ML20043D155

Amend 153 to License DPR-50,revising Tech Specs Re Inservice Insp of Steam Generator Tubes Following primary-to-secondary Leak

ML20043D155
Person / Time
Site:	Crane
Issue date:	05/29/1990
From:	Stolz J Office of Nuclear Reactor Regulation
To:	GPU Nuclear Corp, Jersey Central Power & Light Co, Metropolitan Edison Co, Pennsylvania Electric Co
Shared Package
ML20043D156	List: ML20043D155 ML20043D160
References
DPR-50-A-153 NUDOCS 9006070182
Download: ML20043D155 (8)

Text

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NUCLE AR REGULATORY COMMISSION p!

WASHINGTON,0. C. MDb6 s

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METROPOLITAN EDISON COMPANY j

JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50 289 THREE MILE ISLAND NUCLEAR STATION UNIT N0. 1 AMENDMENT TO FACILITY _ OPERATING LICENSE l

Amendment No.

153 License No. OPR-50 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by GPU Nuclear Corporation, et al.

(the licensee) dated March 12, 1990 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules anc regulations set forth in 10 CFR

. Chapter I; 1

L B.

The facility will o>erate in conformity with the application, l

the provisions of tie Act, and the rules and regulations of the Commission; C.

Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; l-and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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Accordingly, the license is amended by changes to the Technical i

Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No.

DPR-50 is hereby amended to read as follows:

(2) Technical Specificatinns The Technical Specifications contained in Appendix A, as revised through Amendment No.153, are bereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION lb< hA%

g1 ohn F. Stolz, Director Project Directorate I-4 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical

{

Specifications Date of Issuance:

May 29,1990 l

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AiTACHMENT TO LICENSE AMENDMENT NO.153 t;

FACILITY OPERATING LICENSE NO. OPR-50 DOCKET NO. 50-289 Replace the.following pages of the Facility Operating License and the Appendix A Technical Specifications with the attached pages. The revised pages are identified by anendment number and contain vertical lines indicating the area of change.

Remove Insert 4-78 4-78 4 79 4-79 4-80 4 80 4-81 4-81 4-82 4-82 l

l l

3-

each inservice bupaction shall include at least 34 et the total I

meher of tubes in all steen generstas; the tubes selected te these y#

inspections shall be selected an a rendas basis assust 4

n. 'Ihm first segle'of tubes malected te end inservice L

inspect,1crt (subsequent to the irw%) of each steen generate shall ude:

i 2.

All rurplugged tubes that previously had detectable i

L wall penetratione (>2M).

I-l 2.

At least SM of the tubes inspected shall be in those areas Wun esperience has indicated potential problems.

3.

A tube inspection (parsuant to Wicatian 4.19.4.a.8) ehall be performed an and aslected tubs, If any selected tubo does not permit the passage of i.

the addy czarrant gathe tw a tube inspection, this shall be rocceded and an adjacent tube shall be selected and subjected to a tube inspection.

l.

'Nbes in the follcwing grups may be esecluded frtun the 4.

first randos eenple if all tubes in a grup in both L

steen generates are inspected. No credit will be taken far these tubes in meeting minimum sogle sine resguirements.

t (1) Grup A-1: Tubes in rows 73 throu$t 79 adjacent to the open inspection lane, and tubes between and en lines drawn from tube 66-1 to tube 75-15 and tren 86-1 to 77-15.

(2) Grc@ A-2: 'Nbes having a drilled 6W in the 15th apport plata.

b. The tubes selected as the ascend and third ansples (if required by hble 4.19.2) during and inservice inspecticri may be subjected to a partial tube inspection providad:

1.

'!he tubes selected for these second and third senples incluso the tubes from thces areas of the tube ehest array where tubes with inperfecticns were previously j

found.

2.

'Ihm inspection includes thces peticre of the tubes Ware imperfections were previously found.

The results of est aanple inspection shall be classified into cria of the following three categories:

catagary Inspecticri menuits C-1.

less than 5% of the total tubes inspected in a steen generstar are *.esd tubes and ru:rie of the inspected tubes are def vs.

Anerdc,tNo.[,153 (12-22-78) 4-78 i

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c-2 One er acre tubes, but ret amo than 14 of the total tulos inspected in o stamm generate are defective, e butwenn 54 and 10% of the total tubes inspected are esg.eded tubes.

C-3 Mure than 104 et the total tubes inspected in a steen te are degraded tubes w acre than 14 of the tubes are defective.

Herts:

(1) In all inspections, gavvicusly degredad tubes must euhibit significant (>10%) further tall penetrations to be included in the abcNe percentage calculations.

(2) itiere== hi i&lans are perforand putmaant to 4.19.2.a.4, defective er degraded tubes found as a l

result of the inspection shall be included in detera-mining the Inspection Results Chtegory tw that 1

special inspection kut need not be included in estartining the Inspection Results catagery for the general steen generate iWi=t.

l 4.19.3 Inspectien Freepancias l

'the requi. tid inservice inspecticris of stase generate tubes shall be parfarand at the follcwing frequencies:

a. 'the first (baseline) irWien was performed after 6 i

effective full power acnths kut within 24 calendar acuiths of initial criticality. 'the sabesquent inservice inspections shall be performed not acre than 24 calender acnths after the previous inspection. If the results of two consecutive inspections te a given grup of tubes

• anecmpassing not less than is calendar acnths all fall into the C-1 cataycry or demonstrate that ptwvicusly observed Ge.geticri has not continued and no additimal degradation has occurred, the inspecticas interval fr that gray any be extended to a naw4== of ance per 40 aceiths.

b. If the results of the inservice ir==+3cri of a stamm generater conducted in acecadance with Table 4.19-2 at 40 scnth intervals fe a given grup of tubes

• fall into Category c-3 the inspection frequency for that grap shall be inersamed to at lasst once per 20 months. 'the increase in inspection frequency shall apply until the subsequent inspectitzis entisfy the witaria of specificatics) 4.19.3.a; the interval any than be extended to a mav h e of ence per 40 acnths

c. Additicrial, unscheduled insarvice inspections shall be perferned on eacts staan generate in accertlance with the first sample inspecticri specified in Table 4.19-2 &aing the shutdown sabsequent to ary of the following conditions:

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• A grcqp of tubes means:

(a) All tubes inspected pursuant to 4.19.2.a.4, z (b) All tubes in a steam generatar less thces l

inspected pursuant to 4.19.2.a.4 Acerdment No. [153 l

(12-22-78) 4-79 l

4.,

1. A animaic namnTurce greater than tia Cgerating basis Earthganks.

2. A 1ces of coolant accident requiring actaastism of engineering amfeguards, e

3. A asjer amin stama line or feedwater line break.

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d. After ph tube leakage (not including laaks criginating frten tube-tcP4:ube ehest telds) in emmens 2

of the limits of Wificatim 3.1.6.3, en inspection of the affected staan generate will be i

accordance with the following witaria performed in i

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1. If the leek'is abme the 14th tube angpart plate in a t

Qttap as defined in Section 4.19.2.a.4(1) all of the tubes in this Grc in the affected stess will to inspected abwe@the 14th tubs agpart If the results of this ie.ica fall into the 0 3 catagary, e&titional inspecticms will be performed in the asan attap in the other stamm generstar.

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2. If the leaking tube is not as defined in Sectie 4.19.3.d.1, than an inspectice will be parfanned an the affected stana generatar(s) in noocedance with 'mble 4.19-2.

4.19.4 Ar-tanon critarla 1

a. As used in this W ificatient

1. Igarfection means an mesption to the dimensions, finish er acrrtour of a tuka frtan that required by fabrication drawing er specificaticms, akty current testing in11-cations balcw 2M of the ncuninal tube well thickness, if detectable, any be exrsidered as imperfecticms.

2. Degradaticm means a service-indooed cracking, wastage, waar or general corrosien cocurring on either inside er cutside of a tube.

3. Degraded 'naba means a tube crutaining imperfections 22M of the ncatinal tall thickness caused by degradation.

4. t wtien anans the p=w.tage of the tube wall thickness affected or removed by degradation.

5. Defagt means an imperfecticm of such severity that it aw==4= the repair limit. A tube containing a defect is defective.

4-80 AILerbit No.1[,1 153

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,, 4.19.4 Ammanytanas critaria (Omtisaani)

6. Repair Limit means the autant of degradation at a bayed whie the tube shall be npaired a newed trca service -

because it any becues smeerviceable grie to the next

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i&M.

1 Blis limit is agaal to 40% of the nainal tube wall thicknees.

7. Uheervimmable describes the conditism of a tube if it leaks = ocritains a defect large 6 to affect its structural integrity in the event of an operating Resis Earthgaska, a loss of coolant accident, er a steen line er feedwater line numak as specified in 4.lp.3.c., abwe.

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s. ' tuba Inspecticri means an iWice of the steen generatar l

tube fria the bottaa of the typer tubenhast ocupletely to the tcy of the lower tubashast, asempt as permitted by i

4.19.2.b.2, abwe.

i b.

'!he steem gmarote shall be determined CPERAE!J: after ocrpleting the -

plugging, or repair +by kinetic expansicm, slesving, e otherding actiens (

nothods, of all tubes MW the repair limit and all tubes ocntaining thatupwall oracks) required by 'hble 4.19-2.

l 4.19.5 M

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d Fellowing the ocupletion of and irieervice inspection of stena generstar tubes, the nabar of tubes repaired or rammed frtun serviam in each stase generstar shall be repeted to the HR: within 15 days, b.

'Ihe ocuple;e results of the staea generater tube inservice irLMcm shall be repcrtad to the NRC within 3 acoth6 following ecupleticm of the iWlan.

2 tis rispert shall include:

1.

Number and extant of tubes inspected.

2.

Locatica and p eA of wall-thickness i r 1.6. tion for each indioetice of an imperfection.

3.

Identification of tubes repaired er removed frca service.

c.

Results of staan generate tube irMians Wsich fall into estagery C-3 require notification in acoatilance with 10 CFR 50.72 prior to remunption of plant operaticm. 'Ihe written followup of this repcet shall provide a description of investigations cerrtocted to detartine the cause of the tube degradaticm and wu.ctive measures taken to prevent recurrence in accorde.noe with 10 CFR 50.73.

1 4-41 Amandwit No. h, f[, g, Ad, f, Mt 153

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'the surveillanon hequirwasnts for ir--* lcm of the stase generate tubes ensure that the structursl integrity of this partian of the Mcs will be maintained.

'!he progree fe inearvice inspecticm of stase generator tubes is based cm modificatie of hogulatary maide 1.83, Asvisicm'1. 2n-earvion inspection of stase generetcr tubing is essential in order to amintain surveillanos of the omditions of the tubes in the event that there is evidence of andanioni desage er geogressive degradatimi than to design, manufacturing errors, or inservice conditions. Inservice inspection of stase generator tubing also yrtvides a means of characterising the nature and oeuse of any tube degradation so that corrective maneures can be taken.

'the Urdt is owpected to be operated in a manner audi that the primary and enomsary coolant will be maintained within those chanistry limits fcund to result in negligible carrasion of the stana generster tubes.

If the primary er esoendary coolant chanistry is not maintained within these chemistry limits, localised corrosien any likely result.

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'!he extant of stasa generator tube leakage than to orscking wculd be limitad by the neocndary coolant activity, specificatica 3.1.6.3.

'The extant of cracking during plant operation would be limitad by the limitation of total staan generate tube leakage between the grinary coolant systan and the secondary coolant systaa (priumry-te.e eary leakage = 1 gyn). Imakepe in access of this limit will require plant shutdown and an unscheduled inspection, chring Wdch l

the leaking tubes will be lacetad and repaired cr removed trum service.

Wastage-type defects are unlikely with proper cheadstry treatment of the primary er the neocmdary coolant. However, even if a defect would develop in servios, it will be found during scheduled in-l marvice steam generate tube examinations. Steam generetcr tube inspecticrs of operating plants have demonstrated the capability to reliably detect G.p.dation that has penetrated 2M of the eriginal tube well thickness.

Renoval frcan service by plugging, er repair by kinstic expansicm, slesving, or other methods, will be required for degradaticm equal to er in===== of 4M of the. tubs neaninal wall thickness.

Where operience in similar plants with rimilar water chsunbtry, as h=arrted by 15NRC Bulletins / Notices, inticate orjtical F.reas to be inspa: tad, at least SM of the tubes inspected ehenad be frtai these critical areas. First sant>1e inspecticre sanple saa any be andified subject to NRC rwview ar6 QW.

1 4-82 Atrisd-rit No.

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, lh 153

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