IR 05000275/1985030

Insp Repts 50-275/85-30 & 50-323/85-28 on 850826-30.No Violation or Deviation Noted.Major Areas Inspected:Alara, Licensee Organization & Mgt,Facility Tour & Followup on IE Info Notices

ML17083B653
Person / Time
Site:	Diablo Canyon
Issue date:	09/13/1985
From:	Cillis M, Hooker C, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML17083B652	List: IR 05000275/1985030 ML17083B651
References
50-275-85-30, 50-323-85-28, NUDOCS 8510030268
Download: ML17083B653 (10)

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NUCLEAR REGULATORY COMMISSXON

REGION V

Report Nos.

Docket Nos.

License Nos.

Licensee:

Facility Name:

50-275/85-30 and 50-323/85-28 50-275 and 50-323 DPR-80 and DPR-81 Pacific Gas and Electric Company 77 Beale Street, Room 1435 San Francisco, California 94106 Diablo Canyon Units 1 and

Inspection at:

San Luis Obispo County, California Inspection conducted:

August 26-30, 1985

Inspectors:

Approved By:

M. Cillis, Radiation Specialist C. A. Hooker, Radiation Spec'ist G. P. Yuhas, Chief Facilities Radiological Protection Section 9/3 f'ate Signed His s S-Date Signed Date Signed Summary:

Ins ection on Au ust 26-30 1985 (Re ort Nos. 50-275/85-30 and 50-323/85-28)

Areas Ins ected:

Routine unannounced inspection of licensee action on previous inspection findings; licensee's organization and managementj ALARAj facility tour; and follow-up on IE Xnformation Notices.

Inspection procedures 92702, 83728, 83722 and 92717 were covered.

The inspection involved 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br /> onsite by two NRC inspectors.

Results:

No violations or deviations were identified in the five areas inspected.

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Persons Contacted DETAILS A.

PG&E Personnel

>'<R.

C. Thornberry, Plant Manager

>R. Patterson, Plant Superintendent-W. B. Kaefer, Assistant Plant Manager, Support Services-J.

M. Gisclon, Assistant Plant Manager, Technical Services

>C. L. Eldridge, Quality Control Manager

"J. V. Boots, Manager, Chemistry and Radiation Protection

+L. F.

Womack, Manager, Engineering Department-R. P. Powers, Senior Chemistry and Radiation Engineer-R. Weinberg, PGSE News Services T. L. Grebel, Senior Regulatory Compliance Engineer A. I. Dame, Senior Training Instructor W. S. Joiner, Emergency Planning Coordinator R. H. Garacci, Senior Chemistry and Radiation Protection Systems Analyst H.

W. Fong, Chemistry and Radiation Protection Engineer A. O. Taylor, Chemistry and Radiation Protection Engineer W. Fujimoto, Supervising Nuclear Generation Engineer R. J. Harris, Quality Control Engineer/Auditor B.

NRC Resident Ins ectors

"-M. M. Mendonca, Senior Resident Inspector

"-M. L. Padovan, Resident Inspector-T. M. Ross, Resident Inspector

"-Denotes those present at the exit interview on August 30, 1985.

In addition to the individuals identified above, the inspectors met and held discussions with other members of the licensee's and contractor's staff.

2.

3.

Licensee Action on Previous Ins ection Findin s (Closed), Open Item (83-25-$ 4): 'nspection Report Nos. 50-275/83-25 and 50-275/84-27 identified that respiratory protection procedures had not been fully developed and implemented.

This inspection disclosed that.

such procedures have been developed by the licensee.

The implementation of these procedures willbe",verified during a routine inspection.

This matter is closed (83-25-14).

Licensee""sOr anization, and Mana ement

t fl The licensee's organizational'tructure as it relates'o the Chemistry and gadi'ation Protection Program w'as examined.

l'he licensee has'pproved a departmental Chemical and Radiation Protection staff consisting of nineteen professionals, nine foreman, fifty technicians, and five helpers.

All foreman positions had been

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filled, eight technician positions were not filled, and one helper position remains vacant.

The department appeared to have met their human resources objectives for professional and non-professional staffing.

It was, noted that the plant organizational structure was as specified in Section 13.1.2.1 of the PSAR for a two unit operation.

No violations or deviations'ere identified in this area.

The inspectors examined 3.icensee records, audits, attended meetings of the Joint<ALARA Review Committee (JARC) and Plant Staff ALARA Committee (PSAC),'and conducted, interviews of several Diablo Canyon Power Plant (DCPP) workers to verify that the ALARA program is being implemented.

The corporate ALARA policy statement for DCPP is contained in Nuclear Plant Administrative Procedure (NPAP) C-200.

Procedure NPAP C-200,

"General Requirements for Radiation Protection Programs" clearly states:

"It is the policy of Pacific Gas and Electric Company to design, operate, and maintain its nuclear power plants in such a manner as to maintain personnel radiation exposures as low as reasonably achievable."

The company's commitment to maintaining ALARA exposures involves:

Design planning, reviews, system, subsystem, and component selection and location; operator usage considerations; and maintainability.

Construction - procedures, planning, methods, testing, and scheduling.

Operating - procedures, licensee compliance, techniques, equipment usage, maintenance, and operating experience feedback from company and industry experience.

Personnel training, management support, motivation, and supervision.

Administration policy, guidance, controls, licensing position and documentation.

Management involvement, commitment, supervision and oversigh I, f

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The following procedures were reviewed, for implementation of the ALARA program.

Procedure Title Revision/Date Nuclear Plant Administrative Procedure NPAP C>>200 General Requirements 3, 8-15-83 for Radiation Protection Programs Administrative Procedure AP C-200 S2 Operational ALARA Personnel Exposure Implementation 2, 7-4-84, and 3, 6-17-85 Administrative Procedure AP C-200 S3 Use and Control of Temporary Shielding 1$ 4-22-85 Nuclear Plant Administrative Procedure NPAP B>>2 General Training Requirements for Onsite Personnel 4, 7-16-84 Radiation Control Procedure, RCP G-1 Radiation Work Permits 8, 4-29-85 Minutes of the meetings for the joint and plant staff ALARA meetings for the past twelve months were.reviewed.

The review disclosed the following:

Meetings were being conducted at the proper frequencies.

The ALARA Committees were functioning as required.

ALARA goals are utilized.

I The ALARA review and job planning form required by AP C-200 S2 and other pre-job activities were examined for:

(1)

Reactor coolant letdown filter replacement for Unit 1, and (2) the transfer of resins from the chemical and volume control system mixed bed demineralizer to the spent resin storage tank and were found to meet the general criteria of Regulatory Guide 8.8 Section C.3.1, "Preparation and Planning."

Based on the examination of these jobs and a review of other activities, the licensee appears to be providing adequate reviews and pre-5ob planning for keeping radiation exposures ALARA.

The inspectors attended a

PSAC meeting on August 27, 1985, and a JARC meeting on, August 29, 1985.

The PSAC meeting was primarily a general discussion on the proposed Unit 1 shutdown for steam generator tube inspection and repair 'associated with the first refueling outage scheduled for the fal'1 of 1986.

The licensee discussed the purchasing of a steam generator mockup for~ pre-)ob planning and training.

The JARC meeting held discussions on".managem'ent'wareness of radiation protection matters, neutron dosimetry requirements, and 1986 dose goals for Humboldt Bay and,DCPP.

DCPP dose-goals for'1986 are"still being worked on and will be completed by~,the end of this yeaq.

The inspectors noted that

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each of the committees were properly staffed and met the membership requirements as required by NPAP C-200.

Several DCPP workers were interviewed and were found to be aware of the licensee's ALARA program, which is outlined in the general employee training provided for all onsite personnel.

The licensee had instituted the use of color coded maps indicating the lower and higher radiation zones throughout the plant.

These maps are posted near the radiological controlled access area which can be viewed by plant workers making entries into such areas.

The licensee has adopted a

$5,000 man-rem value for use in their cost-benefit analysis.

Since the plant has only been in operation less than one year there has been limited tasks where the licensee could adequately apply this factor in evaluating exposure reducing techniques.

No violations or deviations were identified in this area.

Facilit Tours The inspectors toured the Auxiliary Building, Turbine Building, Fuel Handling Building, Offsite Emergency Operations Facility, and the Technical Support Center.

During the tours the inspectors noted that the areas visited were impressively clean and free of clutter.

An examination of portable radiation survey meters and constant air monitors during the tour disclosed that the instruments were operational and had been calibrated at the required frequencies.

The inspectors noted that the licensee appeared to have an adequate supply of instruments ready for use.

The inspectors also observed that instruments that were inoperable or due for calibration were properly tagged out of service.

The inspectors visually inspected the controls and accessibility to the fuel element transfer tube for Unit 1.

The administrative controls established by the licensee for allowing personnel access to the area were also examined.

The access door to t'e transfer tube area is a locked steel wire door with an audible alarm that actuates when the door is opened.

The inspectors visited areas adjacent to and above the transfer tube for other possible entry pathways and personnel access.

There appeared to be no other entries that would allow unauthorized personnel access.

The inspectors did note that the licensee had used tape to attach the radiation control sign to the access door and, the sign, had fallen to the floor.

In addition, the door was badly warped and was tied with a piece of rope to prevent the 'audible alarm from continuously sounding with the door locked.

These items of concern were brought to the attention of the licensee.

It was noted on the following day that the sign for the access door had been attached in a more permanent fashion, and 'the inspectors were informed by the licensee that the door would be repaired soon.

The licensee had developed an eighteen page Temporary Procedure,

"Fuel Transfer Tube Shield Survey",

TP TC-8501, dated March 16, 1985, to evaluate'the effectiveness of the shielding for the transfer tube and~ controls'td the access area during the licensee's first scheduled refueling outage in the fall of 1986.

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