ML20235U523
| ML20235U523 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/15/1987 |
| From: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20235U509 | List: |
| References | |
| 50-321-87-12, NUDOCS 8707220509 | |
| Download: ML20235U523 (2) | |
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ENCLOSURE 1
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NOTICE OF VIOLATION Georgia Power Company Docket No. 50-321 Hatch License No. DPR-57 During the Nuclear Regulatory Commission (NRC) inspection conducted on May 27 - July 3,1987, violations of NRC requirements were identified.
The violations were for inadequate operating and surveillance test precedures and for failing to follow (implement) equipment control procedures.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Action," 10 CFR Part 2, Appendix C, the violations are listed below:
A.
Technical Specification 6.8.1.c requires the licensee to establish and I
implement procedures for the conduct of surveillance and test activities of safety related equipment.
Technical Specification 6.8.1.a requires the licensee to establish, l
l implement and maintain written procedures covering the applicable activities in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Appendix A of Regulatory Guide 1.33 recommends establish-ment of procedures for the optration of the shutdown cooling system.
Contrary to the above; l
1.
The licensee failed to provide adequate procedures for the performance of excess flow check valve surveillance testing on April 18, 1987.
Improper jumpering and link operating resulted in inadvertent isolation of the High Pressure Coolant Injection and Reactor Core Isolation Cooling systems.
2.
Licensee procedures used to fill the "B" loop of the Residual Heat Removal (RHR) system in the shutdown cooling mode on April 22, 1987, l
were inadequate.
Inadequate RHR filling instructions resulted in draining of the reactor vessel to the plus ten inch level (approximately 15.5 feet above the active fuel).
3.
The lice Mee failed to provide adequate procedures for the performance of operability testing on valve IE11-F078A, Service Water Intertie Valve, on June 15, 1987.
In the absence of written instructions on how to relieve differential pressure across the valve prior to testing, the reactor operator selected and opened two RHR system valves to relieve the differential pressure. Opening of these valves created a flow path from the reactor vessel to the suppression pool resulting in a rapid loss of reactor vessel inventory to the plus ten inch level.
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Gedrgia Power Company 2
Docket No. 50-321 Hatch License No. DPR-57 This is a Severity Level IV violation (Supplement I).
B.
Technical Specification 6.8.1.a requires the ' licensee to establish, implement and maintain written procedures covering the applicable activities in Appendix A of Regulatory Guide 1.33, Revision 2,
February 1978.
Appendix A of Regulatory Guide 1.33 recommends establishment of procedures for equipment control (e.g. locking and tagging).
Licensee's procedure 30AC-OPS-001-OS establishes controls for equipment clearances and tags. This procedure requires that Operations issue a clearance for maintenance isolation.
Contrary to the above, on June 20-21, 1987, licensee personnel performing maintenance on drywell cooler IT47-B008A, failed to comply with-the requirements of 30AC-OPS-001-05. Air operated valves supplying cooling water to the cooler were jacked closed with no clearance issued.
Upon completion of the maintenance the valves were not returned to normal lineup. This resulted in the cooler being left inadvertently isolated and higher than expected drywell temperatures upon return to power operations.
This is a Severity Level V violation (Supplement 1).
Pursuant to 10 CFR 2.201, Georgia Power Company is hereby required to submit to this Office within 30 days of the date of the letter transmitting this Notice a written statement or explanation in reply including:
(1) admission or denial of the violation; (2) the reasons for the violation, if admitted; (3) the i
corrective steps which have been taken and the results achieved; (4) corrective
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steps which will be taken to avoid further violations; and (5) the date when j
full compliance will be achieved. Where good cause is shown,. consideration j
will be given to extending the response time.
j FOR THE NUCLEAR REGULATORY COMMISSION ORIGINAL SIGNED DY
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l VIRG!L L BROWNLEE /
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Luis A. Reyes, Director Division of Reactor Projects l
Dated at Atlanta, Georgia this 15 day of July 1987 j
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