ML18106B067
| ML18106B067 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/12/1999 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18106B066 | List: |
| References | |
| 50-311-98-12, NUDOCS 9902190277 | |
| Download: ML18106B067 (2) | |
Text
APPENDIX A NOTICE OF VIOLATION Public Service Electric and Gas Company Salem Nuclear Generating Station Unit 1 Docket No:
50-311 License No:
DPR-75 During an NRC inspection conducted from December 16, 1-998, through January 16, 1999, a violation of NRC requirements was identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violation is listed below:.
Salem Unit 2 technical specification (TS) 6.8.1 requires in part that written procedures shall be established and maintained covering activities described in Appendix A of Regulatory Guide (RG) 1.33, Revision 2, February 1978. TS 6.8.1 also requires that procedures be implemented for emergency plan implementation. Two examples of a failure to satisfy this TS are listed below:
- 1.
- 2.
RG 1.33 requires that general operating procedures be maintained for reactor plant start up activities, including mode changes from cold shutdown to hot standby.
Contrary to the above, on December 8, 1998, it was identified that procedure S2.0P-IO-ZZ-0002(Q), "Cold Shutdown to Hot Standby," permitted the increase of reactor coolant system (RCS) pressure to 375 psig, which was the setpoint of the residual heat removal common suction line relief valve. Operator implementation of this procedure resulted in the relief valve opening, discharging approximately 1300 gallons of RCS inventory to the containment sump.
The Salem Event Classification Guide (ECG),Section IV.A, requires that the assessment of an emergency condition should be completed in a timely manner, which is conside.red to be within about 15 minutes of recognition of an event.
Contrary to the above, on December 8, 1998, Salem Unit 2 experienced a rapid loss of reactor coolant inventory, which was recognized by control room operators within about
. a minute of initiation. However, the operations superintendent did not make an appropriate event classification until 37 minutes after the event was recognized, exceeding the ECG criteria by 22 minutes.
This is a Severity Level IV violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, Public Service Electric and Gas 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 Violation" and should include for each violation: (1) the reason for the violation, or, if contested, the basis for disputing the violation or 9902190277 990212 PDR ADOCK 05000272 G
2 severity level, (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 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.
If you contest this enforcement aCtion, you should also provide a copy of your response to the Director, Office of Enforcement, United States Nucl~ar Regulatory Commission, Washington, DC 20555-0001.
Because your response will be placed in the NRC Public Document Room (PDR), to the extent
.possible, it should not include any personal privacy, proprietary, or safeguards information so
. that it can be placed in the PDR without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required *by 10 CFR 2. 790(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Dated at King of Prussia, Pennsylvania this 12th day of February, 1999.