IR 05000321/1981023
| ML20039B497 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/16/1981 |
| From: | Brownlee V, Rogers R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20039B472 | List: |
| References | |
| TASK-2.D.1, TASK-3.A.2.1, TASK-TM 50-321-81-23, 50-366-81-23, IEB-79-25, IEB-79-26, IEB-80-07, IEB-80-13, IEB-80-24, IEB-80-7, IEB-81-01, IEB-81-02, IEB-81-03, IEB-81-1, IEB-81-2, IEB-81-3, NUDOCS 8112230134 | |
| Download: ML20039B497 (6) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
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REGION 11 o,
101 MARIETTA ST., N.W., SUITE 3100 g
ATLANTA, GEORGIA 30303 Report Nos. 50-321/81-23 and 50-366/81-23
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Licensee: Georgia Power Company 270 Peachtree Street Atlanta, GA 30303 Facility Name: Hatch 1 and 2 Docket Nos. 50-321 and 50-366 License Nos. DPR-67 and NPF-5
Inspection at Hatch site near Baxley, Georgia -
Inspector: /j Y 8.~ e
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u/WA R.' F. Rogersw Date Signed
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Approved by:
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V. L. Brgwnlee, Chief, Reactor Projects Datie Signed Section 2B, Division of Resident and Reactor Project Inspection
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SUMMARY Inspection on August 21 - September 28, 1981 Areas Inspected'
This inspection involved 150 inspector-hours on site in the areas of technical specification compliance, housekeeping, operator performance, overall plant operations, quality assurance practices, station and corporate management
. practices, corrective and preventive maintenance activities, site security
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procedures, radiation control activities, surveillance activities, NUREG 0737, action items, previous enforcement items, and IE Bulletins and circulars.
- Resul ts Of the 12 areas inspected,- no apparent violations or deviations were identified in 11~ areas, one violation was identified in one area (Failure to make a timely report - paragraph 5).
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8112230134 01121E DRADOCK05000g
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DETAILS 1.
Persons Contacted Licensee Employees
- M. itanry, Plant fianager
- T. Greene, Assistant Plant Manager S. Baxley, Superintendent of Operations R. Nix, Superintendent of Maintenance C. Coggins, Superintendent of Engineering Services W. Rogers, Health Physicist C. Belflower, 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 September 11 and 28, 1981, with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings a.
Violation (Closed) (321/81-21-01) Failure to follow procedure requiring locking of a valve associated with condenser low vacuum switches. The inspector verified that the licensee completed the actions outlined in their response dated September 16, 1981. This item is closed.
(Closed) (366/81-21-01) Failure to follow technical specification 3.7.1.2 requiring plant shutdown with one Plant Service Water (PSW) loop inoperable. The licensee has completed corrective actions outlined in his September 16, 1981 response. This item is closed.
(Closed) (366/81-21-02) Failure to perform ECCS valve surveillance required by technical specification 4.7.1.2.b.
The licensee has approprimately addressed this item as described in his September 16, 1981 response to the NRC.
This item is closed.
(Closed) (321, 366/81-11-01) Failure tc include cause of nonconformance to be documented in licensee procedure HNP-801. This procedure has been suitably revised in Revision 14.
This item is close.
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b.
Unresolved Items (Closed) (366/78-32-01) Evaluation of snubber piston settings to determine if they are acceptable. The licensee has reviewed this item and found that cold midrange settings do not affect the basis for FSAR tion 14.8.15.
This item is closed, c.
Open Items (Closed) (321, 366/80-21-02) Replacement of International Nuclear Safeguards (INS) snubbers. These snubbers have been replaced on both units. This item is c osed.
(Closed) (32I, 366/80-44-02) Evaluation of 2500 series snubber test stand per IEC 78-07.
This evaluation has been performed. This item is closed.
(Closed) (321, 366/80-44-04) Erratic 50 kip snubber behavior. This behavior was due to the test stand rather than the snubber. This item is closed.
(Closed) (321/78-27-05) Heat load on control and power cable trays.
This was evaluated with temperature data taken the summer of 1981 and determined not to be a problem.
This item is closed.
4.
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, instrument 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 alertness and demeanor during plant tours.
During normal events, operator perf ormance and response actions were observed and evaluated.
The inspector conducted random off-hours inspections during the reporting intervals to assure that operations and security remained at an acceptable level.
Shift turnovers '.iere observed to verify that they were conducted in accordance with approved licensee procedures.
During follewup of a reactor scram event of September 9,1981, the inspector noted that although the event occurred at 1124 hours0.013 days <br />0.312 hours <br />0.00186 weeks <br />4.27682e-4 months <br />, the NRC operations center in Bethesda was not notified until 1248 which is in excess of the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> limit required by 10 CFR 50.72. This is a violation (366/81-23-01).
It took in excess of three hours to inform the resident inspecto *
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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 control: were properly established, critical clean areas were being controlled in accordance with procedures, excess equipment er material is stored properly and combustible material and debris were disrosed of expeditiously. During tours the inspector looked for the existence of unusual fluid leaks, piping vibrations, pipe hanger ano seismic restraint settings, various valve and breaker positions, equipm.ent caution and danger tags and component positions, adequacy of fire fighting equipment and instrument calibration dates. Some tours were conducted on backshifts.
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 (LC0's) and results of selected surveillance tests. These verifications were accomplished by direct observation 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 occurrences as they happened.
Within the areas inspected, violations were identified in the areas of HPCI operability, but these will be covered in a subsequent special report.
8.
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 included the organiza-tion 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 areas inspected, no violations or deviations were identified.
9.
NRC Task Action Plant Requirements Review (NUREG 0737) (Units 1 and 2)
The inspector has reviewed the licensees implementation of various requirements associated with the NRC Task Action Plant (TAP) in response to the Three liile Island accident. The current status is summarized below.
Item numbers refer to TAP line item.
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Item No.
Description NUREG 0737 Action Date Completed II.D.1.2.b SRV Plant 10/1/81 Yes Specific Report III.A.2.1 Upgrade 3/1/81 Yes Emergency Plans 10.
Followup on IE Bulletins and Circulars (Units 1 and 2)
For the following IE Bulletins and Circulars, the inspector verified that the response, if requi ed, was timely, included the required information, contained adequate cce.nitments and that corrective action as described in the written responses was completed.
For circulars, the inspector verified that the circular was received, reviewed, and appropriate corrective action taken or planned. These Bulletins and Circulars are addressed as they are issued and summarized below for record purposes.
a.
IE Bulletins (Closed) IEB 79-25 Failures of Westinghouse BFD relays in safety-related systems. Based on the licensee response dated December 21, 1979, and review by the inspector, this type of relay is not in use at Hatch. This item is closed.
(Closed) IEB 79-26 Boron loss from BWR control blades. The licensee
performed subcriticality tests on both units and determined that no
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control blade segment exceeds 25 percent boron 10 average depletion.
This item is closed.
(Closed) IEB 80-07 BWR jet pump assembly failure. The licensee has performed the required visual inspections on both units with no problems noted. This item is closed.
(Closed) IEB 80-13 Tracking in core spray spargers.
The licensee has performed the required visual inspections on both units with no problems noted.
This item is closed.
(Closed) IEB 80-24 Water leakage inside containment. As described in their responses dated December 1, 1980, January 5, 1981, and February 10, 1981, Hatch has taken actions to address the immediate and long tenn aspects of this concern. The Mark-I BWR containment is not particularly susceptable to a flooding event. This item is closed.
(Closed) IEB 81-01 Surveillance of mechanical snubbers. The licensee has completed actions in response to this bulletin and described in their letters dated March 13 and July 31, 1981. All International Safeguards Corporation (INC) mechanical snubbers have been replaced by the Pacific Scientific brand. This item is closed for both Units, o
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(Closed) IEB 31-02 Failure of gate valves to close against differential pressure.
The licensee does not have ilestin9nouse valves of the type referenced installed in either unit. This item is closed.
(Closed) IEB 81-03 Flow blockage of cooling water to safety system components. Mussels are not present in the Altamana river.
Clams though present do not appear to be a problem.
The licensees response dated !!ay 22, 1981 discusses the reasons. This item is closed.
b.
IE Circulars For the IE Circulars listed below, the inspection verified that the circular was received by the licensee management, that a review for applicability was performed, and that if the circular were applicable to the facility appropriate corrective actions were taken or were
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scheduled to be taken.
(Closed) IEC 79-18 Proper installation of Target Rock safety-relief valves.
(Closed) IEC 80-01 Service advice for General Electric induction disc relays.
(Closed) IEC 80-03 Protection from toxic gas hazards.
(Closed) IEC 80-04 Securing of threaded locking devices on safety-related equipment.
(Closed) IEC 80-05 Emergency diescl-generator lubricating oil addition and onsite supply.
(Closed) IEC 80-08 RPS response time.
(Closed) IEC 80-10 Failure to maintain environmental qualification of equipment.
(Closed) IEC 80-11 Emergency diesel generator lube oil cooler failures.
(Closed) IEC 80-12 Actuator key problems.
(Closed) IEC 80-16 Operational deficiencies in Rosemount 'adel 510 DV
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trip units and flodel 1152 pressure transmitters.
(Closed) IEC 80-18 10 CFR 50.59 safety evaluations for changes to radioactive waste treatment systems.
(Closed) IEC 80-20 Changes in safe-slab tank dimensions.
(Closed) IEC 81-21 Regulation of Refueling crews.
(Closed) IEC 80-22 Confirmation of employee qualifications.