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{{#Wiki_filter:ATTACHMENT3TOAEP:NRC:1295PROPOSEDREVISEDTECHNICALSPECIFICATIONPAGES9'809020053'F80828PDRADQCK05000315PPDR 3/4LIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS3/4.4REACTORCOOLANTSYSTEMSURVEILLANCEREUIREMENTS(continued)Note:Inallinspections,previouslydegradedtubesorsleevesmustexhibitsignificant(greaterthanorequalto10%)furtherwallpenetrationstobeincludedintheabovepercentagecalculations.4.4.5.3InsectionFreuencies-Theaboverequiredinserviceinspectionsofsteamgeneratortubesshallbeperformedatthefollowingfrequencies:tThefirstinserviceinspectionshallbeperformedafter6EffectiveFullPowerMonthsbutwithin24calendarmonthsofinitialcriticality.Subsequentinserviceinspectionsshallbeperformedatintervalsofnotlessthan12normorethan24calendarmonthsafterthepreviousinspection.IftwoconsecutiveinspectionsfollowingserviceunderAVTconditions,notincludingthepreserviceinspection,resultinallinspectionresultsfallingintotheC-1categoryoriftwoconsecutiveinspectionsdemonstratethatpreviouslyobserveddegradationhasnotcontinuedandnoadditionaldegradationhasoccurred,theinspectionintervalmaybeextendedtoamaximumofonceper40months.IftheresultsofinserviceinspectionofasteamgeneratorconductedinaccordancewithTable4.4-2at40monthintervalsfallinCategoryC-3,theinspectionfrequencyshallbeincreasedtoatleastonceper20months.TheincreaseininspectionfrequencyshallapplyuntilthesubsequentinspectionssatisfythecriteriaofSpecification4.4.5.3.a;theintervalmaythenbeextendedtoamaximumofonceper40months.Additional,unscheduledinserviceinspectionsshallbeperformedoneachsteamgeneratorinaccordancewiththefirstsampleinspectionspecifiedinTable4.4-2duringtheshutdownsubsequenttoanyofthefollowingconditions:1.Primary-to-secondarytubesleaks(notincludingleaksoriginatingfromtube-to-tubesheetwelds)inexcessofthelimitsofSpecification3.4.6,2.2.AseismicoccurrencegreaterthantheOperatingBasisEarthquake.3.Aloss-of-coolantaccidentrequiringactuationoftheengineeredsafeguards.4.Amainsteamlineorfeedwaterlinebreak.Amendmentgrantedanextensiontothissurveillanceuntilthestartofcycle17.Intheeventthesteamgeneratorsarereplacedatthattime,theretiredsteamgeneratorsareexemptedfromfurthersurveillanceunderthisspecification.COOKNUCLEARPLANT-UNIT1Page3/44-9AMENDMENT98,466,240,20$)
{{#Wiki_filter:ATTACHMENT 3 TO AEP:NRC:1295 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES 9'809020053 'F80828 PDR  ADQCK 05000315 P                PDR
I ATTACHMENT4TOAEP:NRC:1295EXISTINGTECHNICALSPECIFICATIONPAGESMARKEDTOINDICATEPROPOSEDCHANGES r~Ie 3/4LIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS3/4.4REACTORCOOLANTSYSTEMSURVEILLANCEREUIREMENTS(continued)Note:Inallinspections,previouslydegradedtubesorsleevesmustexhibitsignificant(greaterthanorequalto10%)furtherwallpenetrationstobeincludedintheabovepercentagecalculations.4.4.5.3InsectionFruencies-Theaboverequiredinserviceinspectionsofsteamgeneratortubesshallbeperformedatthefollowingfrequencies:+Thefirstinserviceinspectionshallbeperformedafter6EffectiveFullPowerMonthsbutwithin24calendarmonthsofinitialcriticality.Subsequentinserviceinspectionsshallbeperformedatintervalsofnotlessthan12normorethan24calendarmonthsafterthepreviousinspection.IftwoconsecutiveinspectionsfollowingserviceunderAVTconditions,notincludingthepreserviceinspection,resultinallinspectionresultsfallingintotheC-1categoryoriftwoconsecutiveinspectionsdemonstratethatpreviouslyobserveddegradationhasnotcontinuedandnoadditionaldegradationhasoccurred,theinspectionintervalmaybeextendedtoamaximumofonceper40months.b.IftheresultsofinserviceinspectionofasteamgeneratorconductedinaccordancewithTable4.4-2at40monthintervalsfallinCategoryC-3,theinspectionfrequencyshallbeincreasedtoatleastonceper20months.TheincreaseininspectionfrequencyshallapplyuntilthesubsequentinspectionssatisfythecriteriaofSpecification4.4.5.3.a;theinterval,maythenbeextendedtoamaximumofonceper40months.Additional,unscheduledinserviceinspectionsshallbeperformedoneachsteamgeneratorinaccordancewiththefirstsampleinspectionspecifiedinTable4.4-2duringtheshutdownsubsequenttoanyofthefollowingconditions:Primary-to-secondarytubesleaks(notincludingleaksoriginatingfromtube-to-tubesheetwelds)inexcessofthelimitsofSpecification3.4.6.2.AseismicoccurrencegreaterthantheOperatingBasisEarthquake.Aloss-of-coolantaccidentrequiringactuationoftheengineeredsafeguards.Amainsteamlineorfeedwaterlinebreak.COOKNUCLEARPLANT-UNIT1Page3/44-9AMENDMENT98,466,~,~
 
XnsertAHAmendmentgrantedanextensiontothissurveillanceuntilthestartofcycle17.Xntheeventthesteamgeneratorsarereplacedatthattime,theretiredsteamgeneratorsareexemptedfromfurthersurveillanceunderthisspecification.
3/4    LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4  REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS (continued)
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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: t 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 following service 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.
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.
Amendment            granted an extension to this surveillance until the start of cycle 17. In the event the steam generators are replaced at that time, the retired steam generators are exempted from further surveillance under this specification.
COOK NUCLEAR PLANT-UNIT 1                          Page 3/4 4-9                      AMENDMENT98, 466, 240, 20$ )
 
I ATTACHMENT 4 TO AEP:NRC:1295 EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO INDICATE PROPOSED CHANGES
 
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3/4    LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4  REACTOR COOLANT SYSTEM SURVEILLANCE RE 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 Fr 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 following service under AVT conditions, 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:
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.
A seismic occurrence greater than the Operating    Basis Earthquake.
A loss-of-coolant accident requiring actuation of the engineered safeguards.
A main  steam line or feedwater line break.
COOK NUCLEAR PLANT-UNIT 1                        Page 3/4 4-9                AMENDMENT98, 466,         ~,   ~
 
Xnsert A H  Amendment        granted an extension to this surveillance until the start of cycle 17. Xn the event the steam generators are replaced at that time, the retired steam generators are exempted from further surveillance under this specification.
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Latest revision as of 12:03, 22 October 2019

Proposed Tech Specs Requesting Extension of SG Surveillance TS 4.4.5.3,which TSs Require to Be Performed on 990408,until End of Current Fuel Cycle Currently Scheduled for Mar 2000
ML17335A193
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 08/28/1998
From:
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17335A191 List:
References
NUDOCS 9809020053
Download: ML17335A193 (8)
v • d • e


Text

ATTACHMENT 3 TO AEP:NRC:1295 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES 9'809020053 'F80828 PDR ADQCK 05000315 P PDR

3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM SURVEILLANCE RE 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: t 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 following service 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.

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.

Amendment granted an extension to this surveillance until the start of cycle 17. In the event the steam generators are replaced at that time, the retired steam generators are exempted from further surveillance under this specification.

COOK NUCLEAR PLANT-UNIT 1 Page 3/4 4-9 AMENDMENT98, 466, 240, 20$ )

I ATTACHMENT 4 TO AEP:NRC:1295 EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO INDICATE PROPOSED CHANGES

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM SURVEILLANCE RE 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 Fr 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 following service under AVT conditions, 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:

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.

A seismic occurrence greater than the Operating Basis Earthquake.

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

A main steam line or feedwater line break.

COOK NUCLEAR PLANT-UNIT 1 Page 3/4 4-9 AMENDMENT98, 466, ~, ~

Xnsert A H Amendment granted an extension to this surveillance until the start of cycle 17. Xn the event the steam generators are replaced at that time, the retired steam generators are exempted from further surveillance under this specification.

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