ML17332A747

Proposed Tech Specs Allowing Use of laser-welded Sleeves to Repair Defective SG Tubes

ML17332A747
Person / Time
Site:	Cook
Issue date:	04/13/1995
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17332A746	List: ML17332A745 ML17332A747 ML17332A748
References
NUDOCS 9504260149
Download: ML17332A747 (37)

Text

ATTACHMENT 2 TO AEP:NRC:1129D MARKED UP PAGES OF THE QJRRENT TECHNICAL SPECIFICATION PAGES 9504260i49'950413 PDR ADOCK.05000315 P

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REACTOR COOLANT SYSTEM STEQf GENERATO S

ING CONDI ON OR OPERAT ON 3.4.5 Each sceam generator shall. be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.+

~ACT ON:

With one or 'more steam generators inoperable, xestore the inoperable generaeor(s) to OPERABLE scatus prior eo increasing T,~ abo~e 200 P.

SURVEILLANCE RE U 4.4.5.0 Each sceam generator shall be demonseraeed OPERABLE by performance of ehe folLowing augmented'nsexvice inspeceion program and the requirement of Specificaeion 4.0.5.

4.4.5.1 Steam Generator Sa le Se eceion and Ins ect o

- Each steam generator shall be detexmined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table

4. 4-1.

4.4.5.2 Steam Generator be. Sa l.e SeLecti and Ins ection - The steam generator cube minimum sample size, inspeceion resul.e classification, and che corresponding action required shall be as specified in Table 4.4-2.

The insexvice inspection of steam generator cubes shall be performed at che frequencies specified in Specification 4.4.5.3 and ehe inspected tubes shall

~~be verified acceptable per the acceptance criteria of Specification 4.4.5.4.

5 The tubes selected for each inservice

~inspection shall include ae lease 3% of ehe eocal number ox tubes in all steam generators; the tubes selected for these inspections shall be seleceed on a random basis except:

a.

Where experience in similar planes with similar waeex chemistry indicates critical. areas eo be inspected, then ae lease 50% of the tubes inspected shall be from these critical areas.

b.

The first sample of 'tubes selected for each insexvice inspection (subsequent to che presexvice inspeccion) of each steam generator shall include:

1..

All cubes that previously had detectable wall penecraeions (greater than or equal co 20%) that have noe been plugged ox'epaired by sleevtng in the affected area.

is Specification does noe apply in Mode 4 while performing cxevice flushing as long as Limiting Conditions for Opezacion for Specification 3.4.1.3 are ne ~mained.

COuK NUCLEAR PLANT UNIT 1 3/4 4 7

ANNNONNNT NO. AC+

INSERT A When applying the exceptions of 4.4.5.2.a through 4.4.5.2.e, previous defects or imperfections in the area repaired by sleeving are not considered an area requiring reinspection.

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REACTOR COOLANT SYS SURVEILLANCE REOUIREMENTS

~w 2.

Tubes in chose areas where experience has indicared porenrf.ai problems.

3.

A tube inspection (pursuant eo Specification 4.4.5.4.a.8) shall be performed on each selected tube. If any selected tube does not permit ehe passage of the eddy currene probe for a cube inspection, ehis shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

c ~

In addiei.on eo ehe sample required in 4.4.5.2.b.l through 3, all tubes which have had the W crieeria applied will be inspected in ehe roll expanded region.

The roll expanded region of these tubes may be excluded from the requirements of 4.4.5.2.b.l.

d.

The tubes selected as ehe second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a pareial tube inspection provided:

The tubes seleceed for the samples include the tubes from those areas of the tube sheet array where tubes with imperfeceions were previously found.

2.

The inspections include those portions of the tubes where imperfections were previously found.

gpsss I

1 e.

Implementation of the seeam generator tube/tube

.support plate interim plugging crieeri.a for one fuel cycle (Cycle 14) requires a

10OX bobbin coil inspection for hoe leg tube support plate intersections and cold leg intersections down to the lowest cold leg cube support plate with known outer diameter stress corrosion

",racking (ODSCC) indications.

((

.'he results of each sample inspection shall be classified into one of the following three categories:

~Caee ~o1~

Ins ect on Results C-1 Less than 5X of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

C-2 One or more

tubes, but not more than 1X of the total tubes inspected are defective, or between 5X and 10X of the total tubes inspeceed are degraded tubes.

C-3 More chan 10X of the'otal tubes inspeceed are degraded tubes or more chan 1X of the inspected tubes are defective.

COOK NUCLM PLANT - UNIT 1 3/4 4-8 AMENDMENT NO. ~, j&j, P,.:i')',

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INSERT B f.

Inspection of sleeves will follow the initial sample selection (1" sample) and sample expansion requirements of Table 4.4-2.

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REACTOR COOLANT S ST S

VEILLANCE U

NTS Cone ued

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Nota:

In all inspections, previously degxaded tubesgmust exhibie significant (greaeer than or equaL to L0%) furehex walL penetraeions eo be included in the above perceneage calculations.

4.4.5.3 ns act on Fze encies

- The above required insexvice inspections of steam generator tubes shall be perfoxmed at the following frequencies:

The first insexvtca inspection shall be performed after 6 Effective FuLL Power Honehs bue vit:hin 24 calendar months of init:ial criticality.

Subsequent Qisezvice inspections shall be pexfozmed ae intervals of not less than 12 nor more than 24 calendar months after the previous inspection.

If tvo consecutive inspections following service under AVT conditions, not including the presexvica inspection, result in all inspection results falling into tha C-1 category or if tvo consecutive inspections demonserate that previously observed degradation has noe continued and no additional degradation has occurred, the inspeceion interval may be extended to a maximum of once pez 40 months.

b.

If ehe results of insexvice inspection of a steam genexator conducted in accordance with Table 4,4-2 ae 40 month intervals fall in Category'-3, tha inspection frequency shall be increased to at lease once per 20 months.

The increase in inspection frequency shall apply until the subsequent inspections satisfy the crit:aria of

'pec&ication 4.4.5.3.a; the interval may then be extended to a maximum of once per 40 months.

C ~

Addieional, unscheduLed insezvica inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdovn subsequene to any oz ehe follovtng conditions:

1.

Primary-to-secondary tubes leaks (noe including leaks originating from tube-to-tube sheet velds) in excess of ehe Limits of Specification 3.4.6.2.

2.

A seismic occurrence greater than the Operating Basis Earthquake.

3.

A loss-of-coolant accident requiring actuation of the engineered safeguards.

4.

A main steam line or feedwater line break.,

d.

Tubes left in service as a result of application of the tube support plate interim plugging criteria shall ba inspected by bobbin coil probe during all future refueling outages.

COOK NUCLEAR PLANT - UNIT 1 3/4 4-9 ANENDHENT NO.

04 16b

ACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Cont:: nued 4.4 5.4 cce tance Crite a

a.

As used in this Specificatian:

2 a contour of a tube or sleeve from that required hy fabrication drawings or specifications.

Eddy-current testing indicati.ons below 20% of Che nominal tube wall thickness, if detectable, may he cansidered as imperfections.

general corrosi.on occurring on either inside ar outside of a

Cube or sleeve.

3 ~

5.

6 7 ~

e raded Tube ar Sleeve means an imperfection greater Chan or equal to 20%

of Che nominal vali thickness caused by degradatian.

Percent De adatian means the amount of Che tube wall thickness affected ar removed hy degradation.

vhich the tube ar sleeved t service.

Any tube vhi.ch, degradation af.40 percen thickness shall be plugg steam generator to servi the portion of the tube for F~ Cubes.

Any sleeve hall be repaired or removed from inspection, exhibits tube wall more of the nominal tube wall repaired prior to returning the is definition does not apply to tuhesheet below the P+ distance upon inspection

.exhibi.ts wall e

upoor or

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T the which degradaCion of 29 pezcenC or mc e of the nominal wall thickness shall.

be plugged prior to ret ming the steam generat:or to service.

In addition, any sleeve exhibiting any measurable wall loss in sleeve expansion transition or veld zones shall be plugged.

Th's definition does nat apply foz Cubes exper'encing outer diameter st"ess corrosion czacking confirmed by hobb'n probe inspection Co be within the Chi.ckness of the tube supaort

'plates.

See 4.4.5.4.a.l0 for the plugging limit for use vithi.n the thickness of the tube support: plate.

Unserviceable desc ihes the condition of a tube or sleeve if it leaks or contains a defect large enough to affect its structural integrity in the event of an operating Basi.s Earthquake, a loss-of>>coolant accident, or a steam line ar feedwater line break as

.speci. fied in 4.4.5.3.c, above.

Qefec nests st fssfesfeotion of snoh savesity that it extends

- the repair limit.

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-Re air Plu in Limit means perfection depth aC or beyond 8.

or sleeve from the paint: of entry (hat leg aide) completely COOK NUCLEAR PLANT - UNIT 1 3fj'4 4-10

INSERT C

For a tube that has been sleeved with a laser welded sleeve, through wall penetration of greater than or equal to 23% of sleeve nominal wall thickness requires the tube to be removed from service by plugging.

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REACTOR COO le SYST~

SURVEILLANCE REOUIR~M~Vl;S Continued) around the U-bend to the top suppor" of the cold leg.

Fox' tube in which the tube support plate elevateon inter'm plugging limit has been appl'ed, the inspection will include all the hot leg intex'sections and all cold leg intersections down to. at

least, the level of the last crack indication.

10.

9.

a e is permit only in areas ere the sleev spans ther besheet~

rea and whoa ower joinu is rhe pranarp id rub~esh ace.

e ube Su c "

Plate nter'm Plu n~

Criteria is used for disposition of a steam generator tube for continued service that is experiencing outer diameter initiated stress corrosion cracking

~

confined within the thickness of" the cube support plates.

For application of the tube support plate interim plugging limit, the tube's disposition for continued sexvice will be based upon standard bobbin probe signal amplitude.

The plane-specific guidelines used for all inspections shall be amended as appropriate to accommodate the additional information needed to evaluate tube support plate, signals wich respect to the above voltage/depth parameters.

Pending incorporation of the voltage verification requirements in ASHE standard verifications, an ASME standard calibrated agains" the laboratory standard will be utilized in the Donald C.

Cook Nuclea Plant Unit 1

steam genex'ator inspections for consistent voltage normalization.

A'tube can r'emain in service if the signal amplitude of a crack indication is less than or equal to 2.0 volt, x'egardless of the depth of cube wall penetracion, if', as a result, the projected end-ofwcycle distribution of crack indications is verified to result in primary-to-secondary leakage less than 12.6 gpm in the faulted loop during a postulaced steam line br ak event.

The methodology for calculating expected leak rates from the prof ected crack d stribution must be consistenc wich UCAP-13187.

Rev.

0, and as prescribed in dra"t NUREG-1477.

2.

A tube should be plugged or repaired if the signal ampl'rude ox che crack indication is greater than 2.0 vole except as noted in

4. 4. 5.4. a. 10. 3 below.

A tube can remain in service wich a bobbin coil signal amplitude greater than 2.0 volt but less than or equal to 3.6 volts ix a rocacing pancake probe inspection does not detecc deg=adat on.

Indications of degradation with a bobbin coil signal amplitude greater than 3.6 volts will be plugged or xepai"ed.

Z

'"'"*'oward the bottom of the tubesheet that has been conse

~ati ~el) determined to be 1.11 inches (not including eddy current unce tainty).

12.

re Tube 's a -ube wi-h deprada"'on, below he P* dis a".,oe, eo"ai "o or greater than 40X, and not degraded (i.e.,

no indications of cracking) within the F* distance.

COOK NUCL+~R PP~hh

- UNIT 3/4 4wll Ah!END<ENT NQ.

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INSERT D 9.

Sleeving a

tube is permitted with tube support plate sleeves and with tubesheet sleeves.

Tube support plate sleeves are centered about the tube support plate intersection.

Tubesheet sleeves start at the primary fluid tubesheet face and extend to the free span region of tube above the tubesheet.

INSERT E 13.

Tube Re air refers to sleeving as described by the reports listed in 4.4.5.4.c which are used to maintain a tube in service or return a tube to service.

Tubes with degradation indications of less than the plugging limit may be preventively sleeved at the Owner's discretion.

This includes removal of plugs that were installed as a

corrective or preventive measure.

A tube inspection per 4.4.5.4.a.8 is required prior to returning previously plugged tubes to service.

Further restrictions regarding identified indications and their proximity to the joint areas of various sleeving processes may be applicable.

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ACTOR COOLANT SYS HS SURVETLLANCE RE UTREMNTS Cont nued b.

The steam generator shall be determined OPERABLE afte completing the corresponding ac ions (plugging or sleeving all tubes exceeding the repair limi.t and all tubes containing through-wall cracks) zequired by Table 4.4-2.

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4.4.5.5 a ~

b.

Steam generator tube repairs may be made in accordance with the methods described in either WCAP-12623 or CEN-313-P.

~eon'.s g Ace/-]gdeg )

Following each inservice inspection of steam generator tubes, i.f there are any 'tubes zsquiring plugging or sleevi.ng, the number of tubes plugged or sleeved in each steam generator shall be zeported to the Commission within 15 days.

The complete results of the steam generator tube inservice inspectS. on shall be included in the Annual Operating Report for the peri.od in which this inspection was completed.

This report shall include:

~ g4FEPd S 1.

Number and extent of tubes/Iinspected.

2 ~

Location and percent of wall-thickness penetration for each indication of an imperfection.

Co 3."

Identification of tubes plugged or sleeved.

Results of steam generator tube inspections which fall into Category C-3 and

. requi.re prompt notification of the Commission shall be reported puzsuant to Speci ication 6.9.1 prior to resumption of plant ope ation.

The written followup of this repor shall pzovi.de a

description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

d.

The results of inspections performed under 4.4.5.2 for all tubes in which the tube support.

plate interim plugging criteri.a has been applied or that have defects below the F~ distance and were not plugged shall be repor ed to the Coazsission within 15 days following the inspection.

The repor" shall include:

1.

Listing of applicable tubes.

2.

Location (applicable intersections per tube) and extent of degzadation (voltage).

I The results of steam line break leakage analysis performed under T/S 4.4.5.4.a.10 will be reported to the Comission prior to restart for Cycle ]4.

COOK NUCLEAR PLANT - UNIT 1 3/4 4-12 AHZNDF~NT NO

).78

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CTOR COOLANT SYS BASES Degraded steam generator cubes may be repaired by-the inscall'acion of sleeves which span the section of degraded steam generator cubing.

A steam generator cube with a sleeve installed meets ehe structural requirements of cubes which are noe degraded.

To determine che basis for ehe sleeve plugging 1$ud.c, the minimum sleeve wal'k thickness was calculated in accordance with Draft Regulatory Guide 1.121 (August 1976).

In addition, a combined allowance of 20 percene of wall thickness is assumed for eddy current testing.inaccuracies and coneinued operational degradacion per Draft Regulatory Guide 1.121 (August 1976).

The *following sleeve designs have been found acceptable by the HRC staff:

1.

Westinghouse Mechanical Sleeves (WCAP-12623) 2.

Combustion Engineering Leak Tight Sleeves

.(CEN-313-P) 4M~c A's~ W~~s~~s (wchP I3>8B)

Descripeions of other future sleeve designs shall be submitted eo the.

NRC for review and approval in accordance with 10CPR50.90 prior to their use in the repair of degraded steam generaeor tubes.

The submitcal.s related to other sleeve design shall be made ac lease 90 days prior to use.

REACTOR COOLANT SYSTEM BASES 3 4 4.6 RE'ACTOR COOLANT SYSTEM LEAKAGE 3 4 4 6

LEVERAGE DETECTION SYSTEMS The RCS leakage detection systems.required by this specification are provided eo monitor and dececc leakage 'from the Reactor Coolant Pressure Boundary.

These detection syseems are consistenc with the recommendacions of RegQ.aeory Guide'..45, "Reactor Coolanc Pressure. Boundary Leakage Deeeccion G~-stems,"

Bay 1973.

3 4 4 6

OPERAT 0 AL LEAKAG Industry experience has shown chae while a limited amoune of leakage is expected from ehe

RCS, che unidencified portion of this leakage can be reduced to a threshold value of less chan 1 gpm.

This threshold vat.ue is sufficientl.y low to ensure early decection of additional leakage.

The 10 GFM IDENTIFIED LEAKAGE limitations provides allowance for a limieed amount of leakage from know sources whose presence will not interfere with the deeeceion of UNIDENTIFIED LEAKAGE by the leakage deeection systems.

The limitation on seal line resistance ensures that the seal line resiseance is greacer chan or equal to che resiscance assumed in the minimum safeguards LOCA analysis.

This analysis assumes chae all of the flow chac is diverted from the boron injection line to the seal injection line is unavailable for core cooling.

COOK NUCLEAR PLANT - UNIT 1 3/4 4

3 ANENBNENT NO. g P3, g, 162 Correc"ed Page

ATTACHMENT 3 TO AEP'NRC:1129D PROPOSED REVISED TECHNICAL SPECIFICATION PAGES

4 1

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM STEAM GENERATORS LIMITINGCONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 Gild 4.

ACTION:

With one or more steam generators inoperable, restore the inoperable generator(s) to OPERABLE status prior to increasing T>>z above 200'F.

SURVEILLANCERE UIREMENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirement of Specification 4.0.5.

4.4.5.1 Steam Generator Sam le Selection and Ins ection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.

4.4.5.2 Steam Generator Tube Sam le Selection and Ins ection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2.

The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4.

When applying the exceptions of 4.4.5.2.a through 4.4.5.2.e, previous defects or imperfections in the area repaired by sleeving are not considered an area requiring reinspection.

The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:

ae Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% ofthe tubes inspected shall be from these critical areas.

The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:

1.

Alltubes that previously had detectable wall penetrations (greater than or equal to 20%) that have not been plugged or repaired by sleeving in the affected area.

This Specification does not apply in Mode 4 while performing crevice flushing as long as Limiting Conditions for Operation for Specification 3.4.1.3 are maintained.

COOK NUCLEARPLANT-UNIT1 Page 3/4 4-7 AMENDMENT4Q, 466

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM SURVEILLANCERE UIREMENTS (continued) 2.

Tubes in those areas where experience has indicated potential problems.

A tube inspection (pursuant to Specification 4.4.5.4.a.8) shall be performed on each selected tube. Ifany 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.

In addition to the sample required in 4.4.5.2.b. 1 through 3, all tubes which have had the F~ criteria applied will be inspected in the roll expanded region.

The roll expanded region of these tubes may be excluded from the requirements of 4.4.5.2.b.l.

d.

The tubes selected as the second and third samples (ifrequired by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:

The tubes selected for the samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.

2.

The inspections include those portions of the tubes where imperfections were previously found.

Implementation of the steam generator tube/tube support plate interim plugging criteria for one fuel cycle (Cycle 14) requires a 100% bobbin coil inspection for hot leg tube support plate intersections and cold leg intersections down to the lowest cold leg tube support plate with known outer diameter stress corrosion cracking (ODSCC) indications.

f.

Inspection of sleeves will follow the initial sample selection (1" sample) and sample expansion requirements of Table,4 4-2.

The results of each sample inspection shall be classified into one of the following three categories:

~Cate orv Ins ection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.

C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1%

of the inspected tubes are defective.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 4-8 AMENDMENT4R, 446, 477) K8

3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM SURVEILLANCERE UIREMENTS (continued)

Note:

In all inspections, previously degraded tubes or sleeves must exhibit significant (greater than or equal to 10%) further wall penetrations to be included in the above percentage calculations.

4.4.5.3 Ins ection Fre uencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:

The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality. Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection. If two consecutive inspections followingservice under AVTconditions, not including the preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.

b.

If the results of inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40 month intervals fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 4.4.5.3.a; the interval may then be extended to a maximum of once per 40 months.

Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions:

1.

Primary-to-secondary tubes leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2.

2.

A seismic occurrence greater than the Operating Basis Earthquake.

3.

A loss-of-coolant accident requiring actuation of the engineered safeguards.

4.

A main steam line or feedwater line break.

d.

Tubes left in service as a result of application of the tube support plate interim plugging criteria shall be inspected by bobbin coil probe during all future refueling outages.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 4-9 AMENDMEiNT98, 466

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM SURVEILLANCERE UIREMENTS (continued) 4.4.5.4 Acce tance Criteria As used in this Specification:

~tm erfection means an exception to the dimensions, finish or contour of a tube or sleeve from that required by fabrication drawings or specifications.

Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.

~De radation means a sertdce-induced

cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve.

De raded Tube or Sleeve means an imperfection greater than or equal to 20% of the nominal wall thickness caused by degradation.

Percent De radation means the amount of the tube wall thickness affected or removed by degradation.

Defect means an imperfection of such severity that it exceeds the repair limit.

Re air/Plu in Limit means the imperfection depth at or beyond which the tube or sleeved tube shall be repaired or removed from service.

Any tube which, upon inspection, exhibits tube wall degradation of40 percent or more ofthe nominal tube wall thickness shall be plugged or repaired prior to returning the steam generator to service.

This definition does not apply to the portion of the tube in the tubesheet below the F"'istance for Fg'ubes.

Any sleeve, except laser welded sleeves, which upon inspection exhibits wall degradation of 29 percent or more of the nominal wall thickness, shall be plugged prior to returning the steam generator to service. In addition, any sleeve, except laser welded sleeves, exhibiting any measurable wall loss in sleeve expansion transition or weld zones shall be plugged.

This definition does not apply for tubes experiencing outer diameter stress corrosion cracking confirmed by bobbin probe inspection to be within the thickness of the tube support plates.

See 4.4.5.4.a. 10 for the plugging limit for use within the thickness of the tube support plate.

For a tube that has been sleeved with a laser welded sleeve, through wall penetration of greater than or equal to 23% of sleeve nominal wall thickness requires the tube to be removed from service by plugging.

Unserviceable describes the condition of a tube or sleeve ifit leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of~oolant

accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.

~lns ection determines the condition of the steam generator tube or sleeve from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.

For a tube in which the tube support plate elevation interim plugging limit has been

applied, the inspection will include all the hot leg intersections and all cold leg intersections down to, at least, the level of the last crack indication.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 4-10 AMENDMENTQSp 484, 446, AVE

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM SURVEILLANCERE UIREMENTS (continued)

Sieeving a tube is permined with tube support plate sleeves and with tubesheet sleeves.

Tube support plate sleeves are centered about the tube support plate intersection.

Tubesheet sleeves start at the primary fluid tubesheet face and extend to the free span region of tube above the tubesheet.

10.

The Tube Su ort Plate Interim Plu in Criteria is used for disposition of a steam generator tube for continued service that is experiencing outer diameter initiated stress corrosion cracking confined within the thickness of the tube support plates.

For

",application of the tube support plate interim plugging limit, the tube's disposition for continued service willbe based upon standard bobbin probe signal amplitude. The plant-specific guidelines used for all inspections shall be amended as appropriate to accommodate the additional information needed to evaluate tube support plate signals with respect to the above voltage/depth parameters.

Pending incorporation of the voltage verification requirements in ASME standard verifications, an ASME standard calibrated against the laboratory standard will be utilized in the Donald C. Cook Nuclear Plant Unit 1 steam generator inspections for consistent voltage normalization.

A tube can remain in service ifthe signal amplitude of a crack indication is less than or equal to 2.0 volt, regardless of the depth of tube wall penetration, if, as a result, the projected endwf-cycle distribution of crack indications is verified to result in primary-to-second+ leakage less than 12.6 gpm in the faulted loop during a postulated steam line break event.

The methodology for calculating expected leak rates from the projected crack distribution must be consistent with WCAP-13187, Rev. 0, and as prescribed in draft NUREG-1477.

A tube should be plugged or repaired if the signal amplitude of the crack indication is greater than 2.0 volt except as noted in 4.4.5.4.a. 10.3 below.

A tube can remain in service with a bobbin coil signal amplitude greater than 2.0 volt but less than or equal to 3.6 volts ifa rotating pancake probe inspection does not detect degradation.

Indications ofdegradation with a bobbin coil signal amplitude greater than 3.6 volts willbe plugged or repaired.

Fd'istance is the distance from the bottom of the hardroll transition toward the bottom of the tubesheet that has been conservatively determined to be 1.11 inches (not including eddy current uncertainty).

12.

F~ Tube is a tube with degradation, below the Fd'istance, equal to or greater than 40%,

and not degraded (i.e., no indications of cracking) within the F* distance.

13.

T~ube Re air refers to sieeving as described by the reports listed in 4.4.5.4.c tvhich are used to maintain a tube in sevice or return a tube to service.

Tubes with degradation indications of less than the plugging limit may be preventively sleeved at the Owner's discretion.

This includes removal of plugs that were installed as a corrective or preventive measure.

A tube inspection per 4.4.5.4.a.8 is required prior to returning previously plugged tubes to service.

Further restrictions regarding identifie indications and their proximity to the joint areas of various sleeving processes may be applicable.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 4-11 AMENDMENT4&t, 446, IVV, 478

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM SURVEILLANCERE UIREMENTS (continued) b.

The steam generator shall be determined OPERABLE after completing the corresponding actions (plugging or sleeving all tubes exceeding the repair limit and all tubes containing through-wall cracks) required by Table 4.4-2.

c.

Steam generator tube repairs may be made in accordance with the methods described in either WCAP-12623, WCAP-13088, or CEN-313-P.

4.4.5.5

~Re orts a.

Following each inservice inspection of steam generator tubes, if there are any tubes requiring plugging or sleeving, the number of tubes plugged or sleeved in each steam generator shall be reported to the Commission within 15 days.

b.

The complete results of the steam generator tube inservice inspection shall be included in the Annual Operating Report for the period in which this inspection was completed.

This report shall include:

1.

Number and extent of tubes and sleeves inspected.

2.

Location and percent ofwall-thickness penetration for each indication of an imperfection.

Identification of tubes plugged or sleeved.

Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the Commission shall be reported pursuant to Specification 6.9.1 prior to resumption of plant operation.

The written followup of this report shall provide a description of investigations conducted to determine cause ofthe tube degradation and corrective measures taken to prevent recurrence.

The results of inspections performed under 4A.5.2 for all tubes in which the tube support plate interim plugging criteria has been applied or that have defects below the F" distance and were not plugged shall be reported to the Commission within 15 days following the inspection.

The report shall include:

1.

Listing of applicable tubes.

2.

Location (applicable intersections per tube) and extent of degradation (voltage).

The results of steam line break leakage analysis performed under T/S 4 4.5.4.a.10 will be reported to the Commission prior to restart for Cycle 14.

COOK ib UCLEAR PLANT-UNIT1 Page 3/4 4-12 AMENDMENT4M, 446, 477, K4

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3/4 BASES 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.5 STEAM GENERATORS TUBE INTEGRITY Continued Degraded steam generator tubes may be repaired by the installation of sleeves which span the section of degraded steam generator tubing. A steam generator tube with a sleeve installed meets the structural requirements of tubes which are not degraded.

To determine the basis for the sleeve plugging limit, the minimum sleeve wall thickness was calculated in accordance with Draft Regulatory Guide 1.121 (August 1976).

In addition, a combined allowance of 20 percent of wall thickness is assumed for eddy current testing inaccuracies and continued operational degradation per Draft Regulatory Guide 1.121 (August 1976).

The following sleeve designs have been found acceptable by the NRC staff:

1.

Westinghouse Mechanical Sleeves (WCAP-12623) 2.

Combustion Engineering Leak Tight Sleeves (CEN-313-P) 3.

Westinghouse Laser Welded Sleeves (WCAP-13088)

Descriptions of other future sleeve designs shall be submitted to the NRC for review and approval in accordance with 10 CFR 50.90 prior to their use in the repair of degraded steam generator tubes.

The submittals related to other sleeve designs shall be made at least 90 days prior to use.

REACTOR COOLANT SYSTEM BASES 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGEDETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary.

These detection systems are consistent with the recommendations of Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.

3/4.4.6.2 OPERATIONAL LEAKAGE Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 gpm. This threshold value is sufficiently low to ensure early detection of additional leakage.

The 10 GPM IDENTIFIEDLEAKAGElimitations provides allowance for a limited amount of leakage from know sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.

The limitation on seal line resistance ensures that the seal line resistance is greater than or equal to the resistance assumed in the minimum safeguards LOCA analysis. This analysis assumes that all ofthe fiowthat is diverted from the boron injection line to the seal injection line is unavailable for core cooling.

COOK NUCLEAR PLANT-UNITI Page B 3/4 4-3 AMENDMENT&, N, 484, 444

ATTACHMENT 4 TO AEP:NRC:1129D WESTINGHOUSE ELECTRIC CORPORATION REPORT DESCRIBING THE SLEEVING REPAIR PROCESS (WCAP 13088 REV. 3)

ATTACHMENT 5 TO AEP:NRC'1129D NON-PROPRIETARY VERSION OF WESTINGHOUSE ELECTRIC CORPORATION REPORT (WCAP 13O89 aSV.3)

ATTACHMENT 6 TO AEP:NRC:1129D WESTINGHOUSE ELECTRIC CORPORATION AUTHORIZATION LETTER, CAW-95-786, APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE AND AFFIDAVIT