ML20195E275

Informs That PCTs & LOCA Lhr Limits Submitted in Util Ltr for LOCA Reanalysis Performed in Support of TMI-1 20% Tube Plugging Amend Request Have Been Revised.Revised PCT & LOCA Lhr Limit Values Are Provided on Encl Table 1

ML20195E275
Person / Time
Site:	Three Mile Island
Issue date:	06/04/1999
From:	Langenbach J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1920-99-20280, NUDOCS 9906110031
Download: ML20195E275 (3)

Text

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I GPU Nuclear,Inc.

( Route 441 South

""O 1999 NUCLEAR 8 Post Office Box 480 Middletown, PA 17057-0480

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1920-99-20280 Tel717 944-7e:1 U.S. Nuclear Regulatory Commission Attention: Document Control Desk l

Washington, DC 20555 l

j Ladies and Gentlemen: I i

Subject:

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Additional Information - Technical Specification Change Request No. 279 Core Protection Safety Limit I The peak clad temperatures (PCT) and Loss of Coolant Accident (LOCA) Linear Heat Rate ,

(LHR) Limits, previously submitted in GPU Nuclear's letter to the NRC dated March 26,1999 l (1920-99-20088) for the LOCA reanalysis performed in support of the TMI-l 20% tube pluggmg amendment request (Technical Specification Change Request No. 279), have been revised. These revisions result from a Framatome Technologies, Incorporated (FTI) correction to the TMI-l /j LOCA evaluation model to remove a nonconservative assumption regarding use of fuel assembly I/

flow mixing-vane grids. The revised PCT and LOCA LHR limit values are provided on the attached Table 1. The values remain well within acceptance criteria. The revised PCT values are also being reported separately under 10 CFR 50.4ti as a significant change. g.

~ If any additional information is needed, please contact Mr. David J. Distel, GPU Nuclear Licensing and Regulatory Affairs at (973) 316-7955. l Sincerely, James W. La enbach Vice President and Director, TMI

/DJD Attachment - Table 1: Summary of Mk-B9 LHR Limits TMI-l LBLOCA 20% Tube Plugging cc: . Administrator, Region I

~ TMI-l Senior Project Manager TMI-l Senior Resident inspector t :,

File No. 98195 }lo 9906110031 990604 PDR ADOCK 05000289.

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1,9,20-99-20280 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY d/b/a GPU ENERGY

~ GPU NUCLEAR, Inc.

Three Mile Island Nuclear Station, Unit 1 Operating License No. DPR-50 1 Docket No. 50-289 Technical Specification Change Request No. 279 AdditionalInformation COMMONWF.iLTH OF PENNSYLVANIA )

) SS:

COUNTY OF DAUPHIN )

' This additional information on Technical Specification Change Request 279 is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit 1. All statements contained in this submittal have been reviewed, and all such j statements made and matters set forth therein are tme and correct to the best of my knowledge.

l

_ ice President anhitector, Thkl Swom an scribed before me this ay of h>/ ,1999.

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ledsu '  ?

/- // Notary Public '[

/ . NotarblSeal Suzanne C. Miklosik, Notary Public

.t Londonderry Twp., Dauphin County My Commission Expires Nov. P2,1999 Member, Pennsylvania Associabgn of Nota:ms l.;

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.- j i 1920-99-20280: q Nabid f Page1of1

• l TABLEI Summary ofMk-B9 LHR Limits TMI-l LBLOCA 20% Tube Plugging LOCA LHR Limit, kW/ft LOCA LHR Limit, kW/ft LOCA LHR Limit, kW/ft

. (PCT, F) (PCT, F) (PCT, F) -

Elevation - BOL MOL (40000 MWD /intU) EOL (60000 MWD /mtU) 0.0 fL 15.9 15.9 12.0  !

2.506 ft. 16.8 (2059) 16.8 (1855) 12.0 (l535) l 4.264 f1. 16.8 (2030) 16.8 (l883) 12.0 (<l700)  !

6.021 ft. 17.0 (2036)- 17.0 (1864) 12.0 (<1700) 7.779 ft. 17.3 (2104) 17.3 (1976) 12.0 (<l700) 9.536 f1. 16.8 (2083). 16.8 (1935) 12.0 (<1700) ,

' 12.0 f1. 15.9 15.9 12.0 )

. Notes: 1 Analyses at BOL and MOL used a steady-state energy deposition factor (EDF) of 0.973 for the initial core energy deposition and a transient EDF of 1.0. The steady-state (SS) EDF is used to

relate nuclear source power (used in maneuvering analyses) to thermal source power (used in LOCA~ analyses).

LHRn i.ss. == LHRwuci..,

• EDF3s i

I ' Analyses at EOL used a steady-state EDF of 1.0 and a transient EDF of 1.1. To report the LHR

given above on a basis consistent with the BOL and MOL LHRs, it was necessary to divide the EOL LHR of11.7 kW/ft by an EDF of 0.973 to obtain a reported LHR of 12.0 kW/ft. Therefore, all of the LHRs given above are based on nuclear source power with an EDF of 0.973.

2. LHRs may be linearly interpolated between elevations at the same burnup step, and also between MOL and EOL at the same elevation. For BOL and MOL, the core endpoint (0 or 12 ft.) LHR limits are defined as 95 percent of the adjacent elevation's LHR. For EOL, the endpoints are equivalent to the constant EOL LHR limit value.

3. .LHRs are valid for fuel enrichments of 5.1 weight percent (maximum) and an initial fuel rod i prepressure of 355 psia.

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4. The MOL and EOL PCTs were not explicitly calculated. The PCTs from FTI Calculation 32-1266332-01 were conservatively increased by the calculated BOI FCT penalty from FTl

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Calculation 32-1266332-02 to consider the corrected hot channel reflood grid data. j i

. 5. The 7,779-ft. BOL case was also analyzed at the LHR limit of 16.8 kW/ft (limit used in 15%

SGTP analyses) with a calculated PCT of 1964.2 F. Using this increase, the MOL PCT at 16.8 w < kW/ft would be estimated to be 1864 F. i

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