ML20206B413

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Safety Evaluation Supporting Util 850416 Request for Deletion of Constraint of 20-ft Square Modified Penetrations Between Reactor & Auxiliary/Fuel Handling Bldgs.Expanding of Limit to 40-ft Square Acceptable
ML20206B413
Person / Time
Site: Crane Constellation icon.png
Issue date: 04/03/1987
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20206B407 List:
References
NUDOCS 8704090144
Download: ML20206B413 (3)


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SAFETY' EVALUATION FOR EXPANDING LIMITS ON l

MODIFIED CONTAINMENT PENETRATIONS BACKGROUND General Public Utilities Nuclear Corporation (GPUNC), the. licensee, applied for an exemption from General Design Criteria 2, 50 and 51 in a letter dated April 16,1985 (reference 7). This would allow modification of containment penetrations such that they would no longer be seismically qualified. The'NRC staff analyzed the potential offsite dose consequences of accidents involving modified containment penetrations coincident with seismic events (reference 4). The staff concluded that the potential consequences did not represent a threat the health and safety of the public and subsequently allowed GPUNC to modify containment penetrations, to a limit of 20 ft.2, based on this analysis and the granting of the exemption to criteria 2, 50, and 51.

GPUNC has subsequently requested deletion of the current 20 ft.2 limit on modified penetrations. The NRC staff has reviewed its previous analysis and GPUNC's submittals (references 1 and 3)'and has performed additional calculations in making a determination of what action to take on the licensee's request.

EVALUATION In the staff's previous analysis modified containment penetrations to the auxiliary and fuel handling buildings (including the. annulus area) were restricted to 20 ft.2 in area. With this restriction they did not represent the limiting case in the staff's analysis. The staff evaluated doubling the amount of these penetrations and doubled the source leaving the reactor l

building via these penetrations. The resultant worst case involved a dropped fuel canister coincident with the faile,I penetrations. The potential offsite dose consequences for the maximally exposed individual were less than 0.5 rem-(i.e., 387 mrem) whole body dose equivalent. With 40 ft.: of modif'ed penetrations the licensee could reasonably effect temporary. repairs and terminate the release within a few hours as was previously assumed.- With an unrestricted modification this assumption would not be valid and potential offsite doses could exceed a small fraction of 10 CFR 100 guidelines.

CONCLUSIONS The staff has evaluated the potential risks associated with modifying up to 40 ft.2 of penetrations between the containment (reactor building) and the auxiliary and fuel handling buildings. The staff has determined that this action does not involve a significant increase in the probability _or consequences of an accident perviously evaluated or create the possibility of

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a new accident or involve a. significant reduction in the margin of safety.

This action does not authorize an increase in effluents from the facility and -

falls within the bounds of activities previously described in the Programmatic Environmental Impact Statement (PEIS). We therefore conclude that up to 40 ft.2 of the described penetrations can be modified without significant risk to the health and safety of the public.

8704090144 870403 PDR ADOCK 05000320 P

PDR

I REFERENCES 1.

GPUN letter, F. R. Standerfer to W. D. Travers, 4410-86-L-0107, dated June 30, 1986, re Seismic Design Criteria for Modified Containment Penetrations.

2.

NRC letter, W. D. Travers to F. R. Standerfer, NRC/TMI 86-005, dated January 16, 1986, re Seismic Design Criteria.

3.

GPUN letter, F. R. Standerfer to B. J. Snyder, 4410-85-L-0077, dated April 16, 1985, re Seismic Design Criteria.

4.

NRC letter, 8. J. Snyder to F. R. Standerfer, dated November 5,1984, re Exemptions from General Design Criteria 2, 50 and 51.

5.

Regulatory Guide 1.29 " Seismic Design Classification", Revision 3, September, 1978.

6.

NUREG 0800 " Standard Review Plan".

7.

GPUN letter, F. R. Standerfer to B. J. Snyder, 4410-85-L-0077 dated April 16, 1985, re Seismic Design Requirements.

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TMI-2 SERVICE LIST Dr. Thomas Murley Regional Administrator U.S. Department of Energy U.S. Nuclear Regulatory Commission P.O. Box 88 631 Park Avenue Middletown, PA D057-0311 King of Prussia, PA 19406 David J. McGoff Sheldon J. Wolfe, Esq., Chairman Office of LWR Safety and Administrative Judge Technology Atomic Safety and Licensing Board Panel NE-23 U.S. Nuclear Regulatory Commission U.S. Department of Energy Washington, D.C.

20555 Washington, D.C.

20545 Dr. Oscar H. Paris William Lochstet Administrative Judge 104 Davey Laboratory Atomic Safety and Licensing Board Panel Pennsylvania State University U.S. Nuclear Regulatory Commission University Park, PA 16802 Washington, D.C.

20555 Frank Lynch, Editorial Dr. Frederick J. Shon The Patriot Administrative Judge 812 Market Street Atomic Safety and Licensing Board Panel Harrisburg, PA.17105 U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Robert B. Borsum Babcock & Wilcox Dr. Judith H. Johnsrud Nuclear Power Division Environmental Coalition en Nuclear Power Suite 220 433 Orlando Avenue 7910 Woodmont Avenue State College, PA 16801 Bethesda, MD 20814 Ernest L. Blake, Jr., Esq.

Michael Churchhill, Esq.

Shaw, Pittman, Potts, and Trowbridge PILCOP 2300 N Street, N.W.

1315 Walnut Street, Suite 1632 Washington, D.C.

20037 Philadelphia, PA 19107 Atomic Safety and Licensing Board Panel Marvin I. Lewis U.S. Nuclear Regulatory Commission 7801 Roosevelt Blvd. #62 Washington, D.C.

20555 Philadelphia, PA 19152 Secretary Jane Lee i

U.S. Nuclear Regulatory Commission 183 Valley Road Washington, D.C. 20555 Etters, PA 17319 Frederick S. Rice, Chairman Walter W. Cohen, Consumer Dauphin County Board of Commissioners Advocate Dauphin County Courthouse Department of Justice Front and Market Streets Strawberry Square,14th Floor Harrisburg, PA 17101 Harrisburg, PA 17127 Thomas M. Gerusky, Director Mr. Edwin Kintner Bureau of Radiation Protection Executive Vice President Department of Environmental Resources General Public Utilities P.O. Box 2063 Nuclear Corporation Harrisburg, PA 17120 100 Interpace Parkway Parsippany, NJ 07054 Ad Crable Lancaster New Era US Environmental Prot. Agency Region III Office 8 West King Street ATTN:

EIS Coordinator Lancaster, PA 17601 Curtis Building (Sixth Floor) 6th and Walnut Streets Philadelphia, PA 19106

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