (EOG) required that the security guard verify that persons entering the EOG room had proper authorization prior to granting access.
Contrary to the above, on October 24, a security guard permitted two persons to enter the Salem Unit 2 no. 2C EOG room without verifying proper authorization prior to granting access.
This is a Severity Level IV violation (Supplement III).
Pursuant to the provisions of 10 CFR 2.201, PECO Energy Company 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 1, and a copy to the NRC Resident Inspector at the facility that is th~ subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (No-tice). This reply should be clearly marked as a "Reply to a Notice of Viola-tion" 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.
If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked, or why such other action as may be proper not to be taken.
Where good cause is shown, consideration will be given to extending the response time.
Dated at King of Prussia, Pennsylvania this~ day of November, 1994