ML20211C410
| ML20211C410 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/18/1999 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20211C408 | List: |
| References | |
| NUDOCS 9908250232 | |
| Download: ML20211C410 (19) | |
Text
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PROPOSED TECHNICAL SPECIFICATION CHANGES l
l 9908250232 990818 PDR ADOCK 05000368 PDR
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REACTOR COOLANT SYSTEM STEAM GENERATORS LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.
APPLICABILITY: MODES 1,2, 3 and 4.
ACTION:
With one or more steam generators inoperable, restore the inoperable generator (s) to OPERABLE status prior to increasing Tavg above 200*F.
SURVEILLANCE REQUIREMENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance j
of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
NOTE: The requirements for inservice insp... tion do not apply during the steam generator replacement outage (2R14).
4.4.5.1 Steam Generator Sample Selection and Inspection - 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 Sample Selection and Inspection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2.
l 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.
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 l
these inspections shall be selected on a random basis except:
Where experience in similar plants with similar water chemistry a.
l indicates critical areas to be inspected, then at least 50% of I
the tubes inspected shall be from these critical areas.
1 b.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
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l ARKANSAS - UNIT 2 3/44--6 Amendment No.-l&B,4M
l RZACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 1.
All nenplugged tubes that previously had detectable wall penetrations (>20%).
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2.
Tubes in those areas where experience has indicated j
potential problems.
j 3.
A tube inspection (pursuant to Specification 4.4.5.4.a.9) 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.
c.
The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected l
to a partial inspection provided:
l 1.
The tubes selected for these 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.
The result of each sample inspection shall be classified into one to the following three categories:
Category Inspection Results J
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.
Note:
In all inspections, previously degraded tubes must exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations.
l 1
i ARKANSAS - UNIT 2 3/4 4-7 Amendment No.464, E
l' SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.3 Inspection Frequencies - The above required inservice inspections of, steam generator tubes shall be performed at the following frequencies:
The first inservice inspectiog shall be performed after 6 l
a.
Effective Full Power Months but within 24 calendar months of
(
initial criticality following the steam generator replacement l
outage.
Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 I
calendar months after the previous inspection.
If the first l
inspection following the preservice inspection results in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation, with the exception of wear, has not continued and no l
additional degradation has occurred, the inspection interval may be extended to a nmximum of once per 40 months.
b.
If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40 month l
intervals fall into 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.as the interval may I
then be extended to a maximum of once per 40 months.
1 Additional, unscheduled inservice inspections shall be performed c.
on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown l
subsequent to any of the following conditions:
1.
Primary-to-secondary tube 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 i
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1 3.
A loss-of coolant accident requiring actuation of the engineered safeguards.
4.
A main steam line or feedwater line break.
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ARKANSAS - UNIT 2 3/4 4-8 Amendment No. W l
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acceptance Criteria a.
As used in this Specification 1.
Tubing or Tube means that portion of the tube which forms the l
primary system to secondary system pressure boundary.
2.
Imperfection 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 imperfections.
3.
Degradation means a service-induced cracking, wear or general l
corrosion occurring on either inside or outside of a tube.
4.
Degraded Tube means a tube containing imperfections 220% of nominal wall thickness caused by degradation.
5.
% Degradation means the percentage of the tube wall thickness affected or removed by degradation.
6.
Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is l
defective.
7.
Plugging Limit means the imperfection depth at or beyond which the tube shall be removed from service by plugging because it may become unserviceable prior to the next inspection. The plugging limit is equal to 40% of the nominal tube wall thickness.
8.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural
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integrity in the event of an Operating Basis Earthquake,
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a loss-of-coolant accident, or a steam line or feedwater line I
break as specified in 4.4.5.3.c, above, i
9.
Tube Inspection means an inspection of the steam generator
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tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
ARKANSAS - UNIT 2 3/4 4-9 Amendment No. 443,44G,M4
SURVEILLANCE REQUIREMENTS (Continued) l 10.
Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline l
condition of the tubing.
This inspection shall be performed j
after the hydrostatic test and prior to POWER l
i OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2.
l 4.4.5.5 Reports Following each inservice inspection of steam generator tubes the a.
number of tubes plugged in each steam generator shall be l
reported to the Commission within 15 days, b.
The complete results of the steam generator tube inservice inspection shall be reported within 12 months following the completion of the inservice inspection. This report shall include:
1.
Number and extent of tubes inspected.
2.
Location and percent of wall-thickness penetration for each indication of an imperfection.
3.
Identification of tuber plugged.
l c.
Results of steam generator tube inspections which fall into Category C-3 shall be reported in a Special Report pursuant to Specification 6.9.2 as denoted by Table 4.4-2.
Notification of the Commission will be made prior to resumption of plant operation (i.e.,
prior to entering Mode 4).
The written Special Report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
ARKANSAS - UNIT 2 3/4 4-10 Amendment No. f4, 4-33, 442, -144, 44-7
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S AS5 R
S A
REACTOR COOLANT SYSTEM BASES Demonstration of the safety valves' lift setting will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Vessel Code.
1 3/4.4.4 PRESSURIZER A steam bubble in the pressurizer ensures that the RCS is not a hydraulically solid system and is capable of accommodating pressure surges during operation. The steam bubble also protects the pressurizer code I
safety valves against water relief. The steam bubble functions to relieve RCS pressure during a31 design transients.
]
The requirement that 150 KW of pressurizer heaters and their associated controls be capable of being supplied electrical power from an emergency bus provides assurance that these heaters can be energized during
]
a loss-of-offsite power condition to maintain natural circulation at HOT STANDBY.
3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of steam generator tubing is essential in order to 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.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
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 limits, 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
= 150 gallons per day per steam generator).
Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents. Operating plants have demonstrated that primary-to-secondary leakage of 150 gallons per day per steam generator can readily be detected by radiation monitors on the secondary system.
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged.
l ARKANSAS - UNIT 2 B 3/4 4-2 Amendment No. GO,M B,M 4
REACTOR COOLANT SYSTEM BASES Defects are less likely with proper chemistry treatment of l
the secondary coolant.
However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tubes examinations.
Plugging will be required for all tubes with imperfections exceeding the plugging i
limit as defined in Surveillance Requirement 4.4.5.4.a.
Steam generator tube
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inspections of operating plants have demonstrated the capability to reliably detect degradation that could affect tube wall integrity. Additionally, upgraded testing methods will be evaluated and appropriately implemented as better methods are developed and validated for commercial use.
I l
Whenever the results of any steam generator tubing inservice inspection fall into Category C-3 certain results will be reported in a Special Report to the Commission pursuant to Specification 6.9.2 as denoted by Table 4.2-2. Notification l of the Commission will be made prior to resumption of plant operation.
Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS 1
The RCS leakage detection systens 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 REACTOR COOLANT SYSTEM 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 IDENTIFIED LEAKAGE limitation provides allowances for a lindted amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.
The Surveillance Requirements for RCS Pressure Isolation Valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA.
Leakage from the RCS Pressure Isolation Valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.
ARKANSAS - UNIT 2 B 3/4 4-3 Amendment No. M, M3, -144, Gedet dated 4 /20/81,M4,4-84
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f MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS (FOR INFO ONLY) k
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REACTOR COOLANT SYSTEM STEAM GENERATORS LIMITING CONDITION FOR OPERATION G.4.5 Each steam generator shall be OPERABLE.
APPLICABILITY: MODES 1,2, 3 and 4.
i ACTION:
With one or more steam generators inoperable, restore the inoperable generator (s) to OPERABLE status prior to increasing Tavg above 200'F.
SURVEILLANCE REQUIREMENTS 4.4.5.0 Each steam generator chall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
NOTE: The recuirements for inservice inspection do not app 1v durino the steam generator replacement outaap J $ $
4.4.5.1.
Steam Generator Sample Selection and Inspection - 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 Sample Selection and Inspection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Tablee 4.4-2-end 4v4-4.
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 j
4.4.5.4.
The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in all steam generators :nd :t le::t 20S cf ::ch type cf inct:11 d cleaves; the tubes selected for these inspections shall be selected on a random basis except:
Where experience in similar plants with similar water chemistry a.
indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.
b.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
ARKANSAS - UNIT 2 3/4 4-6 Amendment No.M8,444
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 1.
All nonplugged tubes that previously had detectable wall penetrations (>20%).
2.
Tubes in those areas where experience has indicated potential problems.
3.
A tube inspection (pursuant to Specification 4.4.5.4.a. 9) 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.
c.
The tubes selected as the second and third samples (if required by Tablee 4.4-2 cr '
'-3) during each inservice inspection may l
be subjected to a partial inspection provided:
1.
The tubes selected for these 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.
The result of each sample inspection shall be classified into one to the following three categories:
Category Inspection 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.
Note:
In all inspections, previously degraded tubes must exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations.
ARKANSAS - UNIT 2 3/4 4-7 Amendment No.MB, l
r REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.3 Inspection Frequencies - 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 a.
Effective Full Power Months but within 24 calendar months of j
initial criticality following the steam cenerator replacement outage.
Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.
If the first inspection following,bwe-eencccutivc incpection: fcilcuing cc vice l
unde:
""T conditienc, not ine'uding the preservice inspection, l
results in all inspection results falling into the C-1 category l
or if two consecutive inspections demonstrate that previously observed degradation, with the excep_ tion of wear,. has not continued l
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 the inservice inspection of a steam generator conducted in accordance with Tablee 4.4-2-end *
-3 at 40 month l
f intervals fall into 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 c.
on each steam generator in accordance with the first sample inspection specified in Tablee 4.4-2 cnd
- 3 during the shutdown l
subsequent to any of the following conditions:
1.
Primary-to-secondary tube leaks (not including leaks i
originating from tube-to-tube sheet welds) in excess of the l
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.
ARKANSAS - UNIT 2 3/4 4-8 Amendment No. 7 l
t
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acceptance Criteria a.
As used in this Specification 1.
Tubing or Tube means that portion of the tube c: 01 cv: which l
forms the primary system to secondary system pressure boundary.
2.
Imperfection 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 imperfections.
3.
Degradation means a service-induced cracking,-w: tage l
r wear or general corrosion occurring on either inside or outside of a tube.
4.
Degraded Tube means a tube containing imperfections 220% of nominal wall thickness caused by degradation.
5.
% Degradation means the percentage of the tube wall thickness affected or removed by degradation.
6.
Defect means an imperfection of such severity that it exceeds the plugging cr repair limit. A tube containing l
a defect is defective.
7.
Plugging er Depair Limit means the imperfection depth at or l
beyond which the tube shall be removed from service by plugging c repaired by cle ving because it may become unserviceable prior to the next inspection. The plugging c: rcpai+-limit is equal to 40% of the nominal parent-tube and cle ve wall thickness for :1ceve: installed in acecrdance with S:" Tcpical ncpcrt SA" 2045-P? 00 :: suppic=:nted by the information prcvided in S W Repcrt 51-1212530-00, "SW"S Kinetic Sle:vc 00:ign Application tc A"O " nit 2" The plugging limit is equal to 20^
cf the ncminal :10 ve u 11 thickness within th: clecv precour; beundary fcr cl eve in:talled in acccrdance with CE"O n pert CE" f30-r, "nepair cf 3/'" O.0.
Stear Cencratcr Tubc: t' ing L k Tight Sleev," n: vision 01, dated "cvember 1995.
8.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a
loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.
9.
Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
ARKANSAS - UNIT 2 3/4 4-9 Amendment No. 33,-143,-144
i REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 10.
Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed after the fieid-hydro. static test and prior to initial POWER l
OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug er repair all tubes exceeding the plugging or repair limit and all tubes containing through-wall cracks) required by Tables 4.4-2 and '
'-3.
Ocfective tubc may bc cpaired in accc: dance a:th:
1)
Sus Tcpical ncpert E7" 20'5P' 00 : suppicmented by the information p cvided ir S:" "cport 51-1212530-00, "SWNS Kinctic S1ccvc Oceign-Application tc A"O Unit 2" 2)
CE"O ncpert CE"-530 P, "ncpair cf 3/'" O.D.
S t-eer Cc nc ra t c Tubc; U ing Leak Ti-ght 51ccves," ncvicica 01, dated '!cvcmber 100f.
The pcot acid hcat treatment dcccribed 1r CE"-530 P chall be performed.
4.4.5.5 Reports Following each inservice inspection of steam generator tubes the a.
number of tubes plugged er 1ceved in each steam generator shall be l
j reported to the Commission within 15 days.
b.
The complete results of the steam generator tube inservice inspection shall be reported within 12 months following the comp _letion of the inservice inspection en an annual baci for the period in whic' the inspection ac ccmpleted.
This report shall include:
1.
Number and extent of tubes inspected.
2.
Location and percent of wall-thickness penetration for each indication of an imperfection.
)
3.
Identification of tubes plugged er riceved.
l c.
Results of steam generator tube inspections which fall into Category C-3 shall be reported in a Special Report pursuant to Specification 6.9.2 as denoted by Tables 4.4-2-and-4r4-3.
l Notification of the Commission will be made prior to resumption of plant operation li.e.,_ prior to entering. Mode 41 The written Special l
Report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
ARKANSAS - UNIT 2 3/4 4-10 Amendment No. 94,4M,442, M4,4M
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8
F-
- REACTOR COOIAMT SYSTEM BASES Demonstration of the safety valves' lif setting will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Vessel Code.
3/4.4.4 PRESSURIZER A steam bubble in the pressurizer ensures that the RCS is not a hydraulically solid system and is capable of accommodating pressure surges
'i during operation. The steam bubble also protects the pressurizer code safety valves against water relief. The steam bubble functions to relieve RCS pressure during all design transients.
The requirement that 150 KW of pressurizer heaters and their associated controls be capable of being supplied electrical power from an emergency bus provides assurance that these heaters can be energized during a loss-of-offsite power condition to maintain natural circulation at HOT STANDBY.
3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of steam generator tubing is essential in order to 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.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
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 limits, 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
= 150 gallons per day per steam generator).
Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents.
Operating plants have demonstrated that primary-to-secondary leakage of 150 gallons per day per steam generator can readily be detected by radiation monitors on the secondary system.
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged-er
- pal ::d.
J ARKANSAS - UNIT 2 B 3/4 4-2 Amendment No. M,Me,M4 I
t i
I REACTOR COOLANT SYSTEM BASES Wantage type dpefects are less_unlikely with proper chemistry treatment of l
the secondary coolant.
However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tubes examinations.
Plugging cr 31ccving will be required for all tubes with imperfections exceeding the plugging c: repair limit as defined in Surveillance Requirement 4.4.5.4.a.
Defective tubc: may be repaired by ciceving ir accordance ai+h the BCS Tcpical "cpcrt S?? 2045P'-00 supplemented by thc irformation provided r S W nercrt 51-1212539-00, "EW"E Minctic Siccvc Occign-?.pplication tc ?"O " nit 2" or CE"O ncport CE" 530--P, "ncpair cf 3/'" O.D.
Etcar Cc:eeetet Tubcr "cing Leak Tight Slecvcc," ncvicicr 01, dated '!cvcabcr 1996.
Steam i
generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that could affectha penetrated 205 cf the tube wall intearitythickness.
Fc clecved tubcs, the adequacy cf-+hc syster that is used fer periodic incervice incpection aill be validatcd. Additionally, upgraded testing methods will be evaluated and appropriately implemented as better methods are developed and validated for commercial use.
Whenever the results of any steam generator tubing inservice inspection i
fall into Category C-3 certain results will be reported in a Special Report to the Commission pursuant to Specification 6.9.2 as denoted by Table 4.2-2 cr
'-3.
l Notification of the Commission will be made prior to resumption of plant operation.
Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION 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.
I 3/4.4.6.2 REACTOR COOLANT SYSTEM 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 IDENTIFIED LEAKAGE limitatior. provides allowances for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detect..e systems.
The Surveillance Requirements for RCS Press-,
a+
on Valves provide added assurance of valve integrity thereby redun
>bability of gross valve failure and consequent intersystem LOCA.
- s. 4 g
, tom the RCS Pressure Isolation Valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.
ARKANSAS - UNIT 2 B 3/4 4-3 Amendment No. M,4-3-3, M2, Gede-r dated n/20/81,H4, W