ML20096G784
| ML20096G784 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/06/1984 |
| From: | Seiken S STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| SLNRC-84-112, NUDOCS 8409110137 | |
| Download: ML20096G784 (14) | |
Text
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',a L t SNUPPS
- Standardized Nuclear aJnit Power Plant System
!i Choke Cherry Road RockviNo, Maryland 20050 con seSaoio September 6, 1984 SLNRC 84-112 FILE: 0541/M-189 SUBJ: Preservice Inspection Relief Request - Wolf Creek Plant Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation US ~ Nuclear _-Regulatory Commission Washington, D.C. 20555 Docket No.: STN 50-482
Dear-Mr. Denton:
Enclosures A - F provide data in support of a request for relief from preservice examination (volumetric and visual) requirements for selected Wolf Creek component and piping systems.
Enclosure G provides data in support of a volumetric examination relief request for 18 branch connection welds in the Reactor Coolant System. With exception of partial relief requests required for certain weldments in the Wolf Creek
, Reactor Pressure Vessel', no additional volumetric examination relief requests are anticipated.
A supplemental submittal in support of the Wolf Creek ' Reactor Pressure Vessel preservice examination relief request is being finalized and will be forwarded to'the NRC by Sept. 15, 1984.
Very truly yours,
~
8409110137 840906 gDR ADOCK O m S.
Seiken, Manager Quality Assurance SJS/dck/8a19.
Enclosures:
A thru G cc:
G. L. Koester, KSE J. M. Evans, KCPL D. F. Schnell, UE J._H._Neisler/B. H. Little, USNRC/ Cal H. Bundy, USNRC/WC D.-R. Hunter,.' Region IV B. L..Forney, Region III i
R. C. DeYoun, USNRC/IE:HQ
\\
B. Brown, EG Idaho cP
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- q, r.
L SLNRC 84-11'2.
Page Two.
bec:'J.1;A.1 Bailey,KGE/WC
- D. W._-Capone, UE-
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J.'. A. - Holla'nd, ;- KGE/WC -
.D. E. Shafer,'UE-MJ A. Hannah, KGE
- J.;H. Smith, 8 JR. A. Love,' NES-i f '..
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ENCIASURE A System: Main Feedwater Component I.D.
' Category Description Code Requirement Basis For Relief 1-AE-05-FW302 CF 14" Valve to 14" Pipe.
. Volumetric examination Valve geometry and'sockolet by scanning both sides obstruction affects scan i
of weld path. 5% loss of volume coverage.
i l
1-AE-05-F020 C-F -
14" Valve to 14" Pipe Volumetric examination Valve geometry and sockolet by scanning both sides obstruction affects scan of weld path. 5% loss of volume I
covarage.
~
1-AE-04-F020 C-F 14" Valve to 14" Pipe Volumetric examination Valve geometry and sockolet by scanning both sides obstruction affects scan of weld path. 5% loss of volume i
coverage.
1-AE-04-F005 C-F 14" Valve to 14" Pipe Volumetric examination Valve geometry and sockolet on by scanning both sides pipe side' obstructs scan path.
of weld 5% loss of volume coverage.
i i
1-AE-04-F033 C-F 4" Elbow to 4" Valve Volumetric examination Valve geometry obstructs scan l
by scanning both sides path loss of transducer contact.
4 of weld on the elbow inner radius.
I 10% loss of volume coverage.
I l
1-AE-05-F031 C-F 4" Elbow to 4" Valve Volumetric examination' Valve geometry obstructs scan I
by scanning both sides path loss of transducer contact I
of weld on the elbow inner radius.
10% loss of volume coverage.
i 1-AE-04-F031 C-F 4" Elbow to 4" Valve Volumetric examination Valve geometry obstructs scan
{
by scanning both sides path. Loss of transducer contact of weld on the elbow inner radius.
10% loss of volume coverage.
j System: High Pressure Coolant Injection s
i 1-EM-02-S008-M C-F 6" Tee to 6" Pipe Volumetric examination Tee geometry obstructs scan by scanning both sides path. Limited scan due to' lug of weld obstruction on pipe side. 5%
loss of volume coverage.
- =
a ENCLOSURE B System: Steam Generator Component I.D.
Category Description Code Requirement.
Basis for Relief' 1-EBB 01A-SEAN-C-A Tube Sheet to Stub 100% Volumetric.
Flange obstruction limiting scan 2-W Barrel Examination length on tube sheet side. Three latches, instrumentation.. nozzle and I.D. plate obstructing scan I
path on stub barrel side. 5% loss j
of volume coverage at 60%&45*.
l 1-EBB 01A-SEAM-C-A Trdnsition Cone to 100% Volumetric Four instrumentation nozzles, two i
6-W Shell Section C Examination lugs, guages and a feedwater i
nozzle obstructing scan path.
5% loss of volume coverage at 60' scan angle and 10% at a 45' scan i
angle.
1-EBB 01A-SEAN-C-A Shell Section D to 100% Volumetric Loss of transducer contact due to l
8-W Top Head Examination transition section, lug and guage obstructions.
10% loss of volume
[
coverage.
1-EBB 01A-SEAM-C-A Shell Section B 100% Volumetric Loss of transducer contact due to 5-W to Transition Cone Examination transition section and two guages.
10% loss of volume coverage at 60' I
and 5% loss of volume at 0*.
f-1-EBB 01A-SEAM-C-A Stub Barrel to Shell 100% Volumetric Loss of transducer contact due to 3-W Section A Examination transition section and two guages.
10% loss of volume coverage.
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ENCLOSURE C System: Reactor Coolant Category:
-C-F
. Component
Description:
Component Description Reactor Coolant Pump D Seal Component Identification Water Injection Line Welds 1-BG-09-W790 2" X 1h" Reducer to 1 " Pipe 1-BG-09-FW879 1 " Pipe to. Valve 1-BG-09-FW880 Valve to lh" Pipe 1-BG-09-W859 1 " Pipe to 2" X 1 " Reducer Reactor Coolant Pump A Seal Water Injection Line Welds 1-BG-09-W686 2" X 1 " Reducer to 1 " Pipe 1-BG-09-W881 1 " Pipe to Valve 1-BG-09-FW882 Valve to 1 " Pipe 1-BG-09-W779 1 " Pipe to 2" X 1 " Reducer Reactor Coolant Pump C Seal Water Injection Line Weld _s 1-BG-09-W806 2" I 1 " Reducer to lh" Pipe 1-BG-09-FW877 1 " Pipe to Valve 1-BC-09-FW878 Valve to lh" Pipe 1-BG-09-W807 1h" Pipe to 2" X 1 " Reducer
-Reactor Coolant Pump B Seal Water Injection Line Welds 1-BG-09-W814 2" X 1 " Reducer to i " Pipe 1-BG-09-FW875 1 " Pipe to Valve 1-BG-09-FW876 Valve to lh" Pipe 1-BC-09-W696 1 " Pipe to 2" X 1 " Reducer Code Requirements:
Volumetric examination of these welds not required by Code.
Areas For Relief:
Volumetric examination of piping welds.
Basis For Relief:
Combination of small pipe diameter and minimum wall thickness cause volumetric examination to be meaningless.
Alternate Testing:
Penetrant Testing.
. - - - ~.
ENCI4SURE D Systems Essential Service Water System
' Category:
D-A Component
Description:
Pump Supports K-EFil-R005, K-EFil-B003, K-EFil-R001 K-EF11-k006, K-EF11-B004, K-EFil-ROD 2 Code Requirement:
Visual Examination - 3 Areas for Relief:
Entire Examination Basis for Relie7:
The pump supports are inaccessible due to their submersion within the Essential Service Water Pump Pit.
Alternate Testing:
None
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4, ENCIDSURE E-System:
Fuel Pool Cooling and Cleanup Categoryt D-C Component
Description:
Pipe Supports 1-EC-04-R026, 1-EC-04-R027, 1-EC-04-R029, 1-EC-04-R030 Code Requirement:
Visual Examination - 3 Areas for Relief:
Entire Examination Basis for Relief:
These pipe supports will be submerged in the spent fuel pool during the life of the plant.
Alternate Testing:
None k
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ENCLOSURE F Syrtem: Pressurizer Description Code Requirement Basis for Relief Component I.D Category 1-TBB03-4-W B-F Relief Nozzle to Component undulations restricting search Safe-end Weld Volumetric examination unit movement and metal structure of by scanning both sides inconell buttering inhibiting shear of weld.
wave transmission. 20% loss of volume coverage with a 60* axial scan and a 45%
loss of volume coverage with a 45* axial scan.
1-TBB03-3-A-W B-F Safety, Nozzle to Volumetric examination Component undulations restricting search Safe-end Weld by scanning both sides unit movement and metal structure of of weld.
inconell buttering inhibiting shear wave transmission.
50% loss of volume l
coverage with a 60* axial scan and a 35%
loss of volume coverage with a 45* axial scan.
1-TBB03-1-W B-F Surge Nozzle to Volumetric examination Component undulations restricting search Safe-end Weld by scanning both sides unit movement and metal structure of of weld.
inconell buttering inhibiting shear wave transmission.
15% loss of volusu coverage with a 60* axial scan and a 40%
loss of. volume coverage with a 45% axial scan.
1-TBB03-3-B-W B-F Safety Nozzle to Volumetric examination Component undulatiors restricting search Safe-end Weld by scanning both sides unit movement and metal structure of of weld.
inconell buttering inhibiting shear wave transmission.
55% loss of volume coverage with a 60* axial scan and a 40%
loss of volume coverage with a 45* axial
- scan, 1-TBB03-2-W B-F Spray Nozzle to Volumetric examination Component undulations restricting search Safe-end Weld by scanning both sides unit movement and metal structure of of weld.
inconell buttering inhibiting shear wave transmission. 10% loss of volume coverage with a 60* axial scan and a 40%
l loss of volume coverage with a 45' axial q
scan.
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ENCIDSURE F
[
CONT'D Syrtem: Pressurizer Description Code Rcquirement Basis for Relief l'
Component I.D Category.
I-1-TBB-03-3-C-W B-F Safety Nozzle Volumetric examination
-Component undulations restricting search to Safe-end Weld by scanning both sides unit movement and metal structure of of weld.
inconell buttering inhibiting shear wave transmission.
20% loss of volume coverage with a 60* axial scan and a 404 loss of volume coverage with a 45*. axial scan.
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1 ENCLOSURE G RELIEF REQUEST FOR THE VOLUMETRIC PRESERVICE INSPECTION -
WULF CREEK-REACTOR COOLANT i
5YSTEM BRANCH CONNECTIONS I.
ASME CODE SECTION XI REQUIREMENTS!
In Section XI,1977 Edition / Summer 1978 Addenda, Table IWB-2500-1, examination Category BJ, item 89.31 requires a surface and volumetric exanination of regions described in Figures IWB-2500-10 and 11, for i
branch connection piping 2" nominal pipe size and greater. However,
- the above code does not define the specific weld. volume required to be exanined. To address this lack of definition, Figure IWB-2500-8 was used as a guideline to define the examination volume of the branch connection welds.
Figure 01 corresponds to Figure IWB-2500-8 of the Code and Figures 02 and 03 correspond to Figures IWB-2500-10 and 11, respectively, with the modifications as stated above.
The preservice inspection examina-tions were performed to ultrasonically exanine the defined volumes in i
Figures 02 and 03.
II. SPECIFIC RELIEF REQUEST Relief is requested from performing volumetric examinations of 18 branch connection welds on the primary loops of the Reactor Coolant System. The welds are identified in Table I along with identifica-tion of the. type of weld (referring to the weld configuration in the attached figures). Branch connections for the accumulator discharge lines are butt welded to the' reactor coolant loop piping and are not included in this relief request. All branch connections to.the reactor coolant loop piping are covered by this relief request, with the_ exception of the accumulator discharge lines as noted above.
--III.. BASIS FOR RELIEF Due to the materials of construction (austenitic) and the design and fabrication geometry of corner type branch connections depicted in attached Figures 02 and 03, it is concluded that meaningful examina-tion by ultrasonic methods is not feasible and that no other practical volumetric method is available.-
IV. ALTERNATE TEST METHOD As an alternative, VT-2 examinations for leakage will be conducted in accordance with IWA-5240. These will be carried out during the leakage test -specified under IWB-5221. The combination of required surface examination, visual examination for leakage and the Code required fabrication examinations will establish the integrity of the as-built pressure boundary.
SJS/dck24b6
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7 Enclos'ure1G : (contd)
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Table I (h
-BRANCH CONNECTION WELOS VOLUME in
- Item-
- W WELD ~ #.
.KGE WELD #
SIZE ~
UNEXAMINABLE. TYPE OF WELD Loop 1-
~
- 1
'15 1BB 01 S102-3 12" 20%
Figure 03 l2-17' 1BB 01 S105 3" 75%
02
'3-19 188 01 S101-5 4"
60%
02 4-
" 21 188 01 S101 3" 75%
03 15-22
.1BB 01 S101-9 3"
75%
02 Loop 2
^.
6;
-15 18B 01 S202-3 6"
55%
03
.7-17 188 01 S205-5 3"
75%
02 38' il9 188 01 S201 4" 60%
02 9-t21:
' 18B 01 :5201-8 3"
75%
02 --
-Loop 3
~10 15 188-01 S302-3 6"
55%
. 03 -
.11 -
-17 188-01 S305-5
-3" 75%.
02-12
~21 188-01 S305-6 3"
.75%
- 03 13 20 4
'188-01 S301-5 3"
75%
03 Loop.4 11
'15 188-01 5402 14" 10%'
03 4
115'
- 161 188-01 S402-4 12" 20%' 161
- 18-188-01 S405-5 3"
75%
02
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17-
-20 IBB-01 S401-5 3"
75%
02 18
~ 22 IBB-01 S401-6 3"
75%
02
- fSJS/dck24b10 '
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ENCLOSURE G (contd) 6 f
WESTINGHOUSE ELECTRIC CORPORATION
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FIGURE 01 ru.umams oaa RtrtRENCE TABLE 1 SIMILAR AND DISSIMILAR METAL WELDS IN PIPING
_ SURF. EX AM. AREA _
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PROFILE OF VALVE BODY,
[jPUMP CONNECTION VES5EL N0ZZLE, OR 3
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NOM. PIPE SIZE LESS THAN 4 IN.
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A-B PROFILE OF VALVE BODY,
( VE5SEL N0ZZLE, OR PUMP CONNECTION
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ENCLOSURE'G (contd) i
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t WESTINGHOUSE ELECTRIC CORP 5 RATION 2""* **
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FIGURE 03
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REFERENCE TABLE 1
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