ML20216G072
| ML20216G072 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/17/1999 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20216G071 | List: |
| References | |
| NUDOCS 9909280242 | |
| Download: ML20216G072 (20) | |
Text
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- sa PROPOSED TECHNICAL SPECIFICATION CHANGES
> 9909290242 990917 PDR ADOCK 05000313
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- a. The first atmple inspection during each inservice inspection j (subsegurnt to the baseline inspection) of each steam generator shall include:
- ' I
- l. All nonplugged tubes that previously had detectable wall I penetrations (>20%), except tubes in which the wall I penetration has been spanned by a sleeve, and
- 2. At least 50% of the tubes inspected shall be in those areas where experience has indicated potential problems, except where specific groups are inspected per Specification ;
4.18.3.a.3. I I
A tube inspection (pursuant to Specification 4.18.5.a.9) shall be j 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.
- 3. Tubes in the following groups may be excluded from the first )
random sample if all tubes in a group in both steam l generators are inspected. The inspection may be l concentrated on those portions of the tubes where imperfections were previously found. No credit will be taken for these tubes in meeting minimum sample size requirements. Where only a portion of the tube is I inspected, the remainder of the tube will be subjected to the random inspection.
(1) Group A-1: Tubes within one, two or three rows of the open inspection lane.
(2) Group A-2: Unplugged tubes with sleeves installed.
(3) Group A-3: Tubes in the wedge-shaped group on either side of the lane region (Group A-1) as defined by Figure 4.18.1.
- 4. Tubes with axially-oriented tube end cracks (TEC) which have been left inservice for the previous cycle shall be inspected with a rotating coil eddy current technique in the area of the TEC and characterized in accordance with topical report BAW-2346P, Rev.0, during all subsequent SG inspection intervals pursuant to 4.18.4.
The results of this examinaticn may be excluded from the first random sample. Tubes with axial TECs identified during previous inspections which meet the criteria to remain in service will not be included then calculating the inspection category of the OTSG.
- 5. Implementation of the upper tubesheet ODIGA alternate repair criteria requires a 100% bobbin coil inspection of the non-plugged and non-sleeved tubes, sparining the defined region of the upper tubesheet, during all subsequent SG inspection intervals pursuant to 4.18.4. Tubes with ODIGA identified during previous inspections which meet the criteria to remain in service will not be included when calculating the inspection category for the OTSG.
The defined region begins one inch above the upper tubesheet secondary face and ends at the nearest tube roll transition.
ODIGA indications detected by the bobbin coil probe shall be characterized using rotating coil probes in accordance with topical report BAW-10235P, Revision 1.
Amendment No. 34,44,86,M6, 110jl L
)
I l
j b. All tubes which have been repaired using the reroll process will have the new roll area inspected during the inservice inspection.
. .c. The second and third sample inspections during each inservice inspection as required by. Table 4.18-2 may be less than a full tube inspection by concentrating the inspection on those areas of the tube sheet array and on those portions of the tubes.where tubes with imperfections were previously found.
The results of each sample inspection shall be classified into one of 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 l tubes inspected are degraded tubes or more than 1% of the
! inspected tubes are defective.
NOTES: (1) In all inspections, previously degraded tubes whose degradations have not been spanned by a sleeve must i exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations.
(2) Where special inspections are performed pursuant to 4.10.3.a.3, defective or degraded tubes found as a result of the inspection shall be included in determining the Inspection Results Category for that special inspection but need not be included in determining the Inspection Results Category for the general steam generator inspection.
(3) Where special inspections are performed pursuant to 4.18.3.b, defective or degraded tube indications found in the new roll area as a result of the inspection and any indications found above.the new roll area, are not included in,the determination for the inspection results category of a general steam generator inspection.
Amendment No. 34,44,M,M6,-144,MO, 110k M1,
kl. . ,
, 4.18.4 Inepwetion Intervals l The above-required inservice inspections of steam ge..erator tubes shall be l performed at the following frequencies:
- a. The baseline inspection shall be performed during the first refueling shutdown. Subsequent inservice inspections shall be performed at intervals of not less than 10 nor more than 24 i calendar months after the previous inspection. If the results of two consecutive inspections for a given group
- of tubes following service under all volatile treatment (AVT) conditions fall 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 for that group may be extended to a maximum of 40 months.
- b. If the results of the inservice inspection of a steam generator performed in accordance with Table 4.18-2 at 40-month intervals for a given grcup* of tubes fall in Category C-3, subsequent inservice inspections shall be performed at intervals of not less than 10 nor more than 20 calendar months after the previous inspection. The increase in inspection frequency shall apply until a subsequent inspection meets the conditions specified in 4.18.4.a and the interval can be extended to 40 months.
- c. Additional unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4 18-2 during the shutdown subsequent to any of the following conditions:
- 1. Primary-to-secondary leakage in excess of the limits of Specification 3.1.6.3.b (Inservice inspection not required if leaks originate from tube-to-tubesheet welds). If the l leaking tube is from either Group A-1 or A-3 as defined in l Specification 4.18.3.a.3, all of the tubes in the affected )
group in this steam generator may be inspected in lieu of !
the first sample inspection specified in Table 4.18-2. If the degradation mechanism which caused the leak is limited to a specific portion of the tube length, the inspection per this paragraph may be limited to the affected portion of the tube length. If the results of this inspection fall into the C-3 category, all of the tubes in the same group in the other steam generator will also be similarly inspected.
If the leaking tube has been repaired by the reroll process and is leaking in the new roll area, all of the tubes in the steam generator that have been repaired by the reroll process will have the new roll area inspected. If the results of this inspection fall into the C-3 category, all of the tubes with rerolled areas in the other steam generator will also be similarly inspected.
This inspection will be in lieu of the first sample inspection specified in Table 4.18-2.
- 2. A seismic occurrence greater than the Operating Basis Earthquake,
- 3. A loss-of-coolant accident requiring actuation of the engineered safeguards, or
- 4. A main steam line or feedwater line break.
- A group of tubes means: (a) All tubes inspected pursuant to 4.18.3.a.3, or (b) All tubes in a steam generator less those inspected pursuant to 4.18.3.a.3.
Amendment No. M,41, %, M6,-1-34,-140, 1101
W.
I 4.18.5 Acceptenes critaria
- a. As used in this specification:
. 1. Tubing or Tube means that portion of the tube or sleeve which 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, wastage, wear or general corrosion occurring on either the inside or outside of a tube.
- 4. Degraded Tube means a tube containing imperfecticns 2 20% of l the nominal wall thickness caused by degradation, except where all degradation has been spanned by the installation of a sleeve.
- 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 except where the imperfection has been spanned by the installation of a sleeve. A tube containing a defect in its pressure boundary is defective.
- 7. Plugging Limit means the imperfection depth at or beyond 40% of the nondnal tube wall thickness for which the tube shall be sleeved, rerolled, or removed from service because it may become unserviceable prior to the next inspection. This does not. apply during Cycle 16 to ODIGA indications within the defined region of the upper tubesheet. These indications shall be assessed for continued plant operation in accordance with topical report BAW-10235P, Revision 1.
Axially-oriented TEC indications in the tube that do not extend beyond the adjacent cladding portion of the tube sheet into the carbon steel portion are not included in this definition. These indications shall be assessed for continued plant operation in )
j accordance with topical report BAW-2346P, Rev. O. l The reroll repair process will only be used to repair tubes with defects in the upper tubesheet area. The reroll repair process j will be performed only once per steam generator tube using a 1 !
inch roll length. The new roll area must be free of detectable degradation in order for the repair to be considered acceptable.
The reroll repair process is described in the topical report, 3 BAW-10232P, Revision 00.
- 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 Specification 4.18.4.c.
1
- 9. Tube Inspection means an inspection of the steam generator tube from the point of entry completely to the point of exit. For tubes thac have been repaired by the reroll process within the upper tubesheet, that portion of the tube above the new roll can be excluded from future periodic inspection requirements because it is no longer part of the pressure boundary once the i repair roll is installed.
Amendment No . G4,44, M, M6, M4, MO, 110m GE
l
- b. The steam generator shall be determined operable after completing the corresponding actions (plug, reroll, or sleeve all tubes exceeding the plugging limit and all tubes containing non-TEC through-wall cracks) required by Table 4.18-2.
4.18.6 Reports Following each inservice inspection of steam generator tubes, the complete results of the inspection shall be reported to the NRC. This report, to be submitted within 90 days of inspection completion, shall include:
- a. Number and extent of tubes inspected;
- b. Location and percent of wall-thickness penetration for each indication of an imperfection;
- c. Identification of tubes plugged and tubez sleeved;
- d. Number of tubes repaired by rerolling and number of indications detected in the new roll area of the repaired tubes;
- e. Summary of the condition monitoring and operational assessment results when applying TEC alternate repair criteria; and
- f. Summary of the condition monitoring and the operational assessment results (including growth) when applying the upper tubesheet ODIGA alternate repair criteria.
This report shall be in addition to a Special Report (per Specification 6.12.5.d) required for the results of steam generator tube inspections which fall into Category C-3 as denoted in Table 4.18-2. The Commission shall be notified of the results of steam generator tube inspections which fall into Category C-3 prior to resumption of 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.
Amendment No. B4,4-1, M,-lM, H4,- 110ml W ,M O,M 1,BO+,
NL" l
l l l , Btess. I t: .
I The surveillance requirements for inspection of the steam generator tubes ensure t, hat the structural integrity of this portion of the RCS will be maintained. The l program for. inservice inspection of steam generator tubes is based on a 1
! 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. !
In general, steam generator tubes that are degraded beyond the repair lindt can either be plugged, sleeved, or rerolled. The steam generator (SG) tubes that are l '
t plugged are removed from service by the installation of plugs at both ends of the associated tube and thus completely removing the tube from service. When the tube end cracking (TEC) alternate repair criteria is applied, axially-oriented: indications found not to extend from the tube sheet cladding region into the carbon steel region may be left in service under the guidelines of
' topical report BAW-2346p, Rev. O. When the upper tubesheet outer diameter I
-intergranular attack (ODIGA) alternate repair criteria is applied, indications found within the defined region of the upper tubesheet may be left in service !
under the guidelines of topical report BAW-10235P, Revision 1. The defined I region begins one inch above the upper tubesheet secondary face and ends at the nearest tube roll transition. Following a SG inspection, an operational assessment is performed to ensure primary-to-secondary leak rates will be maintained within the assumptions of the accident analysis.
Degraded steam generator tubes can also be repaired by the installation of sleeves which span the area of degradation and serve as a replacement pressure
-boundary for the. degraded portion of the tube, thus permitting the tube to remain in service.
Degraded steam generator tubes can also be repaired by the rerolling of the tube in the upper tubesheet to create a new roll area and pressure boundary for the tube. The rerolling methodology establishes a new pressure boundary below the degradation, thus permitting the tube to remain in service. The degraded tube above the new roll area can be excluded from future periodic inspection requirements because it is no longer part of the pressure boundary once the repair roll is installed in the upper tubesheet. The rerolling repair process will only be used to repair defects in the upper tubesheet in accordance with BAW-10232P, Revision 00.
All tubes which have been repaired using the reroll process will have the new j roll area inspected during future inservice inspections. Defective or degraded j tube indications found in the new roll and any indications found in the original j roll need not be included in determining the Inspection Results category for the generator. inspection.
The reroll-repair process will only be used to repair tubes with defects in the upper tubesheet area. The reroll repair process will be performed only once per steam generator tube using a 1 inch roll length. Thus, multiple applications of j the reroll process to any individual tube is not acceptable. The new roll area ]
must be free of' detectable degradation in order for the repair to be considered l acceptable. After the.new roll area is initially deemed acceptable, future degradation in the new roll area will be analyzed to determine if the tube is ,
- l. defective-and needs to be removed from service. The reroll repair process is described in the topical report, BAW-10232P, Revision 00.
l Amendment No, M,M,M,M6,4M, 110n 4%,4%,4%,2%,
r s MARKUP OF CURRENT ANO-1 TECHNICAL SPECIFICATIONS (FORINFORMATION ONLY) i i
i Legend Strike-through- = Deleted Text Double Underline = Added Text l Shaded. = Text being deleted from current page and being moved to another Boxed = Text being added to current page from another page
1 f.
- 1. , ,
- a. Tha first simple inapection during each inservice inspection
,4 (subasquant to the baselina inspection) of each steam generator shall include:
- 1. All nonplugged tubes that previously had detectable wall penetrations (>20%), except tubes in which the wall penetration has been spanned by a sleeve, and
- 2. At least 50% of the tubes inspected shall be in those areas where experience has indicated potential problems, except where specific groups are inspected per Specification 4.18.3.a.3.
A tube inspection (pursuant to Specification 4.18.5.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.
- 3. Tubes in the following groups may be excluded from the first random sample if all tubes in a group in both steam generators are inspected. The inspection may be concentrated on those portions of the tubes where imperfections were previously found. No credit will be taken for these tubes in meeting minimum sample size requirements. Where only a portion of the tube is inspected, the remainder of the tube will be subjected to the random inspection.
(1) Group A-1: Tubes within one, two or three rows of the open inspection lane.
l (2) Group A-2: Unplugged tubes with sleeves installed. l (3) Group A-3: Tubes in the wedge-shaped group on either side of the lane region (Group A-1) as defined by Figure 4.18.1.
- 4. Tubes with axially-oriented tube end cracks (TEC) which have been left inservice for the previous cycle shall be inspected with a rotating coil eddy current technique in the area of the TEC and characterized in accordance with topical report BAW-2346P, Rev.0, during all subsequent SG inspection intervals pursuant to 4.18.4.
The results of this examination may be excluded from the first random sample. Tubes with axial TECs identified during previous inspections which meet the criteria to remain in service will not be included when calculating the inspection category of the OTSG.
- 5. Implementation of the upper tubesheet ODIGA alterna h ep g criteria recuires_a 100% bpbbin coil inspection of the non-pluaggd and non-s_1_eeved tubes,_spannina the defined recion of the upper tubesheet, durina all subsecuent SG inspection intervals pursuant to 4.18.4. Tubes with ODIGA identified durina previqgg inspections which meet the criteria to remain in_ service _will not be included when calculatina the inspection _cateaory for the OTSG; The defined recion becins one inch above the upper tpbesheet secondarv face and ends at the nearest tube roll transition.
ODIGA indications detected by the bobbin coil probe shall be characterized usina rotatina coil probes in accordance with e
topical iep_ ort BAW-10235P, Revision 1.
Amendment No. 34,44, M,4M, 110jl
a~
Ktube Tinspection"(purs^uaht"to~~ Specification"C18 0 5N9) "sh'all"be1
~
~
,; ' performed on each selected tube;J If,an'y selected, tube does not, j permit the passage of the eddy. current probe for'a tube , , s i
! inspection,,this shall be recorded and;an adjacent, tube shall,be 4
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[ ; characterized in accordance'with' topical report BAW-2346P,~Rev.0,;
' F " during 'all subsequent SG inspection' intervals pursuant to "4.18.4. j s ~',The resnits of this %xamination,may be' excluded from'the first !
- < _ random sample.i Tubes with axial'TECs" identified during previous j c ' ' inspections which meet the criteria to remain in ' service will'not 3 b,,nbe; included,when_ calculating;the;inspectioncategory,ofltheOTSG.; , m
- b. All tubes which have been repaired using the reroll process will have the new roll area inspected during the inservice inspection.
- c. The second and third sample inspections during each inservice inspection as required by Table 4.18-2 may be less than a full tube inspection by concentrating the inspection on those areas of j the tube sheet array and on those portions of the tubes where
{
tubes with imperfections were previously found. j The results of each sample inspection shall be classified into one of the following three categories:
Category Inspection Results l
l C-1 Less than 5% of the total tubes I inspected are degraded tubes l
and none of the inspected tubes '
are defective. l C-2 One or more tubes, but not more j than 1% of the total tubes i inspected, are defective, or between 5% and 10% of the total i tubes inspected are degraded ;
tubes. I C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
Amendment No. 34,44, 84, -146, -144, MO, 110k 304,
.A NOTES: (1) In all inspections, previously degraded tubes whose degradations have not been spanned by a sleeve must exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations.
(2) Where special inspections are performed pursuant to 4.18.3.a.3, defective or degraded tubes found as a result of the inspection shall be included in deteomining the Inspection Results Category for that special inspection but need not be included in determining the Inspection Results category for the general steam generator inspection.
(3) Where special inspections are performed pursuant to 4.18.3.b, defective or degraded tube indications found in the new roll area as a result of the inspection and any indications found above the new roll area, are not included in the determination for the inspection results category of a general steam generator inspection ~.
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- a. The baseline inspection shall be performed during the first refueling shutdown. Subsequent inservice inspections shall be performed at intervals of not less than 10 nor more than 24 calendar months after the previous inspection. If the results of two consecutive inspections for a given group
- of tubes following service under all volatile treatment (AVT) conditions fall 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 for that group may be extended to a maximum of 40 months.
- b. If the results of the inservice inspection of a steam generator performed in accordance with Table 4.18-2 at 40-month intervals for a given group
- of tubes fall in Category C-3, subsequent inservice inspections shall be performed at intervals of not less than 10 nor more than 20 calendar months after the previous inspection. The increase in inspection frequency shall apply until a subsequent inspection meets the conditions specified in 4.18.4.a and the interval can be extended to 40 months.
- c. Additional unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.18-2 during the shutdown subsequent to any of the following conditions:
- 1. Primary-to-secondary leakage in excess of the limits of Specification 3.1.6.3.b (Inservice inspection not required if leaks originate from tube-to-tubesheet weldsl. If the l leaking tube is from either Group A-1 or A-3 as defined in specification 4.18.3.a.3, all of the tubes in the affected group in this steam generator may be inspected in lieu of the first sample inspection specified in Table 4.18-2. If the degradation mechanism which caused the leak is limited to a specific portion of the tube length, the inspection per this paragraph may be limited to the affected portion of the tube length. If the results of this inspection fall into the C-3 category, all of the tubes in the same group in the other steam generator will also be similarly inspected.
Amendment No. B4,41,M,4M,4M,440, 1101
f ~ ,,.
l If tha lacking tuba has buzn repaired by the reroJ1 procasa and
/ is leaking in the n:w roll area, all of the tubss in the steam generator that have been repaired by the reroll process will have the new roll area inspected. If the results of this inspection fall into the C-3 category, all of the tubes with rerolled areas ;
in the other steam generator will also be similarly inspected. l This inspection will be in lieu of the first sample inspection specified in Table 4.18-2.
l
- 2. A seismic occurrence greater than the Operating Basis Earthquake,
- 3. A loss-of-coolant accident requiring actuation of the engineered safeguards, or l 4. A main steam line or feedwater line break. l
\
- A group of tubes means: (a) All tubes inspected pursuant to 4.18.3.a.3, or (b) All tubes in a steam generator less those inspected pursuant to 4.18.3.a.3.
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- my d IEEENT,Mi@lEsissitiUKEMtsilijhassjiB11553igsggg;gEgEgM 4.18.5 Acceptance Criteria
- a. As used in this specification: 1
- 1. Tubing or Tube means that portion of the tube or sleeve ,
which forms the primary system to secondary system pressure l 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 l 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
- 3. Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either the inside or outside of a tube. I i
- 4. Degraded Tube means a ttabe containing imperfections ;$ 20% of l the nominal wall thickness caused by degradation, except where all degradation has been spanned by the installation of a sleeve.
- 5. % Degradation means the percentage of the tube wall thickness affected or removed by degradation. l
- 6. Defect means an imperfection of such severity that it l exceeds the plugging limit except where the imperfection i has been spanned by the installa. tion of a sleeve. A tube I containing a defect in its pressure boundary is defective, j
- 7. Plugging Limit means the imperfection depth at or beyond 19.%_of l j
the nomirtal tube wall thickness for l which th'e tube shall be cestered t: ::: vie:chility by th: )
installati:n ;f a sleeved, rerolled, or removed from service !
because it may become unserviceable prior to the next inepectionAt it i: equel te iCS cf the n :dnel tube w H thickness. This does not_ apply _durino Cygle 16 to the ODLGA ,
iDdiga_tions wLtAin the delip d recion of the upper tubesheet, I These indJc!Lttons shall bugesnd_f_or continued plant opelation !
intacc_oIdance with topical report ?AW-10235P, llevision 1 3 Amendment No. M,44,M,M6,M4,MG, 110m ;
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e Axielly-ori &nted TEC indications in tha tuba that do not extend
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e bsyond the cdjecznt cladding portion of tha tubo shast into the carbon steel portion are not included in this definition. These indications shall be assessed for continued plant operation in accordance with topical report BAW-2346P, Rev. O.
The reroll repair process will only be used to repair tubes with defects in the upper tubesheet area. The reroll repair process will be performed only once per steam generator tube using a 1 inch roll length. The new roll area must be free of detectable l degradation in ordar for the repair to be considered acceptable. I The reroll repair process is described in the topical report, <
BAW-10232P, Revision 00. l
- 0. Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural j integrity in the event of an Operating Basis Earthquake, a j loss-of-coolant accident, or a steam line or feedwater line '
break as specified in Specification 4.18.4.c.
- 9. Tube Inspection means an inspection of the steam generator tube from the point of entry completely to the point of exit. For tubes that have been repaired by the rerolJ process within the upper tubesheet, that portion of the tube above the new roll i can be excluded from future periodic inspection requirements because it is no longer part of the pressure boundary once the repair roll is installed.
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- b. The steam generator shall be determined operable after completing the corresponding actions (plug, reroll, or sleeve all tubes exceeding the plugging limit and all tubes containing non-TEC through-wall cracks) required by Table 4.18-2 3 with the following
- n;;ption:
Tube; with cuter di:::ter intergranula: att:ch indication: uithin the upper tub h::t with potential of th : ugh x:11 depthe g ster than the plugging limit, 10:sted by cddy current between 2.75 inch:: ab;ve th: ::::ndary f :: and bel - th: : 11 transition, : y
- ir ir :::vice for Cycle 15 contingent up:n the fellowing conditiene+
- 1. One hund::d p : cent of the uncle ved tub : :: enemined by b;bbin ::11 cddy current in the upper tub ch::t : gica during the fourteent-h-cefueling cutage,
- 2. S;bbir. ::i1 indication; in the upper tubech::t : gion :::
enemined by : stating pan che coil cddy current and confirmed to be volu=:tric,
- 3. " ::= pari::n shall bc ::d: between th: bobbin : il voltage measured during the thirtc; nth : fueling cutag; fc the
- nfirmed indication and th: bobbin ;;il voltage for the e::: indicati:n: =:: ured during the fourteenth : fueling cut g:, The :: p:ricen ch:11 ::nfirr :::enti:11y n in c re:.se ir voltag; en average,
- 4. Tube; : ntaining indications eith b;bbin : 11 vcitage
- =plitud:: > 0.' velt and having g::xth > 0.3 valt since the last inspection ch:11 be plugged : : pcizedr-end
- 5. !r situ preocur; testing in the "'." st:cr generater during the fourtcenth : fueling cutage confirms, at OSS ;;nf4denee level, th:t the b unding accident leakag; due te volumetri; 00!C'. f1:u within the upper tube:h::t : gion =111 be les:
than 0.5 gall n p:: minute due t: ; ;;ir : tear line brec h i
1 Amendment No. M,4,M,M6,H4, 110ml j M9,HO,Hk,3%, 1 i
i.. . .
Reports l 4.18. 6 l E:ollowing each inservice inspection of steam generator tubes, the complete results of the inspection shall be reported to the NRC. This report, to be submitted within 90 days of inspection completion, shall include:
l a. Number and extent of tubes inspected; l
- b. Location and percent of wall-thickness penetration for each indication of an imperfections l c. Identification of tubes plugged and tubes sleeved; l
- d. Number of tubes repaired by rerclling and number of indications detected in the new roll area of the repaired tubes; and
- e. Summary of the condition monitoring and operational assessment results when applying TEC alternate repair criteriari and
- f. Summ_arv of the condition monitorina and the operational assessment results (includinc crowth) when ,applyinc the upper _tubesheet ODIGA alternate repair cIlteria.
This report shall be in addition to a Special Report (per Specification 6.12.5.d) required for the results of steam generator tube inspections which fall into Category C-3 as denoted in Table 4.18-2. The Commission shall be notified of t:ae results of steam generator tube inspections which fall into Category C-3 prior to resumption of 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.
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Bases The surveillance requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maint&Lned. 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 dt a 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.
In general, steam' generator tubes that are degraded beyond the repair limit can
.either be plugged, sleeved, or rerolled. The steam generator 1SGl_ tubes that are l plugged are removed from service by the installation of plugs at both ends of the associated tube and thus completely removing the tube from service. When the tube end cracking (TEC) alternate repair criteria is applied, axially-oriented indications found not to extend from the tube sheet cladding region into the carbon steel region nay be left in service under the guidelines of topical report BAW-2346P, Rev. O. When tyg upper tubesheet outer diameter interaranular attack- (OQLGA) alternate remLir criteria is aoolied, indications found within the defined reaton of the unge,r tubesheet may_b_e left in service
.under the cuidelines of topical report BAW-10235P. Revision _1 The defined a gign becins one inch above the upper tubesheet secondarv face and ends at the nearest t.ube roll transition. Following & SG inspection, an operational assessment is performed to ensure primary-to-secondary leak rates will be maintained within the assumptions of the accident analysis.
~
Degraded steam generator tubes can also be repaired by the installation cf sleeves which span the area of degradation and serve as a replacement pressure boundary for the degraded portion of the tube, thus permitting the tube to remain in service.
~
Degraded steam. generator tubes can also be repaired by the rerolling of the tube in the upper tubesheet to create a new roll area and pressure boundary for the tube. The rerolling methodology establishes a new pressure boundary below the degradation, thus permitting the tube to remain in service. The degraded tube above the new roll area can be excluded from future periodic inspection requirements because'it is no~ longer part of the pressure boundary once the repair. roll is installed in the upper tubesheet. The rerolling repair process will-only be used.to repair defects in the upper tubesheet in accordance with BAW-10232P, Revision 00.
All tubes which have been repaired using the reroll process will have the new roll area inspected during future' inservice inspections. Defective or degraded tube indications found in the new' roll and any indications found in the original
. roll need not be included in determining the Inspection Results Category for the generator inspection.
The' reroll _ repair process will only be used to repair tubes with defects in the
. upper tubesheet area. The reroll repair process will b<> performed only once per steam generator tube using a 1 inch roll length. Thus< nultzple applications of the reroll process to any indivjdual tube is not accept.-ole. 7he new roll area must be free'of detectable degradation in order for the repir to be considered acceptable. .After the new roll area is initially deemed acceptable, future l ' Amendment No. M,41,M, M6,1M, 110n l ' MG, MG, M1, M1, j
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I.o*:9 y 'd;gredstion in tha n:.w roll crea will b2 cn:lyzId to d,tarmina if tha tuba is dJfactiva cnd n :da to b2 r;:mov d from carvica. The raroll rzpsir proc 2sc is described in the topical report, BAW-10232P, Revision 00.
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