ML20154Q620

TS Change Request 248 to License DPR-50,adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18, Remote Shutdown Sys

ML20154Q620
Person / Time
Site:	Three Mile Island
Issue date:	10/19/1998
From:	Langenbach J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20154Q625	List: ML20154Q620 ML20154Q627
References
RTR-NUREG-1430 1920-98-20183, NUDOCS 9810260033
Download: ML20154Q620 (5)

Text

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Route 441 South NUCLEAR Post Office Box 480 Middletown, PA 17057-0480 Tel 717 944 7621 October 19, 1998 1920-98-20183 U.S. Nuclear Regulatory Conunission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

Subject:

Three hiile Island Nuclear Station, Unit I (TMI 1)

Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 248 - Remote Shutdown System In accordance with 10 CFR 50.4(b)(1), enclosed is Technical Specification Change Request (TSCR)

No. 248.

The purpose of this TSCR is to resise the Th11-1 Technical Specifications to add operability and sun'eillance requirements for the remote shutdown system similar to those in NUREG-1430, " Standard Technical Specifications - Babcock and Wilcox Plants", Section 3.3.18 entitled " Remote Shutdown System"

-Using the standards in 10 CFR 50.92, GPU Nuclear has concluded that these proposed changes do not constitute a significant hazards consideration, as described in the enclosed analysis performed in accordance with 10 CFR 50.91(a)(1). Also enclosed is the Certificate of Senice for this request certifying senice to the chief executives of the township and county in which the facility is located, as well as the designated official of the Conunonwealth of Pennsylvania, Bureau of Radiation Protection.

Sincerely, MN R James W.12ngenb 1 Vice President and Director, Thil ID1D Encl. (1) TMI-l TSCR No. 248 Safety Evaluation, No Significant Hazards Consideration, Technical Specification Revised Pages. .

(2) Certificate of Senice for TMI-l TSCR No. 248 l cc: Administrator, Region I TMl Senior Resident inspector a\

TMI-l Senior Project Manager , 7 , ',, '],

9810260033 981019'

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PDR ADOCK 05000289 P PDR.

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.- . l METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND l PENNSYLVANIA ELECTRIC COMPANY j THREE MILE ISLAND NUCLEAR STATION, UNIT 1  !

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Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 248 I

COMMONWEALTH OF PENNSYLVANIA )

) SS:

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 itquest, proposed replacement pages for Appendix A are also included.

GPU NUCLEARINC. l BY: Mudh N/X W re President and r or, TM[

Swom ubsen to fore me this /,

y of

, -A s.1998 s M/ "

[ [otaryPublic ( '

Notarial Seal Suzanne C. Miklosik. Not ry Public

MyC is on xhi esf4cv. ,1 99 Member, Pennsylvansa Assouation of Notanes 4

i

• 4 ENCLOSURE 1 TMI-I Technical Specification Change Request No. 248 Safety Evaluation No Significant Ilazards Consideration and Proposed Technical Specification Revised Pages i

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Enclosure 1 I

• l 1920-98-20183 Page 1 of 2

1. ' . Technical Specification Change Request No. 248 GPU Nuclear requests that the following changed replacement pages be inserted into existing Technical Specifications:

1 Revised Technical Specification Pages: ii, vi, ~4-2, 4-2a l l

GPU Nuclear requests that the following new pages be insened into existing Technical l

. Specifications:  ;

Add Technical Specification Pages: 3-40g,3-40h,3-40i,3-40j These pages are attached to this enclosure. l l

, 11. Reason for Change The purpose of this Technical Specification Change Request is to revise the TMI-l Technical Specifications to add operability and surveillance requirements for the remote shutdown system similar to those in NUREG-1430, " Standard Technical Specifications - Babcock and Wilcox Plants," Section 3.3.18 entitled " Remote Shutdown Systems".

III. Safety Evaluation Justifying Change The proposed revision to the TMI-l Technical Specifications adds operability and surveillance requirements to the Technical Specifications for the remote shutdown system functions similar to those in NUREG-1430, " Standard Technical Specifications - Babcock Wilcox Plants", Section 3.3.18 entitled " Remote Shutdown Systems." Incorporation of these requirements into the TMI-1 Technical Specifications was requested by NRC letter dated December 27,1994. The remote l s hutdown system meets the NRC Policy Statement as a risk significant item for retention in the l

. Technical Specifications and therefore is being added to the TMI-l Technical Specifications.

Surveillance of the instrumentation and controls associated with the TMI-l remote shutdown system functions listed in the proposed Technical Specification change will continue to be implemented in accordance with the existing TMI-l Fire Protection Program Administrative Procedure (AP) 1038, and associated surveillance procedures. These existing controls currently l envelope the proposed Technical Specification requirements with the exception of the proposed specification requirement for plant shutdown if a required function is not restored to operable s'atus within 30 days. Procedure AP-1038 will be revised to incorporate the proposed Technical Specification requirements, where applicable.

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• Enclosure 1 1920-98-20183 Page 2 of 2 l

Proposed Technical Specification Section 3.5.7, Remote Shutdown System, incorporates the applicability requirements, limiting conditions of operation, operability requirements, required actions and completion times, and Bases. Proposed Technical Specification Section 4.1.4 incorporates the remote shutdown system surveillance requirements. The proposed Technical Specification changes are consistent with the NRC Standard Technical Specification (NUREG-1430) requirements for remote shutdown system. The proposed revision to existing Technical Specification page 4-2a is only to accommodate repagination from page 4-2 as a result of the text added to page 4-2. This change to page 4-2a is only editorial. Therefore, the proposed change providee additional assurance ofopernbility of the TMI-l remote shutdown system functions in the event that operators must place and maintain the unit in a safe shutdown condition from outside the control room.

IV. No Significant Hazards Consideration GPU Nuclear has determined that this Technical Specification Change Request poses no significant hazards consideration as defined by 10 CFR 50.92.

1. Operation of the facility in accordance with the proposed amendment would not involve a i significant increase in the probability of occurrence or the consequences of an accident previously evaluated. The proposed amendment adds operability and surveillance requirements for the existing TMI-l remote shutdown system similar to those contained in 1 NRC NUREG-1430," Standard Technical Specifications - Babcock & Wilcox Plants" The addition of these requirements to Technical Specifications provides further assurance of remote shutdown system operability in the event that operators must place and maintain the unit in a safe shutdown condition from outside the control room. The function and operation of the remote shutdown system has not changed. Therefore, this activity has no affect on the ,

probability of occurrence or consequences of an accident previously evaluated. l

2. Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any previously evaluated. The proposed amendment has no impact on any plant stmetures, systems or components. The function and operation of the remote shutdown system has not changed. Therefore, this activity does not create the possibility of a new or different kind of accident from any presiously evaluated.

3. Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety. The proposed amendment provides additional assurance of remote shutdo.wn system operability. The function and operation of the remote shutdown system has not changed. Therefore, this activity does not reduce the margin of safety.

l V. Implementation l

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GPU Nuclear requests that the amendment authorizing this change become effective thirty (30) l days after issuance.