IR 05000321/1979010
| ML19270G572 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/03/1979 |
| From: | Dance H, Hinkley D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19270G570 | List: |
| References | |
| 50-321-79-10, 50-366-79-12, NUDOCS 7906140093 | |
| Download: ML19270G572 (5) | |
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UNITED STATES pn atGO NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 M ARIETT A STREET, N.W.
ATLANT A. GEORGI A 30303
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Report Nos. 50-321/79-10 and 50-366/79-12 Licensee:
Georgia Power Company 270 Peachtree Street, N.W.
Atlanta, Georgia Facility Name:
Hatch I and 2 License Nos.
DPR-57 and NPF-5 Inspectionat,PlantgitenearBaxley, Georgia
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Inspector:
D. G. Hinckley I
Date Signed r
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Approved by:
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H. C. Dance, Section Chief, RONS Branch Date Signed SUM 1\\RY Inspection on March 14 - 16, 1979 Areas Inspected This routine, unannounced inspection involved sixteen inspector-hours onsite in the areas of IE Circulars and Bulletins, Licensee Event Reports, and previous Inspection finding followup.
Results Of the three areas inspected, no apparent items of noncompliance or deviations were identified.
2270 012 q 9061400%
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DETAILS 1.
Persons Contacted Licensee Employees
- M. Manry, Plant Manager
- C. R. Miles, Jr., QA Field Supervisor kC. E. Belflower. QA Site Supervisor kP. E. Fornell, QA Field Representative
- B. F. Barrett, QA Field Representative
- B.
Nettleton, Construction
- D. McCusker, Quality Control S. X. Baxley, Operations Superintendent W. B. Thigpen, QA Field Representative Other licensee employees contacted during this inspection included technicians, and operators.
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Other Organizations Bechtel kN. J. Cherish kM. S. DeSai General Electric Company
- S.
B. Ballinger 5RC Resident Inspector R. F. Rogers
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 16, 1979 with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings I
a.
Noncompliance (Closed) Infraction (366/78-41-01):
Operating Functional Checks.
The functional checks, required by Appendix H of the Startup 2270 013
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-2-Manual, for heatup for heatup and rated temperature and pressure have been reviewed and signed by the Operations Supervisor.
(Closed) Infraction (321/78-42-01):
Qualification of the Reactor Engineer. The reactor engineer presently meets the Technical Specification requirement, and plant management will make assign-ments, in the future, in compliance with Technical Specification requirements.
b.
Unresolved Items (Closed) (321/78-31-01):
Licensed Operator Requalification Training.
Procedure RNP-200, " Plant Personnel Training and Retraining," has been revised to implement the requirement for evaluation of supervisory staff personnel who hold senior operator licenses. The plant manager and assistar2t plant manager are exempt from the evaluation.
(Closed) (366/78-40-01):
Safety / Relief Valves Accumulator Capacity.
General Electric Company, by letter dated January 22, 1979, has provided GPC with test and calculational data which shows that the currently installed air operators will open each valve a minimum of five times assuming an initial accumulator air pressure of 85 psig or greater.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Plant Status Unit I was operating at near full power.
The refueling outage is scheduled for May 1979.
Unit 2 was shutdown for inspection and repair of anchor bolts.
6.
Inspection and Enforcement Bulletins (IEB's)
GPC's actions on the following IEB's were reviewed to determine that the IEB was reviewed, that the information discussed in the reply was accurate, and that the corrective action was as described in the reply.
Unit 1 Unit 2 78-07 Protection Afforded by Air Line Respirators and Supplied-Air Hoods Closed Closed 2270 014
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-3-GPC's reply stated that Plant Hatch does not use air-line respirators in the demand mode.
Present respiratory protection procedures do not allow protection factors to be applied when using supplied air-hoods.
In the future, the licensee has committed to revise the procedures to reflect the protection factor recommended by the bulletin if hoods are to be used with protection factors applied.
78-11 Examination of Mark-1 Ccatair. ment Torus Welds Open Open GPC can not provide documentation that NDE examination was delayed until after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following welding.
If this documentation is not available, the bulletin recommends paint removal and a magnetic particle inspection.
The licensee has committed to a thorough visual inspection during refueling outages over the next three years.
The acceptability of a visual in lieu of an NDE inspection is being reviewed.
78-13 Failures in Source Heads of Closed Closed Kay-Ray, Inc.
Not applicable to Plant Hatch 7.
Inspection and Enforcement Circular (IEC)
GPC's action on the below listed circular was reviewed to determine that an appropriate review had been made and necessary corrective action taken.
Unit 1 Unit 2 77-15 Degradation of Fuel Oil Flow Closed Closed to the Emergency Diesel Generator 2270 015
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-4-Procedure HNP-2-3803M, " Diesel Generator Fuel Oil Transfer Pump Operability," has been revised to require verification that each transfer pump can raise the level in the day tank during the operation of the diesel generator under load conditions.
8.
Development of LPCI System Logic Functional Tests A previously identified item (321/78-36-03 and 366/78-45-03) concerning safety-related system logic functional tests of the RHR 10.ec time delay relays was followed up by the inspector.
Procedure HNP-1-3153E and HNP-2-3153E, " Residual Heat Removal System - LPCI LSFT," were reviewed in approved draft form. The procedure had undergone an exten-sive revision, and it was verified that functional testing of the RHR 10 see time delay relays had been included.
This item is closed.
9.
Review of Nonroutine Events Reported by the Licensee The following licensee event reports (LER's) were reviewed for potential generic problems, to detect trends, to determine whether the information presented meets Technical Specification reporting requirements, and to determine whether the corrective action appears appropriate.
Those reports identified below with an asterisk (*) received additional review at the site to verify that the events were reviewed and evaluated by the licensee; that appropriate corrective action had been taken or planned; and that safety limits, limiting safety system settings, and limiting conditions for operations were not exceeded.
LER No.
Report Date Subject and Comments 2-78-16 8/25/78 Torus Vacuum Relief Valves Connected Backwards
- 2-78-23 8/29/78 Class 2 Core Spray Piping, hanger lugs and pipe support welds inservice inspection documentation 2-78-26 9/9/78 Two Mechanical and One Electrical Penetration Not Sealed
- 2-78-27 9/9/78 Some Switchgear and Transformer Walls Not Constructed With a 3-ilour Fire Rating 2270 016 a
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- 2-78-31 9/20/78 Core Spray Suction Piping llangers Inadequate 2-78-43 9/27/78 IRM Weekly Surveillance Not Performed Within Specified Time Frame 2-78-36 9/26/78 Fire Watch Not Established During Period of Breached Fire Barriers 2270 017