ML20045J297

TS Change Request 211,revising TS Page iii,3-128,3-129 & 4-7a,per NUREG-1430

ML20045J297
Person / Time
Site:	Three Mile Island
Issue date:	07/15/1993
From:	Broughton T GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20045J296	List: ML20045J295 ML20045J297 ML20045J299
References
RTR-NUREG-1430 C311-93-2096, NUDOCS 9307230307
Download: ML20045J297 (4)

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, , METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT. COMPANY AND PENNSYLVANIA ELECTRIC COMPANY L THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating License No. DPR-50 Docket No. 50-289- l Technical Specification Change Request No. 211 I I

1 COMMONWEALTH OF PENNSYLVANIA )

) SS:  !

l COUNTY OF DAUPHIN )

This Technical Specification Change Request 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. As a part of this request, proposed replacement pages for Appendix A are also included. '

GPU NUCLEAR CORPORATION BY: b'h>

Vice President ( ar.d Director, THI-1 Sworn and Subscribed tp before me this /Ch' day of 6////u , 1993.

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/ lb:?6o Notary Public

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9307230307 930715 9 PDR ADDCK 05000289 y p PDR d

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET NO. 50-289 GPU NUCLEAR CORPORATION LICENSE N0. DPR-50 J 1

CERTIFICATE OF SERVICE .

l This is to certify that a copy of Technical Specification Change Request No.

l 211 to Appendix A of the Operating License for Three Mile Island Nuclear l

Station Unit 1, has, on the date given below, been filed with executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as follows:

Mr. Daryl LeHew, Chairman Mr. Russell L. Sheaffer, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA 17057 Harrisburg, PA 17120 Director, Bureau of Radiaton Protection ,

PA Dept. of Environmental Resources P.O. Box 2063 Harrisburg, PA 17120 Attn: Mr. Richard Janati GPU NUCLEAR CORPORATION BY:

VicePresidentydDirector,THI-l DATE: July 15,1993

j

'. 'C311-93,-2096 ,

I. TECHNICAL SPECIFICATION CHANGE REQUEST (TSCR) No. 211 GPU Nuclear requests that the following changed replacement pages be inserted into existing Technical Specifications: '

Replace the existing pages iii, 3-128, 3-129 and 4-7a with the attached j revised pages iii, 3-128, 3-129 and 4-7a.  ;

r II. REASON FOR CHANGE ,

The existing Technical Specification 3.24 was approved on an interim basis. GPU Nuclear committed to propose an amendment that is consistent with the Standard Technical Specification (STS) resulting from the NRC initiated Technical Specification Improvement Program.

On September 28, 1992, the NRC approved NUREG 1430, entitled "B&W.

Standard Technical Specifications". The B&W Standard Technical Spe:ifications address Regulatory Guide 1.97 Category I variables. At TMI-1, the Reactor Coolant Inventory Trending System (RCITS) is comprised i of two subsystems, the Water Level Trending subsystem and the Void Fraction Trending subsystem. In response to Regulatory Guide 1.97, GPU Nuclear has identified the Water Level Trending Subsystem as Category 1.

The other subsystem of the TMI-l RCITS, Void Fraction Trending, does not produce a Regulatory Guide 1.97 parameter and, therefore, is being ,

deleted from the system description in Technical Specification 3.24. i Similarly, the surveillance requirement for the Void Fraction Trending '

subsystem indicated in T.S. Table 4.1.1 is being eliminated.

The proposed Technical Specification Change Request includes the STS Limiting Conditions for Operation that-two channels are required to be operable when the reactor is critical; if less than two channels are operable, specific actions are required.

III.. SAFETY EVALUATION JUSTIFYING CHANGE The requirements for OPERABILITY of Reactor Vessel Water Level indication, as proposed in this Technical Specification Change Request, are consistent with those included in the B&W Standard Technical r Specifications, which the NRC has previously found acceptable in NUREG 1430. t f

The B&W Standard Technical Specifications include reporting requirements such that a special report,-when required, shall be submitted within 14 days, in accordance with STS Section 5.9.2, entitled "Special Reports".

1 The proposed Technical Specification Change Request specifies reporting requirements to be included in the Monthly Operating Report as covered by existing TMI-l Technical Specification 6.9.1.C.

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, .C311-93-2096 IV. NO SIGNIFICANT HAZARDS CONSIDERATION -l Application of the revised Limiting Condition for Operation has been determined to involve No Significant Hazards Consideration as follows:  !

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1. The revised Limiting Condition for Operation _ represents no increase in the probability of occurrence or consequences of an occident i previously evaluated. l The TSCR represents no change to the physical configuration or '

operation of the Reactor Coolant Inventory-Trending System. -

As stated in the Bases for the existing _ Technical Specification 3.24, the system is not a system required to mitigate accidents. It ,

may be useful to have the system operable, but adverse impact does not result if it is not operable; other useful information for -

monitoring inadequate core cooling is available. The change proposed is in accordance with the Limiting Condition for Operation provided in NUREG I430.

2. The revised Limiting Condition for Operation does not create the possibility of a new or different kind of accident from any accident ,

previously evaluated. '

As identified above, the TSCR represents no change to the physical configuration or operation of the Reactor Coolant Inventory Trending System.

3. The revised Limiting Condition for Operation does not involve a significant reduction in a margin of safety.

The margin of safety for the proposed Limiting Condition for Operation is no different from that for existing Technical Specifications, i

V. IMPLEMENTATION It is requested that the amendment authorizing this TSCR be effective 30 days after issuance.

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