ML20204C189: Difference between revisions

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{{#Wiki_filter:r-                                                                                                    y W84.F CREEK NUCLEAR OPERATING CORPORATION March 20,1987 U. S. Nuclear Regulatory Comnission ATTN: Document Control Desk Washington, D.C. 20555 Ietter: WM 87-0097 Re:      Docket No. 50-482 Subj:    Inservice Inspection Relief Requests for Wolf Creek Cenerating Station Gentlemen:
Attachments 1 through 4 provide data in support of requests for relief fran volumetric examination requirements of ASME Boiler and Pressure Vessel Code Section      XI    1980    Edition through Winter 1981 Addenda for selected components.      These relief requests resulted from the inservice inspections performed during Refuel 1 at Wolf Creek Generating Station.
A copy of this letter is being provided to Mr. Boyd Brown of EG&G Idaho, Inc. If you have any questions concerning this subject, please contact me or Mr. O. L. Maynard of my staff.
Very truly yours, s
Y,__ _
d Bart D. Withers President and Chief Executive Officer BDf:jad Attachments cc: PO'Connor (2)
RMartin JCunnins BBrown
(
SMaaggggngea                                                                  q O
PO Box 411.' Durlington. KS 66839 Phone. (316) 364-8831 An Eoual Opportunity Employer M F HCVET
 
                                                                                                                                ,q l
ATTACHMENT 1 RELIEF REQUEST Ca ponent: TBB03-Circum-5-W Category:  B-B
 
== Description:==
Pressurizer Shell to Bottczn Head Weld Code Requirernent: 100% volumetric exmination from two beam path directions.
Basis for Relief: On the bottcm head side of the weld, the support skirt to bottom head weld obstructs perpendicular scanning with 2.5% loss of voltzne in the 45 angle beam scan and 19.5% loss of voltane in the 60* angle beam scan. On the shell side, integrally welded lugs and instrtznentation nozzles interfere with perpendicular scanning with 6% loss of voltane.
Note: The ciretznferential scan (parallel to weld axis) is unaffected.
Alternate Examination: None ASME Code Section III: Components were accepted in accordance with the requirements of Section III, which included voltznetric and surface examinations as well as pressure tests.
Evaluation of Plant Safety: Sufficient voltane is examined to assure adequate levels of quality and safety for the weld.
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r-ATTACHMENT 2 RELIEF REQUEST        ,
          ; Component: CH-101-101 Category:  B-A
 
== Description:==
Closure Head to Flange Wold on the Reactor Pressure Vessel Code Requirement:    100% voltanetric examination from two beam path directions Basis for Relief: Three lifting lugs obstruct 42% of the exam volume at the lug locations. In the areas not obstructed by the lugs, 4.3% of the exam volume is obstructed by the head flange. The length of the weld obstructed by the lugs is 4.4%. A total of 6% of the weld volume cannot be examined. Note: The circtznferential scan (parallel to the weld axis),
as well as the surface examinations, were unaffected by these obstructions.
Alternate Examination: .None ASME Code Section III: Conponents were accepted in accordance with the requirements of Section III, which included volumetric and surface examinations as well as pressure tests.
Evaluation of Plant Safety: Sufficient volume and surface is examined to assure adequate levels of quality and safety for the weld.
9
 
s A'ITACHMENT 3 RELIEF REQUEST Caponent: EBB 01B-Sean-1-W Category:  B-B
 
== Description:==
Steam Generator B Tubesheet to Channel Head Weld Code Requirment: 100% volumetric examination from two beam path directions.
Basis for Relief: From the tubesheet side of the weld, 22.4% is obstructed by four supports. The 45 angle beam examination is 9.3% obstructed by design of the camponent and the 60 angle beam examination is obstructed 33.4% by the design of the cm ponent.
Insufficient base metal is provided by the design to perform complete angle bean examinations. The loss is 16.7% of the weld and required volme during perpendicular scanning.
Alternate Exanination: None ASME Code Section III: Caponents were accepted in accordance with the requirments of Section III, which included volanetric and surface examinations as well as pressure tests.
Evaluation of Plant Safety: Sufficient volume is examined to assure adequate levels of quality and safety for the weld.
 
r ATTACilMENP 4 RELIEF REGUEST Cmponent: EBB 01A-ll-W
          -Category:  C-B
 
== Description:==
Ste m Generator A Feedwater Nozzle to Shell Weld Code Requirment: 100% volumetric examination fr a two beam path directions Basis for Relief: Examination of the weld required volume is fra one beam path direction only (fr a shell towards nozzle), because of forging geometry. An area of the exam surface is contoured such that the search unit loses contact with the exam surface. We loss is 2.5% of the weld and required volme, in this one direction. Weld geometry precludes examination fra the opposite direction in its entirety.
Required surface examination is not impacted by this basis for relief and has been performed.
Alternate Examination:    "O " ultrasonic examination was performed at the time of the ISI examination to reduce the chance of missing a reflector parallel to the initial required scan.
ASME Code Section III: C m ponents were accepted in accordance with the requirments of Section III, which included volmetric and surface examinations as well as pressure tests.
Evaluation of Plant Safety: Sufficient volme and surface is examined to assure adequate levels of quality and safety for the weld.
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Latest revision as of 23:23, 30 December 2020

Forwards Data in Support of Requests for Relief from Volumetric Exam Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1980 Edition Through Winter 1981 Addenda,Per Inservice Insps During Refuel 1
ML20204C189
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 03/20/1987
From: Withers B
WOLF CREEK NUCLEAR OPERATING CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
WM-87-0097, WM-87-97, NUDOCS 8703250242
Download: ML20204C189 (5)


Text

r- y W84.F CREEK NUCLEAR OPERATING CORPORATION March 20,1987 U. S. Nuclear Regulatory Comnission ATTN: Document Control Desk Washington, D.C. 20555 Ietter: WM 87-0097 Re: Docket No. 50-482 Subj: Inservice Inspection Relief Requests for Wolf Creek Cenerating Station Gentlemen:

Attachments 1 through 4 provide data in support of requests for relief fran volumetric examination requirements of ASME Boiler and Pressure Vessel Code Section XI 1980 Edition through Winter 1981 Addenda for selected components. These relief requests resulted from the inservice inspections performed during Refuel 1 at Wolf Creek Generating Station.

A copy of this letter is being provided to Mr. Boyd Brown of EG&G Idaho, Inc. If you have any questions concerning this subject, please contact me or Mr. O. L. Maynard of my staff.

Very truly yours, s

Y,__ _

d Bart D. Withers President and Chief Executive Officer BDf:jad Attachments cc: PO'Connor (2)

RMartin JCunnins BBrown

(

SMaaggggngea q O

PO Box 411.' Durlington. KS 66839 Phone. (316) 364-8831 An Eoual Opportunity Employer M F HCVET

,q l

ATTACHMENT 1 RELIEF REQUEST Ca ponent: TBB03-Circum-5-W Category: B-B

Description:

Pressurizer Shell to Bottczn Head Weld Code Requirernent: 100% volumetric exmination from two beam path directions.

Basis for Relief: On the bottcm head side of the weld, the support skirt to bottom head weld obstructs perpendicular scanning with 2.5% loss of voltzne in the 45 angle beam scan and 19.5% loss of voltane in the 60* angle beam scan. On the shell side, integrally welded lugs and instrtznentation nozzles interfere with perpendicular scanning with 6% loss of voltane.

Note: The ciretznferential scan (parallel to weld axis) is unaffected.

Alternate Examination: None ASME Code Section III: Components were accepted in accordance with the requirements of Section III, which included voltznetric and surface examinations as well as pressure tests.

Evaluation of Plant Safety: Sufficient voltane is examined to assure adequate levels of quality and safety for the weld.

t s- ,.,,y .-.-.,r-r.= ,-wr 7- ~ - ,, w-m.-- -- . ---- - . - - - v---, _-e,v- - , ---- -

r-ATTACHMENT 2 RELIEF REQUEST ,

Component
CH-101-101 Category: B-A

Description:

Closure Head to Flange Wold on the Reactor Pressure Vessel Code Requirement: 100% voltanetric examination from two beam path directions Basis for Relief: Three lifting lugs obstruct 42% of the exam volume at the lug locations. In the areas not obstructed by the lugs, 4.3% of the exam volume is obstructed by the head flange. The length of the weld obstructed by the lugs is 4.4%. A total of 6% of the weld volume cannot be examined. Note: The circtznferential scan (parallel to the weld axis),

as well as the surface examinations, were unaffected by these obstructions.

Alternate Examination: .None ASME Code Section III: Conponents were accepted in accordance with the requirements of Section III, which included volumetric and surface examinations as well as pressure tests.

Evaluation of Plant Safety: Sufficient volume and surface is examined to assure adequate levels of quality and safety for the weld.

9

s A'ITACHMENT 3 RELIEF REQUEST Caponent: EBB 01B-Sean-1-W Category: B-B

Description:

Steam Generator B Tubesheet to Channel Head Weld Code Requirment: 100% volumetric examination from two beam path directions.

Basis for Relief: From the tubesheet side of the weld, 22.4% is obstructed by four supports. The 45 angle beam examination is 9.3% obstructed by design of the camponent and the 60 angle beam examination is obstructed 33.4% by the design of the cm ponent.

Insufficient base metal is provided by the design to perform complete angle bean examinations. The loss is 16.7% of the weld and required volme during perpendicular scanning.

Alternate Exanination: None ASME Code Section III: Caponents were accepted in accordance with the requirments of Section III, which included volanetric and surface examinations as well as pressure tests.

Evaluation of Plant Safety: Sufficient volume is examined to assure adequate levels of quality and safety for the weld.

r ATTACilMENP 4 RELIEF REGUEST Cmponent: EBB 01A-ll-W

-Category: C-B

Description:

Ste m Generator A Feedwater Nozzle to Shell Weld Code Requirment: 100% volumetric examination fr a two beam path directions Basis for Relief: Examination of the weld required volume is fra one beam path direction only (fr a shell towards nozzle), because of forging geometry. An area of the exam surface is contoured such that the search unit loses contact with the exam surface. We loss is 2.5% of the weld and required volme, in this one direction. Weld geometry precludes examination fra the opposite direction in its entirety.

Required surface examination is not impacted by this basis for relief and has been performed.

Alternate Examination: "O " ultrasonic examination was performed at the time of the ISI examination to reduce the chance of missing a reflector parallel to the initial required scan.

ASME Code Section III: C m ponents were accepted in accordance with the requirments of Section III, which included volmetric and surface examinations as well as pressure tests.

Evaluation of Plant Safety: Sufficient volme and surface is examined to assure adequate levels of quality and safety for the weld.

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