IR 05000272/1979011
| ML18079A956 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/13/1979 |
| From: | Crocker H, Serabian J, Jason White NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18079A955 | List: |
| References | |
| 50-272-79-11, NUDOCS 7909240843 | |
| Download: ML18079A956 (4) | |
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I U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report N /79~11 Docket No. 50-272 License No. DPR-70 Priority -
Licensee:
Public Service Electric and Gas Company 80 Park Place Newark, New Je~sey 07101 Category C Facility Name:
Salem Nuclear Generating Station, Unit 1 Inspection At:
Hancocks Bridge, New Jersey Inspection Conducted:
March 22-23, 1979 Inspectors: Serabia Ra ~ation*
Specialist (Int ~n)
Approved By:~~~)-
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- W:Cl"Ocl<er)C'til1chie Radiation Support Section, FF&MS Branch Inspection Summary:
Inspection on March 22-23, 1979 (Report No. -50-272/79-11)
Areas Inspected:
Routine, unannounced inspection by two NRG regional based inspectors of the radiation protection program as it relates to refueling outage preplanning activities including:
Advanced Planning and Preparation; Training; Qualifications of Personnel; and Respiratory Protectio The inspection involved 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> on site by two NRC inspector Results:
Of the four areas inspected, no items of noncompliance were foun *
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DETAILS Persons Contacted *H. Midusa, Manager-Salem.Generating Station
- J. Gueller, Senior Performance Engineer.
- L. Miller, Station Performance Engineer
- H. Lowe, Quality Assurance Engineer (Resident)
- J. Stillman, Station Quality Assuranc*e Engineer
- W. Grali, Quality Assurance Staff Assistant M *. Bell, Site Coordinator, Rad Services, Inc. (RSI)
P. Greenbaum, Assistant Site Coordinator, RSI R. Hatch, Assistant Site Coordinator, RSI S. Sorenson, Quality Assurance and Control, RSI The inspector also talked with and interviewed several other licensee employees, including station (and contractor) health physics staf *Denotes those present at the exit intervie Advanced Planning ~nd ~reparation The inspector reviewed the licensee's efforts with regard to the outage:* preparation in the following areas: Increased Health Physics Staff - The licensee has arranged to augment its staff with approximately 40 health physics personne These personnel reported on site approximately one week prior to the start of the outage in order to receive training in plant health physics procedure The contractor health physics vendor categorized its personnel into three principle groups:
Level I, Level II, and *Level III Technician A contractor representative stated that the Level I position denotes a junior technician (such as a control point monitor) who is not in a responsible position.., Levels II and III positions denote a senior technician and a crew leader, respectively, and are regarded as able to fill responsible position ANSI 18.lN-1971, "Section and Training of Nuclear Power Plant Personnel" (which is endorsed *by Technical Specification 6.4) states in Section 4.5.2 that technicians shall have a
- minimum of two years working experience in their specialt The inspector reviewed the resumes of 16 contractor health physics personnel designated to be used as Level II and Level III Technicians during the outag The inspecto+
identified two instances in which an individual did not have the required two years of experienc The licensee representative stated that the work* assignments of the two individuals would be modified such that. they were not in responsible position Also, the licensee representative indicated that they would review contractor health physics resumes to ensure that, when applicable,. the required two year experience criterion was me Deployment of contractor health physics technicians is planned to be at several discrete control points through-out the plan Plant health physics technicians have been assigned oversight of the contractor health physics tech-*
nicians whose control point work station is within their area of responsibility (e.g., reactor containment, au and fuel bldgs., etc.).
Special Training*- The inspector learned through discussion with the licensee representative that steam generator mock-up training had been conducted to familiarize personnel with the problems associated with the eddy current testing of the steam generato Increased Supplies - The licensee representative indicated that additional protective clothing would be obtained to support the outage activitie In addition, the licensee has purchased more survey meters and dosimetry; a back-up thermoluminescent dosimeter reader has also been acquire Portable tents (for containment) and air cleanup systems have been acquired for work involving the primary side of the steam generator The inspector observed that the licensee.has setup a special dress-out and access point to accommodate the high influx of personnel expected during the outag An adjacent health physics area has also been set.up in order to bring the organi-zation closer to field activitie No items of noncompliance were identified in this area.
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- 4 - Training The outage required additional personnel to augment the regular station staf Training of supplemental personnel had commenced prior to the beginning of the outage to assure that {new).
personnel were:.* familiar with the emergency, security, and radia-tion protection aspects of the facilit A written examination for each section is given at the conclusion.of the training to test the individual's retentio The licensee representative informed the inspector that an additional instructor has been assigned, in view of the heavy influx of personnel anticipate No items of noncomplian~e were identified in this are..
Respiratory Protection During the course of the inspection, the licensee representative indicated that a respiratory protection program was soon to be implemented in accordance with 10 CFR 20.103, "Exposure of individuals to concentrations of radioactive* materials in air in restricted areas," Section (c), so that allowance could be made for use of respiratory protection in estimating exposures to individuals to airborne radioactive materials; and that a notification letter had been sent to the Commissio The inspector confirmed that the required 30 day notification to the Regional Office Director had been made pursuant to 10 CFR 20.103(e).
The notification letter, dated April 2, 1979, states that the implementation and enforcement of the Respiratory Protection Program shall become effective 30 days from:.the date of the lette No items of noncompliance were identified in this are.
Exit Interview The inspector met with the licensee's representatives (denoted in Paragraph 1) at the conclusion of the inspection on March 23, 197 The inspector summarized the scope and findings of the inspection as noted in this report.