ML18086B365
| ML18086B365 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/01/1982 |
| From: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18086B364 | List: |
| References | |
| 50-272-82-01, 50-272-82-1, 50-311-82-01, 50-311-82-1, NUDOCS 8203160494 | |
| Download: ML18086B365 (2) | |
Text
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i APPENDIX-A NlJHCE OF VIOLATION
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Public Service Electric and Gas Company Docket Nos. 50-272; 50-311 License Nos. DPR-70; DPR-75 Salem Nuclear Generating Station, Units 1 and 2 As a result of the inspection conducted on,January 1 - February 8, 1982, and in accordance with the Inte'f'im Enforcement Policy, 45 FR 66754 {October 7, 1980),
the following violations were identified:
A.
Technical Specification 6.8. l requires the establishment, implementation and maintenance of written procedures as recommended in Appendix 11A 11 of Regulatory Guide 1.33, November 1972, which includes procedures for safety related tagging and expected transients.
Contrary to the above:
- 1. Administrative Procedure 15, Safety Tngging Program was not followed on January 23l> 1982 when the service water and safety injection systems were breached by contractor maintenance p~rsonnel without prior verifi-cation of system isolation as required by procedure.
- 2.
As of January 14, 1982, no procedure was in effect covering stuck open secondary safety valves, an expected transient.
This is a Severity Level IV violation (Supplement I) applicable to DPR-70 and DPR-75.
B.
Technical Specification 6.11 requires that procedures for radiation protection be prepared and adhered to for all operations involving personnel radiation exposure.
Radiological Protectfon Program Procedure 24 requires that Radiation Exposure Permits (REPs) be adhered to.
- 1.
Radiation Exppsure Permit 0008,, required personnel inside the Unit l containment bioshield to wear caps and hoods.
Contrary to the above, on January 8, 1~82, 3 individuals inside the containment bioshield were not wearing caps and hoods.
- 2.
Radiation Exposure Permit 9901 required personnel insi<le contaminated areas of the Unit 1 Fuel Handling Building to wear lab coats and gloves.
Contrary to the above~ on February 2, 1982!) 1 (one) individual inside a contaminated area in the Unit 1 Fuel Handling Building was not wearing a lab coat or gloves.
This is a Severity Level IV violation {Supplement IV) applicable to DPR-70 *
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NRCFORM316(10-80)NRCM0240 OFFICIAL RECORD COPY USGPO: 1981-335-960
APPENDIX A C.
Technical Specification 6.8.2 states that procedures required by Technical Specification 6.8.1 shall be reviewed by SORC and approved by the Manager prior to implementation.
Contrary to the above, on January 149 1982, written guidance for reducing power under low feedwater suction pressure conditions, which constituted a procedure for changing load required by Technical Specification 6.8.1 and Regulatory Guide 1.33 had not been reviewed by SORC or approved by the Manager.
This is a Severity Level V Violation (Supplement I) applicable to DPR-75.
D.
Title 10 Code of Federal Regulations Part 50.72 requires that prompt (less than one hour) notification be made to the NRC for any event that results in the plant not being an a controlled or expected condition while operating or shutdown.
Contrary to the above, on January 14, 1982~ the plant was operating at 80%
thermal power, 50% turbine power, with the steam dump valves shut, with an abnormally high Tavg, with an unseated steam generator safety valve, and with the rod control system inoperable. This unexpected condition was not reported to the NRC within one hour
- This is a Severity Level IV Violation (Supplement I) applicable to DPR-75.
Pursuant to the provisions of 10 CFR 2.201, Public Service Electric and Gas Company is hereby required to submit to this office within thirty days of the date of this Notice, a written statement or explanation in replys including:
(1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further violations; and (3) the date when full compliance will be achieved. Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affi nnati on.
i~here good cause is shown, consideration wi 11 be given to extending your response time. The responses directed by this Notice are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980 0 PL 96-511.
MAR 0 1 1982 Dated ----
Q.riginal SigneQ, BV~
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Richard W. Starostecld, Director Division of Project and Resident Programs OFFICE. -*******.. *******.. -*-**
SURNAME~ -***********-***.. ****-*
DATE.........................
NRG FORM 318 (10-8.0) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960