ML17258B055

Forwards Final NRC Evaluation of SEP Topic II-1.A, Exclusion Area Authority & Control.Assessment May Be Revised in Future If Facility Design Is Changed or If NRC Criteria Are Modified Before Integrated Assessment Is Completed

ML17258B055
Person / Time
Site:	Ginna
Issue date:	05/18/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Maier J ROCHESTER GAS & ELECTRIC CORP.
References
TASK-02-01.A, TASK-2-1.A, TASK-RR LSO5-81-05-036, LSO5-81-5-36, NUDOCS 8105260437
Download: ML17258B055 (8)

Text

REGULATORY FORM'ATION DISTRIBUTION S EM (RIDS)

ACCESSION NBR: 8105260037 DOC ~ DATE: 81/05/18 NOTARIZED:

NO DOCKET' FACIL'.50 244 Robert Emmet Ginna Nuclear Plenty Unit lg Rochester.

G 05000204 AUTH,NAME AUTHOR AFFILIATION CRUTCHFIELDpD ~

Operating Reactors Branch 5

REC IP ~ NAME RECIPIENT AFFILIATION.

MAIERgJ ~ E ~

Rochester-Gas L Electric Corp.

SUBJECT:

Forwards final NRC evaluation of SEP Topic II-1 ~ Af exclusion area-authority 8 control, Assessment may be revised in future if facility design is" changed or if NRC criteria is modified before integrated assessment is complete'de DISTRIBUTION CODE: SEOQS'OPIES RECEIVED:L~TR L; ENCL I

'IZE!'ITLE':

SEP Dist (Draft or Final SER)

NOTES: 1 copy:SEP Sect; Ldr ~

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1 RECIPIENT ID CODE/NAME CRUTCHF IELD SNAIDERr R ~

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Docket No. 50-244 LS05-81-05-036 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 May 18, 1981 Mr. John E. Maier Vice President Electric and Steam Production Rochester Gas 5 Electric Corporation 89 East Avenue Rochester, New York 14649

SUBJECT:

SEP TOPIC II-l.A, "EXCLUSION AREA AUTHORITY AND CONTROL" (GINNA)

Enclosed is the staff's final evaluation of SEP Topic II-1.A, "Exclusion Area Authority and Control" for the R. E. Ginna Nuclear Power Plant.

The staff review of your topic II-l.A safety assessment, submitted March 27, 1981, con-cluded that information pertaining to ownership of mineral rights had been omitted.

After discussions with the RGRE staff, the staff verified'ownership of all mineral rights-'within the exclusion area and we have incorporated this information into this final report.

This evaluation will be a basic input to the integrated safety assessment for your facility unless you identify changes needed to reflect the as-built con-ditions at your facility.

This, assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this subject are modified before the integrated assessment is completed.

Sincerely,

Enclosure:

As stated Dennis M. Crutc field, Chief Operating Reactors Branch b'5 Division of Licensing CC:

See next page gEnq el 05260

@gu usE <j (ops

Nr. John E. Haier CC Harry H. Voigt, Esquire

LeBoeuf, Lamb, Leiby and tlacRae 1333 New Hampshire

Avenue, N.

W.

Suite 1100 Washington, D. C.

20036 Nr. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Jeffrey Cohen New York State Energy Office Swan Street Building Core 1,

Second Floor Empire State Plaza

Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza Alba',

New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontari o 107 Ridge Road West

Ontario, New York 14519 Resident Inspector R. E. Ginna Plant c/o U. S.

NRC 1503 Lake Road Ontario; New York 14519 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460)

U'. Environmental Protection Agency Washington, D. C.

20460 U. S. Environmental Protection Agency Region II Office ATTN:

E I S COORDINATOR 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,

Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D.

C.

20555 Dr. Richard F. Cole Atomic Sa fety and Licens ing Board U. S. Nuclear Regulatory Commission Washington, D.

C.

20555 Dr.

Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Nr.

Thomas B. Cochran Natural Resources Defense Council, Inc.

1725 I Street, N.

W.

Suite 600 Washington, D. C.

20006 Ezra I. Bialik Assistant Attorney General Envi ronmenta1 P rotect i on Bureau New York State Department of Law 2 World Trade Center New York, New York 10047

SYSTEMATIC EVALUATION PROGRAM R.

E. Ginna TOPIC II-1.A - EXCLUSION AREA AUTHORITY AND CONTROL The safety objective of this topic is to assure that appropriate exclusion area authority and control are maintained by the licensee as required by 10 CFR Part 100.

The review was conducted in accordance with the guidance given in SRP 2.1.2.

The capability of the plant to meet the dose criteria of 10 CFR Part 100 at the exclusion area boundary will be evaluated in the Design Basis Event phase of the SEP review.

The R,

E. Ginna plant is located on the south shore of Lake Ontario 16 miles east of Rochester, New York, a city o( 241,539 people (Rochester metropolitan area

,- population is 701,745)

The site exclusion area is completely within the plant boundaries.

The distance from the containment to the nearest site boundary (excluding the boundary on the lake front) is 1550 feet but the minimum exclusion distance is assumed to be 450 meters or 1476 feet.

The site boundary is shown in the attached Figure 1 of this evaluation (note that additional land to the west has been purchased since Figure 2.2-3 of the FSAR was submitted).

No public highways or railroads traverse the exclusion area.

Rochester Gas and Electric Corp.

owns and controls all of the land, includ-ing mineral rights, within the exclusion area.

Regarding the lakeshore frontage within the exclusion a~ca, RGSE',

by New York State procedures, owns the land above 243.8'sl.

This is well below the average lake stage of 246 feet msl, but is above the Extreme Low WaterlLevel of 242.23 feet msl and the lowest regulated level of 243 feet msl.

However, since the low period is generally in the winter and the high period in the summer, it is not expected that there would be any "beach use" of this area.

Previous experience confirms this; thus, no special precautions for potential beach users are in place.

The exclusion area is not defined over the waters of Lake Ontario adjacent to the R.

E. Ginna site.

The NRC staff in recent cases involving shore front sites has interpreted the definition of an ex-clusion area in 10 CFR Part 100,as applying to the entire area surrounding a reactor including the overwater portion.

In these

cases, applicants have been required to make appropriate arrangements to control water traf-fic within the exclusion area in the event of a plant emergency.

While RG&E has not specifically defined an exclusion area over the water, arrange-ments have been made with the (2. Coast

Guard, as documented in the Ginna Plant Radiation Emergency Plan, for the control of water traffic in the event of a plant emergency.

The lack of a defined exclusion area over the water adjacent to the plant site is a deviation from the staff's current interpretation of the criteria in 10 CFR Part 100.

However, the arrangements made by RG&E with the U.S.

Coast Guard meet the intent of the criteria.and, therefore, it is considered n<<h 1

k d i d

1 i

1 d

a significant safety issue for the SER review.

The conclusion can be made that RGSE has the proper authority to determine all activities within the exclusion area, as required by 10 CFR Part 100.

This completes the evaluation of thi.s SEP topic.

REFERENCES 1.

Rochester Gas and Electric Corporation, Robert Emmett Ginna Nuclear Power Plant Unit No.

1 - Final Facility Description and Safety Analysis Report (FSAR), Sections 1.1, 2.1, 2.2 and Appendix 2C.

2.

Rochester Gas and Electric Corporation, R.

E. Ginna Nuclear Power Plant Unit No. 1, Environmental

Report, Volume 1, Section 2.1.

3.

Nuclear Regulatory Coranission NUREG-75/087, Standard Review Plan', Section 2.1.2, September 1975.

4.

,",Official Preliminary 1980 Census Figures,"

taken from'the Rochester Times-Union," September 15, 1980.

5.

RG&E Procedure "Radiation Emergency Plan" (SC-1).

6.

New York State Policy as established by the Land Utilization Department within the NYS Office of General Services.

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