ML20207J540
| ML20207J540 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/29/1986 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | UNION ELECTRIC CO. |
| Shared Package | |
| ML20207J546 | List: |
| References | |
| NUDOCS 8701080510 | |
| Download: ML20207J540 (4) | |
Text
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7590-01 l
UNITFI' ST/TES CF Af/EhlCA NUCLEAR REGULATORY COVI'ISSICN I
In the Matter of
)
Union Electric Cerpariy
)
Docket No. 50-4E3
)
(CALLAWAYPLAhT)
EXEt:PT10f4 l
I.
v l'r.fcr Electric Company, (the licer.see) is the holder of Facility Cpr.rt. tire License No. f.PF-30, issued October 18, 1984, which authorizes ooeration of tFr Callaway Plant (the faci,1,ity) at steady-state reacter ocwer levels not in excess of 3411 mecawatts ttciTaol. This license provides, amor.g cther things, that it is subject to all rules, regulations ard Orders of the Commission now
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or hereafter in effect. The facility consists of a pressurized water reactcr j
a located in Callaway County, fiisscuri.
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II.
10 CFR Part 20, Appendix A, " Protection Factors for Respiratcrs," ef teb-t lishes protecticn factors of air-purifying respirators for protection aoainst particulates only.
Furthermore, footnote d- (c) states, "No allowance is to be made for the use of sorberts agcir,st radioactive gases or vapors." This restriction was needed since an inadequi.te data base had existed for evaluatir.9 the complex interaction of many factors affectirs the service life and removal l
efficiency of radicactive reses and vapors by sorbents canisters.
87010 g Q $ $$ e3 PDR PDR,
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' a-Also, due to the lack of a data base, a NIOSH/MSHA certification schedule to ensure that canisters meet acceptable performance criteria.has not been established.
However,10 CFR Sections 20.103(el and 20.501 allow an exemption to be authorized by the Commission in !ieu of a NTOSH/MSHA certification schedule based on adequate testino, material and perfomance characteristics. An application by a licensee for this authorization must include a demonstration by testing, or on the basis of reliable test infomation, that the material and performance characteristics of the equipment are capable of providing the i
I proposed degree of protection under anticipated conditions of use. The licensee has trade such an application.
1 By letter dated October 22, 1985, as supplemented by letter dated August 29, 1986 the licensee requested an exemption based on 10 CFR 20.103(el to allow the use of a protection factor of 50 when utilizing radioiodine 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 recommended qualification process of NUREG/CR-3403. The Commission staff evaluated the information provided by the licensee to support the exemption request. The Commission's safety evaluation on this matter relating to the use of a radiciodine protection factor for GMR-I canisters at Callaway 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.
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DEC 2 9 1986 III.
Accordingly, the Cctrn.ission has determined that, pursuant to 10 CFR 20.501, an exerrotien as requested by the licensee's letter of October 22, 1985 as supplerrented August 29, 1986, is authorized by law and will not result in undue hazard to life or preferty.
The Cornaission hereby grants an exercption frce: the restrictions of 10 CFR Part 20, Aprcrdix A, footnote d-2(c), and authorizes the use of the GMR-I canister, with restrictions as shown in Attachrcent 1 to this exemption. The exception is subject to modification by rule, regulation or Order of the Cor.raission.
Pursuant to 10 CFR 51.32, the Ccomission has determined that the issuance of the exerrotten will have no significant irr> pact on the environnent (51 FR
).
This Exervtion is of fective upon issuance.
Dated at Bethesda, Maryland this5N day of DCowdM 1986 FCR THE h0 CLEAR REGULATORY CClil!ISS10fi Theras fi. flovak, Acting Directcr Division of PWR Licensing-A Office of ?!uclear Reacter Pegulaticn Attachr;ent:
As stated
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V Limitations, Usage Restrictions, and Controls Applicable to the Use of GMR-1 Canister at the Callevey Plant 1.
Protection factor equal te 50 as a maximum value.
2.
The maxircir rerrissible continuous use tirce is eight hours af ter which the canister will be discardcd.
3.
Canisters are not to be used in the presence cf crganic solvent vapors.
4.
Canisters are to be stored ir scaled, huuidity barrier packaging in a cool, dry environment.*
5.
Tne allowable service life for sorbent canisters is to be calculated from the time of unsealing the canister, including periods of ncn-exposure.
6.
Canister is to tc t' Fed with a full facepiece capable of proviaing pro-tection factors greater than 100.
7_,
Canisters are r.ot to be used in total challenge concentrations of organic iodines and other balogenated compounds greater than 1 ppni, including nonracioactive compounds.
8.
Canisters are not to be used in environments where tenrperatures are greater than 120 F, or dewpo,irt excetes 107'F,.
In addition to the limitations and usage restrictions noted above, the following additional controls >;ill 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 ten.perature corresponding to a dewpoint of 107'F during sorbent canister use.
2.
In the initial implementation cf scrbent canister use, the following pre-grar verificaticn measures will be used:
a.
weekly whole body counts for individuals using the Sorbent 1
canister for radiciodine protection; j
b.
for individuals who exceed 10 PPC bours in seven consecutive days, a whole body ccunt will be required prior to their next entry into a radiciocine atmosphere (i.e., effectively a 10 MPC hour stay time);
c.
if an individual masures 70nci or greater icdine uptake to the thyrcid during a whole body count, the individual's entry into radiciodine atmospheres will be restricted pending health physics evaluaticr; d.
a whole bocy count / survey data base will be comofled to evaluate the results of the program.
- Sorbent canisters will be stored in conditions not to exceed S0*F or 70%
humidity in accordance with Procedure HPH 06-XXX (currently in draft).