ML20138F879

Forwards Addl Info Supporting Requests for Relief from Inservice Exam Requirements for Selected Component & Piping Sys,Two Branch Connection Welds in RCS & Partial Relief Request for Reactor Pressure Vessel

ML20138F879
Person / Time
Site:	Wolf Creek
Issue date:	12/11/1985
From:	Koester G KANSAS GAS & ELECTRIC CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
KMLNRC-85-268, NUDOCS 8512160188
Download: ML20138F879 (19)

Text

4 e KANSAS GAS AND ELECTRIC COMPANY THE ELECTAIC COMPANY GLENN L.MOESTER YlCE P.tS60E8ef **uCLEam -

Decenber 11, 1985 Mr. Harold R. Denton, Director Office of NLiclear Reactor Regulation U.S. Nuclear Regulatory Comission Nashington, D.C. 20555 KMLNRC 85-268 RE: Docket No. SIN 50-482 SUBJ: Inservice Inspection Relief Request Wolf Creek Generating Station

Dear Mr. Denton:

Enclosures A through F provide data in support of a request for relief from inservice examination (volumetric and visual) requirements for selected Wolf Creek conponent and piping systens. Enclosure G provides data in support of a volumetric examination relief request for 2 branch connection welds in the Reactor Coolant System.

Enclosures H through L detail partial relief requests for the Wolf Creek reactor pressure vessel. Enclosure M provides information in support of a request for relief from inservice inspection requirements of INP-2000.

If you have any questions concerning this transmittal please contact me or Mr. O.L. Maynard of my staff.

Very truly yours, Glenn L. Koester Vice President - lAlclear GLK:see Enclosures

, g1 xc: PO'Connor (2) om "8

ADW PlsR ~ URC's U CH SUPPORT }

AD - J. KNIGHT (it.r only) 8512160188 851211 [7C$^I$$l PDR ADOCK 05000482 eseicmia)

G PDR asa (RERLiscra)

FOR (RENAR0YA) 201 N. Market - Wichita, Kansas - Mail Address: Ro. Box 208 l %1chita, Kansas 67201 - Telephone: Area Code (316) 261-6451

ENCIO6URE M System: All systens under the requirements of ASME Section XI-Subsection INF Couponents: All pipe support assenblies requiring examination under ASME Section XI-Subsection INP Class: Classes 1, 2, 3 ASME Section XI Requirements: Article IW-2430 (a) and (b)

Article IW-2510 Alternate Examination:

A statistical sanpling plan with a 95/90 criteria is selected for pipe supports. 'Ihis provides a 95 percent confidence that a population containing 10 percent or more unacceptable assenblies will be detected. This proposed alternative to the requirements of ASME Section XI-Subsection IW provides an acceptable level of quality and safety as outlined in Document Mmber 83A1714.

Basis for Relief:

L 10 CPR 50.55a (a)(3) provides for alternatives to the ASME Code Section XI requirments. This alternate sanpling plan which incorporates a 95/90 statistical criteria, provides an

-acceptable level of quality and safety.

2. To reduce overall radiation exposure to plant personnel.

ENCLOSURE 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'acckolet by scanning both sides . obstruction affects scan .

of weld path. 5% loss of volume coverage.

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 coverage.

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 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.

1-AE-04-F033 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.

1-AE-05-F031 C-F 4" Elbow to 4" Valve Volumetric examinatiod 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.

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.

EENCLOSURE B System: Steam Generator .

Component I.D. Category Description Code Requirement Basis for Relief 1-EBB 01A-SEAM- 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 path on stub barrel side. 5% loss of volume coverage at 60% & 45*.

1-EBB 01A-SEAM- C-A Transition Cone to 100% Volumetric Four instrumentation nozzles, twc 6-W Shell Section C Examination lugs, guages and a feedwater nozzle obstructing scan path.-

5% loss of volume coverage at 60*

scan angle and 10% at a 45* scan angle.

1-EBB 01A-SEAM- C-A Shell Section D to 1007. Volumetric Loss of transducer contact due to 8-W Top IIead 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*

and 5% loss of volume at 0*.

I-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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!: t ENCLOSURE C T

System: Reactor Coolant ,g

Category: C-F .

Component

Description:

Component Description Reactor Coolant Pump D Seal Component Identification -

WaterInjectionLineWe}d_s, 1-BG-09-W790 2" X 1 " R,educer to lh"' Pipe 1-BG-09-W879 1 " Pipe to. Valve

. 1-BG-09-FW880 .-Valve to lh" Pipe

-s 1-BC-09-W859 th" Pipe to 2" X 1 " Reducer

• Reactot Coottnt' Puep A '

Seal Water injection Line Welds 1-BC-09-W686 , 2" X 1 " Reducer-to lh" Pipc -

1-BC-09-W881 1h" Pipe to Valve 1-BG-09-W882 Valve to lh" Pipe 1-BC-09-W779 1h" Pipi to 2" X 1 " Reducer Reactor Coolant Pi::np C Seal Water Injg rion Line Welds 1-BG-09-W806 2" X 1h"' Reducer to 1 " Pipe ,.

1-BC-09-W877 1 " Pipe to Valve-i 1-BG-09-W8 78 Valve to 1 " Pipn'.,

1-BG-09-W807 '

1 " Pipe to 2" X 1h" Reducer ,

Reactor Coolant Pump B -

Seal Water Injection Line Welda 1-BG-09-W814 '

2" X 1h" Reducer to li" Pipe 1-BC-09-W875 1h" Pipe to Valva 1-BC-09-W876 -

Va19e to lh" Pipi 1-BG-09-W695 1h" Pipe to 2" X 1h" Reducer Code Requirements: Volumetric exanination of there 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 m'caningless.

Alternate Testing: Penetrant Testing.

i

--.__---.__----___------ - .- - -- ~n-

P- , ,

s.

ENCIOSURE D b s

^

tem: Essential Service Water System Category: D-A Congonent

Description:

Rap Support ID Equipnent ID K-EPll-R001 IPEF01A-01 K-EPil-R003 1 PEP 01A-02 K-EPil-R005 1 PEP 01A-04 Code Requirement: Visual examination Vf-3 in accordance with the requirements of subsection lWF 2510 Areas for Relief: Entire Examination

< Basis for Relief: Supports of the inpeller shaft casing are inac-cessible for visual examination due to their submersion within the Essential Service Water Pung Pit Alternate Testing: None s

l 4

6

ENCII) SIRE E System: Reactor Coolant System Category: F-A Coriponent

Description:

Reactor Pressure Vessel Supports 1RBB01-01, IRBB01-02, 1RBB01-03, and 1RBB01-04 Code Requirement - Visual Examination - 3 In Accordance with The Requirements of Subsection IW -2510 Areas for Relief: Entire Examination ,'

Basis for Relief: Supports are inaccessible for visual examination because the rupporting structures are obscured by the concrete bio-shield Alternate Testing: None 3

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i 6

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gs

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. ENCLOSURE P' s Shstem: Pressurizer Description Code Requirement' Basis for Relief __

Corponent I.D' Category i

., j - .

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,. b, y .

' ' Component undulations restricting search 1-TBB03-4-W , B-F Relief Nozzle to 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 454-

^

/ loss of volume coverage'with a 45* axial scan.

1-TBB03-3-A-W B-F Safety, Nozzle to Volumetric examination Component undulations restricting sear 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 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 volume coverage with a 60* axial scan and a 404 loss of volume coverage with a 45% axial scan.

1-TBB03-3-B-W B-F Safety Nozzle to Volumetric examination C,omponent undulations restricting seai Safe-end Weld by scanning both sides unit movement and' metal structure of-of weld. -inconell buttering inhibiting shear wave transmission. 55s loss of volume coverage with a 60* axial-scan and a 40s loss of volume coverage with a 45* axial scan.

1-TDB03-2-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. los loss of. volume coverage with a.60* axial scan and a 40%

loss of volume coverage with a 45* axial scan.

' ENCLOSURE F

• CONT'D .

'Systca: Pressurizer Description Code Requirement Basis for Relief Component I.D Category 1-TBB-03-3-C-W B-F. Safety Nozzle ~ e Volum'tric examination Component. undulations restricting ' search -

to Safe-end Weld .lar 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 40%

loss of volume coverage with a 45*. axial' scan.

4

. - - . .- . .- - . _ = . _ - . - - _ - - .

I l

DEWSMtE G .  !

RELIEF REQUEST FOR THE NOLLMETRIC SERVICE INSPECTION N0fE CREEK REACKR COO [ANr SYSTEM BRAPCH 00t@ECTIONS 4

'I. AfME CG)E SECTION XI REOUIREMENTS In..Section XI, 1980 EditiorWinter 1981 Addenda, Table lWB-2500-1, examination Category 'BJ, item B9.31 requires a surface and~ volumetric examination of regions described in Figure' INB-2500 -11, for branch connection piping 4" nominal-pipe size and greater. However, the above code does not define the specific weld volume required to be examined. 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 Figure -03 corresponds to Figure INB-2500 - 11 with the modifications as stated above. The inservice inspection examinations will be performed to ultrasonically examine the defined volumes in Figure 03.

II. SPECIFIC RE1IEF REOLEST 4

Relief -is requested from performing volumetric examinations of 2 branch connection welds on the. primary loops of the Reactor Coolant System. The welds are identified in Table I along with

~

identification. 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 Figure 03, it is concluded that meaningful examination' by ultrasonic methods is not feasible and that no other practical volumetric method is available.

'IV.. ALTERNATE 'IEST METHOD

[R As an alternative, VP-2 ~ examinations for leakage will' be conducted in accordance with Im -5240. These will be carried out during the -leakage test specified .under INB-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.

I i

- . _ . . . - . , _ _ - , _ _ . _ . - _ _ _ . _ _ . . ,. . . . , _,.. _.. ..__ _ -_ m , , - - .

1 DK2fELEE G (contd)

TABLE 1 BRANCII.CCNECTION NEIDS 90LINE Itgm W Whld 3 K2 hE2D 3 SIE UfEXAMINABLE TYPE OF WE2D

- l~ 15 IBB-01 S302-3 6" 55% Figure 03 2 15 IBB-01 S402-3 14" 10% Figure 03

l ENCL 0SURE G (contd)

WESTINGHOUSE ELECTRIC CORPORATION zu.usumva Oxu FIGURE 01 REFERENCE TABLE 1 SIMILAR AND DISSIMILAR METAL WELDS IN PIPING

_St1R F. E X A M. AR E A_

~ '

A-B PROFILE OF VALVE BODY, Qw VESSEL NO22LE, OR

,y, ia4 +,f in. [j PUMP CONNECTION

. A ,, s' 8 INNER SURFACE k NOM. PIPE SIZE LESS THAN 4 IN.

, SURF. EXAM. AREA.

A-B PROFILE OF VALVE CODY, f VESSEL N0Z2LE, OR

• .l gy 4-1 t PUMP CONNECTION 2 Ig /,

A ,,

y

/~kB

. y ,,

}

1 4 4 0 k_ h~

l A

hin h L EX AM. VOL..

I' C - D - E - F ' ,

NON. PIPE' SIZE 4 IN. AND GREATER f

EllCLOSURE G (contd)

WESTINGHOUSE ELECTRIC CORPOR ATION r

nousmT:ve au FIGURE O2  ;

RETEP.ENCE TABLE 1 PI PE BRANCH CONNECTION j i

i DELETED i.

1 1

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g i I i -- --

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ENCLOSURE G (contd)

WESTINGHOUSE ELECTRIC CORPORATION

- i m.ummy" *

FIGURE 03 ;i

! arezmcr 2.m i 4

CONNECTION ',

l PIPE ERANCH i

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j k 'o l l %i , .V \

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' " 3 t-

^ X/.s&

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y o d () 1 I

E s %L(L sr y s 94 / -

- - __s l

4 " / \ l o- ' I IN.

} 'l i l

f -

s 3 RANCH u -

CONNECTION g -> l y i :N.

-+ ,

F (

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g = -

(

t g *e a y(-

l c -

2 O

• E f- d l E5 b,_j gb ss u o v L. -e IN J

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e: a i y n- m i T M* i S -.: =

l \ a \ %et

1. 4 i .

r I g ->+  ;]

" G' l Y w - <.+p .

4,o

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, ENCLOSURE H System: -Reactor: Pressure Vessel.

, Category: B-A Component-Description: Flange to Vessel Weld, (I.D. #1-RV-101-121)

Code' Requirement:

~

100% Volumetric Examination Areas for' Relief: '25% of Weld Volume Basis for Relief: _; Parallel scan portion of examination can on1'y be

-done from lower side due to. presence of flange taper above the weld. Complete perpendicular' scan was done from flange mating surface.

- Alternate Testing: None f

5 Y

l ic O

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'ENCLOS0REI

_ System: Reactor Pressure Vessel

' Category: 'B-D'

Component

Description:

Outlet Nozzle A to Vessel Weld, (I.D. #1-RV-107-121-A).

Outlet' Nozzle D to Vessel Weld, (I.D. #1-RV-107-121-B),

. Outlet Nozzle E to. Vessel Weld, (I.D. #1-RV-107-121-C),

Outlet Nozzle H to Vessel Weld, (I.D. #1-RV-107-121-D)

Code Requ'rement:

i 100% Volumetric Examination Areas for Relief: 'Approximately 10% of total weld' volume for each nozzle.

Basis for Relief: Approximately 10% of the total weld ~ volume for each

~

outlet nozzle is obstructed by contact betwee'n the examination head and the nozzle knuckle extending from the nozzle opening through the plane of the Reactor Pressure Vessel Inner Diameter.

Alternate Testing: None

z. . 3 d

' ENCLOSURE J

-Sy' stem: ~~Reactor. Pressure Vessel Category.: 6B-A.

, ' Component

Description:

Lower Head to Dollar Plate Weld.

--(I.D. #1-RV-102-151) sCode Requirement: 100% Volumetric Examination Areas for Relief: A. total' of approximately 10% of the Lower Head to Dollar 4

Plate Weld.

Basis for. Relief: Obstructions presented by the instrumentation nozzles when' scanning the Lower Head to Dollar Plate Weld.

- Alternate . Testing: None 6

f 9

k r-

)

. -8 ,

. +.. -

ENCLOSURE K System: ~ Reactor Pressure Vessel Category: B-A Component

Description:

Lower Head to Shell Weld -

I (0.D. #1-RV-101-141)

Code Requirement': 100% Volumetric Examination 0*, 45' and 60* Ultrasonic Shear Wave Examination' Angles.

^

' Areas.for. Relief: ; Perpendicular Examination- (shooting down) for the' 60*

ultrasonic shear ~ wave examination not performed. A ,

45* longitudinal wave examination was perfor=ed in

lieu of the 60* shear wave examination.

A total .of approximately.10% of the lower head to shell weld was not examined for the perpendicular examination (shooting down).

' Basis ' for Relief: 0.D. surface taper geometry limits ultrasonic head contact.

Alternate Testing: 'None-1

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m q. ,

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ENCLOSURE L

. System: : Reactor Pressure Vessel'

. Category: B-A; Component,

Description:

Meridional Welds in Lower Head (I.D. #1-RV-101-154A)

(I.D. #1-RV-101-154B)

(I.D. #1-RV-101-154C)

(I.D. #1-RV-101-154D)

Code Requirement: 100% Volumetric Examination J Areas for Relief: Weld Number Percentace Recuestine Relief 1-RV-101-154-A 22%

RV-101-154-B 27%

l-RV-101-154-C 12%

l-RV-101-154-D 14%

' Basis for Relief: 0.D. surfa'ce condition limits' ultrasonic head contact.

1 Alternate Testing: None f

c.