IR 05000321/1979029
| ML19254F401 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/28/1979 |
| From: | Dance H, Roders R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19254F399 | List: |
| References | |
| 50-321-79-29, 50-366-79-33, NUDOCS 7911090196 | |
| Download: ML19254F401 (6) | |
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101 MARIETTA ST., N.W., SUITE 3100
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ATLANTA, GEORGIA 3o3o3
Report Nos. 50-321/79-29 and 50-366/79-33 Licensee: Georgia Power Company 270 Peachtree Street, N. W.
Atlanta, Georgia 30303 Facility Name: Hatch 1 and 2
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Docket Nos. 50-321 and 50-366 License Nos. DPR-57 and NPF-5 Inspection at Hatch Site near Baxley, Georgia 9!2f!79 Inspected by:
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/4 R. F. Rogerd
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H. C. Dance, Section Chief, RONS Branch
'Date' Sighed SUMMARY Inspection on August 4 - September 4, 1979 Areas Inspected This inspection' involved 90 inspector-hours onsite of the Unit I refueling outage, Unit 2 startup testing, technical specification cocpliance, IE Circulars, report-able occurrences, housekeeping, operator performance, overall plant operations, quality assurance practices, station and corporate management practices, corrective and preventative maintenance activities, site security procedures, radiation control activities, followup on open items, unresolved items, and items of noncompliance.
Results Of the fifteen areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted
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Licensee Employees
- M. Manry, Plant Manager
- T. Moore, Assistant Plant Manager
- T. Greene, Assistant Plant Manager S. Baxley, Superintendent of Operations R. Nix, S'iperintendent of Maintenance C. Coggins, Superintendent of Engineering Services W. Rogers, Health Physicist / Radiochemist C. Bellflower, QA Site Supervisor Other licensee employees contacted included technicians, operators, mechanics, security force members, and office personnel.
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on August 10, 17, 24, and 29, 1979, with those persons indicated in paragraph I above.
3.
Licensee Action on Previous Inspection Findings a.
Noncompliance (Closed) (366/78-24-05) Failure to control use of a superceded document.
The inspector reviewed the licensee's corrective action discussed in their letter of July 24, 1978, and had no further questions.
(Clormd) (321/78-33-01) Failure to initiate a procedural revision on APRM calibration. The inspector reviewed the implementation of the licenseds corrective action discussed in their letter of December 6, 1978, and had no further questions.
(Closed) (321/79-03-01) Failure to recalculate drywell leakage.
The inspector reviewed the implementation of the. licensee's corrective action described in their letter of March 7, 1979, and had no further questions.
(Closed) (366/79-08-03) Failure to notify NRC of construction deficiencies in accordance with 10 CFR 50.5Ke). The inspector verified the implemen-
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tation of the licensee's corrective action described in their response dated April 25, 1979, and had no further questions.
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Unresuved Items (Closed) (321/78-17-02) Safety evaluation not included with design change request 77-262.
The inspector reviewed this item and noted that the Plant Review Board had evrluated this item and determined that the equipment involved is not safety related (PRB Meeting 79-162 on 7/13/79).
(Closed) (321/78-33-04) Diesel Generator Restart Control Logic. The inspector verified that control logic changes were completed on both units under design change request (DCR)78-325.
(Closed) (321/78-3/-02) (366/78-45-02) Omissions on equipment tag clearance sheets. Procedure was revised to incorporate the concerns.
(Closed) (321/78-37-04) Exceeding Thermal Units inadvertently. HNP 1005 " Power changes" has been revised to require running AM OD-1 when proceeding grehter than 95% power to assure computer accuracy.
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(366/79-10-03) Uncontrolled criticality.
The inspector reviewed the licensee program for increased training and procedural modifications to prevent reocurrence. I&E Bulletin 79-12 dated May 31, 1979 further addresses this subject.
The licensee has initially responded to this bulletin and evaluation by NRC is in ?rogress.
c.
Open Items (Closed) (321/78-33-05) Exceeding linear heat generation rate limits.
The licensees corrective action discussed in the previous unresolved item 321/78-37-04 applies to this issue.
(Closed) (321/79-16-01 through 04) (366/79-20-02) Procedural revisions required for various systems. The inspector noted that the procedural revisions required for the above items had been implemented.
(Closed) (321/79-25-01 and 02) Procedural revisions required for various systems. The inspector noted that the procedural revisions required for the above items had been implemented.
(Closed) (366/79-26-01 through 03) High Pressure Coolant Injection procedural conce:ns.
The inspector reviewed these three items and
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verified that appropriate procedural changes had been completed.
4.
Unresolved Items
, Unresolved items were not identified during this inspection.
5.
Tours of the Plant (Units 1 and 2)
The inspector conducted plant tours periodically during the inspection interval to verify that monitoring equipment was recording as required, equipment was properly tagged, operations personnel were aware of plant 1309 332
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conditions and were alert, and plant housekeeping efforts were adequate.
Some tours were conducted on backshifts and on weekends.
6.
Review of Nonroutine Events Reported by the Licensee (Units 1 and 2)
The following licensee event reports (LERs) were reviewed for potential generic problems, to detect possible trends, and to determine whether corrective actions appeared appropriate. Events which were reported imme-diately were also reviewed as they occurred to determine that technical specifications were being met and that the public health and safety was of utmost consideration.
LER No.
Date of Report Description 50-321/79-44 7/26/79 Failure to conduct SRM functional test 50-321/79-49 8/1/79 Failure to include a recorder in calibration program 50-321/79-50 7/30/79 Excessive leak on 1C RHR pump 50-321/79-51 8/10/79 Inoperable RHR valves 50-321/79-52 8/14/79 PRB quorum requirements 50-321/79-53 8/17/79 Setroint drift on reactor pres-sure instrument 50-321/79-54 8/10/79 Incore detector control 50-321/79-55 8/10/79 RHR pump relay failure 50-321/79-56 8/13/79 Siesmicity of sump line 50-321/79-57 8/17/79 RWCU coil failure 50-321/79-58 8/17/79 LPCI relay setpoint drift 50-321/79-59 8/17/79 HPCI Exhaust Switch Failure 50-321/79-60 8/17/79
' B Recire Pump Relay 50-321/79-61 8/17/79 Control Room Ventilation Time Delay Relay 50-321/79-62 8/24/79 RHR Valve Timing 50-321/79-65."
8/30/79 Instrument Air Line not Sies-mically Supported
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50-366/79-52 6/27/79 Excessive Cooldown Rate 50-366/79-55 7/2/79 LHGR Exceeded Momentarily 50-366/79-58 7/10/79 CMPF Exceeded Mcmentarily 50-366/79-59 7/6/79 Concurrent UPCI/RCIC Failures 50-366/79-60 7/26/79 CHFLPD Exceeded Momentarily 50-36/79-68 8/16/79 Shield Plug Hoist Lock Broken 50-366/79-73 8/3/79 RHR flow indication inoperable 50-366/79-74 5/24/79 Recirculation Pump Trip 50-366/79-75 8/8/79 CMPF Exceeded Momentarily 50-366/79-76 8/3/79 Loss of Secondary Containment 50-366/79-77 8/3/79
"B" H 0 Analyzer Inoperable
50-366/79-79 8/10/79 Feedwater Flow Instruments Not Properly Calibrated 50-366/79-80 & 81 8/2/79 High Drywell Temperature 50-366/79-82 8/7/79 Recirculation Pump Trip Logic 50-366/79-83 8/7/79 HPCI D/P Setpoint High 50-366/79-84 8/10/79 HPCI Low Suction Trip 50-366/79-86 8/8/79 HPCI Suction Valve Motcr 50-366/79-87 8/23/79 MAPLHCR Exceeded Momentarily 50-366/79-89 8/10/79 Battery surveillance Not Performed 50-366/79-90 8/10/79 HPCI Exhaust Pressure Switch
, Drift 50-366/79-91 8/10/79 Changes Not Reviewed 50-366/79-92 8/29/79 MSL Radiation Alarm Drift
- 50-366/79-93 8/29/79 MSL Pressure Alarm Drift
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High Pressure Coolant Injection and Reactor Core Isolation Cooling Malfunc-tions and Test Programs (Units 1 and 2)
As a result of the simultaneous failure of the High Pressure Coolant Injection syster. (HPCI) and the Reactor Core Isolation Cooling system (RCIC) in June, the licensee completed an extensive test program on Unit 2.
This program was described in detail in IE report 50-321/79-24 and $0-366/79-28. An abbreviated test program was completed on Unit I during this reporting interval which consisted of six automatic starting sequences on the HPCI and RCIC turbines. All starts were successful and measured differential pressures indicated that time delay relays would not be required on this unit. The time delay relays installed on the HPCI system on Unit 2 will be removed as further evaluation by the licensee end NRC has indicated that they are not necessary.
8.
Followup on IE Circulars For the following circulars, the inspector verified that the circular was received., reviewed, and corrective actions taken or planned if appropriate.
IEC 78-18 Dated 11/6/78 UL Fire Test
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IEC 79-13 Dated 7/13/79 Fire Pump Starting Contactors
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9.
Technical Specification Compliance (Units 1 and 2)
During this reporting interval, the inspector verified compliance with selected limiting conditions for operation (LCO's) and results of selected surveillance tests. These verifications were accomplished by direct obser-vation of monitoring instrumentation, valve positions, switch positions, and review of completed logs and records. The licensee's corrpliance with selected LCO action statements were reviewed on selected occurrences as they happened.
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