IR 05000272/1989009
| ML18094A491 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/25/1989 |
| From: | Nimitz R, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18094A490 | List: |
| References | |
| 50-272-89-09, 50-272-89-9, 50-311-89-08, 50-311-89-8, NUDOCS 8906060025 | |
| Download: ML18094A491 (8) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No Docket No ~89-09 50-311_89-08 50-272 50-311 License No DPR-70 OPR-75 Priority Licensee:
Public Service Electric and Gas Company P. 0. Box 236 Hancocks Bridge, New Jersey 08038 Category Facility Name:
Salem Nuclear Generating Station, Units 1 and 2 Inspection At:
Hancocks Bridge, New Jersey Inspection Conducted:
April 24-28, 1989 Inspectors:
Inspection Summary:
c c slzslq date
)fa e Areas Inspected: Routine, unannounced Radiological Controls Inspection of the fol lowing: rad,iological controls organization and staffing; personnel q~alifications' and training; corrective action system and performance monitoring; ALARA; external and internal exposure controls; hot particle exposure control; industrial safety and housekeepin Result~: No violations were identified. A n~mber of weaknesses were identified in the area of housekeeping.
8906060025 890525 PDR ADOCK 05000272 Q
DETAILS 1.0 Individuals Contacted 1.1 Public Service Electric and Gas Company S. LaBruna, Vice-President Nuclear L. Miller, General Manager, Salem Operations
- J. Wray, Radiation Protection Engineer, Salem
- J. Trejo, Manager, RP/Chem Services
,
- D. Mohler, Manager, RP/Chem, Salem Supervisor
- D.A. Perkins, Manager, Station QA
- P. Eldreth, Nuclear Fire and Safety Manager
- T. Cellmer, Radiation Protection Engineer, Hope Creek*
- P. White, Technical Manager, Salem
- J. Webster, Outage Manager
- J. Gueller, Operations Manager NRC Personnel K. Gibson, Senior Resident Inspector, Salem
- S. Pindale, Resident Inspector, Salem 1.3 State of New Jersey
- N. DiNucci, Department of Environmental Protection, State of New Jersey Other licensee and contractor personnel were also contacted or interviewed during the course of this inspectio * Denotes those personnel attending the exit meeting on April 28, 1989.
2.0 Purpose and Scope of Inspection This inspection was a routine, unannounced Radiological Controls Inspection during the Unit 1 refueling outage. The following areas were reviewed:
- organization and staffing;
-
trainin~ and qualifications; correct1ve action system;
- external and internal exposure controls;
- hot particle exposure control; ALARA;
- industrial safety;
- housekeeping.
- 3.0 Licensee Actions on Previous Findings (Closed) Inspector Follow-up Item (50-272/86-17-01; 50-311/86-17-01):
Licensee to evaluate personnel dosimetry placement for those individuals involved in resin disposal operations. The licensee evaluated personnel dosimetry placement for those individuals involved in resin disposal operation Placement was found to be acceptable. This item is close.0 Organization and Staffing The inspector reviewed the organization and staffing of the onsite Radiation Protection Group with respect to criteria contained in the following:
- Technical Specification 6.2, Organization;
- Regulatory Guide 8.8, Information Relevant to Ensurin~ That Occupational Radiation Exposure At Nuclear Power Stations Will As Is Reasonably Achievable; Salem Unit 2 Outage Information Manual;
- Procedure ODP-ZZ-001, Outage Implementation Procedur Be As Low Evaluation of licensee performance in this area was based on discussions with cognizant personnel, review of ongoing work and review of documentatio Within the scope of this review, no violations were identified. The licensee reorganized the radiological controls organization to enhance oversight of outage activities. The licensee also established and staffed a new ALARA group. Personnel were also placed into the planning and scheduling group to improve work planning from a radiological controls and ALARA perspective. The new organization established for the outage provided enhanced supervisory and management oversight of on-going work activities and performance monitorin.0 Training and Qualifications The inspector reviewed the qualification and training of members of the Radiological Controls Organization with respect to criteria contained in Technical Specification 6.3, Facility Staff Qualification. Licensee performance in this area was evaluated by review of resumes and training records and discussions with cognizant personne The inspector's review in this area focused on the qualification and training of contractor radiological controls personnel hired to augment the organization during the outag The inspector also reviewed the adequacy and effectiveness of the performance of these personnel during review of work activities.
Within the scope of this review, no violations were identified. Contractor personnel appeared to have received adequate trainin~ and qualificatio Inspector review indicated the licensee provided training in the revised and upgraded procedures developed as part of the licensee's procedure upgrade progra The licensee also provided training in the areas of Salem Job Awareness and procedural complianc Licensee training provided to radiological controls personnel focused on the need to fully understand and comply with all procedure.0 Corrective Action System and Performance Monitoring The inspector reviewed selected aspects of the licensee's corrective action and performance monitoring progra Within the scope of this review the following positive observations were made:
The licensee assigned an individual to the position of Radiological A~sessor at the start of the outage. This individual was responsible for reviewing ongoing work and radiological controls and notifying, as appropriate, supervision and management of deficient conditions or performanc The licensee significantly increased his awareness and attention to Radiological Occurrence Reports(RORs} and their resolution. The licensee's General Manager meets once per week with all department heads to review and discuss RORs, industrial safety concerns and QA finding Inspector attendance at an ROR discussion meeting indicated good discussion and review of the RORs by all department Appropriate action items were generated and assigned for purposes of preventing recurrenc Licensee radiological controls management was closely monitoring the frequency and severity of radiological incidents ( e.~. personnel contaminations}. Licensee personnel indicated additional actions are taken when unacceptable trends are identifie Inspector observations indicated an apparent decrease in the numbers of radiological events for the Unit 1 outage as compared to the Unit 2 outag The inspector concluded good overall licensee review and evaluation of self-identified findings was performe. 0 External -and Internal Exposure Controls The inspector toured the radiological controlled areas of the plant and reviewed the following elements of the licensee's external and internal
. exposure control program:
posting, barricading and access control, as appropriate, to Radiation, High Radiation, and Airborne Radioactivity Areas;
High Radiation Area access point key control; control of radioactive and contaminated material; personnel adherence to radiation protection procedures, radiation work permits and good radiological control practices; use of personnel contamination control devices; use of dosimetry devices; use of respiratory protective equipment; adequacy of airborne radioactivity sampling and analysis to plan for and support ongoing work; timeliness of analysis of airborne radioactivity samples including supervisory review of sample results; installation, use and periodic operability verifjcation of engineering controls to minimize airborne radioactivity; bioassays and personnel airborne radioactivity intakes; records and reports of personnel exposure; adequacy of radiological surveys to support pre-planning of work and on-going work; and hot particle control The review was with respect to criteria contained in applicable licensee procedures and 10 CFR 20, Standards for Protection Against Radiatio The inspector independently reviewed on-going work activities including personnel entries into steam generators, reactor vessel head work, reactor coolant pump maintenance, various fan cooler work activities, reactor water clean-up and safety injection system valve work, spent fuel ultrasonic testing and reactor control mechanism eddy current testin Within the scope of the above review, no violations were identifie Overall radiological controls were noted to be si~nificantly improved relative to the Unit 2 outag The following positive observations were discussed with licensee personnel:
Licensee attention to and radiological coverage of steam generator work activities was significantly improved relative to observations of similar work activities conducted during the Unit 2 outag Overall source term control resulted in: minimal numbers of personnel contaminations, the capability to work on steam ~enerator platforms without respiratory protection and the accumulation of less exposure d<fto use of special shielding. Management of personnel entries onto st!am generator platforms was significantly improve Licensee control of High Radiation Areas was effectiv Licensee hot particle controls were effective and appeared to optimize personnel exposur I
The following matters were brought to the licensee's attention:
Observations of fuel inspection activities in the Unit 1 fuel storage building indicated some weaknesses in hot particle control and posting and control of radioactive. Postings were obscured on some materials. Also material that was potentially contaminated with hot particles was not indicated as suc Observations of reactor vessel head shroud removal activities indicated some oversight and control weaknesses as follows:
The personnel removing the shroud were working in a dose rate gradient. Dosimetry was not repositioned to.monitor for the gradient. Portions of the body were exposed to apparent higher dose rates than the area actually monitored by the dosimetr Personnel preparing to remove the shroud were standing and waiting for tools in a whole body dose rate of about lOOmr/h Personnel removing the shroud were using ladders in an unsafe manne Although used extensively and properly installed, the licensee does not have a program for periodic verification of proper operation of portable ventilation systems installed to control airborne radioactivit The licensee immediately initiated actions to review the above matter.0 ALARA The inspector reviewed selected aspects of the licensee's ALARA Progra The review was with respect to criteria contained in the following:
Regulatory Guide 8.8, Information Relevant to Ensuring that Occupational Exposure at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable; Regulatory Guide 8.10, Operating Philosophy for Maintaining Occupational Radiation As Low As is Reasonably Achievable; NUREG/CR-3254, Licensee Programs for Maintaining Occupational Exposure to Radiation As Low As Is Reasonably Achievable; NUREG/CR-4254, Occupational Dose Reduction and ALARA at Nuclear Power Stations; Study on High-Dose Jobs, Radwaste Handling and ALARA Incentive Within the scope of this review, no violations were identified. Inspector observation of ongoing work indicated good overall ALARA controls to be in place for in-field work. Licensee planning and preparation for major work tasks appeared good. Exposure accrued was within goals established by the license '
The following matters were discussed with licensee personnel:
The licensee performed planning of major outage exposure tasks using a team leader concept. A team leader was assigned to coordinate planning and preparation. A new ALARA group was also established to review outage tasks. Personnel were also placed in planning and scheduling to improve radiological planning and preparatio The licensee used good techniques to reduce exposures. Innovative shielding was used to reduce steam generator platform dose rates and improve airborne radioactivity control. Gloveboxes_ were used to control contamination extracted from the generat9rs during eddy current testing. Special monitors were installed to monitor for highly radioactive hot particles which could be inadvertently pulled out of steam generator Licensee performance in the ALARA area relative to industry performance indicated good over a 11 performanc The following matter was brought to the licensee's attention:
There is no well defined program to provide for review of radiological work activities which would sustain an ag~regate exposure of less than 5 person-re The inspector est1mated that 10-15% of the outage exposure fell in this category. Although personnel are using guidance provided for review of jobs greater than this value, it was unclear as to the uniformity of the use of this criteri In addition, there is limited ALARA training provided to the staff including the new ALARA grou Licensee preliminary review indicated no apparent ALARA planning problems in this are However, the licensee indicated this matter would be reviewe.0 Plant Tours The inspector toured the radiological controlled areas of the facility periodically during the inspection. The following matters were discussed with licensee personnel:
.
Overall licensee performance in the area of attention to industrial safety appeared improved. Some isolated instances of improper use of ladders was note The inspector noted some individuals who had not received the licensee's special heat stress training which had been instituted as a result of problems encountered last outage in this are The licensee immediately initiated action to address these matter '
Although housekeeping in the Unit 1 containment was considered good, the inspector noted a number of apparent housekeeping concerns throughout the Auxiliary and Fuel Handling Buildings. These included used protective clothing scattered about the areas, newspapers and other papers stuck in instrument racks, and various containers of used unlabeled oil. placed under instrument racks. Licensee personnel took pictures of the various areas for presentation and discussion at outage meeting *
The inspector noted a radwaste operator, apparently on duty, reading a newspaper which is contrary to licensee policy. The licensee immediately initiated a review of this matte.
The inspector noted numerous candy wrappers and observed cigarette butts inside the radiological controlled areas indicating potential problems with worker sensitivity to ingestion of radioactive materia The licensee initiated an immediate review of this matte.0 Exit Meeting The inspector met with licensee representatives denoted in section 1 of this report on April 28, 198 The inspector summarized the purpose, scope and findings of the inspectio No written material was provided to the licensee.