IR 05000344/1985024

Insp Rept 50-344/85-24 on 850805-09.No Violations or Deviations Noted.Major Areas Inspected:Internal Exposure, Transportation,Facility Tour & Followup on IE Info Notices & Licensee Action on Previous Insp Findings

ML20137M192
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	08/28/1985
From:	North H, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20137M186	List: IR 05000344/1985024 ML20137M184
References
50-344-85-24, NUDOCS 8509130166
Download: ML20137M192 (6)

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U.S.NUCLEARREdULATORYCOMMISSION

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v i Report N /85-24 .

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l Licensee: Portland General Electric Company 121 S.W. Salmon Street

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Portland', Oregon 97204 Facility Name: Trojan Nuclear Plant Inspection at: Rainier, Oregon Inspection conducted: August 5-9, 1985 Inspector: 1 II H. S. North, Senior Radiation Specialist Date Signed Approved By: .

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G.P.IQTQa , Chief

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Faciliti N Radiological Protection Section J

Summary:

Inspection of August 5-9, 1985 (Report No. 50-344/85-24)

Areas Inspected: Routine unannounced inspection of licensee action on previous inspection findings; internal exposure; transportation; facility i tour; and followup on IE Information Notices. - Inspection procedures 83725, 83727, 83729, 86721, 92717 and 92702 were covere The inspection' involved 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> onsite by one hTC inspecto Results: No violations or deviations were identified in the five areas

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DETAILS Persons Contacted ,

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• Orser, Trojan General Manager -

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G. Huey, Dosimetry Engineer . .'

L. Larson, Unit Supervisor, Radioactive Materials. Control M. Malmaros, Senior Engineer

• T. Meek, Radiation Protection Supervisor S. Newcomb, Radwaste Engineer _

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• A. Olmstead, Manager, Quality Assurance _

• G. Rich, Chemistry Supervisor

• M. Snook, Acting Quality Assurance Supervisor

• T. Walt, Manager, Radiological Services Branch, NSRD J. Wiles, Unit Supervisor, Radiation Protection Non-licensee

• S. Richards, NRC Senior Resident Inspector B. Reynolds, Truck Inspector, Oregon State PUC

• Denotes those individuals attending the exit interview on August 9,198 In addition to the individuals noted above, the inspector met with and interviewed other members of the licensee's staf . -Licensee Action on Previous Inspection Findings (Closed) Violation (50-344/85-14)

The licensee responded to Notice of Violation resulting from the Unresolved Item (50-344/85-01-03) concerning exposures resulting from steam generator insert handling in a timely fashio In the response, the licensee committed to review the exposure evaluation and the potential weakness in the initial evaluation with Radiological Safety Branch and Trojan Radiation Protection personnel. The inspector verified that the reviews had been performed. This matter is considered close . Internal Exposure Control The licensee evaluations of individual intakes of radioactive materials were examined. No intakes greater than 40 MPC hours were identifie The highest intake (June 26, 1984) was 24 MPC hours of Cr-51, Co-58 and Co-60. A second individual received an intake of 16 MPC hours. The MPC hours were determined through the use of multiple counts with a chair type whole body counter. As a result of this occurrence, the assigned Radiation Protection TcJinician was reprimanded for failure to perform an adequate sutvey. During the recent outage and the reracking of the spent fuel pool using divers, the maximum intake was 16 MPC hours of tritium based on urinanalysis. For whole body counting the licensee uses a three crystal (thyroid, lung and lower torso), closed geometry chair counter (APT Model 6000) and Nuclear Data analyzer. A bed type scanning whole body counter, supplied by a contractor, was maintained casite as a backup. The licensee has performed comparisons of the two systems using

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an APT model BP-6/S, tissue equivalent phantom and known sources of Cs-137 and Co-6 The chair counter was found to be slightly more efficient than the bed counte The licensee has available several engineering control devices such as portable HEPA filtered ventilation systems of 1000 and 2000 cfm capacit The larger units, equipped with charcoal absorbers, are used to support steam generator work. Two plastic containment tents were available. One tent located on the 45 foot elevation was used to service contaminated vacuum cleaners. Glove bags are available and used for filter change This equipment was used to the extent practicable to limit exposures to airborne radioactive materials. The examination of exposures to airborne radioactive materials established that the controls used were effective in limiting exposures to less than 40 MPC hour A log, MPC Hour Work Sheets, Airborne Radioactivity Control, was used to

. document exposures in excess of 2 MPC hours in any 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period and 10 MPC hours in any 7 day period. The records identify the dosimeter number, individuals name, date, entry and exit times from airborne areas, net time, fractional MPC hours, and net MPC hours exposure. The most recent entries were for the period March 11-16, 1985. The highest exposure observed was 9.75 MPC hours received during a plant shutdown to correct a leak inside the bioshield. The exposures for 37 persons had been calculated for that evolutio The licensee has available full face air purifying, SCBA and continuous flow air line supplied full face respirators and continuous flow air line supplied hoods. The protection factors used by the licensee are consistent with the guidance contained in Regulatory Guide 8.15 and NUREG-004 The Radiation Protection staff was responsible for respirator inventory control and issuance. Respirators were cleaned and serviced by Radioactive Materials Control staff personnel. A new respirator cleaning facility is being constructed in the auxiliary building in the location formerly occupied by the process boile Records of bioassays and whole body counting were included in personnel exposure file In cases where dose assessments of intakes of radioactive materials have been performed these records are maintained in individual ext sure file No violations or deviations were identifie , Transportation Procedures Licensee Operating Instruction 01-11-7, Sluicing and Charging' Auxiliary Building Ion Exchangers was revised (Rev. 10) in section VII Resin Liner Dewatering and Discharge Header Flu'shing, . to ' provide for.the use of NUPAC, 50 ft3, High Integrity Containers (HIC) and NUPAC dewatering system in accordance with NUPAC procedure OM-34 (Rev. O, S/N 090-NL).

The NUPAC dewatering procedure had been reviewed and approved by the

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Plant Review Board (PRB). 'No precautionary statement had been included

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in the licensees' procedures to provide assurance that future revisions of NUPAC procedure OM-34 would be reviewed by the PRB prior to initial us The matter was called to the licensees attention during the inspectio Procurement and Reuse of Packages The licensee'has leased a NUPAC, model OH-142, P/N Y-20-100D, S/N 004-11, C of C No. USA 19073/B(), 50 f 3t , cask. - The cask was last serviced, including gasket replacement and pressure test, by NUPAC in November 1984. Future cask servicing is to be done by NUPAC. The licensee also has 50 and 100 ft3, shielded containers which were, purchased from the Washington Public Power Supply System (WPPSS) as surplus. The licensee plans to use the casks only onsite for storage of wast ,

Implementation

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The inspector observed the preparation for and dispatch of waste shipment ,

85-71. The shipment consisted of two casks with liners and one large, s

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strong, tight box on a flat bed traile Documents associated with the shipment were examined, including:

• Certification to the State of Washington on placarding and shipping papers;

Certification - SNM inspection in accordance with condition 17 of NRC license 16-19204-01 issued to U.S. Ecology;

• Certificationofinspection'totheStateofWashingkonDepartmentof Social and Health Services in accordance with the Governor of Washingtons executive order of November 19, 1979;

Le ter to U.S. Ecology identifying MDA values for Tc-99 and I-129; Tc-99 < 9.513E-3 mci

! I-129 <_ 8.911E-3 mci

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Pu238 2.572E-6 gms -

Pu239/240 7.118E-3 gms I Pu241 1.979E-4 gms;

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• Notification to Oregon Department of, Energy; Radioactive Material Shipment and Receipt Record; and

Radioactive Waste Shipment and Disposal Manifes The shipment consisted of, -3 packages'of 352 ft3 containing Pu 7.33E-3 gms, 406 mci H-3, 0.099 mci C-14 and'1092 mci all isotope The inspector observed the transfer of;the shipping documents to the .

driver of the Tri State MotAr'Trandport tractor, the licensees ~ surveys of the load and tractor cab and vehicle placarding and shipping package

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l labelin Independent surveys were perform with an ion chamber survey instrument NRC 015844 due for calibration September 21, 198 Prior to dispatch of any waste shipment the licensee notifies the Oregon State PU In almost all cases an Oregon State truck inspector inspects !

the tractor trailer and load prior to the load's departure from the )

Trojan site. The inspector observed the Oregon State PUC inspection of the subject shipment. The inspection included brakes, lights, emergency s

equipment, trailer loading and tie downs, an independent survey by the PUC inspector using his own instrument and an examination of the drivers license, driver's log (for operating time) and shipping papers. The PUC inspector identified the need for one additional tie down on one cas No other discrepancies were mentioned by the PUC inspecto The inspector also examined shipping documents associated with shipments 85-1 through 85-6 and 85-13 and 85-1 Shipments 85-13 and 85-15 were the first shipments of resin using NUPAC EA-142 HIC's dewatered with the NUPAC system discussed under procedures

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in this report section. These route controlled shipments contained 1970 s and 1700 Ci of radioactive materials respectively. State of Washington Department of > Social and Health Services letters of March 19 and April 4, 1985, granted interim approval for the use of the HIC In addition, a

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State of Washington letter granted a variance to the 10 nCi/gm limit on I Am-241. The _ letter constituted specific approval of the changed level ;

for Appendix E of U.S. Ecologys Washington State license WN-1019-2 based '

I on the results of analysis of resin samples ~by SAI. The licensees Nuclear Safety and Regulation organization calculated dose rates at various distances from the HIC and heat loadings (TRU, daughters ignored, I watt, Non TRU, 12.8 watts). The licensees procedures were revised to permit cask assembly'and leak testing prior to HIC filling and dewatering. The licensee, using Temporary Plant Test-(TPT-122) performed a test of the hydrogen generation in,the spent resin in response to Information Notice 84-72. The worst case, using bad data due to heluim contamination, indicated less than 4% in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Using good data the i

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indicated value was approximately 1% in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. -The total dose commitment including all aspects,of.the evolution was 1.384 manrem for

the first cask and 0.391 manrem for the second cask. Surveys established that the casks satisfied.all dose, rate limits. The shipment was ccmpleted and arrival acknowledged without inciden j Transportation Incidents

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l The licensee reported that no transportation incidents had occurred since I i the last inspection of this area'in July 198 Facilities l

- 'The licensee plans to construct a new Rad Waste Annex adjacent to the i fuel handling building train bay. The facility will house the waste compactor, laundry sorting and waste storage area. A HEPA filtered

^ ' ventilation system will discharge to the plant vent syste No violations or deviations were identified.

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. Facility Tours '

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., The inspector toured the auxiliary building and performed independent

! f surveys with a ion chamber survey instrument NRC 015844 due for

> -' calibration September 21, 1985. The inspectoriexamined the new, temporary access control area, outside the turbine building train bay

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which began operation during the inspection. The licensee is presently remodeling the access control area in the auxiliary buildin No violations or deviations were identifie , Skin and Clothing Contaminations and ALAR As of the date of the inspection (July 1985) the total manrem was 334.85 with a goal of 363. A total of 51 skin and 86 clothing contaminations had occurred. The licensee effectively documented the occurrences of personnel contamination and decontamination, including decontamination methods used and effectiveness, and a preliminary calculation of i resulting doses. Results of dose calculations were included in personnel exposure files when the contamination is 100,000 dpm or> greater (25 mrad per hour of exposure). As of August 8, 1985, four individuals had experienced local contamination of 100,000 dpm or more with a maximum of 450,000'dpm (11.25 mrad). The highest calculated exposure was 75.5 mra No violations or deviations were identifie I Followup on 'Information Notices The inspector verified that the licensee had received, reviewed and was taking or had complete action on Information Notice Nos. 84-55 Supplement 1, 85-34, 85-42, 85-43, 85-46, 85-4 No violations or deviations were identifie . Exit Iuterview The inspector met with those individuals denoted in report section 1 at the conclusion of the inspection. The scope and findings of the inspection was summarized. The licensee was informed that no violations or deviations had been identifie ,

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