ML20034A927
| ML20034A927 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/13/1990 |
| From: | Sinkule M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20034A924 | List: |
| References | |
| 50-338-90-04, 50-338-90-4, 50-339-90-04, 50-339-90-4, NUDOCS 9004250073 | |
| Download: ML20034A927 (3) | |
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- It ENCLOSURE 1 NOTICE OF VIOLATION Virginia Electric and Power Company Docket Nos. 50-338 and 50-339 North Anna License Nos. NPF-4 and NPF-7 During the Nuclear Regulatory Consnission (NRC) inspection conducted on February 17 - March 16,1990, 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.
Technical Specification 6.8.4.a requires that a program be established, implemented and maintained to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a service transient or accident to as low as practical levels. The systems include the recirculation spray, safety injection chemical and volume control, gas stripper, and hydrogen recombiners.
The program shall include the following:
(i)
Preventive maintenance and periodic visual inspection requirements, and (ii) Integrated leak test requirements for each shutdown at refueling cycle intervals or less.
Contrary to the above, the program required by Technical Specification 6.8.4.a was not established, in that the'following:
1.
An adequate preventive maintenance program has not been developed for those Grinnell valves located in radioactive fluid systems outside containment.
2.
Adequate testing has not been conducted to identify and reduce leakage from radioactive fluid systems outside containment, resulting in several personnel gas contaminations.
This is a Severity Level IV violation (Supplement 1).
B.
10 CFR 50 Appendix B Criterion XVI requires that measures shall be established to assure that conditions adverse to quality are promptly identified and cormeted and that the cause of significant conditions adverse to quality be ' determined and corrective action taken to preclude repetition.
9004250073 900413 PDR ADOCK 05000338 O
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Docket Nos. 50-338 and 50-339 North Anna License Nos. NPF-4 and NPF-7 Contrary to the above, a condition adverse to quality was not adequately -
corrected, and corrective action to preclude repetition and determination of the cause were not conducted in that, from June 1989 through March 1990, several seal leaks continued to be identified on the Unit 1 low head safety injection pump, 1-SI-P-1B, without satisfactory permanent resolution of the problem. In addition, with this history of seal problems, seal packages have not been maintained in parts storage.
This is a Severity Level IV violation (Supplement I and applies to Unit 1).
C.
Technical Specification 6.8.1.a requires written procedures be established, implemented and maintained covering those activities contained in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
This document addresses-radiation protection procedures.
Mechanical maintenance procedure MMP-C-FL-5,
" Removal and Reinstallation of the Reactor Coolant Filter, Revision 7, requires:
(1) In a note in step 5.1, that "Do not ~ completely drain and vent the filter vessel until immediately prior to filter cover removal" ard (2) In Step 7.1.5, that the protection cask be positioned over the filter access hole before the cover is removed.
Contrary to the above, procedure fiMP-C-f L-6 was not implemented in that the following:
1.
The filter was isolated at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> -on February 26, 1990, drained and vented at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> and again at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on February 27, 1990, but the filter removal process did not begin until approximately 1120 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.2616e-4 months <br /> on February 27, 1990.
2.
On February 27, 1990, the protection cask was not placed over the access hole until after the cover was removed.
These actions resulted in the contamination of seven personnel.
This is a Severity Level IV violation (Supplement I) and applies to Unit 2.
Pursuant to the provisions of 10 CFR 2.201, Virginia Electric and Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, D.C. 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident inspector, within 30 days of the date of the letter transmitting this Notice.
This reply should be clearly marked as a " Reply to a Notice of Violation" and should include [for each violation]:
(1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.
Where good cause is shovin, consideration will be y n v v
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Docket Nos. 50-338 and 50-339 North Anna License Nos. NPF-4'and NPF-7 t
given to extending the response time.
If an adequate reply is not received within the time specific in this Notice, an order may be issued'to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.
FOR THE NUCLEAR REGULATORY COMMISSION N
c.
Marvin V. Sinkule, Chief Reactor Projects Branch 2 Division of Reactor Projects Dated at Atlanta, Georgia this /sa. day of April 1990 i
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