ML20091C021
| ML20091C021 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/25/1992 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20091C019 | List: |
| References | |
| NUDOCS 9204020239 | |
| Download: ML20091C021 (16) | |
Text
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- ATTAC11 MENT (1)--
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UNIT 1
'TECIINICAL SPECIFICATION REVISED PAGES 3/447 3/44-8 1
i 3/4414
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3/4415 B 3/4 4 2a B3/44-4
-7204020239 920325 PDR.ADOCK 05000317 P
e 4
E Q ;^0LANT SYSTEM SURVEILLANCE REOUIREMENTS (Continued) 2.
Tubes in those areas where experience has indicated potential problems.
The second and third inservice inspections may be less than a c.
full tube inspection by concentrating (selecting at least 50%
of the tubes to be inspected) the inspection on those areas of the tube sheet array and on those portions of the tubes where tubes with igerfections were previously found.
The results of each sample inspection shall be classified into one of the following three categories:
Category Insoection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the in-spected tubes are defective.
C-2 One or more tubes, but not more than 1% of e
the total tubes inspected are defective, or between 5% and 10% of the total tubes inspects.d 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.
Note:
In all inspections, previously degraded tubes must exhibit significant (>10t) further wall penetrations to be included in the above percentage calculations.
4.4.5.3 Inseection Frecuencies - The above required inservice inspections of steam generator tunes snall be performed at the following frequencies:
a.
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 consecu-JNSERTW, tive 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.
CALVERT CLIFFS - UNIT 1 3/4 4-7
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SURVEILLANCE REQUIREMENTS,(Continued)
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If the.intervice inspection of a steata generator conducted in g
b.'
accordance with Table 4.4 2.requir4&-4-third u-N4 iaspectienef @i$/,"It J.;;e eesit: fall-in Category C-3, the inspection frequency he.w J shall beg:due:d to at least once per 20 months. The +odust40n W* *
~ in inspection frequency shall apply until fsubsequent inspectionf dmsmte *$4-e-third-sample taspest4er is aot-esquired,
. T i v.S & W ' 6 c.
' 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 tube leaks (not including leaks I
originatingfremtube-to-tubesheetwelds)inexcessof the limits of Specification 3.4.6.2, 2.
A seismic occurrence greater than the Jrating Basis s
Earthquake, 3.
A loss-cf-coolant accident requiring actuation of the engineered safeguards, or 4.
A main steam line or feedwater line break.
YeceetanceCriteria IO E I 4.4.5.4 a.
ts used in this Specification:
1.
Imoerfection_ means an exception to the dimensions, finish or contour of a tube 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 imoerfections.
2.
Deoradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
3.
Cearaded Tube means a tube containing imperfections 3.20%
of tne nominal wall thickness caused by degradation.
4.
% DeoradEtion means the percentage of the tube wall tnickness affected or removed by degradation.
1 CALVERT CLIFFS - UNIT 1 3/44-8 Amendment No.
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REACTOR COOLANT SYSTEM LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:
9 a.
-No PRESSURE BOUNDARY LEAXAGE, b.
1 GPM UNIDENTIFIED LEAKAGE, all 1 GPM total primary *-to-secondary leakage through Asteam generators);
c.
and :Z~/qff;f7~*O d.
10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System.
APPLICABILITY: MODES 1. 2, 3 and 4.
ACTION:
a.
With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.
With any Reactor Coolant System leakage greater than any orie of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDSY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREMENTS 4.4.6.2 Reactor Coolant System leakages thall be demonstrated to be within each of the above limits by:
a.
Either:
1.
Monitoring the containment atmosphere particulate or gaseous radicactivity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or 2.
With the gaseous and particulate monitors inoperable, conducting the containment atmosphere grab sample analysis in accordance with the ACTION requirements of T.S. 3.4.6.1.
b.
Monitoring the containment sump discharge frequency at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, when the containment sump level alarm system is
- OPERABLE, CALVERT CLIFFS - UNIT 1 3/4 4-14
-Aaenda n. ;w, 107-c l
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i REACTOR COOLANT SYSTEM SURVEILLANCE REOUIREMENTS (Continued)
De te<mh;
-Pt+femen[ Of : Reactor Coolant S t
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C.
at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during *eadyltate a
east once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when required by ACTION 3
- 6"1'b' whe. operating in the shutdown cooling mode, and d.
.Monitcring the reactor vessel head closure seal leakage dete"..jon syste'l at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, I
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lll CALVERT CLIFFS. unir ;
37; ;_;5 c ~__ c..
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REACTOR COOLANT SYSTEM BASES maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.
In-serv ce' inspection of_ steam generator tubing also provides a means of i
characterizing the nature and cause of any tube degradation so that correc-tive measures esn be taken, f/USE/?1~ "2~~
The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes.
If the secondary coolant che.mistry is not maintained within these limits.
localized corrosion may likely result in stress corrosion cracking.
The extent of cracking d0 ring plant operation would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondary coolant system (primary-to-secondary leakage =
1 gallon per minute, total).
Cracks having a primary-to-secondary leakage l-1 l
CALVERT CLIFFS - UNIT 1 B 3/4 4-2a NAmendmant No. ;3 fren e C L. 36-a
-GALVEP" CLIFFS UNIT 2 l
BASES The 10 GPM IDENTIFIED LEAKAGE limitation provides allowance for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.
The total steam generator tube leakage limit of 1 GPM for all steam i
generators ensures that the dosage contribution from the tube leakage will be limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam line break. The 1 GPM limit is consistent with the assumptions used in the analysis of these accidents. (
f NSE R T */ '
PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary. Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.
3/4.4.7 CHEMISTRY i
The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduce the poten-tial for Reactor Coolant System leakage or failure due to stress corro-sion.
Maintaining the chemistry within the Steady State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant.
The associated effects of exceeding the oxygen, chloride and fluoride limits are time and temperature dependent.
Corrosion studies show that operation may be con-tinued with contaminant concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time inter-vals without having a significant effect on the structural integrity of the Reactor Coolant System.
The time interval parmitting continued operation within~ the restrictions of the Transient Limits provides time for taking corrective actions to restore the r.ontaminant concentrations to within the Steady State Limits.
The surveillance requirements provide adequate assurance that con-centrations in excess of the limits will be detected in sufficient time to take corrective action.
3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits following a CALVERT CLIFFS-UNIT 1 8 3/4 4 4
UNIT 1 INSERT "A" If at least 20 percent of the tubes were inspected and the results were in the C-1 Category or if at least 40 percent of the tubes were inspected and were in the C-2 Category during the previous inspection, the next inspection may be extended up to a maximum of 30 months in order to conespond with the next refueling outage if the results of the two previous inspections were not in the C-3 Category. However, if the results of either of the previous two inspections were in the C-2 Category, an engineering assessment shall be performed before operation beyond 24 months and shall provide assurance that all tubes will retain adequate structutal margins against burst throughout normal operating, transient, and accident conditions until the end of the fuel cycle or 30 months, which ever occurs firct.
INSERT "B" satisfy the criteria of Specification 4.4.5.3.a; the interval may then be extended to a maximum of once per 30 or 40 months, u applicable; eu m INSERT "C" d.
The provisions of Specification 4.0.2 do not apply for extending the frequency for performing inservice inspections as specified in Specifications 4.4.5.3.a and b.
INSERT "D" 100 gallons-per-day through any one steam generator, and INSERT "E" An engineering assessment of steam generator tube integrity will confirm that no undue risk is associated with plant operation beyond 24 months of the previous steam generator tube inspection.
To provide this confirmation, the assessment would demonstrate that all tubes will retain adequate structural nnrgins against burst during all normal operating, transient, and accident conditions until the end of the fuel cycle. This evaluation would include the following elements:
1.
An assessment of the flaws found during the previous inspections.
2.
An assessment of the structural margins relative to the criteria of Regulatory Guide 1.121,
lases for Plugging Degraded pWR Steam Generator Tubes," that can be expected before 6e end of the fuel cycle or 30 months, whichever comes first.
3.
An update of the assessment model, as appropriate, based on comparison of the predicted resdts of the steam generator tube integrity assessment with actual inspection results from previous inspections.
INSERT "F" The 100 gallon per day leakage litit per steam generator ensures that steam generator tube integrity is maintained in accordance with the recommendations of Generic Letter 9144.
4 ATTACllMENT (2)
UNIT 2 TECilNICAL SPECIFICATION REVISED PAGES 3/447 3/448 3/4414 3/4415 B3/442a B3/44-4
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REACTOR COOLANT $YSTEM
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SURVEILLANCE REQUIREMENTS (Continued)
)
2.
Tubes in those areas where experience has indicated potential problems.
c.
The second and third inservice inspections may be less than a full tube inspction by concentrating (selecting at least 50%
i of the tubes to be inspected) the inspection on those areas of the tube sheet array and on thora portions of the tuber ehere tubes with imperfections were previously found.
The results of each sample inspection shall be classified into one of the following three categoriest Ca tegory inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the in-spected tubes are defective.
C-2 One or more tubes, but not mure than 1% of s
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 tub.es are defective.
Note in all inspections, previously degraded tubes must exhibit significant (>10%) furthe wall pSr.mtrations to be included in the above percentage calculations.
4.4.0.3 Inspection Frecuencies - The above required inservice inspections of steam generater tubes snall be performed at the following frequencies:
a.
The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar nnths of initial criticality. Subsequent inservice inspecthms sh>11 be r
performed at intervals of not less than 12 nor morv v;an 14 calendar months after the previous inspection.o If two consecu WM^D-tive inspections following service under AYT 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.
CALVERT CLIFFS-UNIT 2 3/4 4-7 fr)S Et? r " B '
3 9
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' REACTOR COOLANT SYSTEMS SURVElllANCE REQUIREMENTS (Continued) accordance with Table 4.4 2 nqair4wthir4-sample 4nspost4em'j g,,,,,/ A If the inservice inspection of a steam generator conducted in b.
,, ka. te 1,wt*"d -whoss-r+sults fall in Category C-3, the inspection frequencynths. The red shall__befeduced-to at least once per 20
" in inspection frequency shall apply until subsequent inspections d emons tra t e s-t ha t-a-third-S ample-4 ns pection-45-ee t-regtti red.
ympfr nc -
c.
Additional, unscheduled inservice inspactions shall be performed on each steam generator in accordance with the first sample inspection specifiid in Table 4.4 2 during the shutdown subsequent to any of the following conditions:
1.
Prircry-to secondary tube leaks (not including leaks I
originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2, 2.
A seu;.iic occurrence greater than the Operating Basis Earthquake, 3.
A loss of coolant accident requiring actuation of the engineered safepards, or 4.
A main steam line or feedwater line break.
4.4.5.4 Acceptance Criteria, a.
As used in this Specification:
1.
Imoerfection means an exception to the dimensions, finish or contour of a tube frorn that required by fabrication drawings or specifications. Eddy-current testing indications below 20t of the nominal tube wall thickness, if detectable.
may be considered as imperfections.
2.
Deoradation reans a service-induced cracking, wastage, sear or general corrosion occurring on either inside or outside of a tube.
3.
Deeraded Tube means a tube containing imperfections >20%
of sne nominal wall thickness caused by degradation.
4.
% Deoradation means the percentage of the tube wall snicKness af fected or removed by degradation.
CALVERT CLIFFS-UNIT 2 3/4 4-8 Amendment No.91 j
c REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System 7eakage shall be limited to:
f a.
No PRESSURE BOUNDARY LEAKAGE, b.
1 GPM UN! DENT!F1ED !.EAKAGE, all 1 GPM total primary to-secondary leak 6ge through/ steam generatorsg c.
and,7 A/56A T "2 d.
10 GPM IDENT!FIED LEAKAGE from the Reactor Coolant System.
APPLICA9ILITY: MODES 1, 2, 3 and 4 ACTION:
i 4.
With any PRE 550RE BOUNDARY LEAKAGE, be in at least HOT STANOBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hour: or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
A SURVEILLANCE REQUIREMENTS 4.4.6.2 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:
a.
Either:
1.
Monitoring the containment atmosphere particulate or gaseous radioactivity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or 2.
With the gaseous and particulate monitors inoperable, conducting the containment atmosphere grab sampla analysis in accordance with the ACTION requirements of T.S. 3.4.6.1.
b.
Monitoring the containment sump discharge frequency at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, when the containment sump level alarm system is
- OPERABLE, i
l CALVERT CLIFFS - UNIT 2 3/4 4-14
,AecndmentidSS-l t
1
'REACTOD. CD0LANT SYSTEM f
SURVEILLANCE PESUIPEMENTS (Continued)
De f erm.nm (*1c-leet.yc c.
Performasi-+f-4 Reactor Coolant System wat+r-4rwentwy-balenet at least once per 72 hcurs during steady state oceration and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when re;uired by ACTION 3.4.5.1.b, e.xcept when operating in the shutdown cooling modt, and d.
tionitoring the reactor vessel head closure seal leakage detection system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i CALVERT CL:FF3 - UN:T :
3/a 4 15 4enoment g_gg_
BASES maintain surveillance of the co' ditions of the tubes in the event that there n
is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.
In-service inspection of steam generator tubing also provides a means of characterizing the nature ant. cause of any tube degradation so that correc-tive measures can be taken.
T A).S CR T " P
- The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes.
If the secondary coolant chemistry is not maintained within these limitt.,
localized corrosion may likely result in stress corrosion cracking.
The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondary coolant system (primary-to-secondary leakage =
1 gallon per minute, total).
Cracks having a primary-to-secondary leakage t
GAL"EF---CLIFF 3 - UNIT B 3/4 4-2a
-Amendment No. a CALVr.M CLIFFS - UNIT 2
-Amendment-Nor :
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L3 REACTOR C001 ANT SYSTEM 8.A1ES The 10 GPM IDENTIFIED LEAKAGE limitation provides allowance for a limited amount of leakage from known sources whose presence will not interfere wita the detection of UNIDENTIFIED LEAXAGE by the leakage detection systems.
The total steam generator tube leakage limit of 1 GPM for all steam '
generators ensures that the dosage contribution from the tube leakage will be limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam line break.
The 1 GPM limit is consistant with the assumptions used in the analysis of these accidents, y y m g /p 7 % +
PRESSURE BOUNDARY LEAKAGE of any 'acM Nde is ur. acceptable since
- li b*e of the pressure it may be indicative of an impencing g) boundary.
Therefore, the present, of o.rty M J SOUNDARY LEAKAGE requires the unit to be promptly Pw%t; DOLL SWT00WN.
3/4.4.7 CHEMISTRY _
The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduco the poten-tial for Reactor Cooknt System leakage or failure due to stress corro-sion.
Maintaining the chemistry within the Steady State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant.
The associated effects of exceeding the oxygen, chloride and fluoride limits are time and temperature dependent.
Corrosion studies show that operation may be con-tinued with contaminant concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time inter-vals without having a significant effect on the structs ral integrity of the. Reactor Coolant System.
The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady State Limits.
The surveillance requirements provide adequate assurance that con-centrations in excess of the limits will be detected in sufficient time to take corrective action.
l 3/4.4.8 SPECJJIC ACTIVITY k'"
The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits following a 4U0 J GM-CALVERT CLIFFS-UNIT 2 9 3/4 4-4
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.l!ML3 INSERT"A" If at least 20 percent of the tubes were inspected and the results were in the C 1 Category (See Note) or if at least 40 percent of the tubes were inspected and were in the C 2 Category during the previous inspection, the next inspection may be extended up to a maximum of 30 months in order to correspond with the next refueling outage if the results of the two previous ins icctions were not in the C 3 Categoiy, llowever, if the results el either of the previous two inspect ons were in the C.2 Category, an engineering assessment shall be performed before operation beyond 24 months and 1
shall provide apurance that all tubes will retain adequate structural margins against burst throughout normal operating, transient, and accident conditions until the end of the fuel cycle or 30 months, which ever cccurs first.
INSERT *ll" NOTE: For Cycle 9, an inspection of 15% of the steam generator tubes with inspection results in the C 1 Category shall be acceptable to extend the next inspection up to 30 months to coincide with the next refuehng outage.
INSERT "C" satisfy the criteria of Specification 4.4.5.3.a; the interval may then be extended to a maximum of once per 30 or 40 months, as applicable; INSERT "D" d.
The provisions of Specification 4.0.2 do not apply for extending the frequency for performing inservice inspections as specified in Specifications 4.4.5.3.a and b.
l INSERT "E" 100 gallons per-day through i.ny one steam generator, and l
--r7**rM PmwWNm P'*==="m'w4m"r'rr-rw
a INSERT "F" An enginecting assessment of steam generator tube integrity will confirm that no undue risk is associated with plant operation beyond 24 months of the previous steam generator tube inspection.
To provide this confirmation, the assessment would demonstrt te that all tubes will retain adequate structural margins against burst during all normal operating, transient, and accident conditions until the end of the fuel cycle. This evaluation would include the following cler..ents:
1.
An assessnient of the flaws found during the previous inspections.
2.
An assessment of the structural margins relative to the criteria of Regulatory Guide 1.121,
' Bases for Plugging Degraded PWR Steam Generator Tubes.* that can be expected before the end of the fuel cycle or 30 months, whichever comes first.
3.
An update of the assessment model, as appropriate, based on comparison of the predicted results of the steam generator tube integrity assessment with actual inspection results from previous inspections.
INSERT "G" The 100 gallon per day leakage limit per steam generator ensures that steam generator tube integrity is maintained in accordance with the recommendations of Generic Letter 914)4.
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