ML18100A817
| ML18100A817 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 01/10/1994 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18100A816 | List: |
| References | |
| 50-272-93-23, 50-311-93-23, 50-354-93-25, NUDOCS 9401210110 | |
| Download: ML18100A817 (3) | |
Text
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APPENDIX A NOTICE OF VIOLATION
. Public Service Electric and Gas Company
- Salem Nuclear Generating Station Docket Nos: 50-272 50-311 Units 1 and 2 License Nos: DPR"'-70 DPR-75 During ari NRC inspection conducted on October 17 - November 27, 1993, violations of NRC requirements were identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1992), the violations are listed below:
A.
Technical Specification 3.8.1.1.b for each unit requires that for Modes 1, 2, 3, and 4, three separate and independent diesel generators shall be operable. Operability requires that the dual air start systems for each diesel be functional and able to operate as designed. Technical Specification 3. 8.1.1, Action a. requires that with one less than the required emergency diesel generators operable, PSE&G shall demonstrate the operability of the remaining A.C. sources by perfomiing Surveillance Requirements 4. 8.1.1. l.a and 4. 8.1.1.2.a.2 within one hour and at least once every 8
- hours thereafter.
Contrary to the above, on April 9, 1993, the licensee isolated an air start system for the 2C emergency diesel generator; on May 13, 1993, the licensee isolated an air start system for the lB emergency diesel generator; on August 5, 1993, the licensee isolated an air start system for the 1 C emergency diesel generator; and on September 12, 1993, the licensee isolated an air start system for the 2B emergency diesel generator. In all these instances, the licensee failed to declare the respective emergency diesel inoperable or take the actions required by TS 3. 8. 1.1, Action a.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Public Service Electric and Gas Company is hereby required to submit to this office within 30 days of the date of the letter which transmitted this Notice, a written statementor explanation in reply, 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. Where good cause is shown, consideration will be given to extending this response time.
9401210110 940110 PDR ADDCK 05000272 G
APPENDIX B
SUMMARY
OF APPARENT EXAMPLES OF DEFICIENT PERFORMANCE Salem Technical Specification 6.8.1.a requires that procedures be established, implemented and maintained, covering the activities as described in the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
Appendix A recommends, in part, that procedures be written for equipment control (e.g.,
- blocking and tagging), for the control of maintenance, and for the control of radioactivity.
Apparent examples of nonconformance with this specification are detailed in the inspection report and include the following:
- 1.
Nuclear Administrative Procedure NC.NA-AP.ZZ-0015(Q), (NAP-15), "Safety Tagging Program," Step 4.1, requires that the job supervisor ensure that equipment has been appropriately tagged and is safe fo work on before beginning a work activity.*
On October 21, 1993, a contract employee conducted maintenance on a breaker for an electro-hydraulic pump without the equipment first being tagged out.
- 2.
NAP-15, Step 5.4.5.b.6, requires that vents and drains within the tagging boundary be verified in the proper position for equipment operation prior to releasing tags.
On October 22~ 1993, an equipment operator incorrectly removed tags related to maintenance on a bleed steam coil drain tank pump and subsequently opened the
. affected valves which allowed steam to blow out drain fitt!~gs and cause the drain hose to whip about due to steam pressure.
- 3.
-NAP-15, Step 5.4.5.a, requires that components being released are the proper components as specified on the Tagging Release Worksheet.
On October 29, 1993, an operator removed the wrong tag from an upstream isolation valve and subsequently restored it to the open position, which permitted pressurized
. water flow to a downstream valve that was still involved in a maintenance work activity.
- 4.
NAP-15, Step 5.1.8, requires job supervisors with personnel working on tagged equipment under their supervision, to tag that equipment in their name or in accordance with a Group Tagging Request.
On October 31, 1993, a job supervisor failed to ensure that a 125 VDC breaker was properly tagged out of service and controlled fo support work on an associated cable.
Consequently, an electrician cut into the energiied cable, though no injury occurred.
Appendix B 2
5.-
Nuclear Administrative PrOcedure NC.NA-AP.ZZ-0009(Q), (NAP-9), "Work Control Process, II Step 2,0, requires that the work control process be applied when work is performed on Q-rated components, systems and plant structures at Artificial Island.
On October 8, 1993, licensee-personnel performing modification work on_the auxiliary feedwater system, a Q system, removed spare positioner cams from a system control valve without using a work order.
- 6.
NAP-9, Step 5.7.2, requires that an individual performing work shall perform the work* as per instructions included in the work package.
On November 4, 1993, Salem maintenance personnel performed work on a service water inlet isolation valve, 23SW58, using an unapproved vendor technical manual which had not been included as part of an approved work package.
- 7.
NAP-9, Step 5.1.5.a, requires that any maintenance that can affect the performance of Q-rated equipment be performed in accordance with approved written instructions.
On November 9, 1993, the inspector noted the following examples of Salem Unit 1 outage work being performed on Q-rated equipment without the use of approved written instructions: (1) a contractor engaged in the removal and replacement of the
-No. 12 service water-header crossover piping ; (2) contract workers working to remove service water piping for a component cooling system heat exchanger; and (3) contract workers performing wiring changes in a fuel pit heat exchanger motor operated valve.
- 8.
Salem Radi~tion Protection/Chemistry Procedure SC.RP-TI.ZZ-0209(Q), "Release Of Items From The Radiologically Controlled Area (RCA)," Step 5.1.3, requires that items released from RCA acces_s points be recorded in an active RCA Free Release Log.
On November 4, 1993, when maintenance personnel removed service water system valve 23SW58, the inlet isolation valve to the No. 23 containment fan coil unit, from the system and subsequently from the RCA, the Radiation Protection Department did not document the free release of the valve from the RCA.