ML16342D727
| ML16342D727 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 07/09/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML16342D728 | List: |
| References | |
| 50-275-97-06, 50-275-97-6, 50-323-97-06, 50-323-97-6, NUDOCS 9707110197 | |
| Download: ML16342D727 (6) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Pacific Gas and Electric Company Diablo Canyon Nuclear Power Plant Docket Nos.:
License Nos.:
50-275 50-323 DPR-80 DPR-82 During an NRC inspection conducted on April 27 through June 7, 1997, three 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.
Technical Specification 6.8.1 states, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures in Appendix A of Regulatory Guide 1.33, Revision 2.
NRC Regulatory Guide 1.33, Appendix A, requires implementing procedures for maintenance of minimum shift complement and call-in personnel.
Operating Procedure OP1.DC12, Revision 6, "Conduct of Routine Operations,"
Section 5.11.1, states that Attachment 7.4 identifies normal occupancy areas to which the individual assigned "Operator at the Controls" shall be restricted.
Section 5.11.3 of OP1,DC12 specifies that Attachment 7.5 to the procedure identifies the areas the "Operator at the Controls" may enter provided that the senior control operator for the unit or another cognizant licensed operator is stationed such that he is clearly attentive to control room indications and alarms.
Contrary to the above, on May 29, '1997, at approximately 10:30 a.m. for a period of approximately 3 minutes, the cognizant licensed operator responsible for being in the Unit 2 "Operator at the Controls" area and attentive to control room indications and alarms (the Unit 1 Senior Controls Operator) left the control room.
As a result, Unit 2 was without a licensed operator assigned to be attentive to control room indications and alarms in the "Operator at the Controls" area until the condition was noted and corrected by the shift foreman.
This is a Severity Level IV violation (Supplement I) (50-323/9706-01).
B.
10 CFR Part 50, Appendix B, Criterion V (Instructions, Procedures and Drawings),
- requires, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.
Operations Procedure OP J-6A:IV,"4160 Volt Breaker Code Order," provides instructions for all 4kV breakers at Diablo Canyon Power Plant.
Section 5.3 specifies that breaker cubicle panel doors must be fully bolted closed to insure structural integrity of the bus housing for postulated seismic events.
9707iioi97 970709 PDR ADQCK 05000275 6
Contrary to the above, on April 30, 1997, the inspector identified that three of the four seismic restraining bolts on the front panel of breaker Cubicle 52-HH-15 (for Safety Injection Pump 2-2) had not been tightened as required by procedure.
This is a Severity Level IV violation (Supplement I) (50-323/9706-02).
C.
Technical Specification 6.8.1 states, in part, that written procedures shall be established, implemented, and maintained covering the fire protection program.
The fire protection program requirements are specified in program directive Procedure OIV!8, Revision 2, "Fire Protection Program."
Section 3 of the program directive defines the fire protection program as is described in Chapter 9, Section 5.1, of the Final Safety Analysis Report, and as approved by NRC in applicable Safety Evaluation Reports and Units 1 and 2 license conditions.
Section C of Appendix 9.5C of the FSAR requires that the reactor coolant pump oil collection system include a sheet metal shield that encloses the lift oil pump and piping so that the spray from a potential oil liftpump leak would be confined within the shield and the spray directed to the oil collection pans.
Contrary to the above, on April 19, 1997, the licensee discovered that the reactor coolant pump oil collection system sheet metal shields did not comply with the fire protection program requirements in that they did not enclose all of the liftoil piping and would not have confined spray from a potential liftoil system leak.
This is a Severity Level IV violation (Supplement I) (50-275/9706-06).
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.
.. Because your response will be placed in th'e NRC Public Document Room (PDR), to the
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extent possible, it 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 9th day of July 1997