ML20059E914
| ML20059E914 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/31/1990 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | GEORGIA POWER CO. |
| Shared Package | |
| ML20059E912 | List: |
| References | |
| NUDOCS 9009110002 | |
| Download: ML20059E914 (5) | |
Text
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[7590-01]
l UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Iri the Matter of GE0h3IA POWER COMPANY Docket No. 50 425 OGLETHOPPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA V0GTLE ELECTRIC GENERATING PLANT, UNIT 1 EXEMPTION I.
Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Gevrgia (the' licensee), are the holders of facility Operating License No. NPF-81 issued March 31, 1989, which l
authorizes full power operation of the Vogtle Electric Generating Plant, Unit 2 (the facility). The license provides, among other things, that it is subject to all rules, regulations and Orders of the Nuclear Regulatory Connission (the Commission)noworhereafterineffect.
The facility consists of a pressurized water reactor at the licensee's site located in Burke County, Georgia.
II.
10 CFR Part 20, Appendix A. " Protection Factors for Respirators," establishes protection factors of air-purifying respirators for protection agsinst particu-lates only. Furthermore, footnote d-2(c) states, "No allowance is to be made for the use of sorbents against radioactive gases or vapors." This restriction was needed since an inadequate data base had existed for evaluating the comple interaction of many factors affecting the service life and removal efficiency of 9000110002 900G31 PDR ADOCK 05000425 F'
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' [7590-01) radioactive gases and vapors by sorbent canisters. Also, due to the lack of a data base, an NIOSH/MSHA certification schedule to ensure that canisters treet acceptable performance criteria has not been established.
10 CFR Part 20.103(e) allows tne Commission to authorize the use of respiratory equipment in lieu of an h10SH/MSHA certification when such an action is justified based on adequate testing of material and performance characteristics. An application by a licensee for this authorization must include a demonstration by testing, or on the basis of reliable test information, that the material and perforrrance characteristics of the equipnent j
arc capable of providing the proposed degree of protection uncer anticipated conditions of use. The licensee has made such an application.
10 CFR Part 20.501 allows an exemption to be granted by the Commission from the requirerrents of the regulations in 10 CFR Part 20 as it determines is authorized by law and will ret result in undue hazard to life or property.
P,y letter dated September 28, 1989 (ELV-00902), the licensee requested an exemption based on 10 CFR 20.501 to allow the use of radiciocine MSA GMR-1 cenisters with a protection factor of 50 for personnel respiratory protection.
The licensee also requested an allowance to store the MSA GMR-1 canisters in a Class C storage envircnment as defined in ANSI N45.2.2. A similar exemption from 10 CFR Port 20 was granted to Vogtle Electric Generating Plant, Unit 1 on October 27, 1988, and subsequently arwnded on February 23, 1990, in support of the Unit 2 exemption request, the licensee citto research data, test results, test protocol and a qutlity assurance sampling plan that, according to the licensee, satisfies the recommended qualification process of NUREG/CR-3403,
" Criteria and Test Methods for Certifying Air-Purifying Respirator Cartridscs l
and Canisters Against Radiciodine."
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' [7590-01)
The Connission's staff evaluated the information provided by the licenset to support the exemption request. The Conimission's Safe.f Evaltation on this matter relating to the use of a radioiodine protection factor of 50 for GMR-1 canisters at Vogtle 2 is being issued concurrently with this Exemption. The Safety Evaluation concludes that the licensee's proposed use of radiofodine MSA GMR-1 canisters with certain usage restrictions and controls can result 'n significant dose savings over alternative methods while still providing effective protection.
III.
Accordingly, the Commission has deterciined that, pursuant to 10 CFR 20.501, an exeniption as requested by the licensee's letter of September 28, 1989, is authcrized by law and will not result in undue hazaro to life or property. The Commission hereby grants an exemption from the restriction of 10 CFR Part 20, Appendix A, footnote d-2(c), and authorizes the use of the MSA GMR-I canister, with restrictions as shown in Attachment 1 to this exemption. Attachment 1 allows storage of the NSA GMR-1 canisters in Class C storage environments. The exemption is subject to mooification by rule, regulation, or Orcer of the Connission.
Pursuant to 10 CFR 51.32. the Consnission has determineo that the issuance of the exemption will have no significant ir. pact on the environment, l
(55 FR 35480).
o e
. [7590-01) i This exemption is effective upon issuance.
Dated at Rockville, Maryland this 31st day of August,1990.
FOR THE NUCLEAR REGULATORY COMNISL IN I
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CA,
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>ven rgd. Wlrec or Division of Reactor Pr ts - 1/II Office of Nuclear Reactor Regulation
Attachment:
Usage Restrictions
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Limitations, Usage Restrictions, and Controis Applicable to the Use of MSA GMR-I Canister at the Vogtle Electric Generating Plant, Unit 2 1.
Protection factor equal to 50 as a maximum value.
2.
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 C or better environment, as defined in ANSI N45.2.2.
5Property "ANSI code" (as page type) with input value "ANSI N45.2.2.</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 full facepiece capable of providing a fit factor equal to or greater than 500.
7.
Canisters are not to be used in total challenge concentrations of organic iodines and other halogenated compounds greater than 1 ppm, including nonradioactive compounds.
8.
Canisters are not to be used in environments where temperatures are greater then 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 measured prior to and/or during the use of GMR-I 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 GMR-1 canister found to have exceeded 3 years f rom date of manufacture will not be used for protection against radioactive iodine.
4 In the initial implementation of the GMR-I program, the following verification measures will be in effect:
a.
Weekly whole body counts for indi. duals using the GMR-I canisters for radioiodine protection; b.
A whole body count for individuals that exceed 10 MPC in a week and used the GMR-I canister for respiratory protection in that period; Anyone that measures 70 nCI or greater iodine uptake to the thyroid c.
during a whole body count will be restricted from entering a radioiodine atmosphere pending Health Physics evaluation; d.
The radiological survey and whole body count information will be compiled to evaluate the effectiveness of the program.
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