ML20214U736
| ML20214U736 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/03/1986 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | KANSAS CITY POWER & LIGHT CO., KANSAS ELECTRIC POWER CORP, INC., KANSAS GAS & ELECTRIC CO. |
| Shared Package | |
| ML20214U739 | List: |
| References | |
| TAC-59366, NUDOCS 8612090378 | |
| Download: ML20214U736 (4) | |
Text
i 7590-01 i-UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION i
In the Matter of i
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Kansas Gas and Electric Company
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)
Kansas City Power & Light Company
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Docket No. 50-482
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Kansas Electric Power Cooperative, Inc. i
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(WOLFCREEKGENERATINGSTATION)
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EXEMPTION I.
Kansas Gas and Electric Company, Kansas City Power & Light Company, and Kansas Electric Power Cooperative, Inc. (the licensee) are the holders of Facility Operating License No. NPF-42, issued June 4,1985, which authorizes operation of the Wolf Creek Generating Station (the facility) at steady-state reactor power levels not in excess of 3411 megawatts thermal. This license provides, among other things, that it is subject to all rules, regulations and Orders of the Commission now or hereafter in effect. The facility consists of a pressurized water reactor located in Coffey County, Kansas.
~
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, 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 complex interaction of many factors affecting the service life and removal efficiency of radioactive gases and vapors by sorbents car.sters.
8612070378 861203 PDR ADOCK 05000482 P
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- Also, due to the lack of a data base, a NICSH/MSHA certification schedule to ensure that canisters meet acceptable performance criteria has not been established.
However,10 CFR Part 20.103(e) allows an exemption to be authorized by the Commission in lieu of a NIOSH/MSHA certification schedule based on adequate testing, material and perfonnance 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 perfon ance characteristics of the equipment are capable of providing the proposed degree of protection under anticipated conditions of use. The licensee makes such an application.
By letter dated July 1,1985, as supplemented by letters dated November 8, 1985, and May 6, 1986, the licensee requested an exemption based on 10 CFR 20.103(e) to allow the use of a protection factor of 50 when utilizing radio-iodine GMR-I canisters for personnel respiratory protection during scheduled refueling outage work. The licensee cited research data, test results, test protocol and a quality assurance sampling plan that it stated satisfies the recorriended qualification process of NUREG/CR-3403. The Comission staff evaluated the infonnation provided by the licensee to support the exemption request. The Comission's safety evaluation on this matter relating to the use of a radiciodine protection factor for GMR-I canisters at Wolf Creek has been issued. The safety evaluation concludes that the licensee's proposed use of radioiodine GMR-I canisters with certain usage restrictions and controls can result in significant dose savings over alternative methods while still providing effective protection.
p III.
Accordingly, the Commission IPds determined that, pursuant to 10 CFR 20.501,
.an exemption as requested by the ' licensee's letter of July 1,1985, and supple-mented November 8, 1985, and May 6, 1986, is authorized by lay and will not result in undue hazard to life or property. The Comission hereby grants an exemption from the restrictions of 10 CFR Part 20, Appendix A, footnote d-2(c),
and authorizes the use of the Ct!R-I canister, with restrictions as shown in Attachment I to this exemption. The exemption is subject to modification by rule, regulation or Order of the Comissicn.
Pursuant to 10 CFR 51.32, the Comission has detennined that the issuance of the exemption will have no significant impact on the environment (51 FR42950).
This Exemption is effective upon issuance.
rd Dated at Bethesda, Maryland this 3 day of December 1986.
FOR THE NUCLEAR REGULATORY COMMISSION Original SiSned b71 nocas M. Novak Thomas M. Novak, Acting Director Division of PWR Licensing-A Office of Nuclear Reactor Regulation
Attachment:
As stated
- SEE PREVIOUS CONCURRENCES
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Limitations, Usage Restrictions, and Controls Applicable to the Use of GMR-1 Canister at the Wolf Creek Gercrating Station 1.
Protection factor equal to 50 as a maximum value.
2.
The maximum pennissible continuous use time is eight hours after which tFe canister will be discarded.
3.
Canisters are not to be used in the preser.ce of organic solvent vapors.
4.
Canisters are to be stored in seeled, humidity barrier packaging in a cool, dry environment.*
5.
The allowabic service lift 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 pro-tection factors greater than 100.
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 than 120'F, or dewpoint exceeds 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 coincidently with the use of GMR-I canisters to assure that work temperatures do not exceed 120*F or ter.iperature corresponding to a dewpoint of 107'F during sorbent canister use.
2.
In the initial implementation of sorbent canister use, the following pro-gram verification measures will be used:
a.
weekly whole body counts for individuals using the sorbent canister for radiciodine protection; b.
for individuals who exceed 10 MPC hours in seven consecutive days, a whole body count will be required prior to their next entry into a radiciodine atmosphere (i.e., effectively a 10 MPC hour stay time);
c.
if an individual measures 70nci or greater iodine uptake to the thyroid during a whole body count, the individual's entry into radiofodine atnospheres will be restricted pending health physics evaluation; d.
a whole body count / survey data base will be compiled to evaluate the results of the program.
- Sorbent canisters will be stored in conditions not to exceed 90'F or 70%
humidity in accordance with Procedure HPH 06-XXX (currently in draft).