ML20002A404
| ML20002A404 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee, Yankee Rowe, Maine Yankee, La Crosse |
| Issue date: | 06/16/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20002A397 | List: |
| References | |
| NUDOCS 8011170081 | |
| Download: ML20002A404 (4) | |
Text
l UNITED STATES NUCLEAR REGULATORY COMMISSION y
7
,, j WeASHINGTON. D. C. 20665 e
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENTS NOS. 40, 36 and 30 TO FACILITY OPERATING LICENSES N05. DPR-3, DPR-28 AhD DPR-36 I
YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION (YANKEE-ROWE)
DOCKET NO. 50-29 VERMONT YANKEE NUCLEAR POWER CORPORATION VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271 FAINE YANKEE ATOMIC POWER COMPANY MAINE YANKEE ATOMIC POWER STATION DOCKET NO. 50-309 t
INTRODUCTION By applications, Yankee Atomic Electric Company (March 9,1977), Vermont Yankee Nuclect Power Corporation (March 30, 1977), and Maine Yankee Atomic r
Power Company (March 3,1977) (the licensees) requested amendment to their respective Facility Operating Licenses Nos. DPR-3, DPR-28, and DPR-36.
The amendments would modify the Technical Specifications for Yankee-Rowe, Vermont Yankee, and Maine Yankee Power Stations relating to controlled entry into high radiation areas. The above-mentioned applications are complete revisions of earlier applications and are based on our discussions with the licensees.
f DISCUSSION AND EVALUATION The proposed change would allow the use of radiation dose' integrating
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devices with an alarm feature or supervision of ongoing work by health physics qualified pe, sonnel as options for personnel entry into high l
r radiation areas. These are alternatives to the current Technical Specifi-cations for each facility which states that "any individual or group of individuals permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area." The change is intended to provide better exposure control during certain operations by use of electronic devices which alarm after pre-set doses have been reached, in lieu of administrative controls which depend on dose rate measurements and the calculations of commensurate " stay times". Also, 801117008/
. during a major shutdown, use of health physics qualified individuals to perform independent periodic radiation surveys would be more desirable than the use of non-qualified individuals who have other tasks to perfom.
The licensees have also proposed that Health Physics personnel not be required to have a Radiation Work Permit (RWP) when entering a high radiation Since Health Physics Department personnel are qualified to evaluate a rea.
and set radiological standards for specific activities is specific areas, this proposal is appropriate.
We have evaluated the licensees' rationale for using alarm dosimeters and their safety considerations with respect to radiation exposure control.
We find that since personnel integrating alarm dosimeters are state-of-the-art instruments in radiation protection programs, and since their use is practicable and desirable in areas where high radiation levels may vary significartly within the area, that the proposed Technical Specifi-cation change is acceptable for radiation personnel monitoring in high radiation areas. The change requires that each individual wearing these devices be made aware of the radiation levels prior to entry into a high radiation area.
Additionally, we concur that a health physics qualified individual (i.e.,
qualified in radiation protection procedures as shown in Appendix 1*) using a dose rate monitoring device to periodically monitor areas at the fre-quency specified by the Plant Health Physicist is an effective method of controlling radiation exposure to people in high radiation areas. We find that there would be positive control over the activities of those people working in the area by an independent person who would assure radia-tion protection management that the conditions of the RWP were being properly administered.
exempt from Finally, we aaree that Health Physics personnel should be'ide the radia-RWP issuance since these individuals are required to prov tion protection control techniques specified in the RWP, and therefore must first enter high radiation areas in order to perform relevant radiological surveillance.
Furthermore, they are required to follow plant radiation protection procedures that they have written prior to entry into high radiation areas.
Based on the above we conclude that the changed requirements for entry into high radiation areas are acceptable as proposed.
- Appendix 1 is attc hed to this Safety Evaluation
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a s.
ENVIRONMENTAL CONSIDERATIONS We have-determined that the amendments do not authorize a change in effluent types or total amounts nor an increase in power level and Having made will not result in any significant environmental impact.
this determination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact and pursuant to 10 CFR 551.5(d)(4) that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of these amendments.
CONCLUSION We have concluded, based on the considerations discussed above, that:
(1) because the amendments do not involve a significant increase in the probability or consequences of accidents previously considered and do not involve a significant decrease in a safety margin, the amendments do not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Dated: June 16,1977 N
APPENDIX 1.
s CRITERIA FOR " INDIVIDUALS OUALIFTED IN RADIATION PROTECTION PROCEDURES" An individual is considered to be qualified in radiation protection procedures when a licensee certifies that each designated individual is capable of successfully accomplishing the following activities as required by federal regulations, license conditions, and facility procedures pertaining to radiation protection.
1.
Conduct special and routine radiation, contamination and airborne radioacti,ity surveys and evaluate the results.
2.
Establish protective barriers and post appropriate radiological signs.
3.
Establish means of limiting exposure rates and accumulated radiation doses, including tne use of protective clothing and respiratory protection equipment.
4.
Perform operability checks of radiation monitors and survey meters.
5.
Recommend appropriate immediate actions in the event of a radiological problem and perform necessary activities until the arrival of health physics personnel.
6.
Conduct other routine radiological duties (e.g.,15 surveillance items) as may be required on backshifts or weekends.
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