ML20097J329

Forwards Apps A-E to Final Preservice Insp Relief Request Re Certain Weldments in Reactor Pressure Vessel.Parallel Scan Portion of Exam Can Only Be Done from Lower Side Due to Presence of Flange Taper Above Weld

ML20097J329
Person / Time
Site:	Wolf Creek
Issue date:	09/14/1984
From:	Seiken S STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM
To:	Harold Denton Office of Nuclear Reactor Regulation
References
SLNRC-84-115, NUDOCS 8409210205
Download: ML20097J329 (6)

Text

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' SNUPPS Standardiaod Nuclear Unit Power Plant Systern 5 Choke Cherry Road n.ckvm. mryiond 20es0 September 19,1984 (301) 86M10 SLNRC 84- 115 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 Ref: SLNRC 84-112 dtd. 9/6/84: Preservice Inspection Relief Request

- Wolf Creek Plant

Dear Mr. Denton:

The' reference letter provided data in support of Preservice Inspection (PSI) relief requests involving selected Wolf Creek component and piping systems and indicated -that a supplemental submittal addressing relief requests for certain weldments in the reactor pressure vessel will be forthcoming. The purpose of this letter is to forward via Appendices A through E, attached herewith, details concerning partial relief requests for the Wolf Creek vessel. The attached submittal should be considered the final relief request for the Wolf Creek preservice inspection 5,rogram.

Very truly yours, S. J. Seiken, Manager Quality Assurance SJS/dck/8bl6 Attachments: A thru E cc: G. L. Koester, KGE

.- 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 R. C. DeYoung, USNRC/IE:HQ B. Brown, EGG Idaho 8409210205 840914 DRADOCK05000g Soo I ili

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APPENDIX A

- System: Reactor-Pressure Vessel n

Category: -B-A Component

Description:

Flange to Vessel Weld, (I.D. #1-RV-101-121)

Code Requirement: .100% Valumetric Examination -

Areas for Relief: 25% of Weld Volume 4

Basis for Relief: Parallel scan portion of examination can only be done from lower side due to presence of flange taper above the weld. Ccmplete perpendicular scan was done from flange mating surface.

Alternate Testing: None i

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APPENDIX B

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

Btsis for Relief: Approximately 10% of the total weld volume for each outlet nozzle is obstructed by contact between 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 4

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APPENDIX C

, System: Reactor Pressure Vessel Category.: B-A Component

Description:

Lower Head to Dollar Plate Weld,

.(I.D. #1-RV-102-151)

Code Requirement: 100% Volumetric Examination Areas for Relief: 'A total of approximately 10% of the Lower Head to Dollar Plate Weld.

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

Alternate Testing: None 0

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APPENDIX D

. System: Reactor Prassure Vessel

~ Category: B-A

' Component

Description:

Lower Head to Shell Weld (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 performed 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 i

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r APPENDIX E Syste : 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 ,

Areas for Relief: Weld Number Percentage Req'sesting Relief 1-RV-101-154-A 22%

1-RV-101-154-B 27%

1-RV-101-154-C 12%

1-2V-101-154-D 14%

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

Alternate Testing: None

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