IR 05000272/1982004
| ML18087A495 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/13/1982 |
| From: | Greenman E, Plumlee K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18087A493 | List: |
| References | |
| 50-272-82-04, 50-272-82-4, 50-311-82-04, 50-311-82-4, NUDOCS 8209300290 | |
| Download: ML18087A495 (10) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
50-272/82-04 Report N /82-04 50-272 Docket N DPR-70 License No. DPR-75 Priority Licensee:
Public Service Electric and Gas Company 80 Park Plaza - 15A Newark, New Jersey 07101 Category C
Facility Name:
Salem Nuclear Generating Station, Units 1 & 2 Inspection at:
Hancocks Bridge, New Jersey Inspection conducted:
January 18-21, 1982 Inspectors:
Approved by:
ate Summary:
Ins ection on January 18-21, 198 Combined Re ort No. 50-272/82-04; 50-311/82-04)
reas Inspected:
Routine, unannounced inspection of radiation protection during Unit 1 refueling including:
Licensee actions on previously identified items, procedures, planning and preparations, training, exposure control, respiratory protection program, posting, radioactive and contaminated material control, surveys, independent measurements, and steam generator moisture carryover measuremen The inspection involved 33 inspector-hours on site by one NRC region based inspecto Results:
No violations were identifie *
DETAILS Persons Contacted W. Britz, Corporate Health Physicist
- A. Darelius, Station Quality Assurance Engineer
- J. Driscoll, Assistant General Manager, Salem Operations
- H. Midura, General Manager, Salem Operations
- J. O'Connor, Radiation Protection Senior Supervisor A. Oguruk, Technical Supervisor
- J. Stillman, Station Quality Assurance Engineer
- denotes presence at the exit interview conducted January 21, 198.
Licensee Action on Previously Identified Items (Closed) Inspector Follow Item (272/79-JS-02):
Unit 2 radiation area prior to fuel loadin The inspector conducted a survey of several areas in and near Unit No improperly controlled radiation areas, contaminated areas, or unlocked High Radiation Area entrances were identifie Controls were verified to be adequate.
(Closed) Violation (311/81-23-01):
Steam Generator Blowdown Monitors inoperable during moisture carryover tes Observation during a retest, and discussions with licensee representatives, indicated that the blowdown was terminated until decay and dissipation lowered tracer concentration to acceptable value The steam generator blowdown monitor trips were adjusted during the retest, but the required conditions were maintaine (paragraph 11). Radiation Protection Procedures The inspector toured the facility to review the licensee's procedural control of radiation work pursuant to the requirements of Technical Specifications Section 6.8, "Procedures," and 6.11, "Radiation Protection Program," during the outag The inspector observed Unit 1 steam generator work, pump and valve maintenance, and refueling activitie The radiation protection procedures were reviewed during inspections 50-272/81-20 and 50-272/80-0 Subsequent changes to these procedures have been reviewe No changes were made or planned in the routine radiation protection procedures with respect to outage activitie The inspector reviewed ten inspection, surveillance, maintenance, and modification procedures to verify these had received ALARA reviews (Details, 4.c and 6.c).
Some of these procedures such as the steam generator inspection procedure, were adapted from previous outage *
The ALARA Supervisor stated he had typically six ALARA Engineers available full-time, and two additional engineers routinely involved in dose-assessment who were available on a priority basis, to review procedure Routine ALARA reviews required about one shift and unusual jobs requiring partic~lar attention to access, shielding, ventilation, or other details were reviewed within two or three day The review and authorization of procedures for the outage, and the outage procedure plan, complied with the licensee's administrative procedures and the technical specification No violations were identifie.
Planning and Preparation Increased Health Physics Staff Technical Specification Section 6.3.1 requires that each member of the facility staff meet the minimum qualifications of ANSI N18.l-1971 for comparable position The Radiation Protection Senior Supervisor stated that, as of January 19, 1981, he headed a department of about 154 personne This included seven supervisors and technical assistants; about 60 personnel required for routine two-unit operation (radiation protection technicians, chemists, clerks, etc.); and 14 personnel required for non-routine job About 42 of the 154 were PSE&G employees, including a few who were in full-time apprentice trainin About 110 were contracted health physics personne The licensee representative stated four more PSE&G personnel were planned for the staf The inspector verified by review of ten contractor and five PSE&G personnel files (including resumes, training records, and job assignments)
that the work assignments were consisten~ with the individual's experience and trainin The inspector also interviewed five contractor employees and five PSE&G employees to verify they had received the training indicated by the record No violations were identifie Radiation Protection-Related Staff A licensee representative stated that a 60-man contract crew was on site to perform housekeeping, collection of trash and contaminated materials, waste packaging, and area decontaminatio The inspector observed their work and interviewed two of these individual *
A four-man crew was contracted to operate a leased portable (trailer-mounted) protective clothing laundry facility during the outag The inspector toured the laundry facility, observed the operation, and interviewed one of these individual No inadequate training or qualifications, and no failures to follow procedures were identifie Special training and equipment The inspector verified by review of selected resumes that the personnel*
assigned to the tasks listed below had previous experience on those job In addition, the licensee provided training on models, mockups, and spare unit Procedures, shielding, and equipment were provided to mitigate personnel radiation exposur Post-LOCA sampling equipment installation Reactor water level sensor installation Hydro-lancing of steam generator tube sheets Reactor cooling pump seal repairs In-core detector thimble replacement Reactor cavity decontamination Nondestructive testing and inspection of piping, nozzles, valves, and steam generator Steam generator tube plugging (using mechanical plugs)
The licensee provided enclosures and ventilating systems for steam generator work, and grinding and decontamination jobs involving actual or potential airborne contaminatio No violations were identifie Supplies and Equipment The inspector toured the facility to observe the availability and use of survey instruments, protective clothing, respirators, shielding, decontamination materials, and special equipmen No survey instruments or friskers were identified as inoperative or overdue for calibratio Based on the inspector 1 s review of service records, there were no lengthy delays in return of instruments to service when due for calibration or repai The licensee has assigned one contract technician to repair, service and calibrate survey instruments and air sampler The following was also noted:
The licensee maintains a routine restock procedure to assure an adequate stock of consumable materials required during outage... *.,
A trailer mounted laundry for protective clothing was in use during the outag Typically, the day's collection of discarded protective clothing was laundered and available for reuse by the next da The inspector noted there was dedicated space for cleaning and storing respirators, and trained personnel were provide No shortage was observed in items such as protective clothing, respirators, shielding, barricades, and sign No violations were identifie.
Training Program The inspector reviewed the training of contract personnel to verify compliance with the requirements of Section 6.4 of the Technical Specifi-cations, Section 5.5 of ANSI N18.l-1971, and 10 CFR 19.1 Procedures specify General Indoctrination Training for all employees, and Radiation Worker Training or Health Physics qualification for personnel involved in such duties.
Based on interviews of ten individuals and reviews of 15 personnel files no failures to complete required training and qualifications were identifie Exposure Control Dosimetry Programs The licensee's personnel monitoring program was examined against the requirements of 10 CFR 20.101, 20.102, 20.401, and 20.408 and within the framework of the following generally accepted codes, standards, publications and examples of good practice:
Regulatory Guide 8.4, 11 Direct Reading and Indirect Reading Pocket Dosimeters
Regulatory Guide 8.7, "Occupational Radiation Exposure Records Systems" ANSI/ANS N13.11, "Draft American National Standard Criteria For Testing Personnel Dosimetry" The licensee representative stated about 2,700 individuals were badged during a typical week of the outag The licensee used self-reader dosimeters and thermoluminescent dosimeters (TLDs).
The latter were read out on site daily, weekly, or monthly as required by procedure The TLD and self-reader dosimeters were picked up on entering an area requiring personnel dosimetr The self-reader
l
dosimeters were zeroed by the control point monitor or the user when picked up; read out by the user; and the results recorded on the RWP sign in/out sheet on leaving the controlled are All visitors wear the dosimetry described above on entering areas normally requiring personnel dosimetr Exceptional, unique provisions may be made infrequently, an example being escorted groups of short term visitor About 2,000 contract personnel were on site during a 24-hr. period wearing visitors badge Extremity dosimetry was provided where the head, hand, foot or various parts of the body received non-uniform exposures to radiatio The personnel monitoring program provided for the preparation and issuance of the following reports and documents:
Daily updates incorporating TLD and daily self-reader dosimeter results Termination reports & estimates Summary information for reports pursuant to the requirements of 10 CFR 20.407 No violations were identifie Procedural Control of Individual Exposures The inspector verified compliance with the requirements of 10 CFR 19.13, 20.102, 20.401, and 20.408 by review of 10 completed Forms NRC-4, equivalent Forms NRC-5, termination reports, and administrative exposure limit authorization On January 20, 1982, the inspector reviewed several pages of the daily computer printout of dosimetry information, averaging about 40 names per pag This listed the status of personnel exposures as of early January 19, 198 No violations were identifie Review of the ALARA Surveillance Program The inspector reviewed the licensee's data to determine any unexpected trends in occupational exposures during the outage, with regard to ALARA contro The licensee's program provides for the reporting of accumulated man-rem exposure each day and job totals for the major tasks respon-sible for these exposure As of January 18, 1982, the total was 127 man-rem expended during the outag The projection had not been adjusted to reflect recent schedule changes, however no overrun was anticipated except for steam generator wor,
Sixteen (16) man-rem was expended for steam generator work compared to a 12 man-rem projectio The licensee believed most of the overrun was caused by nondestructive test equipment failure A complete set of equipment was being leased from a second source to avoid any further problem No violations were identifie Air Monitoring The inspector verified compliance with the requirements of 10 CFR 20.103 to monitor airborne radioactive materials, by observation of the fo 11 owing:
Breathing zone air sampling Grab sampling Continuous air monitor placement and operation Ventilation discharge monitoring The inspector reviewed records of air samples, airborne radioactive materials areas, and contaminated area No violations were identifie.
Review of Respiratory Protection Programs Adherence to Internal Exposure Limits The inspector reviewed the 14 respiratory protection procedures to verify compliance with 10 CFR 20.103 and Regulatory Guide 8.15,
"Acceptable Programs for Respiratory Protection 11 *
These procedures covered respirator training, fit testing, cleaning and disinfecting, use, inspection and repair, and quality assuranc The procedures appeared to assure compliance with the above requirement In addition, the selection of equipment appeared adequate to meet the requirement The inspector verified that records were maintained of physician 1 s determinations of fitness to wear respirator Observation of working conditions during the inspection, and review of records of work permits, air samples, contamination surveys, nasal swipes, skin contamination, and whole body counts did not identify any exposures to airborne radioactive materials in excess of 10 CFR 20.103 limit No violations were identifie *.
8 Bioassay Program The inspector reviewed the bioassay program maintained pursuant to 10 CFR 20.201 to assure compliance with 10 CFR 20.10 The licensee whole body counting program requires radiation workers to be counted at least annually, or an evaluation to be made if counting is imprac-ticable; and in the case of temporary employment, on arrival and on departur The inspector verified the licensee procedures and equipment were adequate to identify nanocurie quantities of typical reactor activation and fission product gamma activitie No violations were identifie Temporary Engineering Controls The inspector verified by observation during tours of the facility that exposures to airborne radioactive materials were controlled by decontamination of surfaces, use of plastic covers and tents to prevent spread of contamination, and use of controlled ventilation systems to prevent exposures to unacceptable concentrations of airborne radioactive material No omissions were identified of the use of such controls on contaminated job No violations were identifie Licensee Evaluations of Controls The inspector noted that the records of the licensee evaluations of controls indicated the selection of acceptable equipment, the use of authorized protection factors, the application of preventive measures, and the evaluation of internal exposure No violations were identifie Respiratory Protection Training and Respirator Fitting and Testing The inspector verified that the medical check, fitting, and training of personnel using respirators was documented and the procedures, described above, appeared to be fully implemente No violations were identifie Respirator Cleaning and Maintenance In order to verify adherence to the above procedures, the inspector observed the collection processs for used respirators, and respirator cleaning and maintenanc The inspector also observed that each user tested the respirator fit each time the respirator was donne No violations were identifie.
Posting and Control of Radiation Areas, Airborne Radioactivity Areas, and Contaminated Areas In order to verify compliance with the requirements of 10 CFR 20.203, 11 Caution signs, labels, signals and controls, 11 the inspector toured the facility to observe posted radiological and survey information, barriers, and enclosure The inspector also surveyed the outdoor radioactive waste storage area fence and barrier ropes, and trailers being loaded with material to be transporte No violations were identifie.
Radioactive and Contaminated Material Control The inspector observed the licensee's management of used protective clothing, contaminated trash, and radioactive wast The inspector verified container labels, transport information and shipping document It was noted that the applicable procedures appeared to be fully implemented and the exposure of personnel to radiation emanating from radioactive waste was reasonably limited by barriers, isolation and shieldin No violations were identifie.
Independent Measurements The inspector surveyed the protected area fence to verify the radiation level did not exceed 0.1 mrem/hr at the fence; source-checked the portal monitors to verify operability and the alarm set-points; and compared measurements throughout the facility with licensee survey result No violations were identifie.
Steam Generator Moisture Carryover Measurement In order to assess the ALARA practices the inspector observed a measurement using 15-hr half-life Na-24 to determine Unit 2 Steam Generator moisture carryove The test authorization No. A6712.l, dated December 17, 1981, was followe The personnel performing the test had rehearsed their assignments, and the shields and barricades were in orde Non-essential personnel were kept out of the radiation area The licensee precautions included the use of emergency equipment in the event of a spill, and backup personnel were availabl Use and disposal of the Na-24 was adequately controlle No violations were identifie '_, "
1 Exit Interview The inspectors met with the licensee representatives, denoted in paragraph 1, at the conclusion of the inspectio The inspector summarized the inspection findings.