ML20100Q953

Requests Relief from Section XI of ASME Boiler & Pressure Vessel Code, Rules for Inservice Exam of Nuclear Power Plant Components, 1986 Edition,No Addenda

ML20100Q953
Person / Time
Site:	Point Beach
Issue date:	03/01/1996
From:	Maxfield G WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PBL-96-0042, PBL-96-42, NUDOCS 9603120183
Download: ML20100Q953 (5)

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Wisconsin Electnc POWER COMPANY Point Beoch Nuclear Plant 6610 Nuclear Rd., Two Rivers, WI 54241 (414) 755-2321 PBL 96-0042 March 1, 1996 Document Control Desk U. S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen:

DOCKETS 50-266 AND 50-301 ASME SECTION XI RELIEF REOUESTS RR-1-17 AND RR-2-21 POINT BEACH NUCLEAR PLANT UNIT 1 AND UNIT 2 In accordance with 10 CFR 50. 55a (g) (5) (iv) , Wisconsin Electric Power Company requests relief from Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, " Rules for Inservice >

Examination of Nuclear Power Plant Components," 1986 edition, no addenda. The requirements for which relief is requested apply to the third inservice inspection interval for Point Beach Nuclear Plant, Unit 1 and Unit 2. The third interval began in December 1990 for Unit 1 and November 1993 for Unit 2.

The attached relief requests, RR-1-17 and RR-2-21, provide the information needed for the NRC to complete a review and approval as required.

Sincerely, e

G. J. axfield Plant Manager caw Attachments I

i 110119 9603120183 960301 PDR ADOCK 05000266 ,Olf g P PDR /j i

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l RR-1-17

_CSMPONENT Reactor Vessel Nozzle to pipe welds Welds: RC-32-MRCI<AIII-03 RC-32-MRCleBIII-03 l

l l EXAM AREA l

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IWB-2500-8 i

ISOMETRIC or COMPONENT DRAWING l ISI-PRI-1120 ISI-PRI-1121 ASME SECTION XI CATEGORY i

B-F  !

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ASME SECTION XIITEM NUMBER l

l B5.130 ASME SECTION XI REOUIREMENT Volumetric and Surface i

ALTERNATE REOUIREMENT l

No surface exam will be performed from the outside diameter (O.D.) surface. Perform volumetric examination from bore utilizing mechanized UT techniques. The examination technique utilized will examine the required volume for volumetric examination and will be l capable of detecting surface indications. The examination process (i.e. equipment and j procedures) will be demonstrated capable of detecting O.D. surface connected,  ;

circumferentially oriented defects. Appropriate calibration standards will be fabricated and O.D. surface cracks induced for qualification in lieu of machined notches.

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REASON FOR PROPOSED ALTERNATE REOUIREMENT To perform surface examination of this weld from the outside diameter surface will result in excessive radiation exposure and exposure of personnel to potentially unsafe conditions. The proposed alternate examination still meets the intent of the examination area in figure l IWB-2500-8 of ASME Section XI and will eliminate the radiation exposure and potentially  ;

unsafe conditions.

To perform a surface examination of these welds from the outside diameter of the weld '

requires removal of a refueling cavity access cover, shielding plug over weld and insulation surrounding the weld. The examination must then be performed by lowering an NDE l examiner into the resultant confm' ed space /high radiation area for the duration of the surface l' exam.

l The radiation exposure associated with this examination is approximately 640 mrem per weld based on past examinations. The dose associated with this process is broken down as l follows:

e Remove refueling cavity cover and remove shield plug - 30 mrem  ;

e Remove insulation around weld - 100 mrem o Perform surface examination - 380 mrem o Reinstall insulation - 100 mrem e- Replace plug and refueling cavity cover - 30 mrem i

Total 640 mrem These examination techniques utilized radiation reduction techniques such as exiting the area  !

and utilizing shielding during dwell times of the surface examination. The alternate examination technique would reduce the radiation exposure approximately 1250 mrem (both j welds).

The personnel safety hazards associated with this examination include those hazards associated with confm' ed spaces (poor air quality, etc.), high temperatures with the potential of heat fatigue, and general industrial safety associated with entering, exiting, and working in a confined space where lighting is poor.

The proposed alternate examination will be performed remotely and will essentially eliminate I the radiation exposure and personnel safety concerns. The proposed examination technique I will be performed utilizing procedures, techniques, and personnel that comply with ASME Codes and Standards and will be capable of detecting surface indications using volumetric I techniques.

RR-2-21 COMPONENT Reactor Vessel Nozzle to pipe welds Welds : RC-32-MRCL-AIII-03 RC-32-MRCI<BIII-03 RC-34-MRCL-AI-01 RC-34-MRCIeBI-01 EXAM AREA IWB-2500-8 ISOMETRIC or COMPONENT DRAWING ISI-PRI-2120 ISI-PRI-2121 ASME SECTION XI CATEGORY B-F ASME SECTION XI ITEM NUMBER B5.130 ASME SECTION XI REOUIREMENT Volumetric and Surface ALTERNATE REOUIREMENT No surface exam will be performed from the outside diameter (O.D.) surface. Perform volumetric examination from bore utilizing mechanized UT techniques. The examination technique utilized will examine the required volume for voitunetric examination and will be capable of detecting surface indications. The examination process (i.e. equipment and procedures) will be demonstrated capable of detecting O.D. surface connected, circumferentially oriented defects. Appropriate calibration standards will be fabricated and O.D. surface cracks induced for qualification in lieu of machined notches.

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. REASON FOR PROPOSED ALTERNATE REOUIREMENT To perform surface examination of this weld from the outside diameter surface will result in excessive radiation exposure and exposure of personnel to potentially unsafe conditions. The proposed alternate examination still meets the intent of the examination area in figure IWB-2500-8 of ASME Section XI and will eliminate the radiation exposure and potentially ,

!- unsafe conditions. >

4 To perform a surface examination of these welds from the outside diameter of the weld j requires removal of a refueling cavity access cover, shielding plug over weld and insulation i surrounding the weld. The examination must then be performed by lowering an NDE l examiner into the resultant confined space /high radiation area for the duration of the surface -

exam.

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The radiation exposure associated with this examination is approximately 640 mrem per weld

based on past examinations. The dose associated with this process is broken down as follows

! e Remove refueling cavity cover and remove shield plug - 30 mrem l e Remove insulation around weld - 100 mrem I e Perform surface examination - 380 mrem

e Reinstall insulation - 100 mrem e Replace plug and refueling vavity cover - 30 mrem Total 640 mrem  ;-

l These examination techniques utilized radiation reduction techniques such as exiting the area i and utilizing shielding during dwell times of the surface examination. The alternate  !

examination technique would reduce the radiation exposure approximately 1250 mrem (both welds).

I

The personnel safety hazards associated with this examination include those hazards j associated with confined spaces (poor air quality, etc.), high temperatures with the potential of heat fatigue, and general industrial safety associated with entering, exiting, and working in a confined space where lighting is poor.

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The proposed alternate examination will be performed remotely and will essentially eliminate the radiation exposure and personnel safety concerns. The proposed examination technique will be performed utilizing procedures, techniques, and personnel that comply with ASME Codes and Standards and will be capable of detecting surface indications using volumetric techniques.

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