ML16343A471
| ML16343A471 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 01/17/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML16342D521 | List: |
| References | |
| 50-275-96-23, 50-323-96-23, NUDOCS 9701280373 | |
| Download: ML16343A471 (6) | |
Text
6b ENCLOSURE 1 NOTICE OF VIOLATION Pacific Gas and Electric Company Diablo Canyon Nuclear Power Plant Docket No.:
License No.:
50-275 50-323 DPR-80 DPR-82 During an NRC inspection conducted on November 10, through December 21, 1996, four 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.
Diablo Canyon Technical Specification 6.8.1 requires written procedures to be established, implemented, and maintained covering the activities referenced in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
Appendix A of Regulatory Guide 1.33 requires, in part, written procedures for the control of plant jumpers (temporary modifications).
Licensee Procedure CF4.ID7, Revision 3, "Temporary Modifications - Plant Jumpers and MSTE," requires, in part, that upon the removal of a temporary modification (1) all information tags associated with the modification shall be removed, and (2) the control operator shall remove any drawing annotation sheets.
Contrary to the above, on November 4, 1996, following the removal of a temporary pressure gauge from the Unit 2 chemical and volume control system, maintenance personnel failed to remove the information tag located at the root valve of the temporary gauge, and operators failed to remove the drawing annotations associated with the temporary gauge from control room drawing OVID ¹ 107708, Sheet 4.
This is a Severity Level IV violation (Supplement I).
B.
10 CFR Part 50, Appendix B, Criterion V, requires that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.
Procedure AD4.ID8, Revision 1, "Identification and Resolution of Loose, Missing or Damaged Fasteners,"
Step 5.1.1, requires identified deficiencies of fasteners associated with safety related equipment to be documented in an action request.
Contrary to the above, on November 19, 1996, following the inspector's identification to licensee personnel of a number of loose fasteners on the front breaker panels of the vital 480V switchgear for Unit 2, the licensee failed to initiate an action request to document this quality problem.
This is a Severity Level IV violation (Supplement I).
970i280373 970ii7 PDR ADOCK 05000275 8
C.
10 CFR Part 50, Appendix B, Criterion XVI (Corrective Action), requires, in part, that measures shall be established to assure that significant Conditions adverse to quality the cause of the condition is determined and corrective actions taken to preclude repetition.
Contrary to the above, between September 1992 and November 21, 1996, eight of.
18 surveillance tests on the 4kV first level undervoltage relays revealed that the time delay feature was greater than the maximum time allowed by Technical Specifications (TS), which are significant conditions adverse to quality. Although the relays were reset prior to placing them back in service, the licensee did not determine the cause of the condition and did not take corrective actions to preclude recurrence of the problem.
This is a Severity Level IV violation (Supplement I).
D.
TS 6.5.2.6 requires, in part, that the Plant Staff Review Committee (PSRC) be responsible for review of the safety evaluations for:
(a) changes to procedures and (b) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions do not constitute an unreviewed safety question.
Contrary to the above, as of October 23, 1996, safety evaluations were performed for the core reloads for Unit 1 Cycle 8 and Unit 2 Cycles 7 and 8, without the PSRC having reviewed the evaluations.
Additionally, fuel sipping was performed during the Unit 2 seventh refueling without the PSRC having reviewed the associated safety evaluation.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Pacific Gas and Electric 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 IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, 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, (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.
0 Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible,~t should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction.
However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public.
Dated at Arlington, Texas this 17th day of January 1997