ML20094F374
| ML20094F374 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 02/07/1992 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML18010A533 | List: |
| References | |
| NLS-92-017, NLS-92-17, NUDOCS 9202240133 | |
| Download: ML20094F374 (14) | |
Text
SERIAL:
NLS + 92 Ol ?
ENCLOSURE 4 SilEARON llARRIS NUCLEAR Pok'ER PLANT NRC DOCEET No. 50 400/ LICENSE NO, NPF-63 REQUEST FOR LICENSE AMENDMENT STEAM GENERATOR F* TUBE PLUCGING CRITl:RIA TECHNICAL SPECIFICATION PAGES t
5 6
L 9202240133 920207 PDR ADOCK 05000400 P-PDR
t REACTOR CCOLANT SYSTEM STEAM GENERATORS SURVEllt.ANCE REOUIRESENTS (Continued) 4.4.5.2 (Continued) 3.
A tube inspection (pursuant to Specification 4.4.5.4a.8) shall be performed en each selected tube.
If any selected tube does not pensit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tuce 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 say be sub-jected to a partial tube inspection provided:
1.
The tubes selected for these samples include the tubes from those areas of *,he 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 site, second sample size and subsequent inspection shall follow Table 4.4-25.
g l
The results of each sample inspection sna11 be classified into one of the following three categories:
Categorv 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 L'; of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraced tubes.
C-3 More than 10% of the total tubes inspected are degraded tubes or more than N of the inspected tubes are defective.
Note:
In all inspections, previously degraded tubes must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.
ww - y e
In addition to the 3% s anipl e, all tubes for which the alternato pluB6 ng criteria (F*) has been previously applied shall be 1
.~
SHEARON HARRIS - UNIT 1 3/4 4-14 frncnedrnm* b*
W'e-y,rv rg--
.y m
e--
yyv-
,gw,-
tv-v w----
p y,
r.
9 r-q w
w.--
.y mz 7
.er-- + + -
m
~ - _.
REACTOR COOLANT SYSTDi 4
STEAM GENExATOR SURVElt. LANCE RE0VIREMENTS (Continued) 4.4.5.4 Acceotance Criteria a.
As used in this specification:
1.
Isoerfection means an exception to the dimensions, finish, or contour of a tuba from that r. quired by f abrication drawings or speci fications.
Eddy-current tasting indications below 2C% of the nominal tube wall thickness, if detectable, say be considered as imperfections; 2.
Degradation means a service-induced cracking, wastage, wear, or general corrosion occurring on either inside or outside of a tube; 3.
Oecraded Tube means a tube containing imperfections greater tnan or equai to 20% of the nomihal wall thickness caused by degradation; 4.
% Degradation means the percentage of the tube wall thickness affacten or removed by degradation; 5.
Defect means an imperfection of such severity that it exceeds tne plugging limit. A tube containing a defect is defective; 6.
Pluonino limit means the imperfection depth at or beyond which tne tune snall be removed from service and is equal to 40% 'A 1 l
of the nominal tube wall thicknessf, (Ingr/ from M&/ f 7.
Unserviceable describes the condition of a tube if it leaks or contains a cef act large enuugn to affect its structural integ-rity 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 4.4.5.3c., above; 3.
Tube Insoection means an inspection of the staan generator tube from tne point of entry (hot leg side) completely around the U-bend to the top support of the cold leg; and Preservice Inspection means an inspection of the full length of 9.
eacn tune in eacn steam generator performed by eddy current techniques prior to service to establish a baseline condition This inspection shall be performed prior to of the tubing.
initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
m.
(fnytt from Met + fage )
he'n NW ? N II.
(Zn' rt A
N0' SHEARON HARRIS
- UNIT 1 3/4 4-16
/loyAdnMM
..m.
.m.
____.._m_.-.__-...
1 3
.l i
4.4,$.4.a.
Inserts:
i 6.
This definition does not apply to the area of the tubes.heet region j
4 below the l'*
Distance provided the tube is not degraded (i.e.,
no indications of cracking) within the F* Distance.
10.
F*
Distance is the distance into the tubesheet froin the face of 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.
11.
Alternate Tube Plurrinr. Criteria does not require the tube to be removed l
from service or repaired when the tube degradation exceeds the pluggi"6 limit so long as the degradation is in that portion of the tube from F* to the bottom of the tubosheet. This definition does not apply to tuber with degradation (i.e., indications of crackinB) in the F* Distance.
i i
i t
(
?
,, m ~,,.m m m w, r-,---,,--r--.-
,w,
~v,,,-,-en,-.-new,--,-..-----r.-
-wa.--.,
.. ~. -. -...__- - - - -..-.-
-STEAM CENERATOR SURVEILLANCE gEOUIREMENTS (Continued) 4.4.5.4 AcceptanceCriteria(Condnue,d,),
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plus all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Tables 4.4-2A and B.
4.4.5.5 Reports t
Within 15 days following the courpletion of each inservice inspection a.
of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission in a 8pecial Report t
pursuant to Specification 6.9.2L b.
The complete results of' the steam generator tube laservice 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 includes 1.
Number and entent of tubes inspected, 2.
Location and percent of wall-thickness penetration for each indication of an imperfection, and 3.
Identification of tubes plugged.
Results of steam generator tube inspections which fall into Category c.
C-3 shall be esported in a Special Report pursuant to.
Specification 6.9.1 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.
d.
The results of inspections 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 si::e of the degradation NRC approval of this report is not required prior to restart.
SHEARON HARRIS - UNIT 1 3/4 4-17 Amendment Wo. }
IABIE 4.4-2A 51EAll GENERA 10R Ill3E INSPICIICH g
C E
IST SAMPLE INSP[ cit 0N 2HD SAMPit IH5PICil0N 3RD SAMPLE INSPICTIols j
Sample Size Result Action Required Result iction Required Result Action Ecquired 1
so U
A minista C-1 Hone l N/A N/A H/A II/A e
of 5 lubes Y
g per 5.G.
Plug defective tubes h C-1 N/A l
f H/A C-2 Hone i
G and inspect additional 25 tubes in this 5.G.
Plug defective tubes 9 C-1 Hone
/l e
C-2 and inspect additional p
45 tubes in this 5.G.
C-2 Piug defective tubes O l Perform n iton for C-3 C-3 result of first sample Perform action u.
D C-3 f or C-3 result of H/A li/A first sample
.G C-3 Inspect all tthes in -
All other this 5.G., plug de y 5.G.s are Hone N/A II/A I
fective tube dand C-1 inspect 25 tubes in each other 5.G.
Some 5.G.s Perform action for N/A il/A C-2 but no C-2 result of second i
additional sample 3
HalifIcation to NRC 5.G.s are n3 pursuant to spect-C-3 R
fication 4.4.5.5.c.
t Additional Inspect all tubes in t
5.G. Is C-3 eacti 5.G. and plug defective tut *esd U d
Hatificatton to NRC N/A N/A F
pursuant to Spect-fication 4.4.5.5.c.
5 = f% where n is the number of steam generators inspected during an inspection.
y
- De fe c t ive tubes which fall under the Alternate Tube Plugging Criteria do not have to be plugged.
1
?
^ - -
nn m
r This plugging l i tu t
- does not apply to fitperfectionsh
- DCTOR COOLAMT SYSTEM located below the f* region of any given tube.
The r*
criterion can be applied only if the tube geornetry in the region selected as the F* distance falls within the BASES analytical liitits of LTAP.12816.
^ _4
~_.n _. ~m m-STHMGENEeATCRS(Continceo},
k The plant is expected to be operated in a manaer such that the secondary coo gible corrosion of the steam generator tubes. ant will be maintained If the seconcary coolant chemistry is not maintained within these Ifmits, localized corrosion may 11hly result in stress corrosion cracking. The extant of cracking during plant oper-ation would be 11mitad by the limitation of steam generator tube leakage between the Reactor coolant Systar and the Secondary Coolant Systas (reactor-to-seconcary leauge = 500 gallons per day per staam generator). Cracts having a reactor-to secondar/ leakage less than this limit during operation will have ah adequata margin of safety to withstand the loads imposed during normal operation and by postulated accidents.
Operating plants have demonstratad that reactor-detected by radiation monitors of steam generator blowcown.to s wnich the leaking tuces will be located and plugged.of this limi Leakage in excess Wastage-type defects are unlikely with proper chemistr/ treatment of the second-ary coolant.
However, even if a cefect should develoo in service, it will be found during schedulee inservice steam generator tube examinations. Plugging will be required for all tubes with imperfections exceeding the plugging limit of 4C of the tuce nominal wall thickness. GLas eenerator tube inspections of operating plants have demonstrated the capability to r 11a6Ty cetect degra- /
dation that has penetratad 2C of the original tube wall thickness.
Whenever the results of any staas generator tubing inservice inspection fall into Categor/ C-3, these rtsults will be reported to the Ccanission in a special Report pursuant to Specification 4.4.5.5.c within' 30 days and prior to resumo-tion of plant operation.
Such cases will be considered by the Ccamission 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 CCOLANT SYSTEM LEAKAGE 1/4.a.6.1 ' LAKAGE OETEC ION
- SYSTEMS The RCS Leakage Detection Systans required by this specification are provided to monitor and detect leakage from the reactor coolant pressure boundary.
These Detection Systaes are consistant with the recommendations of Regulatory Guice 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems,"
May 1973.
3/4.4.6.2 OPE' RATIONAL 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 LEAXAGE requires the unit to be promptly placed in COLD SHtrTDCWN.
SHEARCN HARRIS - UNIT 1 8 3/4 4-3 bW W M.
PFACTOR COO 1 ANT SYSTEM STPAM CENFP.ATORS SURVEI1.1ANCE REOUIREMENTS (Continur_d) 4.4.5.2 (Continued) 3.
A tube inspection (pursuatt to Specification 4.4.5.4a.8) shall be performed on each selected tube.
If any selected tube does not permit the passage of, he eddy current probe for a tube inspection, this shall be ricorded and an adjacent tube shall be selected and subjected to a tube inspection, c.
The tubes selected as the second.nd third samples (if required by Tables 4,4 2 A and B) during each lnservice inspection may be sub-jected to a partial tube inspection provided:
1.
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with impertections 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 28.
In addition to the 3% sample, all tubes for which the alternate e.
plugging criteris (F*) has been previously applied shall be inspected in the tubesheet region.
The results of each saaple inspection shall be classified into one of the foll.owing three categories:
Caterory Insnection Results C1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C2 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 de5raded tubes.
C3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
Note: In all inspections, previously degraded tubes must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.
SHEARON HARRIS UNIT 1 3/4 4 14 Amendment No.
REACTOR C001 ANT SYSTEM ETEAM CENERATORS SURVEILIANCE REOUIRD4ENTS (Continued) 4.4.5.4 Acceptance Criteria a.
As used in this specification:
1.
Ienerfecti2D means an exception to the dimensions, finish, or r
contour of a tube from that required by fabrication drawings or i
6pecifications.
Eddy. current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections; 2.
Derradation means a service induced cracking, wastage, wear, or general corrosion occurring on either inside or outside of a tube; 3.
Derraded Tube means a tube containing imper.'ections greater than or equal to 20% of the nominal vall thickness caused by degradation; 4
4 Detradation means the percentage of the tube wall thickness affected or removed by degradation; 5.
Defect means an imper;
.on of such severity that it exceeds the plugging limit. A tube containing a defect is defective; 6.
Pluggine Limit means the imperfection depth at or beyond which the tube shall be removed from service and is equal to 40% of the nominal tube wall thickness.
This definition 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.
7.
Unearviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integ-rity 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 4.4.5.3c,, above; 8.
Tube Insocetion means an inspection of the steam Senerator tube from the point of entry (hot leg side) completely around the U. bend to the top support of the cold leg; and 9.
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 prior
) initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
1 S!!EARON RARRIS UNIT 1 3/4 4 16 Amendment No,
REACTOR C001 ANT SYSTEM STEAM GENERATORS SURVEILLANCE REQUIREMENTS (Continued)
- 10. F* Distance is the distance into the tubesheet from the face of 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.
- 11. Alternate Tube Pluctine Criteria 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 F* to the bottom of the tubesheet.
This definition does not apply to tubes with degradation (i.e.,
indications of cracking) in the r* distance.
r e
l 4
?
s e
l SHEARON HARRIS UNIT 1 3/4 4 16a Amendment,s
REACTOR COO 1 ANT SYSTEM IIfdji OENERATORS
{
SURVEILIANCE REOUIRD(ENTS (Continued) 4.4.5.4 Accentance Criterin (Continued) b.
The steam generator shall be determined Opr.RABLE after completing the corresponding actions (plus all tubes exceeding the plugging liteit and all tubes containing through. wall cracks) required by l
Tables 4.4 2A and B.
4.4.5.5 Etoorts 3
Within 15 days following the completion of each inservice inspection a.
of steam generator tubes, the number of tubes plugged in each stears generator shall be reported to the Commission in a Special Report-pursuant to Specification 6.9.2; b.
The complete results-of the steam generator tube inservice inspection shall be submitted to the Cominission 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 inspected, 2.
Location and percent of wall thickness penetration for each indication of an imperfection, and 3.
Identification of tubes plugged, Results of steam generator tube inspections which fall into Category c.
C 3 shall'be reported in a Special Report pursuant to Specification 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.
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 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 liARRIS UNIT.1 3/4 4 17 Amendment No.
i TABLE 4.4-2A 1
n.-.. GENERATOR "MBE INSPECTION w*
IST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION g
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 1
S.C.
C-2 Plug defective tubes
- C-1 None N/A N/A l
and inspect additional l
4 2S tubes in this S.C.
e.*
C-2 Plug defective tubes
- C-1 None l
and inspect additional l
45 tubes in this S.G.
C-2 Plug defective tubes
- l C-3 Perform action for C-3 result of first sample w
l
)
C-3 Perform action for C-3 N/A N/A y
result of first sample U
C-3 Inspect all tubes in All other this S.C.,
plug de-S.C.s are None N/A N/A fective tubes
- and C-1 I
inspect 25 tubes in each other S.G.
Some S.C s Perform action for N/A N/A C-2 but no C-2 result of second additional sample S.C.s are Notification to NRC Pursuant to Speci-Additional Inspect all tubes in fication 4.4.5.5.c.
S.C.
is C-3 each S.C. and plug h
defective tubes.*
l m
Notification to NRC N/A N/A f
4 f
pursuant to Speci-g fication 4.4.5.5.c.
- l% where n is the number of steam generators inspected during an inspection.
S Defective tubes which fall under the Alternate Tube Plugging Criteria do not have to be plugged.
l
REACTOR COQiANT SYSZfd J
EASES STEAM CENEPATORS (Continued)
The plant is expected to be operated in a manner such that the secondary cool.
ant will be maintained within those chemistry limits found to result in negli-gible corrosion of the steam generator tubes.
If the secondary coolant 4
chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking.
The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the Reactor Coolant System and the Secondary Coolant System (reactor to secondary leakage - 500 gallons per day per steam Benerator).
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 i
shutdown and an unscheduled inspection during which the leaking tubes will be located and plug 6ed.
Vastage type defects are unlikely with proper chemistry treatment of the secondary coolant.
However, even if a defect should develop in service, it will be found during-scheduled inservice steam generator tube examinations, plugging will be required for all tubes with imperfections exceeding the plug 6 ng limit of 40% of the tube nominal wall thickness.
This pluggin6 limit t
does not apply to imperfections located below the F* region of ar,y 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+12816.
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 Specifica; ion 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 C001 ANT SYST2M LEAPACE 3 /4. 4. 6.1 LEAPACE DETECTION SYSTEMS The RCS Leakage Detection Systems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure boundary, f
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 LEAVACE l
-PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.
Therefore.
l the prevnnce of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTD0VN, i
l l
SHEARON HARRIS UNIT 1 B 3/4 4-3 Amendment No.
i l
~_-,_a_
~
Sl: RIAL.:
tJLS97-017 LNCLOSURL 5 SitEARON llARR1S NUCl.I'AR l'OWER l'l.A!iT NRC f)oCKET NO. 50 400/LICI:NSE NO, tipi'+ 6 3 REQUEST FOR LICENSE AMENDMI: fit STEAM GENERATOR F* TUBE l'1,0GG!NG CRITERIA WCAP 1281h WCAP 12817 Wm.tJnrhouse Aut horir.ation 1.et t < r (LLL1110 Lit 1
Propriet nry 1tiformat ton Notle Copyright Notice T
1 i
I l
,. -. -..,.-, _., _. _ _.,,,,., _.. _. _ - _ - _ _., _ _ _. _ _ _ _. _. _,. - _ _ _ _ _,. - - _. _. - _ _ - _ _.. - _ _ _ _ _ _ ~ -