IR 05000275/1982018

IE Insp Rept 50-275/82-18 on 820426-30.No Noncompliance Noted.Major Areas Inspected:Plant Layout,General Employee Training,Chemistry & Radiation Protection Staff Training & NUREG-0737,Items II.B.3 & II.F.1

ML20054L699
Person / Time
Site:	Diablo Canyon
Issue date:	06/15/1982
From:	Book H, Garcia E, Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20054L693	List: IR 05000275/1982018 ML20054L692
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-TM 50-275-82-18, NUDOCS 8207080378
Download: ML20054L699 (5)

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U. S. NUCLEAR REGULATORY COMMISSION

REGION V

Report No. 50-275/82-18 Docket No. 50-275 License No. DPR-76 Safeauards. Group Licensee: Pacific Gas and Electric Company P. O. Box 7442

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San Francisco, California 94106 Facility Name: Diablo Canyon Unit 1 Inspection at: San Luis Obispo County, California Inspection conducted: April 26-30,1982 Inspectors: . N#ch E. M. Garcia, Radiation Specialist

/f Kne /7/E Date Signed

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Approved by: . .

a 4/M/#.1 i F. A. Wenslawski, Chief, Reactor Radiation ' Date' Signed

. Protection Secti n Approved . Mt et

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H. E. Book, Chief, Radiological Safety Branch 4 5/8".2_

'Dats Signed Summary:

Inspection on April 26-30, 1982 (Recort No. 50-275/82-18).

Areas Inspected: Inspector familiarization with plant layout, general employee training, chemistry and radiation protection staff training, NUREG-0737

. conditions. This inspection involved 35 inspector hours onsite by one regionally ( based inspector.

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Results

Of the four areas inspected no items of noncompliance or deviations were identified.

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B207000378 820615 PDR ADOCK 05000 Q

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DETAILS Persons Contacted

• R. C. Thornberry, Plant Manager

• R. Patterson, Plant Superintendent W. Kaefer, Technical Assistant

• J. V. Boots, Supervisor, Chemistry and Radiation Protection (C&RP)

W. O'Hara, Senior C&RP Engineer (E)

M. Peterson, Senior C&RPE A. Taylor, C&RPE D. Unger, C&RPE L. Vulchev, Solid Radwaste Foreman R. Bliss, Power Plant Engineer (PPE)

• J. M. Gisclow, PPE

• R. C. Howe, Regulatory Compliance Engineer

• Denotes those present at the exit intervie . Familiarization with Plant Layou The main purpose for this inspection was to provide the newly assigned radiation protection inspector an opportunity to familiarize himself with site layout of equipment significant to radiation protectio To this end the inspector took extensive tours of the Auxiliary and

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Containment Building No major problems were identified during these tours. The inspector commented, however, on several observations to the license The NRC Form-3 in the fuel handling building is out of date and should Le replaced with one noting the current Region V address and telephone number. The excessive use of radioactive material stickers should be avoided. Otherwise, their value may be lost and individuals may not notice them because they become part of the visual background. The RHR exhaust duct air particulate monitor had five radioactive material stickers on it. The location of the local

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readout for area radiation monitors should be given some careful l

consideration. The local readout for the Plant Vent Monitor ALARA Monitor RE-34 can not be easily read until the individual is inside the room. During emergencies, access to the plant vent monitor room may-be reoutred. The ALARA monitor provides indication of the radiation l field in the room. It is preferable to know what the radiation levels are before one' enters the room. If the local readout was outside the

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room, the radiation level could be determined before enterin The Incore Room Area Monitor RE-7 readout can not be seen unless one climbs a vertical ladder approximately 15 feet in length, l

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-2-The licensee representative stated that the NRC Form 3 would be updated, the stickers on the monitors were to insure that unauthorized individuals did not tamper with the cabinet and be exposed to radio-active materials, and that the locations of local readout for area monitors would be considered when the whole system is reviewed in the futur No items of noncompliance or deviations were identified.

! General Employee Training The inspector reviewed a proposed handout and outline entitled

" Radiation Protection and Emergency Response Training for Restricted Area Access", and the outline and handout for course #RPD 300 for unescorted protected area access (no access to radiation areas).

These two courses appear to fulfill the requirements of 10 CFR 19.12 for the particular areas for which they are intende The inspector met with the Power Plant Engineer responsible for coordinating general employee training and the Technical Assistant

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to the Plant Manager. The licensee was interested in a clarification of the training requirements pursuant to 10 CFR 19.12, " Instruction to workers". The licensee wanted to know the meaning of restricted area as used in 10 CFR 19.12, i.e., whether it is the same as used in part 20 or as implied in Appendix I of part 50. The inspector reminded the licensee at this meeting and at the exit interview of the provisions of 10 CFR 19.4, " Interpretations." The inspegtor also pointed out that the definition of a restricted area appearing in 19.3(e) was the same as that in 20.3(a)(14). It was also discussed that the licensee had geographically defined the restricted area in the Final Safety Analysis Report Section 2.1.2, " Site Description." The inspector mentioned that historically NRC Region V had applied the restricted area definition as used in Part 20 and Part 19 when determining compliance with 10 CFR 19.12. The inspector suggested that if the licensee was still unclear about meaning of a restricted area as it applies to 10 CFR 19.12, a request for an interpretation from the Commission's General Counsel should be submitted. The licensee wanted to know the extent of the training they will have to provide to NRC inspectors. The inspector stated that NRC inspectors will have had basic Radiation / Contamination Protection Training provided by the Commission. The licensee should provide a site specific orientation relevent to the issuance of badges, escort duties, security procedures and appropriate response to warnings made during emergencies. Inspectors needing to use Respiratory Protection devices will have to be trained and fitted by the license These matters were discussed at the exit intervie No items of noncompliance or deviations were identifie .-. . _- .. - . .

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. Chemistry and Radiation Protection Staff Training Discussions with the C&RP Engineer responsible;for Departmental Training indicate that training of new C&RP~ technicians is progressing.-

At the time of the inspection a chemistry and radiochemistry course was in progress. The course covers all of the chemistry / radiochemistry procedures in the plant manual. The engineer also informed the inspector that MSA corporation had provided' training on the maintenance of self contained breathing apparatus and on the motor powered Air-Purifying Respirators. The inspector also reviewed the training session records for Interim Post LOCA Sampling System (IPLSS)_

conducted on November 30 and December 16, 1981. A four hour course on the handling, packaging and shipping of radioactive materials was offered during the week of March 22-26, 1982. Five

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sessions were presente Training on the health physics and radiation protection procedures *

. of the Plant Manual were to begin the week of May 24 and continue until June 9, 1982. The engineer also informed the inspector that training on the Sentry's permanent post LOCA sampling system was scheduled to being on June 10.

I No items of noncorpliance or deviations were noted.

' NUREG-0737 During this inspection preliminary information regarding the i completion of some NUREG-0737 items was gathered. The inspection was limited to the current status of these items, and did not encompass a detailed review of the technical adequacy of their implementation. A summary follows:

j Item II.B. - Post Accident Sampling. The components for the

! IPLSS appeared to be in place. Training had been provided late

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in 1981 (see paragraph 4 above). A senior C&RP Engineer stated i the new Sentry system would be operational by the time training on it begins in June. Item 1 of the NRC Confirnatory Letter to the licensee dated January 7,1982 is close '

i l Item II.F.1 - Additional Accident Monitoring Instrumentation.

i , Noble Gas Effluent Monitors RE-29 Plant Vent Gross Gamma !

Monitor (high end) appears to be installed and according to the responsible C&RP Engineer calibration has been <

completed and the report is in preparation. The main i steam line monitors RE-71 through 74 are installed and *

calibrated and the report is in preparation. The same for RE-33 the Intermediate Plant Vent Nobel Gas Monito Item 5 of the January 7,1982 Confirmatory Letter is close I

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_4_ Sampling and Analysis of Plant Effluents. RX-40 the Iodine Grab Sampler and RE-32 Plant Vent Iodine Monitors were noted in plac . Containment High-Range Radiation Monitors. The Containment High-Range Area Monitors RE-30 and RE-31 had been relocated as requested in the January 7,1982 Confirmatory Lette Item 2 of the above letter is close No items of noncompliance or deviation were identifie . Exit Interview At the conclusion of the inspection the inspector met with the individuals denoted in paragraph 1. The extent and findings of the inspection were discussed. The licensee was informed that no items of noncompliance had been identifie T