ML20195B533
| ML20195B533 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/27/1988 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | GEORGIA POWER CO. |
| Shared Package | |
| ML20195B535 | List: |
| References | |
| NUDOCS 8811020064 | |
| Download: ML20195B533 (4) | |
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7590-01 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION in the Matter of
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GEORGIA POWER COMPANY
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Docket No.
50-424 OGLETHORPE POWER CORPORATION
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MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA
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CITY OF DALTON, GEORGIA
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V0GTLE ELECTRIC GENERATING PLANT, UNIT 1
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f EXEMPTION l
l Georgia Power Capany. Oglethorpe Power Corporation. Municipal Electric Authority of Georgia, and City of Oalton, Georgia (the licensee), are the holders of Facility Operating License No NPF-68 issued March 16. 1987, which authorizes full power operation of the Vogtle Electric Generating Plant. Unit 1 (the facility). The license provides, among other things, that it is subject to all rules, regulations and Orders of the Comission.
The facilty consists of a pressurized water reactor at the licensee's site location in Burke County. Georgia.
II.
10 CFR Part 20. Appendix A. "Protection Factors for Respirators." estab-lishes protection factors of air-purifying respirators for protection against particulates only.
Furthermore, footnnte d-2fc) states. "No allowance is to be l
made for the use of sorbents against radioactive gases or vapors." This l
8911020064 001027 DR ADOCK 050 44 i
1 restriction was needed since an inadequate data base had existed for evaluating the compivx interaction of many factors affecting the service life and removal officiency of radioactive gases and vapors by sorbent canisters. Also, due tte the lack of a data base, a NIOSH/MSHA certification schedule to ensure that canisters meet acceptable performance criteria has not been established.
10 CFR Part 20.103(v) allows authurization by the Commission in lieu of a NIOSH/MSHA certification schedule based on adequate testing, material and performance characteristics. An application by a licensee for this authoriza-tion must include a demonstration by testing, or on the basis of reliable test information, that the material arid performance characteristics of the equipment are capable of providing the propused degree of protection under anticipated conditions of use. The licensee made such en application.
10 CFR Part 20.501 allcws an exemption to be granted by the Commission f'um the requirements of the regulations in 10 CFR Part 20 as it determin~es are authorized by law and will not result in undue hazard to life or property.
By lester dated August 26, 1988, as supplemented October 6, 1988, the licensev requested an exemption based on 10 CFR 20.501 to allow the use of radiciodine MSA GMR-I canisters with a protection f actor of 50 for personnel respiratory protection during scheduled refueling outage work. The liceitur cited research data, test results, test protocol and quality assurance sampling plan that it stated satisfies the recomendeo qualification process of NUREG/CR-3403, "Criteria and Test Methods for Certifying Air-Purifying Respirator Cartridges and Canisters Against Radiotodine." The NRC staff
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. evaluated the infonnation provided by the licensee to support the exemption request. The NRC staff's safety evaluation on this matter relating to the use of a radioindine protection factor for GMR-1 canisters at Vogtle 1 has been issued. The safety evaluation concludes that the licensee's proposed use of radioiodine MSA GMR-! canisters with certain usage restrictions and controls can result in significant dose savings over alternative methods while still providing effective protection.
III.
Accordingly, the Comission has determined that, pursuant to 10 CFR 20.501, an exerption as requested by the licensee's letter of Augu2t 26, 1988, as supplemented October 6, in88, is authorized by law and will not result in undue hazard to life or property. The Comission hereby grants an exemption from the restriction of 10 CFR Part 70 Append x A, footnote d-2(c), and authorizes the use of the MSA GMR-! canister, with restrictions as shown in Attachrent 1 to this exemption. The exemption is subject to modification by rule, regulation or Order of the Comission.
Pursuant to 10 CFR 51.32, the Comission has determired that the issuance of the exemption will have no significant impact on the environment (53FR 36925).
This exemption is effective upun issuance.
O Dated at Rockville, Maryland this 27 day of October 1988 FOR THE NUCLEAR REGULATORY C0'NISS10N Original Signed By:
Steven A. Varga, Director Divisinn of Reactor Projects 1/11 Office of Nuclear Peactor Regulation
Attachment:
Usace Restrictions
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- t. imitations. Usage Restrictions. and Centrols Applicable to the Use of MSA GMD-! Canister et the Vogtle Electric Generating Plant Unit 1 1.
Protection factor equal to 50 as a maximum value.
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The maximum permissible continuous use time is eight hours after which the canister will be discarded.
3.
Canisters are not to be used in the presence of organic solvent vapors.
4 Canisters are to be stored in a Class A or better environment, as defined in ANSI N45.7.2.
5Property "ANSI code" (as page type) with input value "ANSI N45.7.2.</br></br>5" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..
The allowable service life for sorbent canisters is to be calculated from the time of unsealing the canister, including periods of non exposure.
6.
Canister is to be used with a 'ull facepiece capable of providing a protection factor equal to or greater than 500.
7.
Canisters are not to be used in total challenge concentrations of organic todines and other halogenated corpounds greater than 1 ppm, including nonradioactive compounds.
8.
Canisters are not to be used in environfuents where temperatures are greater than 110*F, or up to 120'F if the dewpoint is equal to or less than 107'F.
In addition to the limitations and usage restrictions noted above, the following additional controls will be utilized by the licensee:
1.
Temperatures will be treasured prior to and/or during the use of GMR-!
canisters to assure that work temperatures are within limits.
2 Air samples will be taken prior to and during any activities that involve the use of the GMR-i canister for protection against radioactive iodine.
3.
A @R-I canister found to have exceeded 3 years ' rom date of manufacture will not be used for protection against radioactive iodine.
4 In the initial implementation of the GMR-! program, the following verif-ication measures will be in effect:
- a. Weekly whole body counts 'or individuals using the GMR-! canisters for radioiodine protection;
- b. A whole boci Count for individuals that exceed 10 MPC in a week and used the GWR-! canister for respiratory protection in that period;
- c. Anyone that measures 70 nCl or greater iodine uptake to the thyroid during a whole body count will he restricted from enterine a radiciodine atmosehere peading Wealth Dhysics evaluation;
- d. The radiological survey and whole body count information will be ccroiled to evaluate the effectiveness of the program.