ML20236S946

Forwards Request for Addl Info Re 960827 Amend Request to Relax Main Steam Line Leakage Requirements & to Eliminate Main Steam Isolation Valve Leakage Control System

ML20236S946
Person / Time
Site:	Perry
Issue date:	07/23/1998
From:	Pickett D NRC (Affiliation Not Assigned)
To:	Myers L CENTERIOR ENERGY
References
TAC-M96931, NUDOCS 9807270340
Download: ML20236S946 (7)

Text

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July 23, 1998 Mr. Lcw W. Mysrs Vice President - Nuclear, Perry Centerior Service Company 1 P.O. Box 97, A200 '

i Perry, OH 44081

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING REVISION OF MAIN STEAM LINE LEAKAGE REQUIREMENTS AND ELIMINATION OF THE MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEM - PERRY NUCLEAR POWER PLANT, UNIT NO.1 (TAC NO. M96931)

Dear Mr. Myers:

By letter dated August 27,' 1996 (PY-CEl/NRR-2076L), Centerior Energy submitted a license emendment request to relax main steam line leakage requirements and to eliminate the main steam isolation valve leakage control system. The proposed changes were based on reanalysis of the design basis Loss of Coolant Accident using the revised accident source term

' from NUREG-1465, " Accident Source Terms for Light-Water Nuclear Power Plants," and the NEl document entitled " Generic Framework for Application of Revised Accident Source Term to Operating Plants." -

The staff has initiated its review of the Perry submittal as one of the pilot plant reviews. As a result of its preliminary review of your submittal, the staff has identified certain items that will be necessary in order to complete our review. These items are identified in the enclosed request for additional information. The staff expects to idantify additional questions when the detailed review is performed.

If you should havn any questions regarding this request, please contact me at (301) 415-1364.

Sincerely, Original signed by: )

- Douglas V Pickett, Senior Project Manager j Project Directorate lil-3 /

Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation

Enclosure:

As stated

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Docket No. 50-440 ~

cc: See next page DISTRIBUTION: g$p rn m -

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PUBLIC PDill-3 R/F . REmch D%$ If k E u c..:, ' u s ,,

EGA1 . RBellamy GGrant, R3.

. BBoger DOCUMENT NAME: G:\ PERRY \96931.RAI i Ta receive a copy of thle document,indcate in f:.s boni "C" = Copy without enclosures "E" = Copy with enclosures 'N" = No copy l

0FFICE- PM:PDlh3 E LA:PDIII-3 & SC:PERB I _

NAME DPicE@tt- EBarnhill f 6,, REmch* j DATE 07/23/98 07/.?3/98 - 07/14/98 j~  ;

• See Emch .to Pickett merma dated July 14, 1998 0FFICIAL RECORD COPY 9907270340 990723 PDR ADOCK 05000440 0 P PDR w

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i

July 23, 1998

^

Mr. Lew W. Myrrs Vice President - Nuclear, Perry

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, Centerior Service Company P.O. Box 97, A200 Perry, OH 44081

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING REVISION OF MAIN STEAM LINE LEAKAGE REQUIREMENTS AND ELIMINATION OF THE MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEM - PERRY NUCLEAR POWER PLANT, UNIT NO.1 (TAC NO. M96931)

Dear Mr. Myers:

By letter dated August 27,1996 (PY-CEl/NRR-2076L), Centerior Energy submitted a license amendment request to relax main steam line leakage requirements and to eliminate the main steam isolation valve leakage control system. The proposed changes were based on reanalysis of the design basis Loss of Coolant Accident using the revised accident source term from NUREG-1465, " Accident Source Terms for Light-Water Nuclear Power Plants," and the NEl document entitled " Generic Framework for Application of Revised Accident Source Term to Operating Plants."

The staff has initiated its review of the Perry submittal as one of the p; lot plant reviews. As a result of its preliminary review of your submittal, the staff has identified certain items that will be necessary in order to complete our review. These items are identified in the enclosed request for additional in'ormation. The staff expects to identify additional questions when the detailed review is performed.

if you should have any questions regarding this request, please contact me at (301) 415-1364.

Sincerely, Original signed by:

Douglas V. Pickett, Senior Project Manager Project Directorate lil-3 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation 2nclosure: As stated Docket No. 50-440 cc: See next page DISTRIBUTION:

PUBLIC PDill-3 R/F REmch EGA1 RBellamy GGrant, R3 BBoger DOCUMENT NAME: G:\ PERRY \96931.RAI Ta receive e copy of this document, Indicate in the box: "C" = Copy without enclosures *E* = Copy with enclosures "N" = No copy

50FFICE PM

PDlUc3 E LA:PDIIU3 & SC:PERB NAME DPickW1 EBarnhill E b. REmch*

DATE 07/23/98 07/.@98 07/14/98

• See Emch to Pickett memo dated July 14, 1998 0FFICIAL RECORD COPY L _

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• • • • e p t UNITED STATES v s 2

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30806 4 001

% / July 23, 1998 Mr. Lew W. Myers Vice President - Nuclear, Perry Centerior Service Comptn/

P.O. Box 97, A200 Perry, OH 44081

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING REVISION OF MAIN STEAM LINE LEAKAGE REQUIREMENTS AND ELIMINATION OF THE MAIN STEAM l SOLATION VALVE LEAKAGE CONTROL SYSTEM - PERRY NUCLEAR POWER PLANT, UNIT NO.1 (TAC NO. M96931)

Dear Mr. Myers:

By letter dated August 27,1996 (PY-CEl/NRR-2076L), Centerior Energy submitted a license 1 amendment request to relax main steam line leakage requirements and to eliminate the main I steam isolation valve leakage control system. The proposed changes were based on reanalysis of the design basis Loss of Coolant Accident using the revised accident source term from NUREG-1465, " Accident Source Terms for Light-Water Nuclear Power Plants," and the NEl document entitled " Generic Framework for Application of Revised Accident Source Term to Operating Plants."

The staff has initiated its review of the Perry submittal as one of the pilot plant reviews. As a result of its preliminary review of your submittal, the staff has identified certain items that will be necessary in order to complete our review. These items are identified in the enclosed request for additional information. The staff expects to identify additional questions when the detailed review is performed.

If you should have any questions regarding this request, please contact me at (301) 415-1364.

Sincerely,

% Vk Douglas V. Pickett, Senior Project Manager Project Directorate 111-3 Division of Reactor Projects -lil/IV Office o' & clear Reactor Regulation

Enclosure:

As stated Docket No. 50-440 cc: See next page I

w____--_____ _ _ _

3

'O 1, Myers Perry Nuclear Power I'lant, Units 1 and 2 -

Centerior Service Company cc: .

1 Jay E. Silberg, Esq. James R. Williams Shaw, Pittman,Potts & Trowbndge Chief of Staff 2300 N Street, NW. Ohio Emergency Management Agency Washington, DC 20037 2855 West Dublin Granville Road Columbus, OH 43235-7150 Mary E. O'Reilly Centerior Energy Corporation'. Mayor, Village of Perry 300 Madison Avenue 4203 Harper Street Toledo,OH 43652 Perry, OH 44081

- Resident inspector's ONice Roy P. Lessy, Jr.

U.S. Nuclear Regulatory Commission - Akin, Gump, Strauss, Hauer P.O. Box 331 and Feld, L.L.P.

Perry, OH 44081-0331 1333 New Hampshire Ave., NW.

Suite 400 Regional Administrator, Region 111 Washington, DC 20036 U.S. Nuclear Regulatory Commission 801 Warrenville Road . Radiological Health Program Lisle, IL 60532-4531 Ohio Department of Health P.O. Box 118 Lake County Prosecutor Columbus, OH 43266-0118 Lake County Administration Bldg.

.105 Main Street Ohio Environmental Protection Painesville, OH 44077 Agency DERR-Compliance Unit Sue Hiatt ATTN: Mr. Zack A. Clayton q OCRE Interim Representative P.O. Box 104g 8275 Munson Columbus, OH 43266-0149 Mentor, OH 44060 Chairman j Tony J. Lodge, Esq. Perry Township Board of Trustees ,

618 N. Michigan Street, Suite 105 3750 Center Road, Box 65 LToledo, OH 43624 Perry, OH 44081 Ashtabula County Prosecutor State of Ohio 25 West JeWerson Street Public Utilities Commission Jefferson, OH 44047 East Broad Street Columbus, OH 43260-0573 Henry L. Hegrat

. Regulatory Affairs Manager William R. Kanda, Jr., Plant Manager Cleveland Electric illumbating Co. Cleveland Electric illuminating Co.

Perry Nuclear Power Plant Perry Nuclear Power Plard i- P.O. Box g7, A210 P.O. Box 97, SB306 Perry, OH 44081 Perry, OH ~ 44081 t

IY

cc: (continued)

Donna Owens, Director '

Ohio Department of Commerce Division of Industrial Compliance Bureau of Operations & Maintenance 6606 Tussing Road ,

' P.O. Box 4009 Reynoldsburg, OH 43068-9009 ,

Mayor, Village of North Perry North Perry Village Hall- j 4778 Locierood Road j North Peny Village, OH 44081 j Attorney General Department of Attorney General 30 East Broad Street l Columbus, OH 43216 I

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e REQUEST FOR ADDITIONAL INFORMATION REVISED ACCIDENT SOURCE TERM PERRY NUCI FAR POWER PLANT. UNIT NO.1 DOCKET NO. 50-440 In SECY-96-242,"Use of the NUREG-1465 Source Term at Operating Reactors," dated November 25,1996, the staff informed the Commission of its approach to allow the use of the revised 'accl dent source term desenbed in NUREG-1465, ." Accident Source Terms for Light-Water Nuclear Power Plants," at operating plants, in this paper, the staff described its plans to undertake (1) a re-baselining assessment of two nuclear power plants to further evaluate the issues involved with applying the revised source term at operating plants, and (2) review of the pilot plant applications for the use of revised accident source terms following completion of the re-baselining. The Commission approved the staff's plans and directed the staff to commence rulemaking upon completion of the re-baselining and concurrent with the review of the pilot plant submittals. The Commission also instructed the staff to use the TEDE dose methodology in the implementation of the revised source term.

The staff has completed its re-baselining effort and initiated licensing review of the pilot plant

. submittals. Based on a preliminary review of the license amendment request submitted by Perry, the staff has identified some significant items that will need to be resolved before detailed reviews can be cornpleted.

(1). Perform the radiological consequence assessments for the design basis accidents using the total effective dose equivalent (TEDE) methodology as defined in 10 CFR Part 20.1003. The analyses should consider significant " radionuclides in each of the radionuclides groups tabulated in Tables 3.12 and ? '3 of NUREG-1465. The applicable

-dose guidelines are:

(1) An fr:dividual located at any point on the boundary of the exclusion area for any 2-hour period following the onset of the postulated fission product release, would not receive a radiation dose in excess of 25 rem total effective dose equivalent (TEDE).

(ii) An individuallocated at any point on the outer boundary of the low population zor,e, who is exposed to the radioactive cloud resulting from the postulated fission product release (during the entire period of its passage), would not receive a radiation dose in excess of 25 rem total effective dose equivalent (TEDE).

(iii) Adequate radiation protection shall be provided to permit access and occupancy of the control room under accident conditiord, without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for L the duration of the accident.

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9 (2) Provide a formal request for an exemy' c a under 10 CFR Part 50.11 from $100.11(a)(1) and $100.11(a)(2), and Part 50, Appendix A, General Design Criterion 19, to substitute TEDE dose acceptance criteria for the currently specified whole body and thyroid dose acceptance criteria. The TEDE dose guidelines which need to be used with the revised source term are not currently provided in regulations goveming operating reactors. This exemption will be applicable only to dose calculations based on the revised source term.

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