ML20076B505
| ML20076B505 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Point Beach |
| Issue date: | 10/22/1981 |
| From: | Kreger W Office of Nuclear Reactor Regulation |
| To: | Novak T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19302F297 | List:
|
| References | |
| FOIA-82-309 NUDOCS 8111090062 | |
| Download: ML20076B505 (4) | |
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'c NUCLEAR REGULATORY COMMISSION W ASHINGT ON. D. C. 20555 s,. m /
cket No.:
50-266 OCT 2 21981 h'
MEMORANDUM FOR: Thomas A. Novak, Assistant Director for Operatirig ' Reactors,* 'DL FROM:
William E. Kreger, Assistant Director for Radiation Protection, DSI
SUBJECT:
POINT BEACH UNIT 1 SAFETY EVALUATION REPORT FOR PROPOSED STEAM GENERATOR SLEEVING DEMONSTRATION PLANT NAME:
Point Beach, Unit 1 LICENSING STAGE: OR DOCKET NUMBER:
50-266 RESPONSIBLE BRANCH: ORB #3; T. Colburn, PM DESCRIPTION OF RESPONSE: SER Input for proposed demonstration Enclosed is the Safety Evaluation Report for the proposed steam generator sleeving demonstration at Point Beach, Unit 1, concerning the radiation pro-tection and ALARA aspects of that dmonstration.
This review Eas performed by Jack Nehemias, RPS, RAB.
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William E. Kreger Assistant Director for Radiation Protection Division of Systems Integration
Enclosure:
As Stated cc: w/ enclosure R. Mattson F. Congel D. Collins J. Nehmias LW. C1 ark T. Colburn
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- s SAFETY EVALUATION REPORT FOR POINT BEACH STEAM GENERATOR SLEEVING Section 8 ALARA Considerations The licensee has taken into account ALARA considerations for each of the radiation activities involved in the proposed steam generator sleeving demonstration at Point Beach. ALARA activities specifically directed to reduction of occupational radiation exposures include: decontamination of steam generators, personnel train-ing in full-size mo:kups, installation of shielding if necessary to reduce radiation exposures to repair personnel.
Administrative control of personnel exposures will be effected by careful planning of maintenance procedures for the job, in order to minimize the number of personnel used to perform the various tasks involving relatively high doses and dose rates.
TV surveillance of personnel during tasks will be used to identify areas resulting in high exposures, and thus to initiate suitable dose-reducing actions.
Based on prior inplant experience with channel head decontamination and laboratory decontamination, no significant increase in airborne radioactivity is to be expected.
However, vapors from the channel head will be drawn through a high efficiency air particulate filtration system before release to the plant filter system. All sleeving operations will be monitored to keep airborne releases to a minimum. The licensee does not expect that auxiliary ventilation or special enclosures will be necessary.
The licensee has made use of experience gained in prior channel head decontamination in planning for the proposed tube sleeving activities.
Data were available for Point Beach (Unit 1), Takahoma (Unit 1), San Onofre (Unit 1), and Turkey Point (Unit 3).
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- In particular, the applicant considered infonnation on mechanisms used in prior decontamination.
The licensee has provided'inTormation relevant to projected occupational radiation exposures resulting from the demonstration decontamination /
sleeving program at Point Beach Unit 1, as well as from the proposed full-scale sleeving program for both units.
The licensee has estimated the radiation doses likely to be associated with the processes involved in the sleeving program:
a) installation of remoting tools and equipment, 5 person, rems b) decontamination of the steam generator, 10 person-rems (including tube decontamination),
c) installation of additional shielding, if necessary, 10.6 person-rems (9.5 for the channel head,1.1 for nozzle shield removal),
d) inspection and testing, 2.9 person-rems (92 millirems / sleeve eddy current inspection, 300 millirems / sleeve test),
e) - de-plugging tubes for sleeving, l
3.4 person-rems / tube (explosive),
l f) sleeving l
4-5 person-rems / tube l
The licensee has provided realistic estimates of dose rates and occupancy factors, as
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l the bases for these dose estimates, and has estimated that the total person-rem dose resulting from the demonstration sleeving program at Point Beach Unit 1, at 48-60 l
person-rems, assuming a decontamination factor of about 2.5.
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3-The radiation exposure data and the operational experience resultiry from the proposed demonstration of the sleeving"plocess at Point Beach, Unit 1, will be a test of proposed radiation control techniques, and will provide a basis for a more refined and more precise estimation of doses likely to result from the l
proposed future sleeving process for both units.
Based on our review of the Point Beach Report, and the additional information provided, we conclude that the licensee's estimated dose for this project appears reasonable and that the licensee intends to implement reasonable radiation pro-tection actions that should maintain in-plant radiation exposures within the applicable limits of 10 CFR Part 20, and should maintain exposures ALARA.
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