ML20138D641

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Proposed Tech Specs Revising Requirements for Sample Scope Initial Size & Expansion for Inservice Insp of Steam Generator Tube Sleeves
ML20138D641
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 04/24/1997
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20138D639 List:
References
NUDOCS 9705010191
Download: ML20138D641 (15)
v • d • e


Text

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REACTOR COOLANT SYSTEM -

' STEAM GENERATORS i

LIMITING CONDITION FOR OPERATION I

3.4.5 Each steam generator shall be OPERABLE.

l APPLICABILITY: MODES 1,2, 3 and 4.

l 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 ,

of the following augmented inservice inspection program and the requirements l l of Specification 4.0.5.

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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 udnimum number of steam generators specified in ,

Table 4.4-1. i l

4.4.5.2 Steam Generator Tube Sample Selection and Inspection - The steam l generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Tables 4.4-2 and 4.4-3. The inservice inspection of steam generator-tubes shall be performed j at the frequencies specified in specification 4.4.5.3 and the inspected tubes 6

shall be verified acceptable per the acceptance criteria of Specification )

4.4.5.4. The tubes selected for each inservice inspection shall include at I least 3% of the total number of tubes in all steam generators znd at least l 20% of each type of installed sleeves; the tubes selected for tuese l inspections shall be selected on a random basis except l a. Where experience in similar plants with similar water chendstry l indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.

1 l 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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9705010191 970424 ADOCK 05000368 PDR P PDR ARKANSAS - UNIT 2 3/4 4-6 Amendment No.%4,

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i REACTOR COOLANT SYSTEM I l

' SURVEILLANCE REQUIREMENTS (Continued) l 1. All nonplugged tubes that previously had detectable wall l penetrations (>20%).

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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 perndt. 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 1 inspection. l l c. The tubes selected as the second and third samples (if required by Tables 4.4-2 or 4.4-3) during each inservice inspection may 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. '

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2. The inspections include those portions of the tubes where ,

imperfections were previously found.

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The result of each sample inspection shall be classified into one to the following three categories: i Category Inspection Results C-1 Less than 5% of the total tubes inspected l are degraded tubes and none of the J inspected tubes are defective. j C-2 One or more tubes, but not more than 1% of l the total tubes inspected are defective, or  ;

between 5% and 10% of the total tubes I inspected are degraded tubes.

C-3 More than 10% of the total tubes inspected j 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.

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ARKANSAS - UNIT 2 3/4 4-7 Amendment No.464, l

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. , REACTOR COOLANT SYSTEM i

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:

( a. The first inservice inspection il be performed after 6 l

Effective Full Power Months but within 24 calendar months of

! initial criticality. Subsequent inservice inspections shall be ,

l performed at intervals of not less than 12 nor more than 24 j l

calendar months after the previous inspection. If two l consecutive inspections following service under AVT conditions, l not including the preservice inspection, result in all inspection I results falling into the C-1 category or if two consecutive

! inspections demonstrate that previously observed degradation has I not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum ,of once per 40 months.

i b. If the results of the inservice inspection of a steam generator conducted in accordance with Tables 4.4-2 and 4.4-3 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.a; the interval may l then be extended to a maximum of once per 40 months.

l l c. Additional, unscheduled inservice inspections shall be performed l l on each steam generator in accordance with the first sample

) inspection specified in Tables 4.4-2 and 4.4-3 during the shutdown j j subsequent to any of the following conditions:

1. Primary-to-secondary tube leaks (not including leaks l 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.

l 4. A main steam line or feedwater line break.

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l ARKANSAS - UNIT 2 3/4 4-8 Amendment No.

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__ ._ _ _ ._ _ _ _ _ . _ . _ . _ m..__ _ _ . _ _ -.m_.- . - . _ . . _ _ _ _ _ _

1 REACTOR COOLANT SYSTEM i SURVEILLANCE REQUIREMENTS (Continued) i i

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 field hydrostatic test and prior to initial POWER i

-OPERATION using the equipment and techniques expected to be t used during subsequent inservice inspections.

b. The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the +

plugging or repair limit and all tubes containing through-wall f; cracks) required by Tables 4.4-2 and 4.4-3. Defective tubes may l be repaired in accordance with:

1) B&W Topical Report BAW-2045PA-00 as supplemented by the t information provided in B&W Report 51-1212539-00, "BWNS Kinetic Sleeve Design-Application to ANO Unit 2".
2) CENS Report CEN-601-P, "ANO-2 Steam Generator Tube Repair Using Leak Tight Sleeves", Revision 01-P, dated July, 1992.

4.4.5.5' Reports

a. Following each inservice inspection of steam generator tubes the  ;

number of tubes plugged or sleeved 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 on an annual basis for the period in which the inspection was completed. 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 or sleeved.
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 4.4-3. l l Notification of the Commission will be made prior to resumption of i plant operation. 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.

i ARKANSAS - UNIT 2 3/4 4-10 Amendment No. M,W,443, i

TABLE 4.4-2 .

STEAM GENERATOR NON-REPAIRED TUBE IN$PECTION l 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION -

Sample Size '

Result Action Required Result Action Required Result Action Required A minimum of C-1 None N/A N/A N/A N/A S Tubes per S.G.

C-2 Plug or sleeve defec- C-1 None N/A N/A tive tubes and inspect additional 25 tubes in Plug or sleeve defec- C-1 None this S.G. C-2 tive tubes and inspect C-2 Plug or sleeve additional 4S tubes in defective tubes this S.G.

Perform action for C-3 C-3 result of first sampie Perform action for C-3 C-3 result of first N/A N/A sample C-3 Inspect all tubes in Other S.G.

this S.G., plug or is C-1 None N/A N/A sleeve defective tubes and inspect 2S tubes in the other S.G. Other S.G. Perform action for N/A N/A is C.2 C-2 result of second sample Special Report to NRC per Specification 6.9.2 Other S.G. Inspect all tubes in is C-3 the other S.G. and plug or sleeve t defective tubes. N/A N/A t

l Special Report to NRC per Spec. 6.9.2 l

i S= 3 2 % Where n is the number of steam generators inspected during an inspection. l n

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l RRKANSAS - UNIT 2 3/4 4-12 Amendment No. M,444,443,448, 1

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l TABLE 4.4-3 '. I STEAM GENERATOR TUBE SLEEVE INSPECTION ,

1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION -

Sample Size Result Action Required Result Action Required j A minimum of 20% of C-1 None N/A N/A  !

cach type of  !

installed sleeve [

per S.G. (1)  !

I C-2 Plug tubes containing C-1 None  !

defective sleeves and  !

inspect all remaining  !

installed sleeves in this S.G. l C-2 Plug tubes containing defective sleeves [

L C-3 Perform action for C-3 result of first sample  !

C-3 Inspect all installed Other S.G. is None sleeves in this S.G., C-1 plug tubes containing ,

defective sleeves and l inspect 100% of the  !

installed sleeves in the other S.G.

Special Report to NRC per Other S.G. is Plug tubes containing defective sleeves j Specification 6.9.2 C-2 f i

i other S.G. is Inspect all installed sleeves in each S.G. i C-3 and plug tubes containing defective sleeves Special Report to NRC per Spec. 6.9.2 4

(1) Each sleeve type is considered a separate population for determination of sample expansion.

ARKANSAS - UNIT 2 3/4 4-12a Amendment No.

. , REACTOR COOLANT SYSTEM BASES Wastage-type defects are unlikely with propor chemistry treatment of i the secondary coolant. However, even if a defect should develop in service,

! it will be found during scheduled inservice steam generator tubes examinations.

! Plugging or sleeving will be required for all tubes with imperfections

! exceeding the plugging or repair limit as defined in Surveillance Requirement 4.4.5.4.a. Defective tubes may be repaired by sleeving in accordance with the B&W Topical Report BAW-2045PA-00 as supplemented by the information provided in B&W Report 51-1212539-00, "BWNS Kinetic Sleeve Design-Application to ANO Unit 2" or CENS Report CEN-601-P, "ANO-2 Steam Generator Tube Repair Using Leak Tight Sleeve.s", Revision 01-P, dated July 1992. Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the tube wall thickness. For sleeved tubes, the adequacy of the system that is used for periodic inservice inspection will be validated. 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 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 4.4-2 or 4.4-3. Notification of the Commission will be made prior to resumption l 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 i Technical Specifications, if necessary.

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS I 1

I The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure 1 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 limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.

l 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 , W ,444, Order dated 4/20/31,

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MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS (FOR INFO ONLY) l l

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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, 2 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 shall be demonstrated OPERABLE by performance j of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

"ste: The curveill:ne: ::qukrement: Of Sp :ificati:n 2.'.5 de net :pply t:

the :pecial ste gencreter tube inspection to be performed during the 2005-I cut;g scheduled to begin en Janu:ry 5, 1405. The :: p and Onpancien-eriteria for this in:pection :: pecified in ecrrespondene to the "nc cubmitted under ::perate ::ver. The :: p and criteria l hnli be approved by the NnC prior t: :niting Med: 5. The :: ult; cf I this in:pection chall be revicu d by the Plant Safety Committe prier t: :::u=ption of plant operation and reported to the Nnc within 20 day: Of :::u=ption of plant Operation 4.4.5.1 Steam Generator Sample Selection and Inspection - Each steam j generator shall be determined OPERABLE during shutdown by selecting and i l inspecting at least the minimum number of steam generators specified in Table 4.4-1.

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l l 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 Tables 4.4-2 and j

4.4-3. 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 l

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 and at least 20% of eae.h type of installed sleeves; the tubes selected for these j inspections shall be selected on a random basis except:  ;

t i a. Where experience in similar plants with similar water chemistry

indicates critical areas to be inspected, then at least 50% of l

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 I

shall include:

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4 ARKANSAS - UNIT 2 3/4 4-6 Amendment No.MB,

REACTOR COOLANT SYSTEM

. l l SURVEILLANCE REQUIREMENTS (Continued)

1. All nonplugged tubes that previously had detectable wall penetrations (>20%). I
2. Tubes in those areas where experience has indicated potential problens.
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 Tableg 4.4-2 or 4.4-3) during each inservice inspection may be subjected to a partial bebe-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.

l The result of each sample inspection shall be classified into one to the j

( following three categories:

1 Category Inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

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

l 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.

t i Note: In all inspections, previously degraded tubes must exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations.

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ARKANSAS - UNIT 2 3/4 4-7 Amendment No.MS, i

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, REACTOR COOLANT SYSTEM l

SURVEILLANCE REQUIREMENTS (Continued) l 4.4.5.3 Inspection Frequencies - The above required inservice inspections l of steam generator tubes shall be performed at the following frequencies: i

a. The first inservice inspection shall be performed after 6 l 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 the inservice inspection of a steam generator conducted in accordance with Tableg 4.4-2 and 4.4-3 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.a; the interval may 4 then be extended to a maximum of once per 40 months.

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c. Additional, unscheduled inservice inspections shall be performed I on each steam generator in accordance with the first sample l inspection specified in Tableg 4.4-2 and 4.4-3 during the shutdown l l subsequent to any of the following conditions:
1. Primary-to-secondary tubes leaks (not including leaks l 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 l engineered safeguards, l
4. A main steam line or feedwater line break.

l ARKANSAS - UNIT 2 3/4 4-8 Amendment No.

- . -.. - - - . ..- ~ _ . - . . . - .- ~ . . ~ . . . - . . . - - . . . - .- .

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REACTOR CCOLANT SYSTEM I t .

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  • SURVEILLANCE REQUIREMENTS (Continued) ,
10. Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy  !

l current techniques prior to service to establish a baseline l condition of the tubing. This inspection shall be performed I

after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.

b.

l The steam generator shall be determined OPERABLE after completing l the corresponding actions (plug or repair all tubes exceeding the i

plugging or repair limit and all tubes containing through-wall i l cracks) required by Tables 4.4-2 and 4.4-3. Defective tubes may l ,

i be repaired in accordance with: }

1) B&W Topical Report BAW-2045PA-00 as supplemented by the

, information provided in B&W Report 51-1212539-00, "BWNS Kinetic .

! Sleeve Design-Application to ANO Unit 2.

l 2) CENS Report CEN-601-P, "ANO-2 Steam Generator Tube Repair f l Using Leak Tight sleeves", Revision 01-P, dated July, 1992.  !

L 4.4.5.5 Reports

a. Following each inservice inspection of steam generator tubes the ,

number of tubes plugged or sleeved in each steam generator shall be  !

reperted to the Commission within 15 days. ,

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b. The. complete results of the steam generator tube inservice ]

inspection shall be reported on an annual basis for the period in i which the inspection was completed. This report shall include:

l .l. Number and extent of tubes inspected.

i l 2. Location and percent of wall-thickness penetration for each indication of an imperfection.

3. Identification of tubes plugged or sleeved.
c. Results of steam generator tube inspections which fall into Category C-3 shall be reported in a Special Report pursuant to l Specification 6.9.2 as denoted by Tables 4.4-2 and 4.4-3. l l Notification of the Commission will be made prior to resumption of plant cperation. The written Special Report shall provide a l description of investigations conducted to deterndne cause of the tube degradation and corrective measures taken to prevent recurrence.

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ARKANSAS - UNIT 2 3/4 4-10 Amendment No. M,4-3-3,14G,

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TABLE 4.4-2 .

STEAM GENERATOR NON-REPAIRED TUBE INSPECTION l 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION

  • Sample Size Result Action Required Result Action Required Result Action Require.2 A minimum of C-1 None N/A N/A N/A N/A .

S Tubes per S.G.

C-2 Plug or sleeve defec- C-1 None N/A N/A tive tubes and inspect  :

C-1 None  !

additional 2S tubes in Plug or sleeve defec-this S.G. C-2 tive tubes and inspect C-2 Plug or sleeve additional 4S tubes in defective tubes  ;

i this S.G.

Perform action for  ;

C-3 C-3 result of first i sample i i

Perform action for C-3 C-3 result of first N/A N/A i esample  ;

C-3 Inspect all tubes in A14-eother, this S.G., plug or S.G.e-ace None N/A N/A sleeve defective tubes is C-1 I and inspect 2S tubes '

in the eaeh other S.G. Geme-Other Perform action for N/A N/A S.G.e is C-2 result of second C-2 but no sample '

Special Report additienci to NRC per S.C. Orc  ;

Specification 6.9.2 G-3  !

Other Inspect all tubes in

?.dditional the other each-S.G.

S.G. is C-3 and plug or sleeve defective tubes. N/A N/A Special Report to NRC per Spec. 6.9.2.

S = 3 gN % Where " is the nu.ber of sten gcncrators in the unit, and n is the number of steam generators inspected l n during an inspection ARKANSAS - UNIT 2 3/4 4-12 Amendment No. M,4-43,443,448,

TABLE 4.4-23, .

r STEAM GENERATOR TUBE SLEEVE INSPECTION .

IST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 2Pa S?fPLE IMS PSCT4GN Sanple Size Result Action Required Result Action Required Reseh . .ctirn P.; quired A minimum of & C-1 None N/A N/A N/A N/A '

hbes 20% of euch type of .

installed sleeve pars.G. (1) ~

C-2 Plug tubes containino C-1 None N/A N/A defective twees sleeves and inspect all remaininc installed sleeves additi n:1 2S tubes in this S.G.

Plug tubes containino G-+ Nene defective tubes sleeves and insp;;t addition:1 iS tub : in thi CC C-2 G-3 Plug :: cle:c; deft tic; tub :

Perfc= :: tion G-3 fee C-2 :: ult of fe+et eemph Perform action for C-3 C-3 result of first & sample tN/A N/A C-3 Inspect all installed A h _ther sleeves tubes in this S.G.e-eee j None N/A N/A S.G., plug _ tubes C-1 containinc defective tubes sleeves and inspect 100% of the Geme-Other 00:f:= ::tien f or installed sleeves as S.G.e 2 C-2 C 2 result f ::: nd N/A N/A tubes in eseh the other but-ee semple Pluc tubes S.G. 2ddition:1 contain1nc defective S.C. cre G-3 sleeves Special Report to NRC per .'.ddit i onal Inspect all sleeves tubes Specification 6.9.2 Other S.G. is in each S.G. and plug C-3 tubes containina defective tubee sleeves. Special Report to NRC per Spec. N/A N/A 6.9.2.

S - ? " ' 9.cre " i: th; nricr cf st = generator in the u-it, 2nd - in the n ri r Of 0t0 = generater in pcoted

" during an in p:Ci n (1) Each sleeve type is considered a separate population for determination of sample expansion.

ARKANSAS - UNIT 2 3/4 4-12a Amendment No. M,4-33,M3,4M,

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REACTOR COOLANT SYSTEM

  • BASES Wastage-type defects are unlikely with proper chemistry treatment of l the secondary coolant. However, even if a defect should develop in service, l it will be found during scheduled inservice steam generator tubes examinations.

l Plugging or sleeving will be required for all tubes with imperfections l exceeding the plugging or repair limit as defined in Surveillance Requirement 4.4.5.4.a. Defective tubes may be repaired by sleeving in accordance with the B&W Topical Report BAW-2045PA-00 as supplemented by the information i provided in B&W Report 51-1212539-00, "BWNS Kinetic Sleeve Design-Application to ANO Unit 2" or CENS Report CEN-601-P, "ANO-2 Steam Generator Tube Repair Using Leak Tight Sleeves", Revision 01-P, dated July 1992. Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the tube wall thickness. For sleeved tubes, the adequacy of the system that is used for periocic inservice inspection will be validated. 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 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 4.4-2 Er 4.4-3. Notification of the Commission will be made prior to resumption l 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 examinationse 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.

l 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 limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systenm.

i The Surveillance Requirements for RCS Pressure Isolation Valves provide l 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 IDENT;FIED LEAKAGE and will be considered as a portion of the allowed limit.

l l

ARKANSAS - UNIT 2 B 3/4 4-3 Amendment No. 91,+33,443, Order-dated 4/20/S1,

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