ML19270H564

Proposed Tech Specs 3.0, Limiting Conditions for Operation

ML19270H564
Person / Time
Site:	Crane
Issue date:	06/27/1978
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML19270H563	List: ML19270H562 ML19270H564 ML19270H566
References
NUDOCS 7911110080
Download: ML19270H564 (14)

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Applies to the operating stctus of reactor coclant systc= cc=ponente.

phacetive To specify these li=iting ccnditiens for operatien of reacter cociant systcn ecmponents which.ust te met to ensure safe resctor cperations.

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3.1.1.1 Reactor Coolant Pucps a.

Pump ccmbinatiens per=issible for given power levels shall be cs shown in Specificatien Table 2 3 1.

b.

Power operation with one idle reactor coolant p=p in each loep shall be restricted to 24 hcurs.

If the reactor is not returned to as acceptable EC pump cperatinC cc=bination at the end of the 2h-hcur pcried, the reactor shall be in a het shutdcun ec.citica within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c.

The beren concentratica in the reacter ecclant syster shall not be reduced unless at lectt ene reac cr, ccclant p=p or cne de -y heat re=cval p=p is circulating ree.cter ecolant.

3.1.1.2 Stee= Generater a.

Ecth stee.n g,enerators shall be cperable whenever the reacter j

coolant averaCe te:perature is above 2 Ocy, 3.1.1.3 Pressuricer Safety valves n.

The reactor chall not re=ain critical unless both pressuricer code cafety valves are. operable with a lift settins of 2500 peg

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b.

When the reacter is suberiticci, at least ene pressuricer cede safety valve shn11 be operable if all reacter ecclent systen ope:dn s are cloced, except fcr hydroc ntic test.< in accorda: e with ASIC Eciler and Fressure Vessel Ocle, Sectica III.

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Pace:

The limitation en power epcration with ene idle PC ump in cach lecp ha: been imposed cince the ECOS cooling perfor 2nce ha: nct.aen cal:ulated in 2:00r-d ar.c a.

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• s A reacter ecciant pump cr decay hect rencval pun; is required to be in cperatien before the beren concentration is reduced by dilutien with =akeup vater.

Either punp vill provide mixing which vill prevent sudden pcsitive reactivity chances :cused by dilute coolant reaching the reactor. Cne decay he t renoval pu..p vill circulate the equivalent of tha reactor ecclant sy:tcu volume in one-half hcur er less.

The decay heat rc= val sy:te= suction piping is desicned for 30^0F and 370 psig; thuc, the yste: an rencve de y heat when the ree.: tor coolant sy te= 1: telev this temperature..I2, 3)

Both steam generaters must be operable before heatup of the Peacter Ccclant Systc= to insure cystem integrity again:t leakcce under normal and transient ccr'i'.4c....

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One pressurizer : de safety valve is capable of preventing everpreocuri:ction when the rec 0 tor is not critical since its relievinc capacity is greater than that required by the sum of the availe.ble hea; scurce: which are pulp m.uey, pressurizer heaters, and reacter dceny heat. b') 3cth pressurizer code safety valves are required to be in service prier to criticality to ecnfon: to the systen' design relief capabilitig?.

The ecde safety valves prevent ever;re:sure for a rod withdrawal accidcnt.l)) The pres e"-4 a-

+0de safety valve lif t set point shall be set at 2500 psig il percent allowance for error and each valve shall be capable of relieving 230,S00 lb/h or saturated steam at a pressure not greater than :hree percent above the set pressure.

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3 1.6.1 If the total reactor c001 ant leakage rate exceeds 10 g;n, the reactor shall be p1n:cd in hot chutdevn within 2h hcurs Cf detecti:n.

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. e such losses vnen cdded to leskage shall not en: cod 30 c;n.

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When reactor ecclant leakage occurs to the Auxiliar-] Euilding, it is collected

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s i.. r Annlie.tility This Technical Specificcti:n cpplies to the inservice inspection of the GTI~

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f Ct *eeti te The objective of this in=ervice inspection progran is to provide cssurance of continued 11tegrity of the tube portien of the Cnce-TPreugh Steam Generatcre, while at the same ti=e =ini=izing radiation exposure to percennel in the perfornance of the inspectica.

Snecification Each cte1= generatcr shall te de=cnstrated CFEEA31E by performance of the 4

following augmented incervice inspection progra and the requirc:ents of Specificctien 3.1.6.3 4.19.1 Steam Geners.ter Etmple Selectice and Insoection Methods Each steam generater : hall be deter =ined CPEEA3LE during shutdevn by 3.

selecting and inspecting at leas; the tininun number of stems generators specified in Table 4.19.1 at' the frequency pecified in 4.19.3.

b.

Inservice inspection of steam generator tubing shall include non-destructive examination by eddy-current testing er other equivalent techniques. The inspection equi;=ent shall be calibrated to provide a sensitivity that will detect defects with a penetration of 20 percent or more of the minimum allevable as-manuf actura i *ube wall thickness.

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claq:ification, and the correspending cetion required chall be a:

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r tubes chall be perfor:cd at the frequencies specified in Specit ;_-

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cach inservice inspection shall include at leset 3% of the total number of tubes in all steam generators; the ttees selected for thece inspections shall be selected on a random basis except:

i a.

The first sample of tubes select:d for each inservice inspection (cubsequent to the preservice inspection) of each steam generator shall include:

1.

All nonplugged tubes that previously had detectable wall penetrations (>20%).

2.

A: least 50~ of the tubes inspected shall be in those areas where experience has indicated potencial problems.

3.

'A tube inspection (pursuant to Specification 4.19.4.a.8) shall be performed on each selected tube.

If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection, d

b. 'The tubes selected as the second and third samples (if required by Ttble 4.19.2) during each inservice inspection may be subje:ted to a partial tube inspection prrvided:

1.

The tubes selected for these second and third samples include the tubes from those areas of the :ube sheet ar. ray where tubes with i= perfections were previously found.

2.

The inspection includes those portions of the tubes where imperfecticas were previously found.

Tie results of each sacple inspection shall be classified into one of the llowing three categories:

Catecorv Inspection Results C-1 Less than 5% of the total tubes inspected in a steam generator are degraded tubes and none of the inspec:ed tubes are defective.

C-2 One or more tubes, but not more than 1% of the total tubes inspected in a steam generator are defective, or between 5' and 10*. of the total tubes inspc__ed are degraded tubes.

C-3 More than 10" of the total tubes ir.spected in a steam generator are degraded tubes or more than 1" of the inspected tubes are defectivc.

Note:

In all inspections, previously degraded tubes must enhibit significan: (>102) further 4:all penetrations to be included

'in the above percentage calculaticas.

4-64 701 9rq

-e o

4.19.3 Insnection Frecuencies The required inservice inspections of steam generator tubes chall be performed at the felicwing frequencies:

a.

The first (baseline) inspecticn was performed af ter 6 ef f ective full power =cnths but within 24 calcadar =cnths of initial criticality. The subscquent inservice inspections shall be perfor=ed not more than 24 calendar cenths af ter the previous inspectien.

If the results of two consecutive inspections encompassing not less than 13 calendar =cnths all fall into the C-1 category or der. castrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extcaded to a =aximum of once per 40 months.

9 b.

If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.19.2 at 40 =cnth intervals fall into Category C-3, the inspection frequency shall be incr. eased to at least once per 20 conths. The increase in inspection frequency shall apply until the subsequent inspec-

1ons satisfy the criteria of Specification 4.19.3.a; the interval =ay then be extended to a maxi =um of once per 40 months.

c.

Additional, unscheduled inservice inspections shall be perforced on each steas generator in accordance with the first sample inspection specified in Table 4.19.2 during the shutdown subsequent to any of the following conditions:

1.

Primary-to-secondary tubes leaks (not including leaks originating frca Tube-to-tube sheet welds) in excess of the limits of Specification 3.1.6.3.

2.

A seismic occurrence grea'ter than the Operating Basis Earthquake.

3.

A loss of coolant cccident requirins actuatien of t!.e eng :.et-ring safeguards, or 4.

A major main stcas line er feedwater line treak.

e 4

4-65

4.19.4 Accertnree Criterin a.

As used in this Gpecificaticn:

1.

Interfec*'.:n n.:n: an enceptien c the diren:icns, finich or C c..'.c"* w.' a..^ a. '.-...*.".G.

• a_ - "..i.- a. d. *y.'u.'.-"*.'..

a

. g

s. e.-. t.e.u..s.e.- n. t - s t.

O m g.j. y a-s c.

e. e e. t.e.s a..t n~.

v.2 A.s........s.

n t

.e s

' elow 205 of the nc=inal tute vall thickness, if detcetable, may be cen:idered as imperfecticns.

2.

Derreda.tien neans a service-induced cra.r?.ing, vastage, vear er cer,cral corresien ec:urring en either inside er out ide of a tube, 1

3 Decreded S2be = cans a tube i:cntaining imperfections >205 of the nc=inal vall thickness etu:ed by degradatica.

k.

% Denredatien means the percentage of the tube vall thichness affected or removed by degradatien.

5 Defee~t means an i= perfection of such severity thac it exceeds the plugging limit. A tube containing a defect is defective.

6.

Plurrine limit =eans the i= perfection depth at or beycnd which the tube shall be re=cved f c= service because it may becc=c unservicechle prier to the ncnt in:pection and is equal to LC5 of the nominal tube vc11 thicknecs unl :s higher limits are shown to be acceptable by analysis and Dpproved by the EC.

7.

Unserviceable describes the cendition of a tube if it laaks or contains a defect large encuen to af f ect its structural integrity in the even: of an Operating 3 asis Earthcuake a loss-of-ecolant accident, or a team line or feedwater liac break as specified in 4.19.3.c, above.

S.

Tube ins eerien means an ins:cetion of the staan gen 2:ator tube frnm the bottom of the unpur tubesnea: :::pletal, :o zcept as permit:cd 'r the top of the icwer tubesheet, 4.19.2.b.2, above.

,4-00

' 7h)

]"j c--

L b.

The stes= cancratcr shall be determined 0?:D/.21I cfter ic:plet-int the correspending actienc (pluccin; including all tutec exceeding the pluccinc ll=it and cil tubec centaining thren;h-vn11 cracks ) required by Table 4.19.2.

4.19.5 Repert.

a.

Follevins the cc=pletien of each inservice inspectica ci stea=

s generator tubes, the number cf tubes plugged in each ctes=

cenerator sht11 be reported to the Cc==ission within 15 days.

b.

The ec=plete results of the ste1= generater tube incervice inspection shall 'ae reported to the NRC vithin 3 =enths follering ec=pletion of the inspection. This report saall include:

~

1.

Nu=ber and extent of tubes incpected.

2.

Location and percent of vall-thickness penetratica fer each indicction of En i= perfection.

3 Identificatien of tubes plucsed.

c.

Results of stea: generator tube inspections which fall into Category C-3 and require prc=pt notification of the Cc==1ssien shall be reported pursuant to Specificatien 6.9.2 prior to resu=ption of plant operation. The written followup of this report shall provide a description of investigations conducted to deter =ine cause of the tube degradation and corrective

=easures taken to prevent recurrence.

Bases The Surveillance Require =ent: for inspectica of the stet = generater tube:

ensure that the structural intecrity of this pcrtien of the RCS will te unintsinet, o?n1 9 ' ')

L-c; u-

\\

1 oi.. progra: for inservice 'nspection of steam generator tubes is based on a

.il t ication of Regulatory Guide 1.53, Revision 1.

Incervice Inspection of

.-wi generator tubing is essential in order to maintain surveillance of the

...titions of the tubes in the event that there is evidence of mechanical ige or progressive degradation due to design, =anuf acturing errors, or ervice conditions.

Inservice inspection of stea= generator tubir.g also

..vides a =eans of characterizing the nature and cause of any tube degradation

hat corrective measures can be taken.

unit is expected to be operated in a =anner such that the secondary ec:lant

.11 bc =aintained within those chenistry limits found to result in neglicible errocion of the steam generator tubes.

If the cecendary ecolant chenistry is

maintained within these chc=istry li=its, localized cerrc icn may likely tralt in stress cerrosien cracking.

l I

I

\\

.e extent of steam generater tube leakage due to cracking would be limited by a cecondary ecciant activity, Specification 3.1.6.3 extent of crackinc during plant operation vculd be limited by the limitc-

, of total steam generator tube leakage between the primary coolant etm and the secondary coolant system (primary-to-secondary leakage = 1 Leakage in excess of this limit will require plant shutdcwr. and an heduled inspection, during which the leaking tubes will be located and Ped.

O7O]

9 ' *[

c._

h-68

4 of the Wa: tace-type defcets are unlikely with preper chc=1:try treat = cat seccadary ecciant.

Ecwever, even if a defect uculd develop in cervice, it will be fcund durinc scheduled in:crvice seca: cencrater tube exa:sination:.

Pluccinc vill te required fer degradatica equal to cr in excecs of 50,5 cf the tube nenib.al vall thi:hnese, unle::. higher limits are shewn to te acce: tabic by analysis and are reviewed and approved by the NRC.

Stea= generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 2G" of the original tube wall thickness.

Where experience in similar plants with similar water chemistry, as documented by USNRC Sulletins/ Circulars, indicate critical areas to be inspected, at least 50~. of the tubes inspected should be from these critical areas. First sa=ple inspections sa:ple size may be modified subject to NRC review and approval.

L'acnever the resdits of cry stcas generater tubing inservice inspection fall into categcry C-3 on the 1st sample inspection, (See Table 4.19.2), these results vill be prc ptly repcrted to the Cc= ission pur uant to Specificati:n 6.9.2 prior to resu=ption of plant operatien. Such cares vill be ccncidered fer by the Cenniscien en a case-by-case ba:is and =ay recult in a requirement analysis, lateratory examinatiens, tests, additional eddy current inspection, and revisien of the Technical S;ccificatiens, 'f nececcary.

=

q7nq q'4 c-h-69

T!GLE 4.19.1 ff.u.. A,..,,.: e Cr S

,s.

.m..n,. v-e.S.C 2..,

L.t.e.P.c.a m rL.e. -..G.. 5 =.. rn e,. =...e...- e.

Preservice Inspection Iione I'o. of Stes: Generaters per unit

?.to First Inser. ice Inspectica

?.co l

Secen:1 & Subsequent Inservice Inspections Cne f

,tvia ' av:,;

AncLL.

l'.

':'ne Inservice Inspecticn may be li=ited to cne steam generater en a rotating schedule enecepassinc 6*: of the tubes in that steam generater if the results of the first and subsequent inspections indicate that bcth stec.s generaters are perfor=ing in a like' manner. !!ote that under se e circu= stances, the operating conditions in ene stea= generator an'/ be fcund to be more severe than these in the other stean generater. Under such circu= stances the sanple sequence shall be =cdified to inspect the ecs; severe conditiens.

6701 97$

L.

s h-70

Tali'.1: 4.19.2 STEAM GEfJEf tATOll TUCE INSPECTION l

IND SAf4PLE INSPECisOfl 3RD SAMPLE IfJCI'ECTIOfJ IST SAMPLE INSPECTION Sample Size Resuit Action Otquired fic' ult Action Itcquised Ecsult Action Requir-J A niinimum of C-1 Nonc IJ/A N/A TJ/A N/A S Tubes per S. G.

~

C-2 Plug defective tobes C-1 Nore IJ/A TJ/A and inspect additinnal Plug defs.ctive tubes C-1 TJone 2S tubes in this S. G.

C-2 anti inspect addition.it C-2 l' lug defccti<e sur ts 4S tubes in this S. G.

h !opn action for C-3 C-3 result of f ast sample Perform action for C-3 C-3 result of first N/A TJ/A s imple C-3 Inspect all tubes in

'Oilie r this S. G., plug de-S.G.

is

! June

'N/A TJ/A tective tutws and (M

unpect 25 tubes in

{i ise r t

Perfoem action for N/A TJ/A O L I6C T 8*I,-

S.(;.

C-2 result of second Psompt notification to fJRC pursuant to specification Otlwr inspe ct all tut;es in e

6.9.2.

3,c, gg each S. G. and plug

&lective tubes.

C-3 Prompt notitecction N/A N/A to NftC pursuant r3 to specilit.eiian 6.').2, and 4

^)

reiguest NRC approval of rerned i al d

action.

J t ',,

S = 3,., Where N is the number of steam generators in the unit. and n is the number of steam generators inspected N

during an inspection e

(c,n.,a) 6.9 - R n.,..,., R ~....3.,...~.

r.......

._...s 6.9 3 Unique Reporting acquirement:

A.

Special reports shall be sub=itted tc the Director of the Regulatcry Operations Ecgicnal Office within the time period specified for each report.

These report: cnali te sut itted covering the activities identified telev:

Tects Submittel f tes (1) C.cntainacnt Structural Integrity Test (a) Tenden Surveillance Precra:

Within 3 ncnth: after perfer:ance of surveillen a program.

(b) Ring Girder Incpection Within 3 month:

Progra=

after performance each inspecticn.

(2)

Stean Generacor Tube Inspeccion Within 3 cenchs after Progran ccepletion of inspeccien.

(3) Containment Integrated Leak Within 6 =entn:

Rute Test after completica of test.

(4) Inservice In pection Procram Within 6 menthe after five year:

of cperatien.

--n0.. n._--

10 o

1.

A cincie submittal may be made for a multiple u. hit tatien.

The sub-cittal shculd ec=bine these sectica: that are cc::en to all units at the statien.

2.

This tabulation sup?1.ecents the requiremenes of 520.hCT of 10 CEF Part 20.

3.

These reperting requirements apply cnly to Appendix A technical speci-ficaticns.

"7n9 9'7 1

6.

a