IR 05000321/1981029
| ML20038D097 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/18/1981 |
| From: | Brownlee V, Rogers R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20038D094 | List: |
| References | |
| 50-321-81-29, 50-366-81-29, NUDOCS 8112160058 | |
| Download: ML20038D097 (10) | |
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-[gner UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
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REGION II
o 101 MARf*TTA ST., N.W SUITE 3100
/J TA, GEORGIA 30303
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Report Nos. 50-321/81-29 and 50-366/81-29
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Licensee: Georgia Power Company Facility Name: Hatch 1 and 2 Docket Nos. 50-321 and 50-366-License Nos. DPR-57 and NPF-5 Inspection at Hatch site near Baxley, Georgia i
Inspector: - d[ M[mv P R. F. Rogers (6enior Resident Inspector
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Date Signed
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Approved by:
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Ddte Signed nwy Lf V. LA Brownlee, Section Chief Division of Resident and Reactor Project Inspection StRfARY Inspection on September 29 - October 20, 1981
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Areas Inspected
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This inspection involved 100 inspector-hours on site in the areas of Technical Specification compliance, housekeeping, operator performance, overall plant i
operations, quality assurance practices, station and corporate management practices, corrective and preventive maintenance activities, site security procedures, radiation control activities, surveillance activities, IE circulars, and Licensee Event Reports.
Resul ts i
Of the 12 areas inspected, no violations or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- H. Manry, Plant Manager
- T. Greene, Assistant Plant Manager
- C. T. Jones, Assistant Plant Manager S. Baxley, Superintendent of Operations R. Nix, Superintendent of Maintenance
- C. Coggins Superintendent of Engineering S2rvices W. Rogers, Health Physicist-
- C. Eelflower, QA Site Super. visor 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 October 2 and 20,1981 with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items were not identified during this inspection.
5.
- Plant Operations Review (Units 1 and 2)
The inspector periodically during the inspection interval reviewed shift logs and operations records, including data sheets, inctrument traces, and records of equipment malfunctions. This review included control room logs and auxiliary logs,. operating orders, standing orders, jumper logs and equipment tagout records. The -inspector routinely observed operator alert-ness and demeanor during plant tours. During normal events, operator performance and response actions were observed and evaluated.
The-inspector conducted-random off-hours inspections during the reporting interval to assure that operations and security remained at an acceptable level.
Shift turnovers were observed to verify that they were conducted in accordance with approved licensec procedures.
Within the area inspected, no violations or deviations' were identified.
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6.
Plant Tours (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 conditions, and plant housekeeping efforts were adequate.
The inspector also determined that appropriate radiation controls were properly estab-lished, critical clean areas were being controlled in accordance with procedures, excess equipment or material is stored properly and combustible material and debris were disposed or expeditiously.
During tours the inspector looked for the existence of unusual fluid leaks, piping vibra-tions, pipe hanger and seismic restraint settings, various valve and breaker positions, equipment caution and danger tags and component positions, adequacy of fire fighting equipment and instrument calibration dates.
Some tours were conducted on backshif ts.
Within the areas inspected, no violations or deviations were identified.
7.
Technical Specification Compliance (Units 1 and 2)
During this reporting interval, the inspector verified compliance with selected limiting conditions for operations (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 compliance with selected LC0 action statements were reviewed on selected occurrence as they happened.
Within the areas inspected, no violations or deviations were identified.
3.
Physical Protection (Units 1 and 2)
The inspector verified by observation and interviews during the reporting interval that measures taken to assure the physical protection of the facility met current requirements. Areas inspected including the organi-zation of the security force, the establishment and maintenance of gates, door and isolation zones in the proper condition, that access control and badging was proper, and procedures were followed.
Within the area inspected, no violations or deviations were identified.
9.
Review of Nonroutine Events Reported by the Licensee (Units 1 and 2)
The following Licensee Event Reports (LERs) were reviewed for potential generic impact, to detect trends, and to detennine whether corrective actions appeared appropriate.
Events which were reported immediately were also reviewed as they occurred to determine that Technical Specifications were being met and that the public health and safety were of utmost con-l sideration. Astericked reports were followed up indepth onsite.
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LER N0.
Date of Report Description N n-siesmic PSW
- 50-321/81-25
_4/9/81 discharge valves
- 50-321/81-26 4/5/81 Failure of D/G UV relays
- 50-321/81-31 4/15/81 Overstress on control building wall
- 50-321/81-39 4/28/81 Overstressed Pipe Supports
- 50-321/81-40 4/28/81 Deformed !!S relief discharge line
- 50-321/81-41 5/6/81 IEB 79-14 support failures
- 50-321/81-42 5/5/81 Setpoint drift on radiation monitor
- 50-321/81-43 5/29/81 High drum radiation
- 50-321/81-44 5/6/81 Release of radwaste prior to sampling
- 50-322/81-45 5/26/81 LLRT failures
- 50-323/81-46 6/3/81 Reactor level switch actuated high
- 50-321/81-49 6/5/81 RCIC valve failure 50-321/81-50 6/12/81 Containment spray isolation valve inoperative
- 50-321/81-51 6/7/81 HPCI overspeed trip failure
- 50-321/81-52 6/21/81 LPCI inverter trips 50-321/81-53 6/10/81 Drywell and Torus temperature recorder inoperative 50-321/81-54 6/12/81
"B" H -0 analyzer inoperative 2 2
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- 50-321/81-55 7/2/81 Inoperable snubbers 50-321/81-56 7/2/81 Inoperable hydrogen off-gas analyzer
- 50-321/81-57 6/30/81 Failure to approve SR0 change within 14 days 50-321/81-58 7/21/81 Inoperative hydrogen and Oxygen analyzers
- 50-321/81-59 7/7/81 Failure to attain containment AP within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 50-321/81-60 7/15/81 Reactor Building stack monitor inoperative 50-321/81-61 7/9/81 Hydrogen analyzers
- 50-321/81-62 7/15/81 Orywell to torus
- d/p system isolated 50-321/81-63 7/17/81 HPCI AP switch setpoint drift
- 50-321/81-64 7/23/81 HPCI steam line pressure switch drift l
50-321/81-65 7/21/81 Hydrogen analyzer inoperative t
- 50-321/81-66 7/17/B1 Reactor recirc pump trip
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- 50-321/81-67 7/28/81 RHR service water pump-discharge valve failure
- 50-321/81-68 8/4/81 HPCI Turbine overspeed trip failure
- *50-321/81-69 7/23/81 Torus high water low 50-321/81-70 7/30/81 Torus high water temperature 50-321/81-71 7/23/81 Torus water level indicator inoperative
- 50-321/81-72 7/21/81 Low condenser vacuum switches Isolated
- 50 321/81 73 7/30/81 Failure to post a fire watch
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50-321/81-74 8/6/81 Off-gas flow recorder inoperative
- 50-321/81-75 8/4/81 Excessive oxygen concentration in the drywell
- 50-321/81-76 7/23/81 0xygen analyzer out of tolerance
- 50-321/81-77 7/31/81 Contamination of radwaste loading dock
- 50-321/81-78 7/21/81 High torus water temperature discharge valve failure
- 50-321/81-79 7/30/81 Inoperative PSW pump 50-321/81-80 8/11/81 H -0 analyzer reading low 2 2
- 50-321/81-81 8/6/81 RHRSW support at intake structure inadequate
- 50-321/81-82 8/20/81 HPCI steam line AP switch failure 50-321/81-83 8/20/81 RCIC high flow switch out of calibration
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out of calibration 50-321/81-86 8/27/81 Inoperative noble gas monitor
- 50-321/81-89 9/3/81
"B" PSU pump failure
- 50-321/81-90 9/29/81 RCIC exhaust diaphragm pressure switches out of calibration 50-321/81-91 9/17/81 Reactor water level switch out of calibration 50-321/81-92 9/25/81 Noble Gas monitor inoperative 50-321/81-93 9/29/81 Drywell to torus LP recorder inoperative.
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- 50-321/81-94 9/29/81 Inoperable SPGT Train "A" 50-321/81-95 10/1/81 RCIC steam line AP switch out of calibration 50-366/81-34 5/14/81 RCIC Area AT switch out of calibratier.
- 50-366/81-35 5/5/81 Torus vacuum bre.ker isolation valve failure
- 50-366/81-36 5/7/81 Diesel Generator flash field failure 50-366/81-37 5/4/81 Control Rod 50-366/81-38 5/7/81 LPCI unverter trip 50-366/81-39 5/21/81 Drywell H -0.2
- 50-366/81-40 5/5/81 Control rod accumulator low
- 50-366/81-41 5/21/81 Diesel generator trip on high crankcase pressure
- 50-366/81-42 5/21/81 Inoperable SBGT
- 50-366/81-43 5/21/81 Defective RCIC flow trans-mitter at Remote shutdown panel
- 50-366/81-44 5/22/81 Failure of HPCI liin Flow valve
- 50-366/81-45 5/28/81 Failureof two itSIVs to close in 5 seconds
- 50-366/81-46 6/11/81 Inoperative PSW pump 50-366/81-47 6/9/81 Drywell and torus temperature recorder inoperative 50-366/81-48 6/2/81 Inoperative control rod accumulator 50-366/81-49 6/25/81 Hi-Hi reactor building vent rad monitor setpoint high 50-366/81-50 6/16/81 SBGT train B not sampled
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- 50-366/81-51 6/30/81 Torus vacuum breaker valve failed open
- 50-366/81-52 6/25/81 Exceedin9 thermal limit 50-366/81-53 7/2/81 First stage pressure switches out of tolerance 50-366/81-54 6/30/81 Drywell and Torus H -0 2 2 analyzer inoperative 50-366/81-55 7/21/81 Hydrogen recombiner breaker trip
- 50-366/81-56 8/11/81 Torus water temperature greater than 95'F
- 50-366/81-57 7/2/81 PSW valve found shut 50-366/81-58 7/15/81 Torus vacuum breaker valve failed open
- 50-366/81-59 7/9/81 Torus water level indicator failure
- 50-366/81-60 7/17/81 Inboard Reactor water cleanup valve inoperative
- 50-366/81-61 7/21/81 Sample pump failure on Reactor building vent radi-ation monitor
- 50-366/81-62 7/9/81 APRii gains not adjusted within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- 50-366/81-63 7/17/81 RHRSW pump failure
- 50-366/81-64 7/17/81 Diesel Generator speed adjust switch inoperative
- 50-366/81-65 7/21/81 H -0 Analyzer inoperative
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- 50-366/81-66 7/17/81 Standby service water pump failure
- 50-366/81-67 7/21/81 Failure to check PSW valves l
- 50-366/81-68 7/15/81 RPV pressure indicator out of tolerance
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- 50-366/81-69 7/21/81 APRI Surveillance not performed as required
- 50-366/81-71 8/6/81 MSIV valve failed to close within 5 seconds
- 50-366/81-73 8/20/81 HPCI exhaust pressure switch drift
- 50-366/81-74 8/20/81 itSIV leakage control system valve failure 50-366/81-75 8/25/81 HCU accumulator low pressure condition 50-366/81-76 8/25/81 Reactor pressure isolation switch out of calibration 50-366/81-77 9/3/81 Orywell pressure and torus water level instrument out of calibration
- 50-366/81-78 9/10/81 RCIC flow controller resistor failure 50-366/81-79 9/10/81 Torus high d/P switch out of calibration
- 50-366/81-80 9/15/81 Torus to Drywell vacuum breaker indication failure
'*50-366/81-81 9/17/81 Reactor water level recorder inoperative
- 50-366/81-82 9/29/81 HPCI auxiliary oil pump failure 50-366/81-83 9/22/81 Torus water level indicator inoperative 50-366/81-84 10/1/81 HPCI steam flow AP switch out of calibration
- 50-366/81-85 9/15/81
"B" LPCI inverter trip
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- 50-366/81-86 9/25/81 HPCI tur bine exhaust pressure switch failure
- 50-366/81-87 10/6/61 Reactor water. sample outboard failed to close
- 50-366/81-88 10/6/81 HPCI discharge valve failure to open
- 50-366/81-89 10/1/81 Torus water level indicator failure
- 50-366/81-91 10/8/81 Torus vacuum relief valve failure
- 50-366/81-93 10/6/81 Main steam line pressure switch setpoint drift
- 50-356/81-95 10/6/81 SRV position indication pressure switches out of calibration 10.-
Followup on IE Circulars (Units 1 and 2)
The inspector verified that the circular was received, reviewed, and appropriate corrective action action taken or planned. These Circulars were addressed as they were issued and summarized below for record purposes.
(Closed) IEC 81-1 Design Problems Involving Indicating Pushbutton Switches Manufactured by Honeywell Incorporated.
(Closed) IEC 81-3 Inoperable Seismic Monitoring Instrumentation (Closed) IEC 81-4 Role of STA and Importance of Reporting Operational Event (Closed) IEC 81-10 Steam Voiding in the' RCS During Decay Heat Removal Cooldown.