ML20211C222

Supplemental Application for Amend to License DPR-50 Re TS Change Request 266.Supplement Provides for Phased Review & Issuance of License Amends & Involves Administrative Correction to TS Decay Heat Removal Sys Leakage Rate

ML20211C222
Person / Time
Site:	Three Mile Island
Issue date:	09/19/1997
From:	Langenbach J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20211C227	List: ML20211C222 ML20211C243
References
6710-97-2425-1, NUDOCS 9709260147
Download: ML20211C222 (2)

Text

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NUCLEAR M.cdletown PA17057 0480 Tel717 944 7621 September 19, 1997 6710-97-2425-1 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

Subject:

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

Operating License No. DPR 50 Docket No. 50-289 Technical Specification Change Request (TSCR) No. 266 Supplemental Change, re: Decay Heat Removal (DilR) System Leakage Limit Ref.: GPUN Letter No. 6710 97-2252, dated July 30,1997 On September 10, 1997 GPU Nuclear (GPUN) Inc. met with representatives of the Nuclear Regulatory Commission (NRC) to discuss TSCR No. 266 which addresses proposed changes in Accident Recirculation Systems (Decay Heat, Building Spray, and Make-Up) Leakage Limits.

TSCR No 266 also serves to revise accident analysis assumptions associated with the calculation of off site does consequences related to the Maximum llypothetical Accident contained in the Updated FSAR (UFSAR) for TMI-1. In subsequent discussions with NRC Staff members, GPUN agreed to a phased approach to be used by NRC in review and approval of TSCR No. 266. The purpose of this phased approach is to allow the Stafr more time for review of the revised accident assumptions used for calculation of dose consequences in the TSCR No. 266 submittal letter referenced above.

The first phase is a proposed revision to the TMl-1 Technical Specification 4.5.4.1 surveillance specification for maximum allowable leakage. The leakage limit will be changed from six gallons per hour (gph) to 0.6 gph to conform the current TMI-l Technical Specifications to the current UFSAR licensing basis accident analysis, and the last sentence of the Bases statements is being deleted accordingly. With implementation of this interim license amendment, GPUN is also committing to limit the total leakage from the accident recirculation portions of the Decay Heat, Building Spray and Make-Up systems to the more restrictive UFS AR 0.6 gph licensing basis value, as noted on the revised page 4-45 enclosed.

The second phase is NRC's expeditious review and approval of GPUN's July 30* TSCR letter  !

referenced above. The review involves consideration of the revised analysis assumptions used in the calculation of both the otT-site and control room radiological dose consequences.

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l U.S. Nuclear Regulatory Commission 6710-97-2252 Page 2 The second phase license amendment for TSCR 266 would then serve to close-out the NRC Inspection Repon No 96-201 open items, discussed in GPUN's June 23,1997 response to IR 96-201.

This supplement to TSCR No. 266 provides for a phased review and issuance of license amendments and involves an administrative correction to the Technical Specification decay heat removal system leakage rate in order to conform it to the UFSAR licensing basis. This interim measure does not impact upon the safety evaluation performed for the original change request and has no impact upon the "No Significant flazards Consideration" analysis for TSCR Nc. 266, pursuant to the standards contained in 10 CFR 50.92.

In accordance with 10 CFR 50.91 (b)(1) a copy of this supplemental information has been sent to the chief executives of the township and county in which the facility is located, as the designated oflicial of the Commonwealth of Pennsylvania, Bureau of Radiation Protection. If you have any questions concerning this matter please contact Sr. Licensing Engineer, Mr. G. M. Gurican at (201) 316-7972.

Sincerely, n

d&j

[$\@(

g James W. Langp bach i

Vice Prcsident and Director, TMl JWUGMG/lah

Enclosure:

(1) Proposed Revision to TM1-1 Technical Specification page 4-45 cc: Administrator Region i TMI Senior Resident Inspector TMl Senior Project Manager

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