ML20094H580
| ML20094H580 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/05/1992 |
| From: | Withers B WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| WM-92-0035, WM-92-35, NUDOCS 9203110121 | |
| Download: ML20094H580 (23) | |
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LFCREEK W@ NUCLEAR OPERATING
~
Bart D, Withers cC$$$.ono, NNh 5,1992 M4 92 0035 U. S. Nuclear Regulatory Commission ATTN Document Control Desk Hall Station Pl-137
-Washington, D. C.
20555
Subject:
Docket No. 50-482 Inservico Inspect.fon Program Relief Requests Gentlemen The purpose of this letter is to trar. smit requests for relief from ASME Section XI requirements for the Wolf Creek Generating Station Inservice Inspection (ISi)
Program in accordance with 10 C/R 50.55a(g)(5)(iii).
Provided in the attachment are relief requerts which apply to ISI Feriods !.
and 2.
Relief Request IIR-23, Ilk-24, 11R-25, 11k-26-11R-27 I1R-20 and 11R-29 concern examinations required by ASME Saction KI.
11R-30 is associated with Wolf Cruk Nucient Operating Corporation's commitment to perform augmented examinations in addition to the examinations required by ASME Section XI.
UCNOC requests approval _of the relief requests prior to May 5, 1992 which coincides with the end of ISI Period 2.
If you have any questions conccrning this matter, please contact me or Mr.
S
.G. Videman of my staff.
Very truly yours, Bart D. Withers Presider.t and Chief Executzve Officer BDW/aen Attachment
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A. T. '!owell (MRC), w/a 7
- 1. D. Martin (NRC). w!a O. A. Pick (NRC), w/a l
W. D. Ecckley (NRC), w/a l
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9203110121 900305 i
PDR ADOCK O$000482 An EquM orcortunty Empk3yer M F HC-VET G
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Attachmsnt to V14 92'-003$
Page 1 of 22 TSI RELIEF _ REQUEST IIR-23 Components:
BB-01-F207 SB-01-F307 BB-01-F407
-BB-01-F305 RB-01-F405 BB-01-F306 BB-01-F203 BB-01-F303
,Ca t e nc ry :
B-J Descriq11on Reactor Coolant _Pamps
'B',
'C' and "D' Suction
- .o Elbow, Steam Generators 'C'Eand "D" Outlet Safe-End to Elbow, Steam Generator
'C' Outlet
?
Elbow to Crossover Leg Spool, and Reattor Pressure Vessel Outlet Nozzles
'B' and
'C' Safe-End to Pipe.
Code Reauif.emont :
Section-XI, Table IWB-2500-1, item B9.1 requires the inner 1/3t of the veld plus 1/4' of the base metal beyond the weld toe to be-3 scanned as shown by Figure IWB-2500-8.
Basis for Reliefs.
The transducers used to examine Cast Stainless Steel (CSS)
-were too large to maintain sufficient contact in the cirewmferential scanning mode (reference Figure 1).
They did,
- however, maintain adequate contact 1when~ scanning perpendicular to the weld axis.
Wolf Creek contends tha ?.
othet transducers may have maintained better contact along the weld crown, but1would not have provided as un effective examination.
This is=because the transducers used to examine this CSS material were designed specifically to enhance-the flaw detection capabilities.
The transducer size,- frequency, damping.. _ focusing and wave mode were 'all
-variables Loptinized.to provide the best. response in this coarse grain material.
When transducers deviate from this design and are used to send sound -into. CSS material --
it-is-' entirely _ probable that the returning-sound /rignal has been so altered by the effects of-scattering that any flaw indicatiens1-would be-masked by the. noise reflections caused by grain boundaries.
With welds P207.-F307,.F407, F305, F405 and F306, the weld crown end weld shrinkage' causes' transducer lift off.
.With welds F203 and F303, the weld
- taper causes transducer lift off.
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.c Attachment to M1 92-0035 Page,2 of 22
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Alternate Examination:
The code required volumetric examiration v!11 he completed p2rpendiculer to the veld axis from two (2F directions, a
ASME Code Section III:
Complete-ultrasonic examinations of these welds at 00 end 410 shewed no indications.
i.
Evaluation of Plant Safety _
Strict ASM3 Section III quality controls were used when designing.- fabricating and installing these velds.
In additxon, these welds -vere examined using ultrasonic equipment,. with no irregularities found.
-Any future indications of significant size vill be faund by the alternate examination and corrective action vill be taken.
A satisfactory level of safety to the plant and its personnel will be achieved by the alternate examination, i
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Attachment to WM 92-0033 Page 3 oE22 ISI RELIEF REQUEST 11R-24 Somr>onents -TEM 01-SEAM-2.W
.-paleRorY:
C.A t
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Description:==
Doron Injection Tank Upper Head to Shell Weld CodeReauffement:
Section XI, Table IVC-2!00-1, Item C1.20, requires the weld plus 1/2" of. the base motal on both sides of the weld be scanned as shown by Figure IWC-2500-1.
f-Basis for Relief:
The transducers used to examine Cast Stainless Steel-(CSS) material were too-large to maintain sufficient contact when running along the weld crown (cis cumferential examination).
Thus, resulting with 02 inspection using the ciremmferential scan (reference Figure 1).
I L-Wolf Creek contends that other transducers may have maintained better-L contact-along the veld crown, but would would not have provided.
as an effective examination. This is because the transducers used to examine this CSS material were designed apecifically to enhance the flaw detection
-capabilities.-
L
-The trans3ucer size, frequency, damping,_ focusing, and wave mode were all variables cptimized to provide-the best response in this coarve-. grain material.
When transducers deviate from this design and are used to send sound into CSS material, it is-entirely probable that the returning sound / signal has been so altered by the effects of. scattering that-any flaw
' indications'would be masked by the noise' reflections. caused by grain boundaries.
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Attachment to WM 92+0035 Page.4 of 22 Alternate -Examinatjsni
-The: code required volumetric examination will-be completed perpendicular to the weld axis fron two (2). directions.
ASME Code'Section III:
A completo ultrasonic examination was performed at an angle of 00 and approximately 50% of the veld was examined with angles of 410 These inspections revealed n'o indications.
- Evaluation of Plant Safety Strict ASME Section III quality controls were used when designing, fabricating and installing this weld.
This weld was ultrasonic inspected to the extent possible, with no irregulacities found.
The probability of a flaw occurring in the area not being examined io.
small-_
Most future indications of significant size will be found by examination of the weld as it la now.
t
't Based on the above, a satisfactory level of safety will be achieved without providing a complete examination of the mentioned wold.
The safety of the plant'and its personnel 19 not being compromised.
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e 94ttachment to WH 92-0035 Page=6.of 22
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-ISI-REblEF REQUEST 11R f
- j lopponents:
EJ-02-F022 Categorvi C-F 9
==
Description:==
12' Pipe to Residual Heat Removal. Heat Exchanger (EEJ01B) -B Inlet Weld 1
Code Reauirement:
Section X.1, Table _IWC-2500-1,' Item Number C5.11, requires 100I-surface examination of the-12" pipe-to heat-exchanger weld as-defined
-by Figure IWC-2500-7 Basis for Re lie,f.:
'The surface examination of the subject-weld I's 392 obstructed.by-a-1 1/2* by 1 5/8" ring.
The ring is.-welded-over the-downetream toe of the welds therefore, making it impossible to get the
-required _1/2' coverage beyond the toe of the weld.
To examine the
' obstructed ares would require physicelly_ removing the welded ring (reference Figure-1).
6 Alt'ernate Examination = None; the Code required surface exam 1+1ation will be completed to the matirr.um extent practical.'
' ASt4E code Section III.
biquid Penetrant enamination showed no indications.
The preservice examination was not t,ubjuct to the obstruction described above.
Evaluntion of' Plant Safety:
Strict.ASME Section-III quality controls were q
used t hen dnsigning.: fabricating and installing this. weld..
In addition,
-this weld _was liquid penetrant examlund, with no irtugularities found.
The probability of a flaiw occurring An the area -not- : being a examined ic ;. small.
~
.Most future indications of'aignificant site will be found by examination.of
-- the weldwas it is now.
Based on the'above,- a satisfactory level of wafety will be achieved without-providing a complete examination of the me'nticned weld.
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? Attachment to WM 92-0035 Page 7:of 22
.. 151 RELIEF REQUEST IIR-26 Component:
EJ-02-C020-Catenory_
0-0.
- p_p.g.cript i on
Integrh11v Welded Attachments - 8 Lugs h
E.2 e P erig!,rement Section XI, Table IWC-2500-1, Item Number C3.20 requires d
1002 surface examinations 01 each integrally welded attachment as definea by IWC-2500-5
,B a s i s,, f,0.J,R e l i e f The surfa,:e exantination of the subject integrully welded attachments _ (lugo) are 242 obstructed on too (2) of the lugs.
The obstruction is-a_ result of a permanent hanger that, is used to support -the Residual Heat. Removal (RHR) piping.
The diagonal supports of this hanger cross over the required inspection area on two of the lugs (reference Figure l
2).
Alterrap,t e rlxaminatign -None; the Code required surface-examination vill be completed to the reximum extent practical, ASME' Code-Section III:
Liquid Penetrant examination showed no indications.
The -preservice examination was not subject to the obstruction described above.
Ev_11ua t ion __of Pla nt S_a_f etY:
Stcict ASME Section III quality controls were used when designing,- fabrict, ting and installing those lugs.
In addition, these lugs: vere liquid penetrant examined, with no irregularities found.
The probability of a flaw occurring in the area not being examined is small.
'Most future indications of significant size vill be found by examination of the lugs as they are now.
- Ba set on.the above, a satisfactory level of safety will be achieved without providing a complete examination of-the mentioned lugs.
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-Attachment to WH 92 0035
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Page 8 of 22:
J ISI RELIEF REQUEST IIR-27 r
l Component TEM 01-SEAM-3-W l.
,qaterg gi C,A y
==
Description:==
Boron Injection Tank Bottom Head to Shell Veld Code Requirement:
Section XI, Table IWC-2500-1, Item Number C1.20, requires l
the weld plus 1/2* of the base metal on both sides-of the weld be scanned as j.
shown by Figure IWC-2500-1.
t Basis for Relief
~The volumetric examination of the subject veld is limited I
in~the following ways j-BEAM T0 WARD BEAM TOWARD L131TATIOES~
SHELL HEAD l
Weld Configuration
-57%
-33Z f
Leg Supports
-222
-25 Instrumentation !!ostle
- 4%~
- 52
'i-s
(-
-Total Weld _ Coverage-17Z 372 l
The circumferential 'examinntion was 1002 limited due to the weld
+
configuration.
_(reference Figures 3A through 3D-for the percentage breakdown).
t j-The transducers uoed to examine Cast Stainleen Steel (CSS) material were too
'Irrgo to-maintain sufficient contact uhen running along the weld crown.
-However,. Wolf Creek contends that other transducers may have maintained
[~
better contact along the weld _ crown, but would not have provided as an cifective examination.
This is because the transducers used.tc examine this i
i CSS material-were designed specifically to enhance thc' flaw detectior.
l
- capabilities.
-The traneducer sir.e, frequency, -damping,.focusin6, 'and wave mode were all l-variables optimized to. provide the best response.in-this coarse grain-l material._
When transducers deviate from this design and are used 'to send sound into CSS material, it is entirely probable that the returning-i sound / signal hr4 been so altered _by che effects-of_ scattering-that any_ flaw
. indications Ts uld be masked by the noise reflections caused:by grain
-boundaries.
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a Altornate Eu mination: Nonet-the Code required volumetric examinstion will be completed to the maximum extent possible.
ASME Code Section III:
A complete ultrasonic examination was performed at
-ani angle -of 00 The axial and circumferential scans were limited in the following:way:=
HEAD TO SHELL TO SCAN METHOD SHELL HEAD.
1 Axial
-402
-90%
Circumferential
.-40%
-907
-These inspections revealed no-indications.
-Evaluation of Plant Safety Strict ASME Section 111 quality controls were used when designing,- fabricating and installing these lugs.
This weld was ultrasonic inspected to the extent-possible, with no irregularities found.
i In addition to ultrasonic examination, a System Pressure Test (STS PE-044A) was-performed on the Boran -Injection-Tanh-in May of 1991, with..no
- ind.ications - of leakage' to the tank.
The upper' head to shell weld (TDIO1-SEAM-2-W) was ultrasonic inspected in Refuel Outage 3 -in the axial direction,= with no indications found.
Based-on-the above, a sativfactory level-of safety will be achieved without
- providing a complete examination of the f.entioned weld.
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Attachment to WM 92-0035' Page.10 of 22 4
Components ? EBB 01A SEAM-1-W catenory:
B-B
.,Qgs cri pt ion s. Steam Generator "A' Tubesheet-to-Channel Head Veld-pode Requirement:
Section XI Table IWB-2500 1, Item Number B2.40, requires 100Z volumetric examination of the Steam Generator Tubesheet-to-Channel Head Veld as defined by Figure IWB-2500-6 Basis for Relief:
The volumetric examination of the aubject weld is 22.4%
obstructed by four (4) supports.
The 600 axial scan on the tubecheet side is 20%. obstructed by the support flange.
The obstruction results from insufficient base metal between the weld and flange to complete this angle-beam examination.
There is approximately 12 obstruction due to veld taper and the' code data plate. Reference Figure 4 for veld layout.
Alternate Examination: Nones the Code required volumetric examination will be completed to the maximum extent practical.
ASME Code Section III:
Ultrasonic scans at 00, 450 and 600 showed no indications.
These preservice examinations wore subject to the obstructions
-deceribed above..
Evaluation of Plant Safety Strict ASME Section III quality controls were used when designing,- fabricating and installing this weld.
In addition, thJs veld was examined using ultrasonic equipment, with no irregularities l
'found.
The probability of a flaw occurring only in one of these areas not L
being examined isLextremely small.
Most future indications of significant i
sire will be found by examination of the weld as it is now.
~
Based on the above, a satisfactory level of safety will be achieved without providing a complete examination of-this weld.
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Attachment to WM 92-0035 Page,11-of-22 ISI RELIEF REQUEST 11R-29.
Component _ EBB 01C-SEAM-1-W Category:
B-B-
Description:
Steam Generator _"C" Tubeeheet-to-Channel Head Weld Code Reauirement:
Section XI. Table IVB-2500-1,- Item Number B2.40, requires 1002 volumetric examination of the Steam Generator Tubesheet-to-Channel Head Weld as defined by Figure IWB-2500-6 Basis for Relief:
The volumetric examination of the subject veld is 22.41 obstructed by four (4) supports.
The 600 axial scan on the tubesheet side is 30% obstructed-by the support flange..The obstruction results from
' insufficient base metal between the weld and flange to complete thic -angle beam examination.
There is approximately 1% obstruction due to weld taper and.the code data plate.
Reference Figure 5 for veld layout.
Alternate Examination: None the Code required volumetric examination will be completed to the maximum extent practical.
ASME Code Section III:
Ultrasonic _ scans at 0,
450 and 600 showed no 0
indications.
These preservice examinations w9re subject to the_ obstructions described above.-
Evaluation of Plant _ Safety - _ Strict ASME Section III quality controls were used_when designing, fabricating and installir: thic weld.
In addition, this weld was examined using_ ultrasonic equipment,. with no irregularities found.
The probability of a flaw occurring only in one of these areas not
',i being. examined is ~ extremely emall.- -Host future indications of significant-
.aize will be found by examination of the weld as it is now.
Based on the.above, a satisfactory level of safety will be achieved without providing a complete examination of this weld.
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1 Attachment to VM 92i0035
- PageL12 of 22" ISI RELIEF REQUEST IlR-29 Cpmnonentsl TBB03-10B-C-W and TBB03-10B-D-W Cuepp1xs B-D Rencriptiont Pressurizer Nozzle to Pressurizer Vessel Head Welds Code Requirement:
Section X1, Table-IWB-2500-1 Item Number B3.110, requires 1002 volumetric examination of the Pressurizer Nozzle to Preneuriser Vessel !!ead Veld, as defined by Figure lWB-2500-7.
Basis for Relief Pressurizer Nor.zle weld taper and base metal taper near-the nozzle causes the transducer to lift off. As a_ result, a portion 91.the weld required volume (WRV) receives no sher.r wave examination.vhen using 450 0
and 60 angle beams.
This:was observed when examining Nozzle to Vessel Velds TBB03-10B-C-W and TBB03-10B-D-W.
For both welds, 157 of.the WRV could 0
not be scanned using a 45 angle beam, and 11.5Z of the WRV could not-be 0
scanned using a 60 angle beam.
Alternate Examination: None the Code required volumetric examination will be. completed to.the-maximum extent practical, t
.ASME Code Section III:
Complete ultrasonic scans at 0,
450 and 600 showed 0
geometrical indications only.
Evaluntion of-Pl ant S a f et ',s.
Strict ASME Section III quality controls were used when designing. -fabr:.cating and' installing these welds.
In addition, these welds were examined using ultrasonic equipment,
showing only geometrical indications.
The probability of a flaw occurring only in one of these areas not being examined is extremely small.
Most future indications of nignificant size will be=found by examination of the velds as they-are
= now.
Based on1the'above, a satisfactory level of safety will be achieved without providini a complete examination of the mentioned-welds.-
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O Attachment to WM 92-0035 Page 13 of 22
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ISI RELIEF REQUEST 11R-30 (Augmented)
Component, PDB01B-FLYWHEEL Cp t.egy.u:
Nil.
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Reactor Coolant Pump *E" Flywheel Code Reautrement:
Augmented examination for compliance with Regulatory Guide 1.14 Reactor Coolant Pump Plywheel Integrity, Section C.4 requires surface examination of all esposed surfaces Basis for Relief:
The Jurface examination of the subject Flywheel is 3%
obstructed by a seal ring that is located on the bottom side of the Flywheel (reference Figure 6).
Tight clearances are required for seal ring location.
This ring reduces the vacuum effect produced by the rotating flywheel in order to prevent oil from being sucked out of the oil reservoir stand pipe. After the ring is set, it shou!d not be moved unless absolutely necessary.
Alternate Examination:
None; the Code required surface examination will be completed to the maximum extent practical.
ASME Code Eection III:
This is the Preservice Inspection ExamJnation.
No rejectable indications were found.
There were four (4) small (1/16' and less) rounded surface (penetrant exam) indications found in the Core Area and Keyways.
Evaluation of Plant Safety:
The Flywheel was examined to the f,ullest extent possible, utilizing UT, MT and PT examination methods. The probability of a finw occurring in the stea not being exmmined is extremely small.
Based on the above, a satisfactory level of safety will be achieved without providing a complete examination of the Flywheel.
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