Proposed Tech Specs Modifying TS 3/4.4.5, SG to Add Alternative to Tube Plugging,Repair of SG Tubes That Have Indications of Degradation| ML18011A105 |
| Person / Time |
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| Site: |
Harris  |
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| Issue date: |
08/20/1993 |
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| From: |
CAROLINA POWER & LIGHT CO. |
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| To: |
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| Shared Package |
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| ML18011A104 |
List: |
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| References |
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| HNP-93-831, NUDOCS 9308260322 |
| Download: ML18011A105 (23) |
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ENCLOSURE TO SERIAL:
HNP-93-831 ENCLOSURE 5
SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT STEAM GENERATOR TUBE REPAIR TECHNICAL SPECIFICATION PAGES 930B260322 930B20 PDR ADOCK 05000400 P
PDR
REACTOR COOLANT SYST"=9 3/4. 4. 5 S i cAN GENERATORS LIHITING CONOITION FOR OPERATION 3.4.5 Ea'ch steam generator shall be OPERABLE.
APPLICABILITY:
HOOES 1, 2, 3, and 4.
ACTTQH:
With.one or more steam generators inoperable, restore the inoperable genera or(s) to OPERABLE status prior to increasing T
above 200'F.
SURVEILLANCE REOUIREHENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.Q.5.
4.4.5.l Steam Generator Sanale Selec ion and Insaection - Each staaa generator shall be determined ounng snutoown oy se ecting and inspec-ing at least Cho minimum number of steam generators specified in Table 4.4-1.
4.4.5.2 Steam Generator Tub~ample Selection and Insaection - The staam generator tuoo mxnzmum samp e size, snspectIon resu t c asss
- ication, and the corresponding action required shall be as specified in Tables 4.4-2 A and B.
The inservica 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 these inspections shall be selected on a random basis except:
a.
Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50" of the tubes inspected shall ba from these critical areas; b.
The first sample of tubes solectad for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:.
1.
All nonplugged tubes that previously had d'itactable wall penetrations (greater than 20"),
2.
Tubes in those areas where experience has indicated potential prob 1 emspQg~
%When referring to a
steam generator
- tube, the sleeve shall be considered part of the tube if the tube has been repaired per Specification 4.4.5.4.a.12.
SHEARON HARRIS UNIT 1 3/4 4-l3
IP SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.2 (Continued)
INKS'TMHQ~N"A' tube inspection (pursuant to Specification 4.4.5.4a.8) 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 ad]scent tube shall be selected and sub]ected to a tube inspection.'
~
The tubes selected as the second and third samples (if required by Tables 4.4-2 A and B) during each inservice inspection may be sub-
)ected to a partial tube inspection provided:
d.
1.
The tubes selected for these samples include the tubes from those areas of the tube sheet array vhere tubes vith imperfections were previously found, and
'I 2.
The inspections include those portions of the tubes vhere imperfections were previously found.
Each inspection shall include a sample of those tubes expanded in the preheater section of the steam generator.
The first sample
- size, second sample size and subsequent inspection shall follow Table 4.4-2B.
In addition to the 3% sample, all tubes for vhich the alternate plugging criteria (W) has been previously applied shall be ec the tubesheet region.
When applying the exceptions of 4.4.5.2.a through 4.4.5.2.e, previous defects or imperfections in the area required by the sleeving are not considered an area requiring reinspection.
The results of each sample inspection shall be classified into one of the folloving three categories:
C-l Less than 5i of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C-3 C-2 Ona 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.
More chan 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective. Ro~uES Note: In all inspections, previously degraded tube t significant (greater than 10%) further vali penetrations to be included in the above percentage calculations.
SHEARON HARRIS - UNIT 1 3/4 4-14 Amendment No. 31
Attachment "A" Insert at 4.4.5-2 Technical Specification 3/4.4.5
>>ge
>/0 %H+
3.
At least 34 of the total number of sleeved tubes in all three steam generators or all of the sleeved tubes in the generator chosen for the inspection program, whichever is less.
These inspections will include both the tube and the sleeve>
and
SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 e
e OR 5LKVe a.
As used in this specifi.cation:
5166 6'epcion co the dimensions, finish, or contour of a tube from thee required by fabrication drawings or specifications.
Eddy-current testing indications below 20% of the nominal
/wall thickness, if dececeable, may be considered as imperfections; 3.
cra king) ithin the W distan e.
N~Vf contains a defect large enough to affect its structural integ-rity in the event of an Operating Basis Earthquake, a lass-of-caolant accident, or a steam line or feedwaeer line break as specified in Specification 4.4.5.3c.,
above; f6%a.t
%hQN&K 6 gener occurring on either inside or oucside of a cube OR. 5LGEVB ideiuoixm, ah SmauG iF -Me Td6E HMBREA K6$/HP60~
on g
r g
at a
or equal eo 20% of the nominal wall thickness caused by degradation; C 5'.VG affected or removed by degra tion; aiZ SLEE.VP S. ~~~ means an imperfec on s
severity that it exceeds the luggin limit.
A tubgcontaining a defect is defeceive I
RePhll2ED. (g. SMEV R
QSCrAh Ul Iran'eans the imperfection depth ac o e
w c
the tube shall ePremoved from service and is equal to 40% of e nam na e wall thickness g
es noc apply to e area o
e esheet region below the W stance provided the cube is not degraded (i.e.,
no indications of c
w c
es from the point of entry (hoc leg side) co lee
-be d e
ort xs ~
!'-ATA681ilN@QJ @AHAB K~~ll~& Nk
~H iV~fibQ 6HOuio MfvuPE TAG S
Sf-0~4 b~ ~<~BC~
ec an ng each cube in each steam generator performed by eddy currenc techniques pri.or to service eo escablish a baseline condition of the cubing.
This inspection shall be performed prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservica inspecti.ons.
SHEARON HARRIS - UNIT 1 3/4 4-16 Amendment No 31
Technical Specification 3/4.4.5 Page
$/Q Q
g Attachment "B", Insert at 4.4.5.4.a.6 t
Plugging will be required for all tubes that have been repaired by sleeving where the sleeve imperfection is greater than 404 of nominal wall thickness.
The portion of the tube and sleeve for which indications of wall degradation must be evaluated is as follows:
~
~ll illa The entire length of the sleeve shall be subject to the plugging limit; That portion of the tube in the entire upper joint region and the lower joint/expansion roll shall be subject to the plugging limit; That portion of the tube above the upper joint and below the lower joint/expansion roll shall be subject to the plugging limit.
C 0 SURVEILLANCE REQUIREMENTS (Continued) 10.
the.tubesheet or the top of the last hardroll, whichever is lower (further into the tubesheet),
that has been conservatively chosen to be 1.6 inches.
does not require the tube to be removed from service or repaired when the tube degradation exceeds the plugging limit so long as the degradation is in that portion of the tube from W to the bottom of the tubesheet.
This definition does not apply to tubes with degradation (i.e.,
indications o
cracking) in the W distance.
l2.
Ttls& KPPIJQ V6F&Rs TD MEcAAlQleAL GLEEV(QB'iAS 9EKARD iu 5
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MAiQTAIQ h XlSQ inL MGJiLG CK %MIX A f0% fQ MCeLG
%is )HCulOeh ME J!WavhiOF Ptu&5 TAAt NkK id&TA~
AS A CO~(1idC. CX fKEVECTA'AM M~~@F SHEARON HARRIS - UNIT 1 3/4 4-16a Amendment No. 31
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SURVEILLANCE REOUIREKBFZS (Continued) 4.4.5.4 b.
0 u
0 RiC The steam generator shall be e
OPERABLE after completing the corresponding actions (plu all tubes exceeding the plugging limit and all tubes containing 'ough-wall cracks) required by Tables 4.4-2A and B.
4.4.5.5 a.
b.
Within 15 days following the completion of each inse ce ection of steam generator
- tubes, the number of tubes plugged'ach steam generator shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2; v4<eQQS 6mcleel The complete results of the steam gene or inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection.
S c
1 Report shall include:
AQO~~eves 1.
Number and extent of tube 2.
Location and percent of wall-thickness penetration for each indication of an imperfection, and 3.
Identification of tubes, plugged dg PJEPA)REDi C ~
Results of steam generator tube inspections vhich fall into Category C-3 shall be reported in a Special Report pursuant to Specification 6.9.2 vithin 30 days and prior to resumption of plant operation.
This report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
d.
The results of the inspection of F+ tubes shall be reported to the Commission in a report, prior to the restart of the unit folloving the inspection.
This report shall include:
l.
Identification of W tubes, and 2.
Location and size of the degradation.
NRC approval of this report is not required prior to restart.
SHEARON HARRIS - UNIT 1 3/4 4-17 Amendment No. 31
1ST SAHPLE INSPECTION 2ND SAHPLE INSPECTION 3RD SAHPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required h minimum of C-1 S Tubes per S.G.
None cCZ~NiR.
N/A N/A N/A N/A C-2 Plug@a factive tubes'-1 and inspect additional 2S tubes in this S.G.
None N/A N/A C-2 Pluggefective tubes and inspect additional 4S tubes in this S.G.
C-1 K RePAik C-2 Plug efective tubes' C-3
'erform action for C-3 result of first sample C-3 Inspect all tubes in this S.G., plugge-fective tubes'nd inspect 2S tubes in each other S.G.
Notification to NRC pursuant to Speci-fication 4.4.5.5.c.
C-3 hll other S.G.s are C-1 Some S.G.s C-2 but no additional S.G.s are C-3 Additional S.G. is C-3 None N/A Perform action for C-2 result of second sample N/A Inspect all tubes each S.G.
and plu Cggfilk defective tubes.'otification to NRC pursuant to Speci-fication.4.4.5.5.c.
N/A Perform action for C-3 N/A result of first. sample N/A N/A N/A N/h S - $t where n is the number of steam generators inspected during an inspection.
- Defective tubes which fall under the Alternate Tube Plugging Criteria do not have to be plugged oR REf+gpg,
lAOiE e.<-2a SlEAH GEHERAlOR lUBE INSPECllOH - 1UBE DPANBED IN PRENEATER REGION lQ QHPLE IHSPECTIOH 2Ntl SAHPLE INSPECTION Saxhple Size Result Action Required Result Action Required A ainiaua of S of the tubes expanded in.
the preheater section C-1 C-2 C-3 Rew<R Plu efective tubes and i spect all other expanded tubes in this Steaw Generator inspect all expanded tubes in this Ste ORRFPAlP Ge>>erator, plug efec-tive tubes and nspect all expanded tubes in.
each other Steaw Generator.
Notification to HRC pursuant to Specification 4 I;5.5.c.
N/A C-I C-2 C-3 All other S.G.s are C-1 O>>e or <<ore S.G.s C-2 but no addi-tional S.G.s are C-3 Additional S.G.
is C-3 H/A
<<A
~g;eAi~
Plug efectiva tubes Perforw action for C-3 result of first sawple oK RePR~W Plu efect ye tubes
&$hFe Plug ec ve tubes.
Hotification to NRC pursuant to Specifica-tion 4 4.5.5.c.
S = -X where n Is the nuaber of steaa generators Inspected during an Inspection.
9 n
BASES The plant is expected to be apex'ated in a manner such that the secondary cool-ant will be maintained within chose chemistxy limits found to result in negli-gible corrosion of the
'steam generacor tubes.
If the secondary coolant chemistry is not maintained within these lind.ts, localixed corrosion may likely result in seress corrosion cracking.
The extent of cracking during plane operation would be lind.ted by the limieation of steam generator tube leakage between the Reactor Coolant Syseem and cho Secondary Coolant System (reactor-co-secondary leakage 500 gallons per day per steam generator).
Cracks having a reactor-to-secondary leakage less than this limit during operation will have an adequace margin of safeey to vixhscand the loads impased during normal operation and by postulated accidents.
Operating plants have demonstrated that reactor-to-secondary leakage of 500 gallons per day per steam generator can readily be detected by x'adiation monitors of steam generator blowdown.
Leakage in excess of this limitwill require plant shutdown and an unscheduled inspection, during, which che leaking cubes will be located an eNtKEQ ok Vascage-ax'e unlikely with proper chemisery treatment of the secondary coolant.
Hovovor, oven if a defect should develop in service, it v 11 be found during scheduled insexvice seeam generator tube examinations.
Qpgf gg ugging will be required for all tubes vieh imperfections exceeding che plugging limit of 40% of the tube nominal vali thickness.
This plugging limit does not apply to imperfectio'ns located bolov che Fo region of any given tube.
The Po criterion can be applied only if the tube geometry in the region selected as ehe W distance falls within the analytical limits of @CAP-12816.
Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradacion chat has peneeraced 20% of the original tube vali thickness.
Whenever the results of any steam generator cubing inservice inspection fall into Category C-3, these xesules villbe reported to the Commission in a Special Report pursuant to Specification 4.4.5.5.c within 30 days and prior to resumption of plant operation.
Such cases will be considered by the Commission on a case-by-case basis and may x'esult in a requirement for
- analysis, laboratory examinations,
- costs, addieional eddy-currene inspeccion, and revision of the Technical Specifications, if necessary.
4 4 The RCS Leakage Detoccion Systems required by this specification are provided to monitor and detect leakage from the reactox coolant pressure boundaxy.
These Detection Systems aro consistent vith the xecommendations of Regulatory Guide 1.45, "Reactor Coolant pressure Boundary Leakage Dotection Syscemsi" May 1973.
4 4 PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross'failure of che pressure baundary.
Therefor'e, the presence of any PRESSURE BOUNDARY LEQCAdE requires the unit to be prampely placed in COLD SHUTDOQN.
SHEARON HARRIS - UNIT 1 B 3/4 4-3 Amendmenc Na. 31
C
REACTOR COOLANT SYST I
3 4.4.5 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 T,
above 200'F.
SURVEILLANCE RE(UIREMENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
4.4.5. 1 Steam Generator Sam le Sel'ection and Ins ection - 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* Sam le Selection and Ins ection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Tables 4.4-2 A and B.
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 these inspections shall be selected on a random basis except:
Where experience in similar plants with similar water chemistry 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:
1.
All nonplugged tubes that previously had, detectable wall penetrations (greater than 20%),
2.
Tubes in those areas where experience has indicated potential
- problems, When referring to a steam generator
- tube, the sleeve shall be considered part of the tube if the tube has been repaired per Specification 4.4.5.4.a. 12.
SHEARON HARRIS - UNIT 1
3/4 4-13 Amendment No.
'E REACTOR COOLANT SYS STEAM GENERATORS SURVEILLANCE RE(UIREMENTS (Continued) 4.4.5.2 (Continued) 3.
4.
At least 3%-of the total number of sleeved tubes in all three steam generators or all of the sleeved tubes in the enerator chosen for the inspection program whichever is ess.
These inspections will include both the tube and the
- sleeve, and A tube inspection (pursuant to Specification 4.4.5.4a.8) 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 Tables 4.4-2 A and B) during each inservice inspection may be subjected to a partial tube inspection provided:
1.
The tubes selected for these samples include the'ubes from those areas of the tube sheet array where tubes with imperfections were previously found, and 2.
The inspections include those portions of the tubes where imperfections were previously found.
d.
Each inspection shall include a sample of those tubes expanded in the preheater section of the steam generator.
The first sample
- size, second sample size and subsequent inspection shall follow Table 4.4-2B.
e.
In addition to the 3% sample, all tubes for which the alternate plugging criteria (F*) has been previously applied shall be inspected in the tubesheet region.
f.
When applying. the exceptions of 4.4.5.2.a through 4.4.5.2.e previous defects or imperfections in the area required by tfie sleeving are not considered an area requiring reinspection.
The results of each sample inspection shall be classified into one of the following three categories:
~Cate or C-1 Ins ection Results Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
Note:
C-3 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.
More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
In all inspections, previously degraded tubes or sleeves must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.
SHEARON HARRIS - UNIT 1
3/4 4-14 Amendment No.
. 'EACTOR COOLANT SYS STEAM GENERATORS SURVEILLANCE RE(UIREHENTS (Continued) 4.4.5.4 Acce tance Criteria
'a ~
As used in this specification:
~IF i
pti t
h di i,5ih, or contour of a tube or sleeve from that required by fabrication drawings or specifications.
Eddy-current testing indications below 20% of the nominal tube or sleeve wall thickness, if detectable, may be considered as imperfections; 2.
3.
4.
6.
De radation means a service-induced
- cracking, wastage,
- wear, or genera corrosion occurring on either inside or outside of a tube or sleeve; I
De raded Tube means a tube, including the sleeve if the tube as een repaired containing imperfections greater than or equal to 20% of tie nominal wall thickness caused by degradation;
% De radation means the percentage of the tube or sleeve wa t ic ness affected or removed by degradation; Defect means an imperfection of such severity that it exceeels the p'lugging limit.
A tube or sleeve containing a
defect is defect>ve; Plu in Limit means the imperfection depth at or beyond w ic t e tu e shall be repaired, (i.e. sleeved) or removed from service and is equal to 40% of the nominal tube wall thickness.
Plugging will be required for all tubes that have been repaired by sleeving where the sleeve imperfection is greater than 40% of nominal wall thickness.
The portion of the tube and sleeve for which indications of wall degradation must be evaluated is as follows:
i.
The entire length of the sleeve shall be subject to the plugging limit; ii.
That portion of the tube in the entire upper joint region and the lower joint/expansion roll shall be subject to the plugging limit; iii.
That portion of the tube above the upper joint and below the lower joint/expansion ro11 shall be subject to the plugging limit.
The plugging limit does not apply to the area of the tubesheet region below the F* distance provided the tube is not degraded (i.e.,
no indications of cracking) within the F* distance.
SHEARON HARRIS - UNIT 1
3/4 4-16 Amendment No.
REACTOR COOLANT SYST STEAM GENERATORS SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acce tance Criteria (Continued)
I 7.
8.
9.
10.
12.
Unserviceable describes the condition of a tube or sleeve if d f t 1
g h t ff it structural integrity in.the event of an Operating Basis Earthquake a loss-of-coolant
- accident, or a steam line or feedwater )ine break as specified in Specification 4.4.5.3c.,
above; Tube Ins ection means an inspection of the steam generator tu e
rom t e point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
For a
tube that has been repaired by sleeving, the tube inspection should include the sleeved portion of the tube; Preservice Ins ection means an inspection of the full length o
eac tu e
>n eac steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing.
This inspection shall be performed
~
~
rior to initial POWER OPERATION using the equipment and echniques expected to be used during subsequent inservice inspections.
F* Distance is the distance into the tubesheet from the face h t th t p f th 1
t h
d 11, Ii h is lower (further into the tubesheet) that has been conservatively chosen to be 1.6 inches.
Alternate Tube Plu in Criteria does not require the tube to e remove rom service or repaired when the tube degradation exceeds the plugging limit so long as the degradation is in that port>on of the tube from F* to the bottom of the tubesheet.
This definition does not apply to tubes with degradation (i.e., indications of cracking) in the F* distance.
Tube Re air refers to mechanical
- sleeving, as described in Bh uc ear Service Company Report BAW-2045 PA, Rev-1 which is used to maintain a tube in service or return a tube to service.
This includes the removal of plugs that were installed as a corrective or preventative measure.
SHEARON HARRIS - UNIT 1 3/4 4-16a Amendment No.
~
'EACTOR COOLANT SYST STEAM GENERATORS SURVEILLANCE RE(UIREMENTS (Continued) 4.4.5.4 Acce tance Criteria Continued b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the plugging limit and all tubes containing through-wall cracks) requsre6 by Tables 4.4-2A and B.
4.4.5.5
~Re orts a 0 b.
C.
d.
Within 15 days following the completion of each inservice inspection of steam generator
- tubes, the number of tubes plugged or repaired in each steam generator shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2; The complete results of the steam generator tube (including sleeves) inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection.
This Special Report shall include:
1.
Number and extent of tubes and sleeves inspected, 2.
Location and percent of wall-thickness penetration for each indication of an imperfection, and 3.
Identification of tubes plugged or repaired.
Results of steam generator tube inspections which fall into Category C-3 shall be reported in a Special Report pursuant to Specsfication 6.9.2 within 30 days and prior to resumption of plant operation.
This report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
The results of the inspection of F* tubes shall be reported to the Commission in a report, prior to the restart of the unit following the inspection.
This report shall include:
1.
Identification of F* tubes, and 2.
Location and size of the degradation.
NRC approval of this report is not required prior to restart.
SHEARON HARRIS - UNIT 1 3/4 4-17 Amendment No.
~ +~
I 1ST SAMPLE INSPECTION TABLE 4.4-2A STEAM GENERATOR TUBE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sam le Size Result Action Re uired Result Action Re uired Result Action Re uired A minimum of C-1 S Tubes per S.G.
C-2 None Plug or repair.
defective tubes and inspect additional 2S tubes in this S.G.
N A C-1 C-2 C-3 N A None Plug or repair.
defective tubes and inspect additional 4S tubes in this S.G.
Perform action for C-3 result of first sam le N A N A C-1 C-2 C-3 N/A None N A N A
- t N/A Plug or repair.
defective tubes Perform action for C-3 result of first sam le C-3 Inspect all tubes in this S.G.,
plug or repair defective tubes and inspect 2S tubes in each other S.G.
Notification to NRC pursuant to Specification 4.4.5.5.c.
All other S.G.s are C-1 None N/A Some S.G.s C-2 but no additional S.G.s are C-3 Perform action for C-2 N/A result of second sample Additional S.G.
Inspect all tubes in is C-3 each S.G.
and plug or N/A repair defective tubes.
Notification to NRC ursuant to ecification 4.4.5.5.c.
N/A N/A N/A 9
S
=
1.
where n is the number of steam generators inspected during an inspection.
~
n Defective tubes which fall under the Alternate Tube Plugging Criteria do not have to be plugged or repaired.
CD TABLE 4.4-2B STEAM GENERATOR TUBE INSPECTION - TUBE EXPANDED IN PREHEATER REGION 1ST SAMPLE INSPECTION Sam le Size Result Action Re uired Result 2ND SAMPLE INSPECTION Action Re uired A minimum of S of the tubes expanded in the preheater section C-1 C-2 None N A C Plug or repair defective tubes C-1 and inspect all other expanded tubes in this Steam Generator N A N A Plug or repair defective tubes Perform action for C-3 result of first sam le I
CD C-3 Inspect all expanded tubes in this Steam Generator, plug or repair defective tubes and inspect all expanded tubes in each other Steam Generator.
Notification to NRC pursuant to Specification 4.4.5.5.c.
All other S.G.s are C-1 None Additional S.G. is C-3 Plug or repair defective tubes.
Notification to NRC pursuant to Specification 4.4.5.5.c.
One or more S.G.s C-2 but Plug or repair no additional defective tubes S.G
~ s are C-3 tD 9,
=
where n is the number of steam generators inspected during an inspection.
n
tA
e REACTOR COOLANT SYSTEM BASES STEAM GENERATORS Continued 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 crackinq.
The extent of cracking during lant operation would be limited by the limitation of steam generator tube eakage between the Reactor Coolant System and the Secondary Coolant System (reactor-to-secondary leakage
= 500 gallons per day per steam generator).
Cracks having a reactor-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 reactor-to-secondary leakage of 500 gallons per day per steam generator can readily be detected by radiation monitors of steam generator blowdown.
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and repaired or plugged.
Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant.
However even if a defect should develop in service, it
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will be found during schedu/ed inservice steam generator tube examinations.
Repair or plugging will be required for all tubes with imperfections exceeding the plugging limit of 40% of the tube nominal wall thickness.
This plugging limit does not apply to imperfections located below the F* region of any given tube.
The F* criterion can be applied only if the tube geometry in the region selected as the F* distance falls within the analytical limits of WCAP-128l6.
Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.
Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be reported to the Commission in a Special Report pursuant to Specification 4.4.5.5.c within 30 days and 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.
3 4.4.6.2 OPERATIONAL LEAKAGE PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.
Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.
SHEARON HARRIS - UNIT 1
B 3/4 4-3 Amendment No.