IR 05000280/1979021
| ML18116A213 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/30/1979 |
| From: | Ewald S, Jenkins G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18116A212 | List: |
| References | |
| 50-280-79-21, 50-281-79-32, NUDOCS 7907300028 | |
| Download: ML18116A213 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303
~eport Nos.: 50-280/79-21 and 50-281/79-32 Licensee: Virginia Electric and Power Company Richmond, Virginia 23261 Facility Name: Surry Power Station Docket Nos.: 50-280 and 50-281 License Nos.: DPR-32 and DPR-37 Surry, Virginia Section Chief, FF&MS Branch SUMMARY Inspection on Hay 7-11, 14-15, 1979 Areas Inspected sho/71 Date Signed S-~o/7y1 DateSigned This routine unannounced inspection involved 58 inspector-hours onsite in the areas of radiation protection including licensee audits, portable instrument and dosimeter calibrations, facility tours, and concerns expressed by worker Results No apparent items of noncompliance or deviations were identified.
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DETAILS Persons Contacted Licensee Employees
- W. L. Stewart, Station Manager
- T. A. Peebles, Superintendant Technical Services
- R. M. Smith, Health Physics Supervisor
- A. L. Parrish, III, SGRP Project Manager P. P. Nottingham, IV, SGRP, Assistant Supervisor Health Physics C. E. Foltz, Assistant Supervisor, Health Physics M. R. Beckham, Assistant Supervisor, Health Physics H.F. McCallum, Assistant Supervisor, Health Physics S. Sarver, System Health Physicist
- G. E. Kane, Operating Supervisor Other licensee employees contacted included 12 technicians, three operatores, three security force members, and three office personne NRC Resident Inspector
- D. L. Burke
- Attended exit interview Exit Interview The inspection scope and findings were summarized on May 11 and 15, 1979 with those persons indicated in Paragraph 1 abov.
Licensee Action on Previous Inspection Findings Not inspecte.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviation New unresolved items identified during this inspection are discussed in paragraph.
Licensee Audits The licensee is required by Section 18.5 of the Station Quality Assurance Manual to conduct a yearly audit of the Health Physics Progra The inspector reviewed Audit Report No. 579-3, conducted April 20, 1979, and noted no discrepancies were identified in the audit repor I~
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-2-Portable Instruments The inspector reviewed revisions to portable instrument calibration procedures and selected five instruments and one air sampler ready for use and reviewed calibration records for the period April 10, 1978 through May 11, 197 The inspector also verified current calibration stickers on equipment at seven frisking stations. The inspector noted records of an instrument response to known radiation levels not yet filed with the individual instrument record The inspector had no questions relating to portable instrument calibra-tion The inspector reviewed source and drift check records of pocket dosimeters for the previous six month The inspector verified acceptance criteria on dosimeter performance are being properly implemented and are consistent with Regulatory Guide The inspector selected four low range (200 mrem) and three high range (1000 mrem) dosimeters from the ready to issue bins and verified source and drift checks had been performed within the previous six month The inspector had no questions relative to pocket dosimeter source and drift check Procedures The inspector reviewed revisions to station health physics procedures approved during the period May 1978 through April 197 Most of the revisions dealt with instrument calibrations. The inspector verified all procedures had been reviewed and approved as per Technical Specification 6.4.E and had no questions relative to station health physics procedure The licensee has issued a separate SGRP Health Physics Manual and Procedures specific to the SGRP. The inspector has reviewed these procedures as they were develope The basic manual was approved March 29, 1978 and revisions and additions through March 16, 1979 have been examine The inspector had no questions relative to the manual at this tim.
Facility Tours The inspector toured the Auxiliary Building, Fuel Building, Decon Building, Unit 2 Containment, Hot Machine Shop and the outside areas of the Radiation Controlled Area (RCA).
The inspector performed independent radiation level surveys and found no unposted area During these tours, the inspector observed preparations for lifting the B Steam Generator and reactor coolant pipe decontamination operation The inspector observed removal and storage operations for the Band A steam generator During tours of the hot machine shop, the inspector observed weld preparation work on a section of reactor coolant pip l
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.. ' -.. During tours of the turbine building and outside RCA, the inspector noted a door exiting the turbine building, just past the emergency diesel generators, was not posted as an entrance to the RCA. Pocket and TLD dosimetry is required prior to entry to the RCA. The door gave access between two security fences and, prior to entering the RCA proper, an individual would be required to pass a security guar An Assistant Supervisor of Health Physics stated he would assure the posted guard was aware of his responsibility for controlling RCA access and also established a frisking station for workers entering the turbine building from this area. The inspector had no other questions relative to the above item During a tour of the fuel building, the inspector noted a hand hole had been cut in the trap door that provided access to a pipe tunnel between the Auxiliary Building, Fuel Building, P.G. Pumphouse and Decon Building. This was the same trap door discussed in RII Report Nos. 50-280/79-9 and 50-281/79-10, Details paragraph 9.f. The trap door was properly posted as accessing areas with radiation levels in excess of 1 rem/h Even though the trap door was locked, the hand hole would allow an individual to reach under the floor plate and remove the nut and bolt securing the door's has The inspector removed the hasp in approximately 15 seconds and noted the door had been tack welded close :;
The inspector discussed the trap door with health physics and opera-tions representatives and was told the trap door had been welded closed within the last few day Operations representatives stated the hand hole had been cut in the trap door to allow personnel entering the pipe tunnel to lock the door behind them and provide egress capability as required by 10 CFR 20.203(c)(3). The inspector reviewed Maintenance Report (MR) No. 0902160801 indicating the hole was cut February 20, 197 The HR also indicated a Flame Permit was obtained and the work performed under the standing Radiation Work Permit for general access to the Fuel Buildin The inspector expressed concern over the adequacy of the lock with the hand hole, to prevent unauthorized access to the high radiation area The inspector acknowledged licensee comments that the trap door was locked and a deliberate action was required to defeat the loc The inspector also expressed concern that the hole had been cut without a special RWP in that contamination levels were in excess of 30,000 dpm/100 cm. Discussions with licensee representa-tives revealed the decision as to applicability of the standing RWP versus generating a special RWP is made by the particular group forema The inspector stated that the issue of RWP applicability and adequacy of the lock would be unresolved (280/79-21-01; 281/79-32-01) pending further review by the inspector.