ML20199D317
| ML20199D317 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/12/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20199D308 | List: |
| References | |
| 50-354-97-07, 50-354-97-7, NUDOCS 9711200309 | |
| Download: ML20199D317 (4) | |
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APPENDIX A NOTICE OF VIOLATION Public Service Electric and Gas Company Docket No:
50-354 Hope Creek Generating Station License No: NPF-57 During an NRC inspection conducted between August 24,1997 and October 4,1997, violations of NRC requirements were identified, in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600,the violations are listed below:
A.
10 CFR 50 Appendix B, Criterion XVI, requires in part that conditions adverse to quality, such as failures, malfunctions and deficiencies, be promptly identified and corrected.
Contrary to the above, on September 14,1997, the electric motor-driven fire pump supply breaker opened during an electrical bus swap which rendered the pamp inoperable, a condition adverse to quality. Despite several opportunities to detect this condition earlier, tha inoperable fire pump was not identified and corrected until September 15,1997, approximately 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> after electrical supply breaker opened.
This is a Severity Level IV violation (Supplement 1).
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Hope Creek technical specifica+ ion 6.8.1.a requires in part that written procedures shall be established and impleriented for the applicable activitics specified in Appendix A of Regulatory Guide (RG) 1.33 Revision 2. RG 1.33 reouires administrative procedures be implemented which prescribe procedure adherence practices. PSE&G Nuclear Administrative Procedure NC.NA-AP.ZZ-0001 (NAP-1),
specifies procedure usage requirements, including Category I (in-hand with verbatim step-by step compliance) and Category II (available at work site and completed as applicable).
Contrary to the above, two examples of failures by maintenance technicians to implement the procedure adherence requirements of NAP 1 were identified as follows:
(1) On September 18,1997, technicians deviated from the sequence of steps specified in a Category I maintenance procedure, HC.MD-ST.PB-0010(O),in order to complete a 4160 VAC vital bus relay test.
(2) On October 4,1997 technicians completed feed water system flow transmitter calibration checks and adjustments without completing the applicable sections of the governing Category 11 maintenance procedure, HC.lC-DC.ZZ-0030(Q).
This is a Severity Level IV violation (Supplement 1).
9711200309 971113 PDR ADOCK 05000354 G
2 C.
10 CFR 50.59(b)(1) requires, in part, that the licensee shall maintain records of changes in the _f acility made pursuant to this cection, to the extent that these changes constitute changes in the facility as described in the safety analysis report (UFSAR). These records must include a written safety evaluation which provides the bases for the determination that the change does not involve an unreviewed safety question.
Section 7.4.1.1 of the UFSAR describes the functions and operation of the reactor core isolation cooling (RCIC) system and includes a flow control diagram showing instantaneous trig. ping of the turbine on high reactor vessel water level.
Contrary to the above, on and before September 30,1997, no written safety evaluation was peformed to ensure that a change to the facility involving the delay of the RCIC turbine trip on high reactor vessel water level did not involve an unreviewed safety question.
This is a Severity Level IV violation (Supplement I).
D, 10 CFR 50.49, sections (d) and (j) require, in part, that licensees prepare a list of electric equipment important to safety covered by this section [ requiring environmental qualification) and that a record of qualification be maintained in an auditable form to permit verification that each item of electric equipment important to safety is qualified for its application and meets its specified performance requirements when it is subjected to the conditions predicted to be present when it must perform its safety function up to the end of its qualified life.
Contrary to the above, on or before April 7,1997, five safety-related Struthers-Dunn relays located in a harsh environment were not included in the list of equipment important to safety requiring environmental qualification; were not replaced at the end of the qualified life specified for other relays subjected to the same conditions predicted to be present when they must perform their safat',*
function; and were not adequately justified to be able to meet their performance requirements af ter the end of their qualified life.
This is a Severity Level IV violation (Supriement 1).
E.
10 CFR 50, Appendix B, Criterion Ill,' Drisign Control, requires in part that design control measures provided for verifyi7g or checking the adequacy of design, such as by the performance of design reviews, or by the performance of a suitable testing program.
Contrary to the above, on or oefore September 30,1997, the control measures provided for verifying or checking the adequacy of the design were inadequate in that independent reviews of design calculations developed to extend the service life of safety-related Agastat and Telemechanique relays in a mild environment f ailed to verify the adequacy of the coil temperature rise used in the calculations. The use of incorrect coil temperature rise values resulted in longer service lives.
3 This is a Severity Level IV violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, Pubic Service Electric and Gas Company is hereby required to submit a written statement rir 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 f acility 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, (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 eference or include previous docketed correspondence,if the corresponderwe adequately addresses the required response. If an adequate reply is not received w' thin the time specified in this Notice, an oraer 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.
Because your response will be placed in the NRC Public Su ument 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 E411 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 piivacy or provido the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financialinformation). If sa'eguards 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 November,1997.
APPENDIX B
- NOTICE OF VIOLATION REQUIRING NO RESPONSE
- Public Service Electric & Gas Corporation Docket No. 50 354
- Hope Creek Nuclear Generating Station License No. NPF 57 During an inspection conducted from June 2,1997 to June 10,1997, a violation of NRC requirements was identified. In accordance with the " General Statement of Policy ad Procedure for NRC Enforcement Actions," NUREG 1600, the violation is listed below:
10 CFR 71.5 states that each licensee who transports licensed material or delivers licensed material to a carrier for transport, shall comply with applicable DOT regulations in 49 CFR parts 170 through 189 appropriate to the mode of transport.
49 CFR 172.203(d)(11) requires that for a shipment of low specific activity material, the appropriate group notation of LSA 1, ' SA II, or LSA Ill shall be indicated on the shipping papers.
- Contrary to the above, since April 1,1996 through June 9,1997, the licensee has conducted multiple laundry shipments without specification of the LSA group indicated on the shipping papers.
This is a Seve.ity Level IV violation (Supplement V).
No response to this violation is required.
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