IR 05000454/1982008

IE Insp Repts 50-454/82-08 & 30-17034/82-01 on 820524-26.No Noncompliance Noted.Major Areas Inspected:Preoperational Radiation Protection Program for Unit 1 & for Byproduct Matl License Authorizing Sources for Storage & Calibr

ML20055A154
Person / Time
Site:	Byron, 03017034
Issue date:	06/28/1982
From:	Greger L, Hueter L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20055A148	List: IR 05000454/1982008 ML20055A147
References
30-17034-82-01, 30-17034-82-1, 50-454-82-08, 50-454-82-8, NUDOCS 8207150528
Download: ML20055A154 (7)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Reports No. 50-454/82-08(DETP); 30-17034/82-01(DETP)

Docket Nos. 50-454; 30-17034 Licenses No. CPPR-130; 12-05650-18 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Byron Station, Unit 1 Inspection At: Byron Site, Byron, IL Inspection Conducted: May 24-26, 1982 n'). pal Inspector: LI J. Ilueter d*j/ EN/ bub N#

Approved By: L. R. Greger, Chief 6,[28/ld bI Facilities Radiation Protection Section Inspection Summary:

Inspection on May 24-26, 1982 (Reports No. 50-454/82-08(DETP);

30-17034/82-01(DETP))

Areas Inspected: Routine, unannounced inspection of initial preoperational radiation protection program for Unit 1 and for the byproduct material license authorizing various sources for storage, instrument response, and calibratio The inspection included organization and staffing, training, radiation pro-tection procedures, facilities, instruments and equipment, and respiratory protection program. The inspection involved 25 inspector-hours onsite by one NRC inspecto Results: No items of noncompliance or deviations were identified.

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DETAILS 1. Persons Contacted

• S. Barrett, Station Chemist

• A. Chomacke, Assistant Technical Staff Supervisor G. Geissler, Training Instructor R. Querio, Station Superintendent

• Sues , Assistant Superintendent, Maintenance

• K. Weaver, Station Health Physicist

• R. Westberg, QA Engineer

• J. Van Laere, Rad-Chem Supervisor

• Forney, NRC Senior Resident Inspector

• Denotes those present at the exit meetin . General This inspection of the radiation protection program for preoperational Unit 1 and byproduct material License No. 12-05650-18 began about 10:30 a.m. on May 24, 198 It included tours of Unit 1 containment and selected areas of the auxiliary building, turbine building, and service buildin . Organization, Staffing, and Training This inspection included a review of the status of the licensee's organ-ization, staffing, and trainin Regarding the organizational structure, the Radiation-Chemistry Super-visor reports to the Administrative and Support Services Assistant Superintendent for normal matters. Additionally, he has direct access to the Station Superintendent in radiation protection matter The radiation protection section and the chemistry section are currently combined at Byro As noted in Section 12.5.1 of the Byron SER dated February 5, 1982, the NRR staff's position, based on NUREG-0731, is that the radiation protection section should be a separate section with its own supervisor or the applicant should provide an alternative proposal to ensure that the Rad / Chem Technicians maintain adequate qualification in both technical disciplines. As noted in the SER, the applicant has committed to review the matter and either submit proposed changes to his organization or provide documentation of his Rad / Chem Technician training and retraining program for further review by the NRR staf Staffing of the Rad / Chem group currently includes the Rad / Chem Super-visor, the Station Health Physicist, 1 Health Physicist, 1 Health Physi-cist Engineering Assistant, 2 Rad / Chem Foremen, 18 Rad / Chem Technicians (RCTs), the Station Chemist, 2 Chemists, and 2 Chemistry Engineering i

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Assistants. The inspector reviewed qualifications of the above staff

, based on ANSI N18.1-197 By Unit 1 fuel load date, the licensee is committed by the FSAR to pro-vide a minimum of one RCT per shift for implementation of the Radiation Protection Progra In lieu of ANSI N18.1-1971 qualification, the FSAR currently proposes that the individual be qualified for this duty upon certification by the licensee that the individual is capable of success-fully accomplishing specified radiation protection activities. The in-

, spector expressed concern in the exit meeting that this proposal requires no time period of experience in radiation protectio The licensee's RCT certification program includes training and prac-tical factors. The certification program has not been implemented to date as some of the equipment and procedures which are to be a part of the practical factor section have not been set u Six RCTs have been in the RCT program at Byron since early 1979. All six have completed the 15-week RCT training program and have worked two refueling outages at Quad-Cities Nuclear Power Station. Two of them have 1-1) years of previous RCT experience at other CECO operating power plants. The re-maining 12 RCTs, who started as technicians in April of this year, are currently attending the 15-week RCT training program at the statio Licensee personnel stated that they plan to send some or all of these technicians to a refueling outage this fall. ANSI N18.1-1971 qualifi-cation of RCTs will be reviewed at a later date following implementa-tion of the licensee's certification program and resolution of the matter involving potential separation of the radiation protection section and the chemistry sectio The Station Chemist does not at this time meet the criteria of ANSI N18.1-1971 regarding a minimum of one year of experience in radiochem-istry. The Station Chemist has completed a 10-12 week Westinghouse chemistry / radiochemistry course and is in the process of obtaining three months experience in radiochemistry at a nuclear power plant under oper-ating conditions. Additional experience will be gained in the Byron Sta-tion radiochemistry department when it becomes operational about August this year. The qualifications of the Station Chemist will be reviewed

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I During a previous inspection *, the resident inspector questioned the qualifications of one of the Rad / Chem Foremen compared to the criteria in ANSI N18.1-1971 (supervisor not requiring N3C license). The licensee l

committed to review the individual's experience, and document the

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review and any actions necessary to meet the qualification criteria. The l individual had one year and five months plus 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> overtime work at an operating plant before starting employment at Byron Station. Also,

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since beginning work at the Byron Station, the individual has worked one l

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refueling outage at Quad-Cities Station in the capacity of a Rad / Chem Foreman. The licensee plans to send the individual to another refueling outage in the same capacity this fall. The qualification of this Rad / Chem Foreman will be reviewed further during a future inspectio l Inspection Report No. 50-454/82-07 i

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The Rad / Chem Technician (RCT) training course consists of 15 weeks specialized training, including 2 weeks of basic math and chemistry, lj weeks of basic RCT training, 3 weeks of specialized Radiation Technician training, I week of the RCT Chemistry Laboratory course, and 6 days of reactor simulator and systems training at the Westinghouse Training Reactor. Written tests with passing grades are required for satisfactory completion of the training. Chemists and health physi-cists are required to take parts of the technician training cours Although annual retraining is planned for the technicians, the program has not yet been establishe The licensee's annual general employee training program (NGET), which includes radiation protection, was initiated in 1981 for CECO employees and is to be expanded to include contractor employees and others in the near future. From a review of the training material used by the licensee, it appears the program will adequately cover the instruction to workers required by 10 CFR 19.12 and prenatal exposure in accordance with Regulatory Guide 8.1 The facilities for training appear adequat No items of noncompliance or deviations were identifie . Radiation Protection Procedures Radiation protection procedures are estimated to be 85 percent complete and chemistry procedures 75 percent complet The following administrative and radiation protection procedures were selectively reviewed for consistency and compatibility with FSAR commit-ments and 10 CFR Parts 19 and 20 regulations:

BAP 575-1 Revision 0 Radiation Protection Program BAP 575-2 Revision 0 llose Identification BAP 700-1 Revision 0 ALARA Program BAP 700-2 Revision 0 ALARA Review BRP 1000-A-1 Revision 0 Radiation Protection Standards BRP 1300 Al-A6 Revision 0 Whole Body Count Program BRP 1310-1 Revision 0 Selection Issuance and Control of Radiological Respiratory Protection Equipment BRP 1380-1 Revision 0 Assessment of Exposure to Radioactive Materials in Air

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No significant problems were identified with the procedure The ALARA procedures reviewed include a management commitment to ALARA principle . Facilities, Instruments, and Equipment During a tour of the facility, the inspector observed the status of the following areas, equipment, and instruments involving radiation protection: The area tentatively selected for the whole body counter and mask fit test equipment is located in the northeast corner of the tur-bine building on the 432' level. The room is not yet closed off, The control point for personnel access to the auxiliary building will be from the turbine building to the auxiliary building at the 426' elevation (adjacent to the RCT office area). The personnel decontamination room is located adjacent to the ac-cess control area. The planned shower and sink have not been installe The mask issue room, located near the personnel decontamination room, does not have cleaning facilities or fume hood installe Access to this room may be hampered by the installation of an elec-trical panel in front of the doo The hot maintenance and decontamination area and the Change Room, although used for other purposes currently, are conveniently near the entrances to the containment The laundry facility, on the 426' elevation of the auxiliary build-ing, currently has two dry cleaning units, one water washer unit and two dryer units installed. The licensee plans to obtain one additional dry cleaning unit and one additional water washe The counting room equipment is on hand and is currently being set up and tested in the counting roo Procedures for operating the equipment are being develope As noted in Section 7, the licensee has a limited inventory of survey meters, counting equipment, air samplers, and personal dosi-metry devices. More equipment is on orde . Area monitors have not been installe No items of noncompliance or deviations were identifie .

. Respiratory Protection Program As noted in Section 5, the area for maintenance of respiratory equip-ment and mask issuance has been selected and the area for the fit test booth has been tentatively selected. The fit test booth is onsite but not set up. The maintenance and mask issuance room is not equipped at this time. Most of the procedures for the respiratory protection pro-gram are written. No significant problems were identified in the selec-tive review of these procedure No items of noncompliance or deviations were identifie . Byproduct Material License No. 12-05650-18 This license, initially issued October 31, 1980, and amended on January 22, 1982, to make certain changes and additions, authorizes possession and use of various sealed and unsealed sources for storage, instrument response, and calibratio Included in the authorization are a number of sealed neutron sources and one large cesium sealed source. The latter is to be used for calibration of the containment high radiation monito Although many sources are authorized, the only ones received to date (besides generally licensed source sets) are 10 strontium-90 sealed sources of 0.3 mci each. These 10 sources will be installed in spe-cial devices having various shield thicknesses for use in routine performance checks of survey meters. At the time of this inspection, these 10 sources were still in the original shipping container, which was labeled and in locked storage since receipt in April 1982. No pro-blems were identified during the inspector's review of the receipt survey record The inspector observed that the licensee possessed numbers and types of instruments specified in the license application. The inventory in-cludes laboratory counting equipment, meters for measuring contamination, and meters for measuring a wide range of radiation levels. Also included are meters for measuring alpha contaminction and neutron dose rate Air samplers for collecting particulates and iodine activity were also availabl Instruments were found to be calibrated as shown by review of calibration records and by observation of calibration stickers on the instruments. Calibrations have generally been performed at other CECO plants to date since most calibration sources have not been re-ceived at the Station. Personal dosimetry is also provide No items of noncompliance or deviations were identifie . Special Nuclear Material License No. SNM-1860 Since no material has been received under this license to date, this licensed program was not inspected. The uranium-235 contained in incore monitoring detectors will probably be received about six months before core loading. An application for an amendment to this license is cur-rently being prepared to authorize receipt of fuel, according to licensee personne >

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, Exit Meeting The inspector met with licensee representatives (denoted in Section 1)

at the conclusion of the inspection on May 26, 1982, and by telephone with R. Querio and others of his staff on June 11, 198 The following matters were discussed, The purpose and scope of the inspectio The inspector noted that Special Nuclear Material License SNM-1860 was not inspectabic at this time in that no material has been re-coived to date under this license. (Section 8) The inspector noted that no items of noncompliance or defici-encies were noted during the inspection of Byproduct Material License No. 12-05650-18. (Section 7) The inspector noted that the Station Chemist and one of the

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Rad / Chem Foremen currently do not meet ANSI N18.1-1971 qualifica-tions. The licensee noted that specialized training and/or experi-ence at an operating nuclear power plant is being provided and/or planned in the near future for these individuals in the interest of ensuring that applicable ANSI qualifications are me The inspector noted that the licensee has not yet implemented the RCT certification program. The licensee stated that 6 of the 18 RCTs need only minimal additional effort to complete the qualifications once the program is implemented. The inspector expressed concern that the FSAR currently proposes certification criteria for shift RCTs which are less restrictive than the ANSI N18.1 qualification criteri (Section 3) The inspector noted that no significant problems were identified during review of selected radiation protection procedures and admin-1strative procedures involving radiation safety. A few suggestions for minor revisions were discussed. The licensee agreed to pro-vide a controlled copy of the Station's radiation protection and chemistry procedures to the inspector by November 1982. (Section 4)

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