ML20135C306
| ML20135C306 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/25/1996 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20135C297 | List: |
| References | |
| 50-321-96-13, 50-366-96-13, NUDOCS 9612060273 | |
| Download: ML20135C306 (3) | |
Text
.
NOTICE OF VIOLATION Georgia Power Company Docket Nos. 50-321. 50-366 Hatch Units 1 and 2 License Nos. DPR-57. NPF-7 During the NRC inspection conducted from September 15, 1996 through October 26, 1996. 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.
Unit 2 Technical Specification 3.6.1.7 Reactor Building-to-Suppression Chamber Vacuum Breakers. Limiting Conditions for 0)erations required that each reactor building-to-suppression i
clamber vacuum breaker shall be operable. Technical Specification Surveillance Requirement 3.6.1.7.3 stated:
Verify the opening i
setpoint of each vacuum breaker is less than or equal to 0.5 psid.
Unit 2 Bases B 3.6.1.7. Reactor Building-to-Suppression Chamber Vacuum Breakers, stated, in part. "The design of the external (reactor building-to-su)pression chamber) vacuum relief provision consists of two vacuum areakers (a mechanical vacuum breaker and an air operated butterfly valve). located in series in each of two lines from the reactor building to the su)pression chamber air space." The butterfly valve is actuated )y differential pressure.
Contrary to the above, since the unit was licensed on June 13.
1978. until September 17. 1996, the licensee failed to verify that the opening set)oints of Reactor Building-to-Suppression Chamber Vacuum Breaker autterfly valves 2T48-F310 and 2T48-F311 were less than 0.5 psid.
This is a Severity Level IV Violation (Supplement I). This violation is applicable to Unit 2.
B.
Hatch Technical Specification 5.4 requires that written procedures be established, implemented, and maintained covering activities delineated in Appendix A of Regulatory Guide (RG) 1.33.
Revision 2. February 1978.
RG 1.33. Appendix A: Typical Procedures for Pressurized Water Reactors and Boiling Water Reactors. paragraph 1.c recommends procedures for equipment control, paragraph 9 recommends procedures for performing maintenance, paragraph 9.e.(1) recommends methods for obtaining permission and clearance for personnel to work, and paragraph 7.e(4) recommends written l
procedures for contamination control.
Procedure 30AC-0PS-001-0S, Control of Equipment Clearances and Tags. Revision 15. Step 8.7.1.3 stated in part, that a clearance is to be performed by positioning the component and securing danger tags to the component indicated by the master parts list and/or location of the component.
9612060273 961125 I
PDR ADOCK 05000321
{
G PM I
.4 1
i Procedure 51GM-MNT-017-0S. Control of Lubricants. Revision 1.
I Section 7.2.4 stated. in part, that lubricant containers will be marked so the lubricants contained therein can be easily identi fied.
Procedure 60AC-HPX-007-0S:
Control of Radioactive Materials.
Rev. 3.
Step 8.1 stated, in part, that equipment, parts.
material and waste which have fixed surface contamination levels 2
l exceeding 5000 dpm/100cm beta-gamma shall be controlled as radioactive
.terial.
Contrary to the above, written procedures were not implemented in l
that:
1..
On October 1,1996, during the performance of procedure 30AC-0PS-001-0S, a plant operator repositioned a component not l
on the clearance.
This caused the operating Unit 1 Control Rod l
Drive Pump Motor to trip resulting in a temporary loss of normal rod drive motive' force, seal water to the reactor l
recirculating > umps, and water supply to the reactor level reference leg (eep-fill system.
2.
On October 10. 1996, during the performance of procedure 51GM-MNT-017-0S, the inspectors observed an unmarked container being used to add lubricant to the Unit 2 Reactor Core Isolation Cooling Pump. Also, there were several additional unmarked containers on the room floor containing oil residue.
3.
On or about April 12, 1996. radioactive materials with fixed 2
l surface contamination levels exceeding 5000 dpm/100cm were i
removed from a radiologically controlled area and not L
controlled as radioactive material: as required by i
This is a Severity Level IV Violation (Supplement.I).
4 Pursuant to the provisions of 10 CFR 2.201. Georgia Power Com]any is hereby required to submit a written statement or explanation to the J.S. 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. Hatch Nuclear Plant, within 30 days of the date of the
-letter transmitting this Notice of Violation (Notice). This reply should be l
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.
l Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the recuired res)onse.
If an adequate l
reply is not received within the time specifiec in this lotice, an order or l
1
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 3 roper 1
should not be taken. Where good cause is shown, consideration will 3e given to extending the response time.
Because your res)onse will be placed in the NRC Public Document Room (PDR), to the extent possi)le, it should not include any personal privacy. )roprietary, or safeguards information so that it can be placed ir the PDR witlout 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 Atlanta, Georgia this 25th day of November, 1996 i