IR 05000280/1979020
| ML18116A190 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/19/1979 |
| From: | Burke D, Cantrell F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18116A189 | List: |
| References | |
| 50-280-79-20, 50-281-79-31, NUDOCS 7907240279 | |
| Download: ML18116A190 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report Nos. 50-280/79-20 and 50-281/79-31 Licensee:
Virginia Electric and Power Company Richmond, Virginia 23261 Facility Name: Surry Units 1 and 2 Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37 Inspectio~, :irginia Inspector. :-:s:/Br4 flj/_~:{;;
D. J. Burke SUMMARY Inspection on March 19 through April 27, 1979 Areas Inspected D e Signed
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Date Signed This routine, unannounced inspection involved 115 inspector-hours on-site in the areas of plant operations, plant physical protection barriers, plant maintenance, including the Unit 2 steam generator replacement outage work, radiation protec-tion, and followup of Licensee Event Reports and IE Bulletin 79-06 Results Of the six areas inspected, no apparent items of noncompliance or deviations were identified.
W. L. Stewart, Station Manager A. L. Parrish, Project Manager, SGRP
- J. L. Wilson, Superintendent Operations
- T. A. Peebles, Superintendent - Technical Services
- R. F. Saunders, Superintendent Maintenance
- R. M. Smith, Supervisor, Health Physics
- R. L. Baldwin, Supervisor, Administrative Services G. Kane, Operating Supervisor
- F. L. Rentz, Resident QC Engineer Other licensee employees contacted during this inspection included control room operators, shift supervisors, QC, engineering, HP, plant maintenance, security and administrative personne Other Organizations Commonwealth of Virginia Bureau of Occupational Health A. C. McNeer, Radiation Specialist Commonwealth of Virginia Department of Labor and Industry G. L. Weaver, Industrial Safety Representative
- Attended exit intervie Management Interviews The scope and findings were summarized on a weekly basis with those persons indicated in Paragraph 1 abov The individual radiation overexposure occurrence of April 14, 1979, is covered in a separate inspection repor Licensee Action on Previous Inspection Findings Not inspecte Unresolved Items Unresolved items were not identified during this inspection.
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-2-Review of Reportable Occurrences The inspector reviewed the Reportable Occurrence (RO) reports listed below to ascertain that NRC reporting requirements were being met and to deter-mine the appropriateness of corrective action taken and planne Certain Licensee Event Reports (I.ER) were reviewed in greater detail to verify corrective action and determine compliance with the Technical Specifica-tions and other regulatory requirement The review included examination of log books, internal correspondence and records, review of SNSOC meeting minutes, and discussions with various staff member Within the areas inspected, no items of noncompliance or deviations were identifie LER 280/79-02 concerned an inoperable electrical penetration seal between the turbine building and the emergency switchgear room; the penetration was immediately resealed and verified operable by local leak testin This I.ER is close I.ER 280/79-03 addressed the main steam flow instrumentation calibra-tion error which was the result of a setpoint change due to increased steam generator tube pluggin The error was less than 2% up to 20%
of full load, but the instrumentation was accurate between 20% and 110%,
A 2% conservative bias is being incorporated into the setpoint to accommodate slight instrument errors or drift. This item is close LER 280/79-05 concerned the malfunction of radiation monitor recorder RR-17 Although the recorder stopped printing until the seized gear shaft bushing was repaired, the radiation monitors were operable and were monitored by the operating staff. This LER is close LER 280/79-06 concerned the discovery of an unsealed fire barrier and an untested penetration seal in the control room envelop The in-spector verified that the fire barrier conduits were sealed and that the penetration seals were acceptably teste This LER is close LER 281/79-01 addressed the inability to leak test the containment personnel access hatch after use (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />), due to mechanical prob-lems with the inner doo The outer door was sealed and administra-tively controlled to prevent opening, which insured containment integrit The door was subsequently repaire This item is close LER 281/79-02 addressed the drift which occurred in pressurizer pressure channel I instrumentation and caused the channel to read some 5 psi hig The pressure transmitter was replaced and the channel returned to normal; the protective instrumentation trips were also returned to normal mode This LER is closed.
- LER 281/79-03 concerned the failure to perform the "after entry" test on the containment equipment hatch airlock within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> leak rate test was performed satisfactorily four hours after the This item is close leak The 7 LER 281/79-04 addressed the conservative drift in seven of the main steam safety valve setpoints found during periodic testing; the maximum deviation was 7%.
The remainder of the 15 valves were within the+ 3% as required, and all valves were reset as require This item is close LER 281/79-05 addressed the failure of service water valve 203C to cycle electrically during shutdown testin The valve was repaired and bench-tested; post-installation testing is planne This item is close LER 281/79-06 addressed the failure of service water valve 203D to cycle during the same periodic test (8.SA).
The valve was repaire This item is close.
LER 281/79-07 concerned the failure of ventilation damper 103A to close during the SI initiation functional test. Subsequently, the damper operated properl This item is close LER 281/79-09 concerned the discovery that three hydraulic snubbers were not specified on periodic test 39A-1 and 39B-1 for visually inspecting the snubber The snubbers were inspected and determined operable, and were added to the PT' This item is close.
IE Bulletin No.79-06A The inspector verified that the licensee received IE Bulletin 79-06A, which identifies actions to be taken by Westinghouse pressurized water reactors as a result of the Three Mile Island Unit 2 inciden The licensee's response to the Bulletin is being evaluate The inspector, along with the other NRC personnel, participated in the review and discussions conducted at the site on the incident and the IE Bulletins associated with the TMI event Surry Unit 1 remains shutdown pending pipe stress analysis reso-lution and Unit 2 is in the midst of the steam generator replacement projec Plant Maintenance The inspector reviewed certain Unit 1 and 2 plant maintenance to verify that work was performed in accordance with the Technical Specifications and the applicable procedure Within the areas inspected, no items of noncom-pliance were identifie The licensee stated that certain SGRP procedures would be revised to include stay times and other precautions appropriate to reduce the potential for heat exhaustion when working in or around equip-ment enclosed by contamination control tent '.
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-4-Plant Operations The inspector toured the Unit 1 and 2 control rooms and certain plant areas to observe that monitoring equipment and plant instrumentation was function-ing as required, and that the facility operations were in accordance with the Technical Specification Plant logs and records were also reviewe Within the areas inspected, no items of noncompliance or deviations were identifie The inspector verified that the licensee had a contingency plan for ade-quately staffing the site in case the negotiations between the IBEW and VEPCO were interrupte Plant Physical Protection The inspector verified the following by observation: Gates and doors in protected and vital area barriers were closed and locked when not attende Isolation zones described in the physical security plans were not compromised or obstructe Personnel were properly identified, searched, authorized, badged and escorted as necessary for plant access contro Meeting with Surry County Board of Supervisors The inspector and R. C. Lewis, Acting Chief, RONS Branch met with the Surry County Board of Supervisors on April 19, 197 The meeting was attended by the six supervisors and about twenty local resident Issues discussed included NRC/IE related activities, the Resident Inspector Program, and activities occurring at the plant and the current plant statu NRC personnel responded to questions from the supervisors and the local residents *