ML20247H567
| ML20247H567 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/16/1989 |
| From: | Crocker L Office of Nuclear Reactor Regulation |
| To: | Hairston W GEORGIA POWER CO. |
| Shared Package | |
| ML20247H571 | List: |
| References | |
| TAC-71145, TAC-71146, NUDOCS 8909200021 | |
| Download: ML20247H567 (2) | |
Text
!
.c March 16, 1989
'~
Docket Nos. 50-321 50-366 Mr. W. G. Hairston, III Senior Vice President -
Nuclear Operations Georgia Power Company P. O. Box 1295 Birmingham, Alabama 35201
Dear Mr. Hairston:
SUBJECT:
EXEMPTION AND AUTHORIZATION FOR USE OF SOLVENT IODINE CANISTERS, EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 (TACS 71145/71146)
The Nuclear Regulatory Connission has granted the enclosed Exemption and authorized the use of a radiciodine protection factor of 50 for certain res-piratory protection canisters used by workers at the Hatch Nuclear Plant, Units 1 and 2.
The Exemption and authorization was granted in response to I
your letter dated October 25, 1988, as supplemented January 12, 1989.
We find that granting the Exemption is authorized by law and will not result in undue hazard to life or property.
Also enclosed is a safety evaluation supporting granting of the Exemption and authorizing the use of equipment which has not been certified by NIOSH/MSHA.
The Exemption is being forwarded to the Office of the Federal Register for publication.
Sincerely, Lawrence P. Crocker, Project Manager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
Exemption 2.
Safety Evaluation cc w/ enclosures:
See next page 8909200021 890316 PDR ADOCK 05000321 P
- SEE PREVIOUS CONCURRENCES PDII-3 PDII-3 PRPB:NRR PDII-3
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- LCunningham
- DMatthews 1/11/89 1/11/89 1/24/89 2/24/89
Mr..W. G. Hairston, III Edwin I. Hatch Nuclear Plant, Georgia Power Company -
Units Nos. 1 and 2 cc:
G. F.'Trowbridge, Esq.
Mr. R. P. Mcdonald Shaw, Pittman, Potts and Trowbridge Executive Vice President -
2300 N Strr>at, N. W.
Nuclear Operations
'Washingto)
C.
2CO37 Georgia Power Company P.O. Box 1295 Mr. L. T uucwa Birmingham, Alabama 35201 Engineering Department Georgia Power Company
.P. O. Box 1295 Birmingham, Alabama 35201 Nuclear Safety and Compliance Manager Edwin I. Hatch Nuclear Plant Georgia Power Company P. O. Box 442 Baxley, Georgia.31513 Mr. Louis B. Long Southern Company Services, Inc.
P. O. Box 1295 Birmingham, Alabama 35201
~ Resident Inspector U.S. Nuclear Regulatory Comission Route 1, Box 725 Baxley, Georgia 31513 Regional Administrator, Region II U.S. Nuclear Regulatory Comission 101 Marietta Street, Suite 2900 Atlante, Georgia 30323 Mr. Charles H. Badger l
Office of Planning and Budget Room 610 270 Washington Street, S.W.
' Atlanta, Georgia 30334 Mr. J. Leonard Ledbetter, Commissioner Department of Natural Resources 270 Washington Street, N.W.
Atlanta, Georgia 30334 Chairman Appling County Commissioners County Courthouse Baxley, Georgia 31513
'
- f.
March 16, 1989 l
DISTRIBUTION Docket File NRC PDR Local PDR PDIl-3 Reading TMurley/JSniezek 12-G-18 D. Crutchfield 12-G-18 S. Varga 14-E-4 G. Leinas 14-H-3 D. Matthews 14-H-25 M. Rood 14-H-25 Lv-Crocker 14-H-25 C. Rossi 11-E-4 OGC 15-B-18 E. Jordan fiNBB-3302 B. Grimes 9-A-2 T. Meek (8)
P1-137
-ACRS (10)
H-1016 GPA/PA 17-F-2 ARM /LFMB AR-2015 VOGTtE PLANT FILE Nabh.,
i 4
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l s
_.___.____._______..._.___A.___
________.___.____.____._.___________._______m_____
7590-01 tiNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
)
)
.20RGIA POWER COMPANY
)
Docket Nos.
50-321 OGLETHORPE POWER CORPORATION
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50-366 MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA
)
CITY OF DALTON, GEORGIA
)
)
EDWIN 1. HATCH NUCLEAR PLANT, UNITS I and 2 )
EXEMPTION I.
Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensee), are the holders of Facility Operating Licenses Nos. DPR-57 and NPF-5, which authorize full power operation of the Edwtn I. Hatch Nuclear Plant, Units 1 and 2, respec-tively (the facility). The licenses provide, among other things, that they are subject to all rules, regulations and Orders of the Commission.
The facility consists of two boiling water reactors at the licensee's site located in Appling County, Georgia.
II.
10 CFR Part 20, Appendi). A, " Protection Factors for Respirators," estab-lishes protection factort, of air-purifying respirators for protection against particulate 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 h
2 efficiency of radioactive gases and vapors by sorbent canisters.
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.
10 CFR Part 20.103(e) allows authorization by the Comission 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 incluce a demonstration by testing, or on the basis of reliable test information, that the r.aterial and performance characteristics of the equipment are capable of providing the proposed degree of protection under anticipated conditions of use. The licensee mode such an application.
10 CFR Part 20.501 allows an exemption to be granted by the Comission from the requirements of the regulations in 10 CFR Part 20 as it determines are authorized by law and will not result in undue hazard to life or property.
By letter dated October 25, 1988, as supplemented January 12,1989, the licensee requested an exemption based on 10 CFR 20.501 to allow the use of PSA GMR-1 canisters with a protection factor of 50 or greater for personnel respiratory protection against radiciodine and particles.
The licensee cited research data, test results, test protocol and quality assurance controls that it stated satisfy the recommended qualification process of NUREG/CR-3403,
" Criteria and Test Methods for Certifying Air-Purifying Respirator Cartridges and Canisters Against Radiciodine." The NRC staff evaluated the information provided by the licensee to support the exemption request. The NRC staff's safety evaluation on this matter relating to the use of MSA GMR-I canisters for protection against radiciodine at Hatch Units 1 and 2 has been issuet'. The safety evaluation concludes that the licensee's proposed use of tGA GMR-1
. ' ' canisters for radiciodine protection with certain usage restrictions and controls con result in significant dose savings over alternative methods while still providing effective protection.
111.
Accordingly, the Commission has determined that, pursuant to 10 CFR 20.501, an exemption as requested by the licensee's letter of October 25, 1988, as supplemented January 12, 1989, is authorized by law nnd will not result in undue hazard 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-1 canister, with restrictions as shown in Attachment I to this exemption. The exemption is subject to modification by rule, regulation or Order of the Commission.
Pursuant to 10 CFR 51.32, the Commission has determined that the issuance of the exemption will have no significant impact on the environment (54FR11093).
This exemption is effective upon issuance.
th Dated at Rockville, Maryland, this 16 day of March 1989 FOR THE NUCLEAR REGULATORY COMMISSION Bruce A. Boger, Acting Director Division of Reactor Projects 1/II Office of Nuclear Reactor Regulation
Attachment:
Usage Restrictions
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N.7 Limitations, Upce Restrictions, and Controls Applicable i
u to th se of MSA GMR-I Canister at the Edwin I
.tch Nuclear Plant, Units I and 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 preser.ce of organic solvent. vapors.
4 The allcwable service life for sorbent canisters is to be calculated frem the time of unsealing the canister, including periods of non-exposure.
5.
Canister is to be used with a full facepiece capable of providing a fit factor equal to or greater than 500.
6.
Canisters are not to be used in total challenge concentrations of organic iodines and other halogenated cog ounds greater than 1 ppa, including nonradioactive compounds.
7.
Canisters are not to be used in environments where temperatures are greater i
than 110*F, or up to 120*F if the dowpoint 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 uw 9f 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 uf the GMR-I canister for protection against radioactive iodine.
3.
A GMR-1 canister found to have exceeded 3 years from date of manufacture l
will not be used for protection against radioactive iodine.
l 4
In the initial iglementation of the GMR-I program, the following verif-ication measures will be in effect:
l
- a. Whole body counts for individuals using the GMR-I canisters for radiciodine protection will be performed at the end of each job.
j
- b. A whole body count for individuals that exceed 10 MPC in any 7-day period and who used the GMR-I canister for respiratory protection in that period;
- c. Anyone that measures 70 nCI or greater iodine uptake to the thyroid during a whole body count will be restricted from entering a radiciodine 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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