IR 05000272/1987005

Insp Repts 50-272/87-05 & 50-311/87-07 on 870224-27.No Violations Identified.Major Areas Inspected:Control of Internal Exposures,Processing of Routine Survey Data, Organization & Staffing & Control of Radioactive Matl

ML20205G083
Person / Time
Site:	Salem
Issue date:	03/23/1987
From:	Dragoun T, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20205G061	List: IR 05000272/1987005 ML20205G057
References
50-272-87-05, 50-272-87-5, 50-311-87-07, 50-311-87-7, NUDOCS 8703310368
Download: ML20205G083 (6)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

50-272/87-05 Report N /87-07 50-272 Docket N DPR-70 License N DPR-75 Priority --

Category C Licensee: Public Service Electric and Gas Company P.O. Box 286 Hancocks Bridge, New Jersey 08038 Facility Name: Salem Nuclear Generating Station Units 1&2 Inspection At: Hancocks Bridge, New Jersey Inspection Conducted: February 24-17, 1987

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Inspectors: d% 23 T'. DFag enior Radiation Specialist ' date Approved by: # 3 // /M/

M. Shanbaky, Ctfief, facilities Radiation 7/27[f7

~ date Protection Section Inspection Summary: Inspection conducted on February 24-27, 1987 (Combined Inspection Reports 50-272/87-05 and 50-311/87-07)

f Areas Inspected: Routine unannounced safety inspection of the Radiation Protection program including: control of internal exposures; processing of routine survey data; organization and staffing; control of radioactive I material; and status of previously identified item Results: No violations were identified, i

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DETAILS 1.0 Persons Contacted

1.1 Licensee Personnel

• Zupko, J., General Manager, Salem Operations

. Bergendahl, H., Senior Supervisor, RP Operations

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• Dulee, R., QA Principal Engineer

• Gray, N., Licensing Engineer Hunkele, W., Senior RP Supervisor - Material Control i Mohler, D., Radiation Protection Engineer Reuter, D. RP Supervisor

• Trejo, J., RP/ Chem Manager Zitkevitz, L., RP Supervisor i

• Attended the exit interview on February 27, 198 .2 NRC Personnel Gibson, K., Resident Inspector

2.0 Purpose The purpose of this routine unannounced inspection was to review the licensee's radiation protection program with respect to the following

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elements:

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Control of internal exposure

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Processing of routine survey data

Organization and staffing

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Control of radioactive material Status of previously identified item I 3.0 Control of Internal Exposures

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The licensee's program for the use of respirators to control internal exposures was reviewed with respect to the criteria contained in:

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10 CFR 20.103 Exposure of individuals to concentrations of radioactive materials in air in restricted area CFR 20.401 Records of surveys, radiation monitoring, and disposal.

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10 CFR 19.13 Notifications and reports to individual !

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Regulatory Guide 8.15, " Acceptable Programs for Respiratory Protection."

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Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will be As low As Is Reasonably Achievable"

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Station Procedures RP202, RP1001, RP201, and RP3.02 The licensee's performance relative to these criteria was determined from interviews with selected personnel, a review of records and inspection of facilities. Within the scope of this review no violations or program weakness were identifie The issuance of respirators and documentation of the small number of intakes appears well controlled. Under a recent formal agreement, the responsibility for cleaning, repair, and testing of respirators was transferred to Hope Creek Station. The adequacy of this arrangement will be reviewed in a future inspectio .0 Processing of Routine Survey Data The licensee's program for the review and processing of routine radiation survey data was reviewed with respect to criteria contained in:

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Technical Specification 6.10 Record Retention

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10 CFR 20.201 Surveys

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10 CFR 20.401 Records of surveys, radiation monitoring, and disposa Regulatory Guide 8.P., " Guide for Administrative Practices in

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ANSI N13.2, " Guide for Administrative Practices in Radiation Monitoring"

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Station Procedures RP1.010, RP4.001, RP4.002, RP4.003, RP4.004, i RP4.005, and RP4.019.

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discussions with RP supervisors

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review of completed surveys maps

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observation of surveying by a technician

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inspection of ready-to-use survey meter l l

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Within the scope of this review no violations were identified. A i sampling of survey data indicated that it is clear and consistent, j Completed survey maps receive two levels of supervisory review and I sign-off prior to filing. The maps are filed at the control point for approximately 3 months and used by technicians to generate RWP's or for t

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trending radiological conditions. There are then microfilmed for the permanent record with a microfilm copy returned to the control point for future us .

5.0 Organization and Staffiag The licensee's organization and staffing of the RP department was reviewed with respect to criteria contained in:

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Technical Specification 6.2 Organization

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Technical Specification 6.3 Facility Staff Qualifications

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ANSI N18.1-1971 " Selection and Training of Nuclear Power Plant Personnel"

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ANSI N18.7 " Administrative Controls for Nuclear Power Plants"

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NUREG/CP-1280 " Power Plant Staffing"

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NUREG-0761 " Radiation Protection Plans for Nuclear Power Reactor Licensees" The licensee's performance relative to these criteria was determined from discussions with the RP/ Chem Manager, a review of a proposed ~ organization chart, and a review of " Report of Organizational Design Task Team" dated January 30, 198 Within the scope of this review no violations were identified. The licensee recently completed an excellent review of the RP organizational structure using management tools and assistance contracted from the American Telephone and Telegraph Company (AT&T). This provided the staff with a clear view of the work objectives and working relationships required for an effective RP and Chemistry department. A revamped organization chart was issued in early February 198 The RP/ Chem Manager stated that new functional job descriptions would be completed by April 15, 1987. These will be reviewed in a future inspectio (50-272/87-05-01 and 50-311/87-07-01).

6.0 Control of Radioactive Material The licensee's program to label and control radioactive material and radioactive material storage areas was reviewed with respect to criteria contained in:

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10 CFR 20.203 Caution signs, labels, signals and controls

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10.CFR 20.207 Storage and control of licensed material in unrestricted area . O

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Station procedures AP-29, RP1.020, RP1.028 and RP1.01 The licensee's performance relative to these criteria was determined from discussions with the Radiation Protection Engineer and Material Control Senior Supervisor and a tour of the " hot tool" cage and other storage area Within the scope of this review no violations were observed. The licensee had implemented a new policy during the latest outage that prohibited removal of material from the Radiologically Controlled Area (RCA) consis-ting of containment and auxiliary buildings for both units. The " ho tool" cage area inside the RCA was expanded, however no other additional storage was provided. Recently revised procedures allow up to 5 mr/hr at 1" on hot tools,however other procedures (e.g. RP1.020) require that such tools be decontaminated or sent to radwaste. Likewise, the labeling /

tagging requirements are unclear as are the posting requirements for storage areas inside the RC The licensee stated that the RP department will coordinate with other site departments to identify storage needs and clarify posting / labeling requirements by June 30, 1987. This item will be reviewed in a future inspectio (50-272/87-05-02 and 50-311/87-07-02)

7.0 Status of Previously Identified Items 7.1 Procedures Revision - In January 1987 the RP department at Salem was directed by the PSE&G Vice President to coordinate the current revisions of procedures to ensure consistency with Hope Creek station. In response to inspector concerns regarding impact on revision timetables and differences regarding PWR/BWR RP program needs, the licensee stated that the consistencies will only affect

" techniques" and that the Salem Radiation Protection Engineer will have final authority in resolving differences. The licensee stated that the original revision schedule will be met and that this inten-tion will be confirmed to the NRC by May 1, 1987. This matter will be reviewed in a future inspection (50-272/87-05-03 and 50-311/87-07-03).

l 7.2 Use of Computers - A licensee strength was previously noted in the use of computers for record keeping and analysis in support of the RP progra During this inspection it was noted that the licensee i expanded these efforts to include the following:

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improved technique to forecast dose and enhance ALARA goal i setting.

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projecting radiological conditions in containment due to fuel i pin failures that occurred after the latest refuelin schedule routine monthly surveys.

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track all work in progress in any radiologically controlled are .0 Exit Interview The inspector met with the licensee denoted in section 1.1 at the conclusion of the inspection on February 27, 1987. The scope and findings of the inspection were discussed at that time.