IR 05000313/1986010

Insp Repts 50-313/86-10 & 50-368/86-10 on 860428-0502.No Violation or Deviation Noted.Major Areas Inspected:Radiation Protection Program,Including Mgt Controls & Organization, Training & Qualification & ALARA Program

ML20199E877
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/12/1986
From:	Chaney H, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20199E859	List: IR 05000313/1986010 ML20199E855
References
50-313-86-10, 50-368-86-10, NUDOCS 8606240135
Download: ML20199E877 (17)

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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-313/86-10 Licenses: DPR-51 50-368/86-10 NPF-6 Dockets: 50-313 50-368 Licensee: Arkansas Power & Light Company (AP&L)

P. O. Box 551

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Little Rock, Arkansas 72203 Facility Name: Arkansas Nuclear One (ANO), Units 1 and 2 Inspection At: ANO Site, Russellville, Pope County, Arkansas Inspection Conducted: April 28 through May 2, 1986

, 4//.t/p4 Inspector:[ H,fhaney, Radiation' Specialist, Facilities Date

/ & Radiological Protection Section a

Approved: , 4 4[At[r4 B//urray, Chief, Fdcilities Radiological Date UProtection Section

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Inspection Summary Inspection Conducted April 28 through May 2, 1986 (Report 50-313/86-10; 50-368/86-10)

Areas Inspected: Routine, unannounced inspection of the licensee's radiation protection program including management controls and organization; training and qualification; and the ALARA program.

i Results: Within the areas inspected, no violations or deviations were

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identified.

t f 8606240135 860619

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PDR ADOCK 05000313 G PDR

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DETAILS

, Persons Contacted AP&L

, *J. M. Levine, Director, Site Nuclear Operations

*E. C. Ewing, General Manager, Plant Support i

• D. J. Wagner, Health Physics (HP) Superintendent (Acting)

B. L. Bata, Quality Assurance (QA) Engineer E. E. Bickel, HP Specialist i

M. J. Bolanis, HP Specialisc R. A. Cantwell, HP Technician

! *P. E. Campbell, Plant Licensing Engineer '

l F. H. Chilcoat, Instruments and Controls (I&C) Technician

J. R. George, Maintenance Coordinator i T. Green, Trainer, General Employee Training (GET)

W. L. Hada, HP Supervisor

• D. L. Helm, HP Specialist (ALARA Coordinator)

*D. Howard, Manager, Special Projects

• P. Jones, Superintendent, I&C i W. R. Pool, Assistant Supervisor, Radiochemistry l T. Pugh, Lead Trainer, GET T. Rolniak, Lead Trainer, HP and Radioactive Waste

• D. D. Snellings, Manager, Nuclear Programs (Corporate HP)

R. J. Terwilliget, HP Technician J. D. Vandergrift, Nuclear Training Superintendent J. Waid, Supervisor, Technical Specialist Training

, *R. P. Wewers, Manager, Work Control Center

! G. D. Prover:her, Quality Engineering Supervisor

• D. O. Lomax, Plant Licensing Supervisor j Others

• D. Johnson, Senior NRC Resident Inspector

*C. C. Harbuck, NRC Resident Inspector L. Holloway, Contracted Firewatch

• Denotes those present at the exit interview on May 2, 198 i l The NRC inspector also interviewed other licensee employees including

QA/QC and HP personne . Licensee Action on Previously Identified Inspection Findings (Closed) Unresolved Item (368/7818-03)

Environmental Dosimeter Placement - Amendment 60 to Unit-2's Technical Specifications (TS)

resolved this item concerning the quantity and placement of environmental j dosimeters. A review of Annual Radiological Monitoring Reports for ANO,

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3 Units 1 and 2, was conducted and no discrepancies on dosimeter placement were noted. This item is considered close (Closed) Unresolved Item (368/7818-04): Detection Limits for Tritium in Water Samples - Amendment 60 to the Unit-2 TS resolved this ite AN0's Lower Limits of Detection are now in agreement with NUREG-0472 recommendation This item is considered close (Closed) Unresolved Item (368/7818-05): Environmental Ground Water Samples - A review of AN0's 1984 and draft 1985 Annual Environmental Monitoring Reports indicated that both surface and ground water samples were in agreement with Radiological Effluent Technical Specifications (RETS) requirements. This item is considered close (Closed) Open Item (368/7904-02): ANO, Unit 2 Start Up Radiation Surveys - A review of the Updated Safety Analysis Report (USAR) indicated that radiation zones had been revised to reflect radiation levels identified in the Unit 2 start-up surveys. This item is considered close (Closed) Open Item (313 & 368/8419-01): Control of Chelating Agents -

The licensee had performed an evaluation of the amount of chelating agents used in the plant and their possible effect on radioactive liquid wast The licensee determined that only small amounts of chelating agents were used in plant areas that could adversely affect waste disposal operations, but action would be taken to control inventories of chelating agents in order to demonstrate compliance with 10 CFR Part 61. This item is considered closed.

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(Closed) Open Item (313 & 368/8419-03): Quaility Control (QC) Department Training - Provisions for hiring of a full-time QC/QA trainer has been provided for in the ANO 1986 budget. This item is considered close (Closed) Open Item (313 & 368/8435-01): Training Procedures for Respiratory Protection - The licensee had revised training procedures to reflect that respiratory protection masks could not be reused after removal following work in areas that have loose surface contaminatio This item is considered close (Closed) Deviation (313 & 368/8509-01): Continuous Air Monitoring (CAM) - The NRC inspector verified that the licensee had installed and maintained operational a sufficient number of CAMS in both Units 1 and 2 to satisfy the commitments stated in the USAR. This item is considered close (Closed) Violation (313/8519-01 and 368/8520-01): Inability to Collect and Analyze Post-Accident Samples - The NRC inspector verified that the licensee had implemented a routine surveillance and preventative maintenance program for Units 1 and 2 Post-Accident Sampling System This violation is considered close _ _ - _ - - ____________

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(Closed) Open Item (313 & 368/8609-02): Portable HP Instrumentation Radiation Response Check - The NRC inspector verified that the licensee had implemented a portable instrument response check program that ensures that instruments are response checked over the range that the instrument is expected to be used. This item is considered close (Closed) Open Item (368/7916-01): Condenser Vacuum Exhaust Monitor - This monitor was the subject of several Licensee Event Reports (79-47, 80-45, and 81-33) due to moisture buildup in the detector chamber. The licensee has heat traced the sample lines and the detector housing was shielded to prevent recurrence of the problem. This item is considered close . Inspector Observations The following are observations the NRC inspector discussed with the licensee during the exit meeting on May 2, 1986. These observations are neither violations nor unresolved items. These items were recommended for licensee consideration for program improvement, but they have no specific regulatory requirement, QA Auditors HP Expertise - The QA department currently does not have any auditors with specialized experience in radiation protectio (See paragraph 4.) Backshift HP Support - HP technicians with the least plant experience are designated as shift HP technicians. (See paragraph 4.) Industrial Hygiene Monitoring - Various industrial hygiene monitoring activities are routinely performed by HP technicians. These tasks are not included in their job descriptions nor is there a formal training program for such activitie (See paragraph 5.)

4. Radiation Protection Organization and Management Controls The NRC inspector examined the corporate and on-site organizations and staffing to determine compliance with ANO, Units 1 & 2 USAR-Sections 11.2.6, 12.1 and 12.3 (ANO-1), and 12.3, 13.1 and 1 (ANO-2) commitments; the requirements of 10 CFR Parts 19 and 20; the requirements of Technical Specifications (TS) 6.1, 6.2, 6.5, 6.6, 6.8, and 6.10 (ANO-1), and 6.1, 6.2, 6.5, 6.8, 6.9, 6.11 (ANO-2); and the recommendations of NRC Regulatory Guides (RG) 1.33, 1.8, 8.8, and NUREG-0731-Section II, and Industry Standard ANSI N18.7-197 The NRC inspector reviewed the current on-site and corpt organizations, staff position assignments, and position descriptions. The licensee had recently reorganized both the on-site and the corporate (AP&L General Office, Little Rock) staff The licensee's organizational changes have been submitted to the NRC as a TS amendmen The NRC inspector discussed with licensee representatives the replacement of the HP Superintendent (the equivalent to the RG 1.8 referenced Radiation Protection Manager) by the Assistant HP Superintendent. ANO on-site HP

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staff and corporate HP support staff (Nuclear Programs) assignment of responsibilities concerning the radiation protection programs at AND, backup for the HP Superintendent (both onsite and offsite), direct and indirect communication interfaces, and reporting chain-of-commands were reviewed. The NRC inspector also reviewed HP staff authorities (stop work); adequacy of shift manning; corporate staff involvement in on-site activities; operating procedures review, approval and issuance; management directives governing radiation and respiratory protection; and ALARA activitie Attachment 1 to this report contains a listing of the documents reviewed during this inspection. The NRC inspector also discussed with licensee representatives the progress on implementing the new computerized radiation exposure /HP records management system and the new external dosimetry system. The NRC inspector reviewed the licensee's i management and supervisory oversight / inspection program for inplant work activitie The NRC inspector reviewed the licensee's audit and surveillance programs for activities involving the radiation protection progra The licensee had conducted several QC surveillances of HP activitie The NRC inspector discussed with a licensee QC representative the limited scope of their surveillance checklist The QC representative stated that the HP surveillances were being revised due to comments from a previous audit of QC activities. The NRC inspector reviewed the December 1985 QA department audit of the HP and radwaste management activities. The NRC inspector r

also reviewed audit checklists, pre and post audit meetings, auditor qualifications, corrective action procedures and status of corrective actions to audit findings. The NRC inspector expressed concern that the QA department staff does not include auditors with radiation protection experience. Licensee QA representative stated that recruiting efforts were under way to fill an auditor position and that they were anticipating filling it with someone with radiation protection experienc '

The HP department's shift staffing and workload were reviewed. The NRC inspector determined that the HP department had not experienced any significant turnover of personnel for the past 5 years. It was noted that the HP staff had been growing and expanding in the area of HP staff technical specialists and apprentice HP technicians. The licensee's program for evaluation, qualification, and control of contractor personnel was reviewe I The NRC inspector noted to the licensee a concern regarding the policy for shift assignment of HP technicians. The NRC inspector noted during a review of the qualifications of HP technicians assigned to shift work that all technicians were technically qualified per ANSI N18.1-1971 criteri However, the NRC inspector determined that the licensee's shift assignment policy designates that HP technicians with the least experience be placed on shift work. Since the permanent staff turnover is low, only the new hires and the most recently promoted apprentice HP technicians with the least plant experience fill the shift position The NRC inspector discussed with selected shift HP technicians theoretical jobs that they may be required to cover, emergency response duties, and the verbal

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instructions given to them by the HP department on initiating major radiological work operations. The NRC inspector discussed with licensee representatives the necessity that shift HP techniques possess sufficient experience so that they could control situation without immediate supervisor involvement. The NRC inspector did not identify any specific violations or deviations concerning the qualification of HP shif t workers, but the licensee was advised that shi 4 worker are considered personnel in responsible positions and they shoula have the necessary experience to respond properly to HP situation The licensee's internal communications regarding several NRC Information Notices were reviewed as were the program for ensuring that industry information notices, regulatory documents, and general reading material is brought to the attention of the the staf The licensee's reporting of incidents and events per TS and 10 CFR Part 20.401 requirements were reviewe No violations or deviations were identifie . Radiation Protection Training and HP Staff Qualifications The radiation protection training programs were reviewed to determine compliance with USAR-Sections 11.2.6, 11.3.3, 12.1.3, 12.2 (ANO-1), and 12.4.3, 13.1.1.2, 13.1.3 (ANO-2); ANO Emergency Plan-Section N- commitments; the requirements of TS 6.3 and 6.4 (ANO-1 & 2); the requirements of 10 CFR Part 19.12; and the recommendations of RG 1.8, 8.2, 8.8, 8.27, NUREG-0761, and ANSI N18.1-197 The NRC inspector reviewed the licensee's onsite and corporate office HP staff experience and qualifications, position assignments, training records, and conducted interview The nuclear training department staff qualifications, facilities, implementing procedures, and lesson plans were reviewed. Specialized training for general employees, radiation workers, and HP personnel including radwaste personnel were reviewe General Employee Training (GET, Category I)

The radiation protection and emergency plan training programs for visitors, unescorted and escorted personnel, and contractors were reviewed. The NRC inspector determined from a review of training records, lesson plans, and interviews with personnel that the GET program satisfies the licensee's commitments to ANSI N18.1-1971, and the recommendations of RG 8.13, 8.27, and 8.29. The NRC inspector also determined that basic radiation protection training (GET, Category I) is provided to everyone except personnel that will be under escort and will not be entering any radiologically controlled areas and those personnel with previous specialized training in radiation protection that are evaluated and approved by the HP superintendent. Lesson plans, test material, records, and instructor qualifications were reviewed.

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i Radiation Worker Training (GET, Category II)

The NRC inspector reviewed the radiation worker training program regarding lesson plans, course handout material, training facilities,

radiological control practical factors, audio visual aids, materials for hands-on familiarization, and course presentatio The NRC l inspector determined that radiation workers with extensive previous

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experience were given the opportunity to bypass the normal 16-hour training program if they can pass a screening examination. If they j pass the screening examination, they attend a 4-hour site-specific j training session.

i The respiratory protection training session was observed by the NRC i inspector and it was noted that each type of radiological respiratory j protection equipment utilized by the licensee was made available to the class for inspection and familiarizatio '

The NRC inspector discussed with licensee personnel the content and scope of a planned Category III advanced radiation protection training program that will

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be presented to a limited number of plant personnel that will allow i

them to perform limited radiological surveillance of their work areas. The licensee's biannual requalification program for Category II

, and respiratory protection training were reviewe Radiation Protection Personnel Training The NRC inspector reviewed the revised training program for HP

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department personnel. This included a review of lesson plans,

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instructor qualifications, and observation of a portion of training being provided to newly hired radwaste helpers. The NRC inspector discussed with licensee representatives the formal qualification program for ANO and contract HP technicians and the HP technical i apprenticeship program for unexperienced personnel. HP technician

, on-the-job training log books were reviewed, as were records of training in emergency response requirements. The licensee is awaiting the onsite review of the HP training program by the Institute of Nuclear Power Operation sometime this yea The NRC inspector determined that plant HP technicians were routinely performing industrial hygiene duties. These duties involved monitoring

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of plant spaces (reactor containment, and other tanks and voids in

! radiologically controlled areas) for explosive atmospheres and to I

verify that suitable breathing air was present. The NRC inspector i determined also that these duties were not identified in the licensee's official task analysis (position description) for the HP technicians i

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and that HP technicians were not'provided formal training in the evaluation of atmospheres that could be immediately hazardous to life

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(IHL). The licensee stated that HP technicians were performing the

! IHL monitoring instead of the plant industrial hygienist due to ALARA l considerations. The licensee provided the NRC inspector with a draft

procedure that would establish a formal training and certification

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these industrial hygiene functions. Approval of the procedure was expected to be completed by the end of May 198 No violations or deviations were identifie . ALARA Progra The ALARA program was reviewed to determine compliance with the commitments in USAR, Sections 11.2.6 (ANO-1), and 12.1.1, 12.2.1.A, and 12.3, 12.3.2.6 (ANO-2); the requirements of 10 CFR Part 20.1(c); and the recommendations of RG 8.8, 8.10, and 8.2 The NRC inspector reviewed the licensee's ALARA program including staffing, management directives, implementing procedures, ALARA committee meetings, corporate engineering checklist for design reviews, ALARA improvement suggestion program, pre and post job briefings, and quarterly ALARA reports for 1985 and 1986 (draft). The NRC inspector determined that the licensee's ALARA staff consisted of an ALARA coordinator along with two HP technicians assigned to the Work Control Center for assisting in job planning. The ALARA coordinator is provided additional staffing during outage situations. The NRC inspector noted that corporate HP personnel are routinely involved in plant ALARA activities. The NRC inspector discussed with licensee representatives the preparations being made for the Unit 2 refueling outage and any special jobs that will be performed. The licensee was noted to routinely use equipment mockups for training personnel involved in high dose rate work operations. The licensee was noted to be evaluating the potential ALARA problems associated with possible refurbishment of Unit 1 reactor coolant pump Several plant modification design review packages with ALARA checklists were reviewed and discussed with the ALARA coordinato The NRC inspector determined that the licensee establishes departmental as well as overall station goals on external radiation exposure, respiratory protection use, and personal skin contamination that seek to improve on past performance The NRC inspector discussed with the licensee the current program under way to remove the protective clothing requirements in Unit 1 & 2 auxiliary buildings which was made possible by an improved decontamination program, additional work force training, and improved worker adherence to radiological work practices. The NRC inspector noted that the licensee routinely meets the exposure reduction goals established and has shown a significant reduction in personnel ~ exposures at ANO. The NRC inspector reviewed specialized training in ALARA practices given to workers, supervisors, and corporate engineers. The licensee's Person-Rem expenditures for work operations expending greater than five Person-Rem and a 5 year comparison with other light water reactor plants in the United States in presented in Attachment 2 to this report. The NRC inspector noted that recent annual Person-Rem data indicate that the AN0 ALARA program is effective.

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7.' . Exit Interview The NRC inspector met with the licensee's representatives and the NRC resident inspectors identified in paragraph 1 of this report at the conclusion of the inspection on May 2, 198 The NRC inspector sumarized the scope and the results of the inspectio I f*

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ATTACHMENT 1 TO NRC INSPECTION REPORT 50-313 AND 368/86-10 APPENDIX DOCUMENTS REVIEWED IIILE REVISION DAIE Energy Supply Department Management Directive 86-5, Radiation Protection O O2-01-86 Energv Supply Department Management Directive

86-14. Respiratory Protection O O2-01-86 AP&L and ANO Organization Charts O 04-07-86 ANO Memorandums on ALARA Program:

ANO-85-05302, First Quarter 1985 ALARA Report O 04-29-86 ANO-85-10715, Second Guarter 1985 ALARA Report O 07-29-85 ANO-85-12910. Third Quarter 1985 ALARA Report O 10-22-85 ANO-86-01082. Fourth Quarter 1985 Alara Report O 01-29-86 ANO-06-01678, Monthly Exposure Report for January 1986 0 02-19-86 ANO-06-02595, Monthly Exposure Report for February 1986 0 03-14-86 ANO-86-02891, Change In Anti-Contamination Clothing Requirements O 04-15-86 Form HP-10.14, Month 1y Exposure Summary for March 1986 APhi Ouality Assurance (OA) Manual _ 7 05-31-85 UH Adini n t s trat i ve Procedures (OAA)

OAA-1, OA Organization 2 05-25-84 UAA-2. Personnel Oualification, certification & Training 2 06-07-85 04A-5, OA Gurvei11ance 3 03-27-85 OAA-6, OA Audits 4 10-04-85 OAA-9, Corrective Action 2 03-28-85 OAA-11, CA Activity Planning and Rnporting 1 07-29-83 APhL 04 Procedures (OAP)

OAP-1, Vendor / Contractor Audits 1 10-01-84 DAP-3, tiealth Physics and Radweste 11anagement 2 07-30-85

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OAP-9, Design Control 1 10-15-84 DAP-t0. Carrective Action O 07-02-85 t%P-22, Chemistry. Radiochemistry, and Envieonmental Monitorino 1 03-07-85

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@O_OA Audt ts:

OAP-3, HP and Radwaste Management 01-31-86 ANO OC Section Surveillance Checklists:

HP-1, Radiological Fosting and Entry Requirements 2 02-04-83 HP-2, Respiratory Equipment Inspection Regmt O 12-17-81 HP-3. Radiological Evaluations and Surveys 1 02-07-83 HP-4, Purchase and Receipt of Radioactive Sources 1 04-22-86 HP-7, ALARA Program 1 07-09-85 HP-9, HP Instrument Response Check O O2-12-82 HP-12, Anti-c Handling / Monitoring O O2-02-83 HKG-01, General House Keeping (HP Items Included) 1 03-14-84 ANO OC Section Survei11ances:

OCSF-86-062, General House Keeping 01-30-86 OCSF-86-095, General House Keeping 03-25-86 UCSF-86-103, HP-3 Checklist, Surveys 04-07-86 OCSF-86-105, HP-1 Checklist, Posting /High Rad 04-16-86 OCSF-86-106, HP-2 Checklist, Respiratory Protection 04-17-86 ANO Gtation Administrative Procedures 1000.001, Organization & Responsibility 14 08-14-85 1000.004, Procedural Program Requirements 20 12-18-85 1000.005, Procedure Format and Content 11 07-29-85 1000.006, Procedure Review, Approval, and Revision Control 22 10-12-85 1000.008, NRC Reporting & Communication 20 12-29-83 1000.012, Control of Site Contractors 08 05-23-85 1000.015. Station Training Pragram 7 12-28-84 1000.025, Radiological Safety Infraction Condition Report 4 06-13-85 1000.031, Radiation Protection Manual 3 06-07-85 1000.032 Pespiratory Protection Manual 6 03-29-86 1000.033, ANO ALARA Manual 3 12-19-85 1000.049 Industrial Hygiene / Confined Space Entry Procram O 07-18-83 Pl ann t n_q _& _Schedul.ing__Admi ni st r a t i ve Pro _cedures 1001.002. Outage Scheduling and Management 2 11-19-84 UPa1.th Phrucs_QlP) Agjmi n ijit r_a t i ve _Pr oc ed ur_es_

1012.001. HP Shift Turnover Loq o 09-28-84 10l?.002, Solid RW Management Process Control O O2-12-86

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REylSIOt4 D81E 1 r w i n i n tLAdminist_r_ative Procedures 1063.001, Station Training 7 10-12-84 1063.002, Instructional System Development i 12-23-85 1063.003, Standards for Training Documents 2 11-20-84 1063.004, Training Evaluation / Test Control 5 12-23-85 1063.005, On-The-Job-Training 4 11-13-85 1063.006, Trainer / Instructor Training Program 1 02-16-84 1063.007, General Employee Training Program 4 04-17-85 1063.010, Maintenance Training Program 4 12-18-85 1063.014. HP Training Sequence 3 10-29-84 1063.018. Professional / Technical Training 1 06-27-85 1063.019, Supervisory / Management Training O 10-19-84 1063.021. Emergency Response Training Program 7 03-29-86 1063.022. OC Training Program O 10-22-84 1063.023. Contractor HP Training Program O 09-25-85 1063.025, Respirator Fit Testing 3 04-24-85 Other Nucioar Tr ai n t nq_Dep ar t men t Documents IIILE D81E Computer Printout of Training Received by:

T. R. Smith Black CantwelI Durchard G. McCaslin Smith Irainino Attendance Reports (Form 1063.01):

Radiological Emergencies - Course # AX 20901-005 03-01-83 02-24-83 03-04-83 02-25-03 02-22-83 02-11-83 02-10-83 02-14-83 02-09-83 01-22-85 02-13-85 02-20-85 02-27-85 03-06-85 01-08-86 01-15-86 03-04-86

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IITL4 D81E Non-Routine Emergency Equipment - AX 20901-009' 03-07-83 03-11-83 03-01-03 03-15-83 02-14-85 02-21-85 03-14-85 04-12-85 01-21-86 ALARA Design - AS 3OOl6V-OO1 12-16-81 -

ALARA Training for Engineers and Supeervisors'- ~~'

AG-10089-OO3 08-20-84 08-27-84 09-10-84 Principles of Radiation Protection - AT 20101-047 11-23-81 05-13-82 Lesson Plans:

AG 10042-061 - Industrial Hygiene AG 10101-041 - GET Category 1 Retraining 08-08-84 AX 20901-005 - Onsite Rad Monitoring Team 01-24-86 AX 20901-006 - Emergency Facility Equipment 12-30-82 AX -'0901-008 - Dose Assessment 12-20-83 AX 20901-009 - Non-Routine Equipment 01-24-86 AG 10089-003 - ALARA for Supervisors 07-30-84

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AG 10100-043 - GET Respiratory Protection Retraining 07-08-85 HP Technician Training:

AH 10103-001 - Radiation Surveys 03-12-86 AH 10103--004 - High Dose Rate Work 03-26-86 AH 10103-005 - High Contamination Work 03-21-86 AH 10103-007 - Radiation Work Permits 03-19-86 AH 10201-009 - Respiratory Protection 04-02-86 AH 10201-010 - Personnel Access, Exposure Reduc AH 10201-011 - Surveys. Posting, and Job Coverage 04-02-86 AH 10201-013 - HP Emergency Monitoring 04-01-86 AT 20000-006 - HP ANSI Certification Written Exam 11-11-85 AT 20000-007 - HP ANSI Certification Oral Exam 12-03-85 Quarterly, HP Supervisor GET Training Evaluations 1985 IIILE REylSION D8IE Pad i_o Logi cal Resp _iratory Protection Procedures:

1609.001, Issue and Return of Respiratory Equipment 4 03-14-85 1609.002, Respiratory Hazards 3 09-12-84 1609.003. Une of Respiratory Equipment 2 09-12-84 1609.007, Respiratory Protection Equipment 4 07-22-85 1 -

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TIILE REVISION DOIE ej. ARA Procedures:

1609.001, Mock Up Training & Prejob Briefings 1 09-12-84 1612.002, Access & Control of RCA's 5 06-05-85 1612.003, Radiological Work Permits 10 12-05-85 1612.004, Anti-c Requirements 6 04-25-86 1612.006, Exposure Reduction Methods 5 12-05-85 1612.007, Job Preparation and Cleanup 2 06-05-85 1612.013, Contract HP Technician Selection 1 09-09-85 1612.01 RX Building Access Control 3 12-20-84 1612.01 HP Evaluation of GET 1 07-03-85 G e n e r_ a l Radiolooical Wort Procedures:

1622.006, Radiological Air Sampling Program 5 03-30-85 1622.007, ALARA Job Coverage Practices 3 06-15-85 1622.009, Requirement for Reactor Building Power Entries 2 10-10-85 1622.022, HP Area Inspections 6 07-25-85 1622.023, Control and Calibration of HP Inst .026. HP Requirements for Steam Generator Entries 2 09-12-85 1622.028, Airborne Iodine 131 Determinations Using SAM 2/RO22 1 09-12-85 1622.035, Radiological Controls for Radiography Operations 3 03-07-86 Drjft - 1053.005. Confined Space Entry Program O 04-22-86

- APOL Summary of Nuclear Programs Section Responsibilities en ARA _ Imp _rovement Forms (1000.33f):

Modification of Job Orders 03-11-86 Operating Reactor Cavity Valves 03-30-84 Replacement of High Dose Rate Valve 03-26-84 ALAPA Design Change Review Packaoes_1 ESP-202-F11):

80-1118B, Installation of RCP Work Platform 08-27-84 83D-1063, Replacement of Upper Core Barrel Bolts 08-10-84 83-1076, Replacement of Flow Transmitters 07-06-84 83-2228, Low Level Radioactive Waste Storage Bld ,- 2 1 7 1 , Containment Cable Spreading 01-13-86 83D-1030, Installation of CRDM Flexible Hoses /OD's 12-26-84 AL ARA Post Task Evaluations Jper RWP]_:

RWP-2175R, Cutout and Replace GCH-12 01-10-86 RWP-3162R, Polar Crane Work 12-16-85 PNP-2370T, Retin Transfer 11-15-85 PNP-2020R, Post-Accident Sampling Valve Work 09-04-85 I< WP- 219 7R , Valvo Welding 08-22-85

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Position Desc r s pL ion t _s :

0331.0, HP Superintendent 01-14-84 0460.0, Assistant HP Superintendent 12-01-83 0334.O. HP Supervisor 02-23-82 t 0237.1 through 0237.5, HP Specialist (I-V) 06-19-84 Position Task Analysis. HP Technician / Apprentice HP 10-31-85 0238.O/O239.O. AND Trainer I/II Chemistry and RadioChe .0/0239.0, AND Trainer I/II, GET 06-22-85 0238.0/0239.0, AND Trainer I/II. HP and Radwaste 06-22-85 0238.0, AND Trainer Generic 11-17-83 0239.0, ANO Trainer Generic (Lead Trainer) 06-22-85 0264.0. Engineering and Technical Support Manager 06-22-85 Qther Doca.imen t s :

ANO Update Safety Analysis Report. Unit 1 3 ANO Update Safety Analysis Report, Unit 2 3

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ATTACHMENT 2 ARKANSAS NUCLEAR ONE COMPARISON WITH NATIONAL SINGLE REACTOR RADIATION EXPOSURE PERFORMANCE AND WORK OPERATIONS WITH RADIATION EXPOSURE EXPENDITURES GREATER THAN 5 PERSON-REM TABLE 1 AN0 Annual Person-Rem Versus PWR National Average YEAR 1981 1982 1983 1984 1985 578 592 556 ***

PWR AVERAGE: 652 AN0: 551 401 610 387 115

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ATTACHMENT 2 CONT'D TABLE 2 Work Operations That Exceeded 5 Person-Rem During 1986 Job Description Person-Rem Unit-2 R4 Outage: (March 15 through June 12, 1986)

Snubbers 11.085 Health Physics Support 10.854 Reactor Coolant Pumps (RCP) 9.750 Inservice Inspection 8.205 Extend 2CV-2060 Valve Operator 6.540 Decontamination and Trash Collection 5.310 Modify RCP Pipe Supports 5.305 Inspections and Tours 6.055 Steam Generator (SG) Sludge Lancing 10.851 SG Manways and Handhole Removal / Install 5.812 SG Eddy Current Testing- 5.461 Reactor Vessel (RV) Stud Work 8.035 Outage Summary:

Reactor Building 100.970 Steam Generators 24.709 RV and Refueling Operations 22.643 Auxiliary Building 13.280 Radioactive Waste Activities 1.700