ML17305B310
| ML17305B310 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/27/1990 |
| From: | Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17305B309 | List: |
| References | |
| 50-528-90-42, 50-529-90-42, 50-530-90-42, NUDOCS 9101150072 | |
| Download: ML17305B310 (6) | |
Text
0 APPENDIX A NOTICE OF VIOLATION Arizona Nuclear Power Project Palo Verde Unit 1, 2, and 3
Docket Nos. 50-528, 50-529 and 50-530 License Number NPF-41, NPF-51, and NPF-74 During an NRC inspection conducted on October 1 through November 9,
- 1990, three 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 (1990), the violations are listed below:
A.
10 CFR Part 50, Appendix B, Criterion III, states that design controls will be established to assure that applicable regulatory requirements and the design basis are correctly translated into specifications,
- drawings, procedures, and instructions.
Section 8.1.4.1 of the Palo Verde Nuclear Generating Station (PVNGS) updated Final Safety Analysis Report (UFSAR) states that one of the principal design bases applied to the offsite power system is that:
"The outage of a single startup transformer does not jeopardize continued plant operation, i.e., at least one offsite source to plant auxiliaries and ESF (engineered safety features) buses is available with a single startup transformer outage."
Contrary to the above, the offsite power system was not designed to minimize the likelihood of simultaneous failure of both offsite sources when three Units are powered from two startup transformers and a fast bus transfer of non-Class lE loads from the unit auxiliary transformer to the startup transformer occurs.
For example, from August 9 to August 12, 1988, the ratings of startup transformers XOl and X03 (Z and' output windings respectively) may have been exceeded due to excess current if a reactor trip, turbine trip, or loss of coolant accident had occurred in Unit 2.
This may have resulted in a loss of both offsite power sources to Unit 2.
This is a Severity Level IV Violation (Supplement
- 1) applicable to Units 1, 2, and 3.
B.
10 CFR Part 50, Appendix B, Criterion V, as implemented by 17.2.5 of the Palo Verde Nuclear Generating Station (PVNGS) Updated Final Safety Analysis Report (UFSAR), states that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings and shall be accomplished in accordance with these instructions procedures, or drawings.
Procedure 81-DP-4CC04, Revision 1, "Calculations," requires that calculations be prepared in accordance with procedure 81-DP-OCC05.
Procedure 81-DP-OCC05',
Revision 0, "Design and Technical Document Control," requires the responsible engineer to ensure that all affected engineering and plant configuration documents are addressed for update and to provide a design that meets all the functional requirements called for by the design change request.
9101150072 901227 PDR ADOCK 05000528 Q
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e Contrary to the above, Calculation 13-EC-MA-212 was not revised to reflect the loading information provided in Calculation 13-EC-DG-200.
Specifically, various motor loading data used in Calculation 13-EC-MA-212, Revision 7, "Auxiliary System and Transformer Sizes,"
were taken from Calculation 13-EC-PE-110, Revision 5, dated June 22,
- 1989, "Diesel Generator Sizing."
Calculation 13-EC-PE-110 was then superseded by Calculation 13-EC-DG-200, Revision 5, dated September 6, 1990, "Diesel Generator Load Calculation." This calculation showed engineered safety feature equipment loading values that were greater than the load values in 13-EC-PE-110 by approximately 100 hp.
- However, as of October 23,
- 1990, loads indicated on Calculation 13-EC-MA-212 were not updated to reflect the loads indicated in Calculation 13-EC-DG-200.
This is a Severity Level IV Violation (Supplement
- 1) applicable to Units 1,2, and3.
C.
Technical Specification 6.8. 1 states, in part, "Mritten procedures shall be established, implemented, and maintained covering...the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978."
Section 9 of Regulatory Guide 1.33 requires that maintenance that can affect the performance of safety-related equipment be properly preplanned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances.
General Electric's Load Center Vendor Manual, Maintenance Instructions, specifies as a minimum requirement, an annual check for switchboard devices and connections.
Contrary to the above, as of November 9, 1990 the licensee had not implemented written procedures'= or schedules for vendor recommended maintenance for class lE Load Centers
- D25, D26, D27 and D28 since startup of each unit, except for Load Center D25 in Unit 2.
This is a Severity Level IV Violation, (Supplement I) applicable to Units 1, 2, and 3.
Pursuant to the provisions of 10 CFR 2.201, Arizona Public Service Company is hereby required to submit a written statement or explanation to the U.
S.
Nuclear Regulatory Com'mission, ATTN: Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region V, and a copy to the NRC Resident Inspection office at the Palo Verde Nuclear Generating Station, within 30 days of the date of the letter transmittinp 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 if admitted; (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.
If an adequate reply is not received within the time specified in. this Notice, an order may be issued to show cause why the license-should not be modified,
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suspended, or revoked or why such other action as may be proper should not be taken.
Consideration may be given to extending your response time for good cause shown.
FOR THE NUCLEAR REGULATORY COMMISSION Dated at Malnut Creek, California this g75day of gC8M 1990
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Division of Reactor Safety and Projects
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