ML20206R111

Application for Amend to License DPR-50,requesting That License Sections 2.a.(3) & 2.c.(7) & TS Section 3.1.1 Be Revised to Incorporate Administrative Updating & Changes to Bases Statement

ML20206R111
Person / Time
Site:	Three Mile Island
Issue date:	05/13/1999
From:	Langenbach J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20206R114	List: ML20206R111 ML20206R117
References
1920-98-20387, NUDOCS 9905200001
Download: ML20206R111 (6)

Text

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l l GPU Nucleer,Inc.

( Route 441 south NUCLEAR '**'*c*B***80 Middletown. PA 17057-0480 U. S. Nuclear Regulatory Commission Attention: Document Control Desk May 13,1999 Washington, DC 20555 3

1920-98-20387

Subject:

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

Operating License No. DPR-50 l j

Docket No.53-289 Technical Specification Change Request No. 275 Administrative, and Bases Related Changes .

i In accordance with 10 CFR 50A (b) (1), enclosed is Technical Specification Change Request No. f 275. Also enclosed is the Cenificate of Service for this request certifying service to the chief executives of the township and county in which the facility is located, as well as the designated oflicial of the Commonwealth of Pennsylvania, Bureau of Radiation Protection.

The purpose of this TSCR is to request that the TMI-l License No. DPR-50 Sections 2.a.,

2.c.(3), and 2.c.(7) and Technical Specifications Section 3.1.1 be revised to incorporate administrative updating, and changes to a bases statement.

I Pursuant to 10 CFR 50.91 (a) (1), enclosed is our analysis, applying the standards in 10 CFR //, -

50.92 to make a determination of no significant hazards considerations. // .

We have provided a copy of this letter, the proposed changes in License No. DPR-50, the Technical Specifications, and our analyses of no significant hazards considerations to the designated representative of the Commonwealth of Pennsylvania.

Sincerely,f)

_n ,

(All--

9905200001 990513 PDR ADOCK 05000289 J. W. Langenba P PDR Vice President and Director, TMI VLK i

Enclosures:

(1) Technical Specification Change Request No. 275 (2) TMI-l License and Technical Specification revised pages (3) Certificate of Service for Technical Specification Change Request No. 275 cc: Administrator Region I TMI Senior Resident Inspector TMI-l Project Manager File 98110 190075

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Enclosure 1 TMI-l Technical Specification Change Request No. 275 l

And No Significant Hazards Consideration Analysis

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1920-98-20387 Enclosure 1 Page1of4 I. TECHNICAL SPECIFICATION CHANGE REOUEST frSCR) No. 275 GPU Nuclear requests that the following changed replacement pages be inserted into the existing License and Technical Specification:

License revised pages: 2,4, and 5 and Technical Specifications revised page 3-2.

These pages are attached to this change request.-

II. REASON FOR CHANGE AND BRIEF DESCRIPTION OF CHANGES This change is submitted as a result of changes to a bases statement, organizational changes, and administrative updating. The License currently refers to obsolete revisions of the Final Safety Analysis Report, and other obsolete references. Generic references to documents will be used to eliminate License changes wherever specific revision numbers change.

The following refers to page numbers associated with the location of text on the revised pages and describes the changes:

License Pane 2:

'Ihe references to specific amendments of the Final Safety Analysis Report and Environmental Report were deleted and replaced with generic references to eliminate frequent License and Technical Specification changes.

Mark up:

2. Facility Operating License No. DPR-50 is hereby issued to the Metropolitan Edison Company, Jersey Central Power and Light Company, Pennsylvania Electric Company d/b/a GPU Energy and GPU Nuclear,Inc. to read as follows:

a. This license applies to the Three Mile Island Nuclear Station, Unit 1, a pressurized water reactor and associated equipment (the facility), owned by the Metropolitan Edison Company, Jersey Central Power and Light Company, Pennsylvania Electric Company d/b/a GPU Energy and operated by GPU Nuclear, Inc.. The facility is located in Dauphin County, Pennsylvania, and is described in the Updated Final Safety Analysis Report" as supplemented and amended

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,y '- ". 3! i- :# 47) and the Emironmental Report as supplemented and amended License Pane 4:

The references to specific dates of revision of the Modified Amended Physical Security Plan, the Security Personnel Training and Qualification Plan, and the Safeguards Contingency Plan were replaced with the generic term "as revised" to eliminate changes to the license when these documents are revised.

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1920'-98-20387 Enclosure 1 Page 2 of 4 Mark up:

(3) Physical Protection The licens chai! fully implement and maintain in efTect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the cuthority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain safeguards information protected under 10 CFR 73.21, are entitled: "Three Mile Island, Units 1 and 2, Modified Amended Physical Security Plan," whh =vi:!c= =h=hted thrcugh Ja!y S,19S8 as revised; "Three Mile Island, Units 1 and 2, Security Personnel Training and Qualification Plan,"

whh =vi:!c= =h=h::d $rcugh Ncvc=bc 28,1986 as revised; and "Three Mile Island, Units 1 and 2, Safeguards Contingency Plan," with =vi;ica =hr.::::d th= ugh Jun: 20,1986 as revised. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

License Pane 5:

This license condition in paragraph (7) requires a report to be submitted to the NRC for aircraft movements at the Harrisburg Intemational Airport for calendar year 1984. He report 5211 2086," Updated Prediction of the Frequency of Aircraft Crashes at the Three Mile Island Unit 1

- Site," was submitted to the NRC May 1,1985, which fulfilled this license condition. Therefore this paragraph was deleted. Detailed aircraft crash data and analysis is contained in FSAR Section 2.4.

Mark up:

(7) Aircraft Movements DELETED Six'y (60) by: f !!=;;;; S: apen = !==P. :===:: :: 6:Harrisberg

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=....: '-' = :i==P. =:===:: :: i Hz !d=; In:==:! =! Ai: pen cd up'"-f --'::=! r.=i:! =d n'= =d i:!! 5:ir:f = S: ==: =:Sede! gy p:==::d by M:=pe!!:= Edi== C =p=y = ==p::d by i: App =! Be=d in ALAB 692. Fe! brin; ==g: sf =d =pn NRC .ci!!, :P.= d!===!= wii CPU N=!= , !=., &'rH= i: :=d for inh = pried!; ;ir =2 p:ddi!!:y

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Technical Soecificction Bases Pane 3-2:

This Technical Specification revision is to correct an error in the Technical Specifications Section 3.1.1 Bases. The statement " ..each valve shall be capable of relieving 280,800 lb/hr" will be deleted from Technical Specifications. This value (280,800 lb/hr) is in conflict with the design of the system and values used in safety analysis. The correct value as determined from Dresser

1920'-98-20387 Enclosure 1 Page 3 of 4 Drawing 3NC-006 Sheet 6 and from the valve nameplate (VM-TM-0212) is 297,846 lb/hr with the valve fully open, at 3% accumulation. The statement deleted also contains the liR requirement of 3 percent above set pressure. This requirement is still described by providing the statement that a 3% pressurizer code safety valve drift tolerance is acceptable in accordance with 1 ASME Section XI code and within the assumptions of the TMI-1 Safety Analysis. No change is made to the *1 percent lift setpoint for the valves.

Mark up:

One pressurizer code safety valve is capable of preventing overpressurization when the reactor is not critical since its relieving capacity is greater than that required by the sum of the available heat sources which are pump energy, pressurizer heaters, and reactor decay heat. Both pressurizer code safety valves are required to be in service prior to criticality to conform to the system design relief capabilities. The code safety valves prevent overpressure for a rod withdrawal or feedwater line break accidents (Reference 4). The pressurizer code safety valve lift set point shall be set at 2500 psig 1% allowance for error =' =h v:!v: da!! be sin 5!: sf

=!!:ving 23^,^^^ !bb. cf :=:' d === :: : prax:: ::: ;=:= i= f.ru p===: :5:v: 6: =: ,

presswo: Surveillance requirements are specified in the Inservice Testing Program.

Pressurizer code safety valve setpoint drift of up to 3% is acceptable in accordance with ASME Section XI (Reference 5) and the assumptions of TMI 1 safety analysis.

III. SAFETY EVALUATION JUSTIFYING CHANGE The proposed changes have no impact on the continued safe operation of the TMI-l nuclear power plant. The administrative changes do not alter the functions performed at the plant and do not alter any obligations under the license for TMI-1. The proposed changes do not involve modifications of any systems, structures, or components and do not alter any operating limits. Therefore there will be no impact on safe operation of TMI-l as a result of the proposed changes.

IV. NO SIGNIFICANT HAZARDS CONSIDERATIONS GPU Nuclear has determined that the requested Technical Specification Change poses no  ;

significant hazard consideration as defined by NRC in 10 CFR 50.92.

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1. Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated. Most of the proposed amendment is only administrative; it adds to the Technical Specifications generic references to various documents. These changes have no affect upon the plant design or operation.

l The proposed change to the Technical Specification Bases 3.1.1 is the removal of the specnied pressurizer code safety valve flow-rate for which no basis could be found and the seceptance of a 3% setpoint drift (as-found) as per the ASME code. The 3% code limit is in accordance with the plant's Inservice Test Program submittal, which was evaluated by the NRC staff for the current

1920-98-20387 Enclosure 1 Page 4 of 4 10 year interval and documented under f JitC TAC No. M93777. The Correct pressurizer  !

code safety valve flow is provided in the FSAR Table 4.2-8. The proposed change is supported by a revise Startup Accident analysis with the revised safety valve flow-rate at the 3% setpoint drift, which demonstrated that the acceptance criteria for the event were met with considerable margin. The proposed change does not affect the Technical Specification 3.1.1.a, pressurizer code safety valve operable (as-left) requirement ofil%.

Therefore, operation in accordance with the proposed amendment does not involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated.

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 accident previously evaluated, because no new failure modes are created by the proposed changes. The administrative changes are cosmetic and have no impact on plant design or operation.

3. Operation of the facility in accordance with the proposed amendment will not involve a significant reduction in a margin of safety. The proposed amendment does not change any operating limits for reactor operation.

V. IMPLEMENTATION GPU Nuclear requests that the amendment authorizing these changes become effective upon issuance.

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