IR 05000272/1982029
| ML20028D533 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/24/1982 |
| From: | Dan Collins, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20028D530 | List: |
| References | |
| 50-272-82-29, 50-311-82-27, NUDOCS 8301190231 | |
| Download: ML20028D533 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-272/82-29 50-311/82-27 Docket No.
50-272 50-311 License No. DPR-70 & DPR-75 Priority
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Category C
Licensee:
Public Service Electric and Gas Company Mail Code TI5A, P.O. Box 570 Newark, New Jersey 07101 Facility Name: Salem Nuclear Generating Station Units 1 and 2 Inspection At: Hancock's Bridge, New Jersey Inspection Conduc
- November _1-5, 1982
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Inspectors:
D.J.Collin/s'RadiationSpecialist,
'date signed Facilities Radiation Protection Section Approved by: M.
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R. 'M. Shah 6aky, Chieff Facil'1 ties daf.e s'ig'ned Radiation Protection Section Inspection Summary:
Inspection on November 1-5, 1982 (Combined Inspection Report No. 50-272/82-29, 50-311/82-27)
Areas Inspected:
Routine, unannounced safety inspection on routine and back j
shif ts by a region-based inspector of whole body counting; respirator fit
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testing; dosimetry records; Radiation Exposure Permits (REPS); radiological (
surveys; high radiation area controls;'previously identified items and non-compliance corrective actions; and outage ALARA actions. Additionally, the
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inspector reviewed Health Physics actions connected with the October 22, 1982
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service air system contamination. The inspection required 51 inspector-hours on-site.
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Results: No violations were identified.
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8301190231 830106
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DETAILS 1.
Persons Contacted 1.1 Public Service Electric and Gas Company L. Adler, Radiation Protection Supervisor
- W. L. Britz, Radiation Protection Manager, PSE&G J. Cislo, Radiation Protection Supervisor
- J. M. Ortscoll, Assistant General Superintendent, Salem W. Ferguson, Senior Radiation Protection Supervisor F. McFadden, Instructor
- J. M. O'Connor, Senior Radiation Protection Engineer, Salem 1.2 Nuclear Regulatory Commission
- L. J. Norrholm, Senior Resident Inspector R. J. Summers, Resident Inspector 1.3 Additional licensee and contractor perso.'nel were contacted during the course of the inspection.
- Attended exit interview on November 5, 1982.
2.
Licensee Actions on Previously Identified Items 2.1 (Closed) Infraction (79-31-02):
Failure to maintain document con-
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trol and adequate review of procedures. The inspector reviewed the corrective actions identified in the licensee's response dated February 11, 1980. The actions were verified and found to be adequate.
2.2 (Closed) Inspector Followup Item (79-31-06):
Review document control.
The shipping documents are controlled by the Senior Radiation Protec-tion Engineer and are listed in the licensee's procedures as references.
The procedures direct that current information be used in preparing radwaste shf:ments. This action was found to be adequate.
3.
Service Air System Contamination
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During a scheduled air system outage on October 22, 1982, a quantity of radioactively contaminated water leaked from the Refueling Water Storage Tank (RWST) through a temporary air line, into the Station Service Air i
System.
RWST water radioactivity was 6.8E-6 microcuries per milliliter (pCi/ml) of cesium-134, ari 7.2E-6 pCi/ml of cesium-137.
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The contamination was discovered when water leakage into the Station
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Service Air System caused the failure of air-operated tools in the Reactor Building (RB). Air samplers running in the 0.B area showed no increases in air radioactivity. No use of the serv '-:e air system for breathing purposes had been made.
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Public Service Electric & Gas Co.
The air system was blown dry at low points. The licensee operated a continuous air sampler at a valve in the service air system. No detectable activity was identified in the air from October 28 through November-3, 1982.
A temporary air line was installed from the uncontaminated turbine building compressor receivers for use as a source of breathing air for steam generator entries. Air samples at the local manifolds verified that there was no detectable radioactivity in that air system.
Whole body counts of the workers involved showed no detectable uptakes of radioactise material.
The licensee continues to operate the air sampler and will initiate a procedure change to the breathing air system procedure to provide for evaluation of breathing air quality prior to use.
Consider-ation is being given to using a particulate filter system at the breathing air system connection.
No violations were identified.
4.
Exposure Control 4.1 The inspector selectively reviewed copies of daily computer printouts which listed dosimetry information incorporating thermoluminscent dosimeter and self-reader dosimeter results, and quarterly and annual accumulated exposures for station and contractor employees.
The inspector also reviewed completed Forms NRC-4, Forms NRC-5 and termination reports.
No violations were identified.
4.2 The inspector reviewed the operation and calibration records of the whole body counting and respirator fit testing systems used at the station.
The records and discussions with the operators indicated the systems are operated in accord with procedures and appropriate actions are taken when discrepancies are identified.
No violations were identified.
5.
Radiation Exposure Permits and Plant Tours The inspector reviewed active Radiation Exposure Permits (REPS) and Extended Radiation Exposure Permits (EREPs) for the outage to verify the appropriateness of the radiation protection requirements based upon work scope, location, and radiological conditions.
During plant tours, the inspector observed the adherance of radiation workers to the REP and EREP requirements as established. The inspector measured exposure rates at various locations in determining that posting was appropriate, surveys were adequate to evaluate the hazards involved, and REPS were written using the latest available and appropriate information.
No violations were identifie....
Public Service Electric & Gas Co.
6.
High Radiation Area Controls The inspector reviewed the controls placed on high radiation areas by means of procedure review, records review and interviews.
No violations were identified.
7.
Outage Task Planning Licensee man-rem exposure for the outage was reviewed. Preliminary data indicated that the total man-rem exposure goal for the entire outage was approximately 330 man-rem. Approximately one third of the outage had elapsed at the time of the inspection. With approximately 90% of the steam generator tasks completed, the licensee had expended 76.38 man-rem against a projected 116.5 man-rem. Overall performance has been 104.5 man-rem versus a projected 295 man-rem.
Aiding the effort to maintain exposures as low as reasonably achievable (ALARA) has been the placement of approximately 7500 pounds of temporary lead shielding in the Reactor Building.
The shielding has been placed with considerations given to weight, support, exposure expended to install and remove, and total man-hours expected in the areas.
Locations have been recorded to aid in removal at the completion of work.
No violations were identified.
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Exit Interview An exit interview was conducted at the conclusion of the inspection on November 5,1982 (personnel present are noted in paragraph 1). The inspector summarized the scope and findings of the inspection.
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