IR 05000309/1981001
| ML20032B579 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 10/07/1981 |
| From: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Groce R Maine Yankee |
| Shared Package | |
| ML20032B580 | List: |
| References | |
| NUDOCS 8111050684 | |
| Download: ML20032B579 (6) | |
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i OCT 0 71981 Docket No. 50-309
.:,i i Maine Yankee Atomic Power Company g
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Mr. Robert H. Groce
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Senior Engineer - Licensing
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g 1671 Worcester Road Framingham, Massachusetts 01701
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Gentlemen:
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Subject: Health Physics Appraisal y
The NRC has identified a need for licensees to strengthen t
sics programs at nuclear power plants and has undertaken a significant effort to assure that action is taken in this regard. As a first step in this e. fort, the Office of Inspection and Enforcement is conducting special team appraisals of the health physics programs, including the health physics aspects of radio-active waste management and onsite emergency preparedness, at all' operating power reactor sites.
The objectives of these appraisals are to evaluate the overall adequacy and effectiveness of the total health physics program at each site and to identify areas of weakness that need to be strengthened. We will use the findings from these appraisals as a basis not only for requesting individual licensee action to correct deficiencies and effect improvements but also for effecting improvements in NRC requirements and guidance. This effort was identified to you in a letter dated January 22, 1980, from Mr. Victor Stello, Jr., Director, NRC Office of Inspection and Enforcement.
During the period of January 18-30, 1981, the NRC conducted the special appraisal of the health physics program at the Maine Yankee Nuclear Generating Station.
Areas examined during this appraisal are described in the enclosed report (50-309/81-01). Within these areas, the appraisal team reviewed selected procedures and representative records, observed work practices, and interviewed personnel.
It is requested that you carefully review the findings of this
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report for consideration in effecting improvements to your health physics I
program.
The findings of the appraisal at Maine
.ee indicate several weaknesses in the health physics area that appear to I.
related to insufficient personnel
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resources to implement and maintain the radiation protection program. These items were discussed in a meeting between Mr. E. Wood and others of your staff, and Mr. J. White and members of the Health Physics Appraisal Team on January 30, 1981.
RI:FRPS RI:EPS RI:FRPS RI:EP&PSB RI DEP-0S RI:D '
RI: DIRECTOR
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Haynes
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'11050684 811007 R ADOCK 05000309
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Maine Yankee Atomic Power Company
OCT (f 7 1981 We recognize that an explicit regulatory requirement pertaining to each-signif-icant weakness identified in Appendix A may not currently exist. However, to determine whether adequate protection will be provided for the health and safety of workers and the public, you-are requested to submit a written-statement within sixty (60) days of your receipt of this letter, describing your corrective action for each signficant weakness identified in Appendix A, including:
(1)
steps which have been taken; (2) steps which will be taken; and (3) a schedule for completion of action. This request is made pursuant to Section 50.54(f)
of Part 50, Title 10, Code of Federal Regulations.
No items of noncompliance were identified within the scope of this appraisal.
You should be aware that the next step in the NRC effort to strengthen health physics programs at nuclear power plants will be the imposition of a requirement that each licensee develop and implement a Radiation Protection Plan.
Each licensee will be expected to include in the Radiation Protection Plan sufficient measures to provide lasting corrective action for significant weaknesses identified during the special appraisal of the current health physics program.
Guidance for the development of this plan has been developed in draft form and was published as NUREG-0761, " Radiation Protection Plans for Nuclear Power Reactor Licensees."
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosures will be placed in the NRC's Public Document Room.
If this material contains any information that you believe to be proprietary, it is necessary that you make a written application within 20 days to this office to withhold such information from public disclosure. Any such application must be accompanied by an affidavit executed by the owner of the information, which identifies the document or part sought to be withheld, and which contains a statement of reasons which addresses with specificity the items which will be considered by the Commission as listed in subparagraph (B)(4) of Section 2.790. The information sought to be withheld shall be incorporated as far as possible into a separate part of the affidavit.
If we do not hear from you in this regard within the specified period, this letter and the enclosures will be placed in the Public Document Room.
Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely, OriSinal Signed Bgt Ronald C. Haynes Director 0FFICIAL RECORD COPY J
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Maine Yankee Atomic. Power Company
00i 0 7 1981 Enclosures:
1.
Appendix A, Significant Appraisal Findings 2.
Office of Inspection and Enforcement Inspection Report Number 50-309/81-01-cc w/encls:
E. Wood, Plant Super.intendent E. W. Thurlow, President J. H. Garrity, Director,' Nuclear Engineering & Licensing Public Document Room.(PDR)
Local Public Document Roon. (LPDR)
' Nuclear Safety Information Center (NSIC)
State of Maine
.NRC Resident Inspector
' Region I Docket Room.with concurrences)
Chief, Operational Support Section (w/o encis)
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APDENDIX'A Significant Appraisal Findings In the course' of this appraisal, the following items were identified as needing improvement in order to achieve an. acceptable program.
1.. The organizational structure is currently not in -accord with. the recommenda-tions of Regulatory Guide 8.8, NUREG-0731 and NUREG/CR-1280, in that the~
designate _i Radiation Protection Manager is not independent of station divisions having responsibility for the continuity and improvement-of station operability.
(Section 1)
2.
There are marginal personnel resources currently available in terms of supervisory, technical support and technician personnel to support the.
continuity or improvement of the radiation protection program.
(Secticn 1)
3.
Tha licensee procedures do not:
adequately define the basis for surveil-knce activities;' provide sufficient detail; or, reflect current methodology, equipaer c and instructions. Specific subjects or areas requiring improvement-include:
instrument selection and use; survey methodology; instrument calibration techniques; air sampling; daily checks of counting equipment; alarm point settings for_ friskers; use of protective clothing; guidance and procedure for issuing RWP's; and, qualifications of self monitors.
(Section 3.3)
4.
Methods for specifying protective clothing and equipment requirements for extended RWP's to ensure positive management control in this area are not adequately established.
(Section 3.3)
5.
Methods for ensuring that non plant or non-Health Physics personnel are qualified to issue RWP's also needs to be established.
(Section 3.3)
6.
Adequate air samples are not always taken when personnel enter the Reactor Building even for short duration entries. The practice of relying on the installed monitoring system is not considered adequate unless the licensee can demonstrate that the data obtained from that system accurately reflects the air activity.
(Section 3.3)
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The air sampling program does not include:
the use of lapel samplers; guidance for sampling when jobs are in progress; the information recorded; conversion factors used; larger volume gas samples; adequate description of air sampling methods; and the use of the proper equipment, such as orifices, when sampling.
(Section 3.3)
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Appendix A
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Suitable methods for determining efficiencies on health phys 4s counting equipment' for smears and air samples; correcting for quench in the liquid scintillation counter; and, developing suitable standards for ceta and alpha counting of air particulate.. filters have not been established.
(Section 3.3)
9. - Formal procedures are not developed and implemented for the flow devices for all of the type', of' air sarpling devices used~by the licensee.
(Section 3.3)
10.
The calibration program and procedures for portable survey _ instruments and installed area monitors does not meet the recommendations of ANSI N323, " Radiation Protection Instrumentation Test and Calibration."
(Section 3.3)
11. Operational checks of portable survey instruments as recommended in ANSI N323 are not performed.
(Section 3.3)
12. The personn.d responsibilities for the Radioactive Waste Management Program are not established to provide for overall coordination of the program.
(Section 4.0)
13. The licensee's procedures for handling and shipment of radioactive waste do not contain sufficient detail on shipping regulations, burial site criteria or methods used to determine the activity in containers.
(Section 4.0)
14. The calibration procedures for process and area monitors does not provide for electronic calibration of each channel. The licensee.needs to incor-porate methods for controlling the use and the alarm set points of area
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and process monitors.
(Section 4.0)
15. The effects of line loss on the results from particulate and iodine monitor process have not been determined.
(Section 4.0)
16. The information required by the Radioactive Release Permits is not properly recorded in accordance with the procedure.
(Section 4.0)
17. Discrete,i.easurable goals are not sufficiently specified to permit management to assess the performance of the ALARA program.
Formal manage-ment control systems are not established and maintained to monitor,
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control and measure the success of the licensee's efforts in ALARA.
(Section 5.0)
18. Adequate personnel resources are not available to provide technical support to establish, maintain and implement an adequate ALARA program.
(Section 5.0)
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Appendix A
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Improved and/or larger facilities are needed for: Health Physics office and work space; instrument calibration; record storage and work area; respiratory fitting area; whole body counting; instrument, equipment and supply storage; laundry storage, Health Physics Counting Room; Chemistry Counting Room; Chemistry laboratory work area; and, Chemistry sample storage.
(Section 6.0 20.
Procedures are not developed which describe the rationale, methods and equipment for on-site (out-of plant) radiological surveys.
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