IR 05000321/1987007
| ML20206F905 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/03/1987 |
| From: | Cantrell F, Holmesray P, Nejfelt G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20206F867 | List: |
| References | |
| TASK-2.E.4.2, TASK-2.F.1, TASK-2.K.3.16, TASK-2.K.3.18, TASK-TM 50-321-87-07, 50-321-87-7, 50-366-87-07, 50-366-87-7, IEB-83-08, IEB-83-8, NUDOCS 8704140395 | |
| Download: ML20206F905 (6) | |
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A Stc UNITED STATES oq'o NUCLEAR REGULATORY COMMISSION
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101 MARIETTA STREET.N.W.
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Report Numbers:
50-321/87-07 and 50-366/87-07 Licensee: Georgia Power Company P.O. Box 4545 Atlanta, GA 30302 Docket Numbers:
50-321 and 50-366 License Numbers:
DPR-57 and NPF-5 Facility Name: Hatch 1 and 2 Inspection Dates:
February 20 - March 27,1987
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Inspection at Hatch site near Baxley, Georgia Inspectors:
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Peter Holmes-Ray, Senior Resident Inspector Date Signed
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Gregory M. Nejfelt, Resident Inspector Datd Signed Approved by:
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/ 87 Floyd S.~Cantrell, Chief, Project Section 2B Date Signed Division of Reactor Projects SUMMARY Scope:
This routine inspection was conducted at the site in the areas of Licensee Action on Previous Enforcement Matters, Operational Safety Verification, Maintenance Observation, Plant Modification and Surveillance Observation, Reportable Occurrences and Three Mile Island (TMI) items.
Results: No violations or deviations were identified.
8704140395 870409 PDR ADOCK 05000321 O
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i REPORT DETAILS 1.
Persons Contacted Licensee Employees T. Beckham, Vice President, Plant Hatch H.C. Nix, Plant Manager
- D. Read, Plant Support Manager
- H.L. Sumner, Operations Manager
- P.E. Fornel, Maintenance Manager
- T.R. Powers, Engineering Manager R.W. Zavadoski, Health Physics and Chemistry Manager C. Coggin, General Support Manager
- H. Googe, Outages and Planning Manager
- 0.M. Fraser, site Quality Assurance (QA) Manager C.T. Moore, Training Manager S.B. Tipps, Superintendent of Regulatory Compliance K. C. Dyar, Superintendent of Nuclear Security Other licensee employees contacted included technicians, operatnrs, mechanics, security force members and office personnel.
NRC regional management on site during inspection period:
F.S. Cantrell, Chief, Project Section 2B (on March 17,1987)
- Attended exit interview 2.
Exit Interview (30703)
The inspection scope and findings were summarized on March 27, 1987, with those persons indicated in paragraph 1 above.
The licensee did not identify as proprietary any of the material provided to or reviewed by the inspector during this inspection. The licensee acknowledged the findings and took no exception.
3.
Unresolved Items *
(Closed) Unresolved Item 366/85-05-08, Failure to Perform Diesel Generator Maintenance Items. The licensee has revised the applicable procedures to include the diesel generator water test, camshaft inspection and holddown bolt check. This item was closed for Unit 1 in Report 321/86-03 and was mistakenly left open in Unit 2.
This item is closed.
- An unresolved item is a matter about which more information is required to determine whether it is acceptable or may involve a violation or deviation.
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4.
Licensee Action on previous Enforcement Matters (92702)
(Closed) Violation 85-32-02, Failure to Revise a Procedure to Reflect a DCR Modification. GPC letter of January 13, 1986, and NRC response of March 5, 1986, were reviewed. The corrective actions by the licensee are considered adequate. This item is closed.
(Closed) Violation 85-39-01, Failure to Properly Perform a Safety Clearance. GPC letter of March 17, 1986, was reviewed. The corrective actions of incorporating the causes of the flooding of the Unit 1 South East diagonal into a lesson plan and distributing this plan to licensed Operations Department personnel and to revise the existing tagout procedure as well as writing a new procedure to provide general guidelines for isolating and restoring equipment were considered adequate.
These actions were complete on March 22, 1986, when procedure 34G0-0PS-179-0S, General Guidelines for Isolating and Restoring Equipment, was effective.
This item is closed.
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5.
Operational Safety Verification (71707)
The inspectors kept themselves informed on a daily basis of the overall plant status and any significant safety matters related to plant operations. Daily discussions were held with plant management and various members of the plant operating staff. The inspectors made frequent visits to the control room. Observations included instrument readings, setpoints and recordings, status of operating systems, tags and clearances on equipment, controls and switches, annunciator alarms, adherence to limiting conditions for operation, temporary alterations in effect, daily journals and data sheet entries, control room manning, and access controls. This inspection activity included numerous informal discussions with operators and their supervisors.
Weekly, when on site, selected Engineering Safety Feature (ESF) systems were confirmed operable.
The confirmation was made by verifying the following:
accessible valve flow path alignment, power supply breaker and fuse status, instrumentation, major component leakage, lubrication, cooling, and general condition.
General plant tours were conducted on at least a biweekly basis. Portions of the control building, turbine building, reactor building, and outside areas were visited.
Observations included safety related tagout verifications, shift turnover, sampling program, housekeeping and general plant conditions, fire protection equipment, control of activities in progress, radiation protection controls, physical security, problem identification systems, and containment isolation.
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During the inspection period, the housekeeping has been maintained in an overall good condition. Isolated housekeeping problems identified by the inspectors were immediately reported to the licensee for correction; and fixed.
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In the course of the monthly activities, the resident inspectors included a review of the licensee's physical security program. The performance of various shifts of the security force was observed in the conduct of daily activities to include: protected and vital access controls, searching of personnel, packages and vehicles, badge issuance and retrieval, escorting of visitors, patrols and compensatory posts.
No violations or deviations were identified.
6.
Maintenance Observation (62703)
During the report period, the inspectors observed selected maintenance activities. The observations included a review of the work documents for adequacy, adherence to procedure, proper tagouts, adherence to technical specifications, radiological controls, observation of all or part of the actual work and/or retesting in progress, specified retest requirements, and adherence to the appropriate quality controls.
No violations or deviations were identified.
7.
Plant Modification (37700)
The inspectors observed the performance of selected plant modification Design Change Requests (DCRs). The observation included a review of the DCR for technical adequacy, conformance to Technical Specifications, verification of test instrument calibration, observation of all or part of the actual surveillances, removal from service and return to service of the system or components affected, and review of the data for acceptability based upon the acceptance criteria.
No violations or deviations were identified.
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Surveillance Testing Observations (61726)
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The inspectors observed the performance of selected surveillances.
The observation included a review of the procedure for technical adequacy, conformance to Technical Specifications, verification of test instrument
calibration, observation of all or part of the actual surveillances, removal from service and return to service of the system or components affected, and review of the data for acceptability based upon the
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acceptance criteria.
No violations or deviations were identified.
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ESF System Walkdown (71710)
The inspectors routinely conducted partial walkdowns of ESF systems. Valve and breaker / switch lineups and equipment conditions were randomly verified both locally and in the control room to ensure that lineups were in accordance with operability requirements and that equipment material conditions were satisfactory.
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Within the areas inspected, no violations or deviations were identified.
10.
IE Bulletin Followup (92703)
(Closed) IE Bulletin No. 83-08, Electrical Circuit Breakers with an Undervoltage Trip Feature In Use In Safety-Related Applications Other Than the Reactor Trip System. By letter dated December 14, 1984 GPC committed to perform periodic testing of the undervoltage trip attachment on the Westinghouse 50DHP250 breakers.
This preventive maintenance is being performed by procedure 52PM-R22-001-0S, 4160 Volt AC Switchgear and Associated Electrical Components Preventive Maintenance.
This item is i
closed.
11. Reportable Occurrences (90712 & 92700)
A number of Licensee Event Reports (LERs) were reviewed for potential
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generic impact, to detect trends, and to determine 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 the public health and safety were of utmost consideration.
Unit 1:
81-134*,81-135, 85-28**, 85-32**
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Unit 2:
85-28**, 85-38**
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Unit-1 LER 81-134, concerning a failure to establish a fire watch,
has been corrected by procedure 40AC-FPX-001-0, Revision 1, Section 4.5.
The Operations Department is required to maintain control of fire protection systems and components, which are removed and are
returned to service (e.g., establishing a fire watch).
These LERs, involving missed TS surveillances, were collective closed
in IE Report 50-321,366/86-28. The licensee has partially addressed these and other missed surveillances in terms of Procedure Upgrade Program (PUP) milestones and completion dates in their response of December 12, 1986, to violation 50-321,366/86-28-02.
NRC letter of i
January 12, 1987, has requested additional information, 12. Operating Reactor Events (93702)
The inspectors reviewed activities associated with the below listed reactor events.
The review included determination of cause, safety significance, performance of personnel and systems,and corrective action.
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The inspectors examined instrument recordings, computer printouts, operations journal entries, scram reports and had discussions with operations maintenance and engineering support personnel as appropriate.
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On March 20, 1987, operations was attempting to drain the Reactor Water Cleanup (RWCU) heat exchanger for maintenance when RWCU isolated on room high temperature.
The isolation was caused by a seat leak on a heat exchanger isolation valve (2G31-F042) and the RWCU check valve (2G31-F001-and 2G31-F004) did not stop the follow through the open heater drain valves (2G31-F018C and 2G31-F019C).
The drain valves were shut to stop the flow. Leak Repair Company personnel injected material between the drain valves to stop the leakage.
The drain valves are scheduled for replacement in the next outage (January 1988). The resident inspectors will follow the licensee's analysis of the backleakage from the feed system and any corrective action.
Within the areas inspected, no violations or deviations were identified.
13. Three Mile Island Items (item numbers are from NUREG 0737)
Item II.E.4.2.7 concerns closure of the containment purge and vent lines on a high radiation signal.
DCRs83-167 and 83-168 for Units 1 and 2 modified the logic to provide closure of the 18" purge and vent valves on a high radiation signal.
The two inch purge and vent valves were not modified.
Per a telephone conversation between the Senior Resident Inspector, the Licensing Project Manager, NRR and Mr. E. Reeves, NRR on March 26, 1987, Mr. Reeves stated that no requirement to modify the two inch purge and vent valves for closure on a high radiation signal exists.
This item remains open pending issue of the Technical Specifications (TS)
amendments to incorporate the closure logic into the TS.
Item II.F.1.6 was reviewed for completion of the post accident hydrogen monitoring capability.
The only equipment qualification (EQ) work remained outstanding to complete this item.
Design ~ Change Request (DCR)81-132 for Unit 1 and DCR 81-165 for Unit 2 performed the EQ work.
DCR 81-132 and DCR 81-165 are both field complete and operable but are not yet closed. The inspectors will follow the closecut action for the two DCRs.
This item remains open pending review of the completed DCR packages.
Item II.K.3.16.b included Low Low Set (LLS) relief valve logic, lowered Main Steam Isolation Valve (MSIV) water level setpoint, increased simmer margin (no change required at Hatch), Safety Relief Valve (SRV) preventive maintenance program, installation of the Analog Transmitter Trip System (ATTS) and improved SRV pneumatic supply. ATTS and LLS were installed by DCR 81-138 for Unit 1 and DCR 81-139 for Ur.it 2.
DCR 81-138 is field complete and in the process of close out while DCR 81-139 is closed.
Technical Specifications for Units 1 and 2 were amended to reflect LLS.
SRV pneumatics were modified by DCRs81-111 and 81-112 which are complete and closed.
This item remains open pending review of DCR 81-138 upon closure of that DCR.
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Item II.K.3.18.c was discussed in NRC Inspection Report 321,366/87-02.
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