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Q' A lb UNITED STATES NUCLEAR REGULATORY COMMIS310N j
WASHINGTON, o. - C. 20655
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Docket No. S0-219 i
George Lear, Chief, Operating Reactors. Branch #3, DRL JJBSEY CENTRAL POWER 6 LIGHT COMPANY'S REQUEST TO WI'MiOLD PROPRIETARY DOCUMENTS ENTITLED " RESPONSES TO NRC QUESTIONS ON CYCLE S RELOAD" AND
" ADDITIONAL DATA REGARDING THE LOSS-OF-COOLANT ACCIDENT ANALYSIS FOR GE FUEL" By letters dated April 24 and 28, 197S, Jersey Central Power 6 Light Company (JCPL) submitted two proprietary documents containing additional information in connection with their requests for operation of the Oyster Creek Nuclear Generating Station with Cycle 5 Reload and the Reevaluation of the ECCS. The submittal of April 24, 197S, entitled
" Responses to NRC Questions on Cycle S Reload" contains information considered proprietary by Exxon Nuclear Company and withholding is requested for the following reasons:
1.
The information reveals certain distinguishing aspects j
of fuel design when prevention of its use by any of Exxon Nuclear's competitors without license from Exxon Nuclear constitutes a competitive economic advantage over other companies; 2.
The information contains product design data, which data secures competitive economic advantage by design optimization and improved marketability; and 3.
The use of the information by a competitor would reduce his expenditure of resources or improve his competitive position in th.e design and manufacturer of a similar product.
The April 28, 197S, submittal entitled " Additional Data Regarding the Loss-of-Coolant Accident Analysis Reevaluation for GE Fuel" contains information considered proprietary by the General Electric Company and i
withholding is requested for the following reasons:
1.
The figures contain information which is of the type which General Electric customarily maintains-in confidence and withholds from public disclosure in accordance with the procedures and standards of the General Electric Proprietary Classification System; and 8
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The analytical methods and data which would be compromised by disclosure of these figures were developed at considerable expense to the General Electric Company and the release of the information would allow competitors to conform similar designs without incurring similar expense."-
We have reviewed the data presented in Jersey Central Power 6 Light Company's letters requesting withholding from public disclosure of this infomation.. We' concur that the documents do contain information concerning the processes and analytical methods that are used exclusively by Exxon and General Electric and constitutes an economic advantage over other companies. The in' formation was furnished in accordance with our requests for additional information in order,for us to review the request by JCPL to operate with Cycle 5 Reload and their ECCS reevalua-tion. The licensee has submitted nonproprietary versions of the information by letters dated May 5 'and May 8, 1975,'and those documents as well as documents dated October 30, 1974, January 31, March 25, 29 and April 30,
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1975 relating to the core reload and the ECCS reevaluation have.been provided for inspection at the Public Document Rooms. We conclude that sufficient information is provided in these nonproprietary documents for any interested member of the public to identify the safety considerations j
applicable to the operation of Oyster Creek with Cycle 5 reload and the ECCS reevaluation without disclosure of the information in the proprietary documents.
Exxon and the General Electric Company have gone to considerable expense
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to obtain the analytical methods and data for improved fuel design and manufacture of the fuel furnished to the nucicar industry.
If the data and processes were made available through public disclosure of this information to their competitors, it would reduce the competitors i
expenditures, improve their competitive position and give them a competitive economic advantage at the expense of Exxon and General Electric.
l I find that the licensee has supplied sufficient justification for with-holding this information from public disclosure. Therefore, in view of the foregoing, I have determined that disclosure of the information contained in the above referenced documents is not required in the public interest nor by 10 CFR Part 9, and that it should be withheld from public inspection pursuant to 2.790(b) of 10 CFR Part 2.
/dl& Ab4w Walter A. Paulson Operating Reactors Branch #3 Division of Reactor Licensing
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UNITED STATES NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C, 20555 I
JW a 275 Docket No. 50-219 Licensee: Jersey Central Power G Light Company Pacility: Oyster Crhek Nuclear Generating Station SIM!ARY OF MEETING !! ELD ON MAY 8,1975 TO DISCUSS NRC CONCEPWS REGARDING Tile EXXON CRITICAL llEAT FLUX CORRELATION On May 8, 1975, a meeting was held in Bethesda, Maryland with representatives of General Public Utilities Service Corporation and Exxon Nuclear Company. The purpose of the meeting was to discuss our concerns with Exxon's critical heat flux correlation. A list of attendees is enclosed.
We discussed two approaches that would be acceptable to us to account for the over prediction of critical heat flux by the Exxon critical heat flux correlation, XN-1 /F (where F is the Tong factor usedtoaccountfornon-uniformIEEE1powerd$sNibution).
The two approaches are:
1.
Reduce the value of critical heat flux calculated using XN-1 /Ftong by a factor acceptable to us, or 2.
Increase the MCifPR values that will be allowable during operation to values acceptable to us.
We and GPUSC have not agreed on a penalty factor that would be appli-cable to XN-1 /,FTong.
Exxon discussed a critical power ratio analysis and how it might be' l
applied to the Oyster Creek Cycle 5.
Exxon proposed a minimum critical power ratie of 1.28 for 7x7 fuel and 1.31 for 8x8 fuel.
Exxon stated that they would determine a translator to go from MCIIFR to MCPR. Exxon also stated that the rod withdrawal error transient may have to be redone using the critical power ratio analysis. We stated that the minimum critical power ratios i
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proposed are not adequately supported by the Oyster Creek Cycle 5 reload submittals. We stated that it is our position that the i
values proposed are too low and therefore, they are unacceptable. -
We stated that in the absence of more data we would accept either a penalty factor of 0.5 applied to XN-1/Ffactorof2timesthepresentMCHFRlimit o
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Furthermore, if
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the critical power procedure is now going to be used, without a penalty being applied to XN-1/PTong, we would accept a limiting CPR of 1.5.-
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i N. A. Paulson Operating Reactors Branch #3 I
Division of Reactor Licensing i
Enclosure:
l List of Attendees 1
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e ENCLOSURE List'of Attendees MEETING WIT 11 GENERAL PUBLIC (TTILITIES SERVICE CORPORATION AND EXXON NUCLEAR COMPANY
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MAY 8, 1975 Nuclear Regulatory Commission W. Paulson R. Schemel T. Novak' D. McPherson-R. Frahm Exxon Nuclear Company
' G. Owsley G. Sofer General Public Utilities Service Corporation T; Crimmins G. Bond T. Robbins (Pickard Lowe 6 Associates) i W. Lowe (Pickard Low 6 Associates) i
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NUCLEAR REGULATORY COMMISSION W ASHINGTON. D. c. 20555 Docket No 50-219 4
DISTRIBUTION OF MEETING
SUMMARY
G. P. Trowbridge, Esquire Jersey Central Power 6 Light Co.
Shaw, Pittman, Potts, Trowbridge 6 Madden ATTN: Mr. I. R. Pinfrdek, Jr.
Barr Building Vice President -Generation 910 17th Street, N. W.
Madison Avenue at Punch Bowl Rd.
Washington, D. C. 20006 Morristown, New Jersey 07960 Jersey Central Power 6 Light Company -
Ocean County Library ATIN:
Mr. Thomas M. Crimmins, Jr.
15 Hooper Avenue Safety and Licensing Manager Toms River, New Jersey 08753 GPU Service Corporation l
260 Cherry Hill Road Parsippany, New Jersey 07054 1
Anthony Z. Roisman, Esquire Berlin, Roisman 6 Kessler 1712 N. Street, N. W.
Washington, D. C. 20036 l
T.Novakk,
Docket File D. Ziemann D. Ross G. Lear
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NRC PDR R. W. Houst'on Local PDR P. Collins T. Ippolito ORB #3 Rdg G. Knighton C. Long G. Dicker V. Moore G. Lainas B. Youngblood R. DeYoung V. Benaroya D. Skovholt W. Regan, Jr.
R. Vollmer D. Muller S. Varga B. Grimes R. Denise F. Williams W. Gammill J. Stolz F. Schroeder J. Kastner K. Kniel R. Maccary M. Spangler A. Schwencer V. Stello R. Ballard D. Vassallo R. Tedesco O. Parr W. Butler H. Denton ACRS (16)
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UNITED STATES NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20555 JUN 3 gyg 1
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j Denket No. 50-219 1
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LICENSRE: JBRSEY CENTRAL POWR 4 LIGff COWANY
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FACILITY: OYSTER CREEK WCLEAR GENBRATING STATION 1
SIDGd4RY OF MBTING MIA ON MAY 5,1975 TO DISCUSS THE EIXON WC12AR j<.
CORPORATION'S CRITICAL NEAT FLU 1 CORRELATION i
On May 5, 1975, a mostlag was held in Bethmsda with representatives of General Public Utilities Service Corporation (GPUSC) and Exmom i
Muslear company. The purpose of the meeting uns to discuss our l
conceras with Exann's IN-1 critical heat flux correlation. A-list of attendees is enclosed.
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j Jersey Central Per s and Light Compmay has submitted transient analyses la Amendosat 76 to the Oyster Creek PDSAR in support of the Oyster Creek Cycle 5 reload application. Based en our review of the informa-tion submitted, we found that Exxon's IN-1 correlation apparently i
non-conservatively everpredicts critical heat flux by 40 to 60%. A l
meeting was held with GPUSC and Exzen se Sunday, May 4, 1975 to discuss the bases for our conclusions. 1he meeting am May 5, 1975 was to discuss same additional infommaties presented by Exzen on May 4,1975.
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l Exxon r. x: M an error analysis for the 25 pertinent data points in the Nuclear Services torporaties status report (Progress Report on i
Noenniform QC', April 15,1975) which was given to as in the May 4, 1975 meeting.. The Exmon arrer analysis showed an average ove power l-predictism of 12.7% at departure from ancleate boiling and an average of 50% overpredictiam of CHF. We stated that the current version of IN-1 is not acceptable for use in predicting critical heat flux (CHP) for either 7 x 7 or 8 x 8 fool assenh11es.
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We agreed on a method to account for the effect of cold rods in predicting critical heat flux. Exxon describe the iterative method that they use in predicting average power at burnout. We agreed to make a camparison of predicted versus==manneed values (either using average critical host flux or critical power) using the Exxon iterative
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predictive technique.
i Walter A. Paulson Operating Reactors Branch #3 Division of Reactor Licensing Baclos:are:
DISTRIBtTrION:
List of Attendees Docket j
ORB-3 Reading NRR Reading 4
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MIETING WITH GENERAL PUBLIC (frILITIES SERVICE CORPORATION i
Ale EXXON MACI,BAR COMPANY i
NAY 5. 1975 1
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IEJCLEAR REGULATORY C0D0GSSION
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W. Paulson T. Novak D. NsPherson D. Ross
.W. Niamers BIXON NUCl2AR CORPORATION i
K. Galbraith G. Owsley G. Sofer GENERAL PUBLIC LFrILITIES SERVICE CORPORATION G. Bond l
T. Robbins (Pickard Lowe 4 Associates) l NUCLEAR SERVICES CORPORATION 4
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DISTRIBUTION OF MEETING
SUMMARY
G. F. Trowbridge, Esquire Jersey Central Power 6 Light Co.
Shaw, Pittman, Potts, Trowbridge 5 Madden ATTN: !!r. I. R. Finfrdek, Jr.
Barr Building Vice President -Generatio 910 17th Street, N. W.
Madison Avenue at Punch Bowl Rd.
Washington, D. C. 20006
!!orristown, New Jersey 07960 Jersey Central Power G Light Company Ocean County Lib'rary A'ITN: !!r. Thomas M. Crimmins, Jr.
IS Ilooper Avenue Safet'y and Licensing flanager Toms River, New Jersey 087S3 GPU Service Corporation 260 Cherry 11111 Road Parsippany, New Jersey 070S4 Anthony Z. Roisman, Esquire Berlin, Roisman ti Kessler 1712 N. Street, N. fl.
tlashington, D. C. 20036 T.Novalti Docket File D. Ziemann D. Ross
- NRC PDR G. Lear R. W. Iloust'on
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Local PDR P. Collins ORBil3 Rdg G. Knighton T. Ippolito V. Moore G. Dicker C. Long G. Lainas R. DeYoung B. Youngblood D. Skovholt W. Regan, Jr.
V. Benaroya R. Vollmer L. Nuller S. Varga B. Grimes R. Denise F. Williams W. Ganr.ill J. Stolz F. Schroeder J. Kastner
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K. Kniel R. Maccary A. Schwencer V. Stello M. Spangler R. Ballard l
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E. Tedesco O. Parr W. Butler H. Denton ACRS (16) l K. Coller J. P. Knighu S. A. Teets T. Speis S. Pawlicki P.. Clark L. Shao OELD nTu m NRC Participants Project Manager q#
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UNITED STATES NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20$$5 l
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Decket No. 50-219 j
Licensee: Jersey Central Power 4 Light Cogany l
Pacility: Oyster Creek Nuclear Generating Station SLMIARY OF E BTING HELD ON MAY 15, 1975 NITH JERSEY CEWTlAL POWER j
4 LIGHT COMPANY AND GENERAL PUBLIC (TTILITIES SERVICE CORPMTION On May 15, 1975, a meeting was held in Bethesda, Maryland, with representatives of Jersey Central Power 4 Light Company (JCP4L) and General Public Utilities Service Corporation (GPU). The purpose of the meettag was to discuss JCP4L's submittal dated j
May 14, 1975 which proposes establishing minimus critical power j
ratie (MCPR) thermal limit criteria for the Oyster Creek Cycle 5.
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All previous cycle 5 reload submittals were based on minimum critical heat flux ratio (MCf!PR) thermal criteria. A list of attendees is enclosed.
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-Based on our preliminary review of the submittal dated May 14, 1975,.
which was received about three hours prior to the meeting, we decided that i
we will need a step-by-step sample calculation showing the relationship i
between minimum critical power ratio and misimum critical heat flux ratio.
We agreed that we would review with GPUSC the details of the calculational methods that we used to evaluate test data.
Our position continues to be that the MCPR of 1.'4, proposed by JCP4L is i
not supported by the information submitted to date. We 'further indicated that a EPR of 1.5 would be acceptable to us.
JCP4'L representatives stated that they were planning to -do their hydrostatic test of the RCS pressure boundary on May 15, 1975; if the test is successful they would be ready to start-up on May 17, 1975.
If the test is not successful, JCP4L estimated that they would be ready to start up on May 20, 1975, assuming that we approve their application.
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Ne also discussed the proposed Technical Specification regarding the 2
mininum allowable control rod density. We stated that the Specification as proposed is not acceptable because it specifically excludes the necessity for NRC review of any futsre relaxation of the proposed 3.5 percent rod density' limit.
It is our position that we should review
.any proposed reduction.in the allowable control rod density.
i W. A.'Paulson Operating Reactors Branch #4 Division of Reactor Licensing
-Enclosure List of Attendees l
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ENCLOSURE
. List of Attendees NRC W. Paulson r
R. Woods
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D. McPherson G. Lear D. Fieno R.'Schemel-R. Frahm JCP6L I.'
Finfrock, Jr.
D. Ross-W Lowe (Pickard Lowe 6 Associates).
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GPUSC T. Crimmins G.' Bond l
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U *I h b UNITED STATES NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555 Docket No 50-219 DISTRIBUTION OF MEETING SLTMMARY_
G. F. Trowbridge, Esquire Jersey Central Power G Light Co.
Shaw, Pittman, Potts, Trowbridge 6 Madden ATTN:
Mr. I. R. Finfrdek, Jr.
Barr Building Vice President -Generatio:
910 17th Street, N. W.
liadison Avenue at Punch Bowl Rd.
Nashington, D. C. 20006 Morristown, New Jersey 07960 Jersey Central Power G Light Company Ocean County Lib'rary ATfN: Mr. Thomas M. Crimmins, Jr.
15 llooper Avenue Safety and Licensing Manager Toms River, New Jersey 08753 GPU Service Corporation 260 Cherry 11111 Road Parsippany, New Jersey 07054 Anthony Z. Roisman, Esquire Berlin, Roisman G Kessler Ii gto l
C.2b36 T. Novak'.;
Docket File D. Ziemann D. Ross~
NRC PDR G. Lear R. W. Houston 1.ocal PDR P. Collins T. Ippolito ORBi)3 Rdg G. Knighton V. Moore G. Dicker C. Long G. Lainas R. DeYoung B. Youngblood V. Benaroya D. Skovholt W. Regan, Jr.
R. Vollr.er D. Muller S. Varga B. Grimes R. Denise F. Williams W. Gammill J. Stolz F. Schroeder J. Kastner K. Kniel R. Maccary A. Schwencer V. Stello M. Spangler R. Ballard D. Vassallo R. Tedesco O. Parr' W. Butler H. Denton ACRS (16)
K. Coller J. P. Knight S. A. Teets T. Speis S. Pawlicki R. Clark L. Shao OELD nTW (3L NRC Participants ng Project Manager p
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