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__ } . a ucf / %, UNITED STATES "' l' ) # ; NUCLEAR REGULATORY COMMISSION * ;, t WASHINGTON. D. C. 20555 t i March 10,1988 %, ...../ Docket No. 50-368 Mr. T. Gene Carpbell Vice President, Nuclear Operations Arkansas Pnwer and Light Company Post Office Box 551 Little Rock, Arkansas 72203 | Dear Mr. Campbell: 1 SUBJECT: REQUEST FOR APPLICATION OF ASME CODE CASE N-234 ' ' ' ARKANSAS NUCLEAR ONE, UNIT 2 (ANO-2) - TAC NO. 67397 The Comission has completed their review of the Arkansas Power and Light ' (AP&L) request for NRC approval tG use the ASME Boiler and Pressure Vassel | Code Case N-234 as requested in the submittal dated March 1,1988(2CANO38802). i Approval for application of Case N-234 would permit AP&L to extend the time between calibration checks required during ultrasonic exarination of the reactor vessel. The ASME code of record for the present ANO-2 Inservice Inspaction Program is the 1974 Edition through Sumer 1975 Addandum of Section XI of the ASME Boiler . and Pressure Yessel Code. AP&L stated that the ANO-2 reactor vessel will be | examined during the present refueling outage. For the performance of the 1 i ultrasonic examiration of the vessel, automated ultrasonic examination system calibration checks are presently required once every four hours and with any change in examination personnel in accordance with Appendix I (I-4230) of Section XI. ASME Code Case N-234 allows the time period between the calibration ; ; checks to be extended to 12 hours and eliminates the requirements that a I calibration check be perfomed with a change in operatirg personnel. Footnote 6 to 10 CFR 50.55a permits the use of Code Cases, in addition to | those accepted in Regulatory Guide (R.G.) 1.84 or R.G.1.85, upon authorization ! by the Director of the Office of Nuclaar Reactor Regulation upon request J pursuanttoSection50.55a(a)(3). Alternatives to the requirements of Section . ! XI of the ASME Code are pemitted by 10 CFR 50.55a(a)(3) if the applicant can I i demonstrate that (i) the proposed alternatives would provide an acceptable | 1evel of quality and safety or (ii) compliance with the specified requirements of this section would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety. 4 R.G. 1.147, Revision 5. "Inservice Inspection Code Case Acceptability ASME Section XI Division I", dated August 1986, lists Code Cases that are generally 3 j acceptable to the NRC staff for implementation in the intervice inspection of light-water cooled nuclear power plants. Code Case N-234 is er.dorsed in i R.G. 1.147 with no exceptions taken by the NRC staff to the Code Case. This ) i 8803210137 000310 1 PDR ADOCK 050 3jO i P 1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . |

l' ) # ' UNITED STATES NUCLEAR REGULATORY COMMISSION · 2020. 10. 17. · Washington, D.C. 20036 County Judoa of Pope Count'y,, Pope County Courthouse | Regional Adninistrator, Renien

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    a ucf/ %, UNITED STATES"'l' ) # ; NUCLEAR REGULATORY COMMISSION*

    ;, t WASHINGTON. D. C. 20555t i March 10,1988%, ...../

    Docket No. 50-368

    Mr. T. Gene CarpbellVice President, Nuclear

    OperationsArkansas Pnwer and Light CompanyPost Office Box 551Little Rock, Arkansas 72203

    |

    Dear Mr. Campbell:

    1 SUBJECT: REQUEST FOR APPLICATION OF ASME CODE CASE N-234'

    '' ARKANSAS NUCLEAR ONE, UNIT 2 (ANO-2) - TAC NO. 67397

    The Comission has completed their review of the Arkansas Power and Light '

    (AP&L) request for NRC approval tG use the ASME Boiler and Pressure Vassel |Code Case N-234 as requested in the submittal dated March 1,1988(2CANO38802). iApproval for application of Case N-234 would permit AP&L to extend the timebetween calibration checks required during ultrasonic exarination of thereactor vessel.

    The ASME code of record for the present ANO-2 Inservice Inspaction Program isthe 1974 Edition through Sumer 1975 Addandum of Section XI of the ASME Boiler .and Pressure Yessel Code. AP&L stated that the ANO-2 reactor vessel will be |examined during the present refueling outage. For the performance of the

    1i ultrasonic examiration of the vessel, automated ultrasonic examination system

    calibration checks are presently required once every four hours and with anychange in examination personnel in accordance with Appendix I (I-4230) ofSection XI. ASME Code Case N-234 allows the time period between the calibration;

    ; checks to be extended to 12 hours and eliminates the requirements that aIcalibration check be perfomed with a change in operatirg personnel.

    Footnote 6 to 10 CFR 50.55a permits the use of Code Cases, in addition to |those accepted in Regulatory Guide (R.G.) 1.84 or R.G.1.85, upon authorization !by the Director of the Office of Nuclaar Reactor Regulation upon request JpursuanttoSection50.55a(a)(3). Alternatives to the requirements of Section .

    ! XI of the ASME Code are pemitted by 10 CFR 50.55a(a)(3) if the applicant can Ii demonstrate that (i) the proposed alternatives would provide an acceptable |

    1evel of quality and safety or (ii) compliance with the specified requirementsof this section would result in hardship or unusual difficulties without acompensating increase in the level of quality and safety.4

    R.G. 1.147, Revision 5. "Inservice Inspection Code Case Acceptability ASMESection XI Division I", dated August 1986, lists Code Cases that are generally

    3

    j acceptable to the NRC staff for implementation in the intervice inspection oflight-water cooled nuclear power plants. Code Case N-234 is er.dorsed in iR.G. 1.147 with no exceptions taken by the NRC staff to the Code Case. This )i

    8803210137 0003101 PDR ADOCK 050 3jOi P

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    cede case states that---when performing ultrasenic examinations in accordancewith either Appendix I or Appandix III of Section XI, Divisinn 1, if automatedultrasonic examination systens ara used, the time period between calibrationcheckt, required by I-4230 or 111-3330 may be extended tc 12 hr and need notbe coincident with a change of operator persernel.

    ApAL request of March 1, 1988 stated that the application of Code Case N-234would result in a reduction of approximately 36 hours ir the outage criticalpath time required for the examination ard, consistent with haalth physicsALARA objectives, a reduction of radiation exposure of personnel perfoming theexaninatien. Applicatier of Code Case N-234 is in accordance with the provi-sions of 10 CFR 50.55a(a)(3)(i) in that calibration checks of 12 hours duringuse of the autcrated ultrasonic exanination systems would provide an acceptablelevel of quality and safety. Further, using the four heur calibration intervalswould increase personnel radiation exposure with no compensating increase in

    1 the level of quality and safety.

    Tha staff has detemined in accordance with the provisions of 10 CFR 50.55a(a)(3)that your rec,uest for authorization for usa n' Code Case N-234 for the ultrasonicexamination of the reactor vessel as previously described provides an acceptablelevel of quality ard safety, and that recuiring the four hour calibration checkswould result in increased radiation exposure without a compensating increase inthe systems level of cuality and safety.

    This letter shall serve as authorization of your request to use Code Case N-234in lieu of currently perfoming the four hour calibration checks as part of the>inservice irspection of the reactor vessel in accordance with Appendix ! of iSection XI of the ASME Code.

    The Comission hereby authorizes this use of ASME Ccde Case N-234 for thispertion of reactor vessel inservice inspection program pursuant to 10 CFR50.55a(a)(3) and finds that this use (1) provides an accaptable leval ofquality ard safety, (2) that corpliance with the present requirements wouldincrease radiation exposure not conpersated by the resultant increase inquality and safety, and (3) is authorized by law and will not endarger life orproperty or the comon defense and security and is otherwise in the publicinterest.

    Sincerely,i

    |u 4 CJ A' Jose A. Calvo, Director !Project Directorate - IV |Division of Reactor Projecte - III, |

    ; IV, Y and Special Projects !i

    cc: See next page

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    Mr. T. Gene CampbellArkansas Power & Light Company Arkansas Nuclear One, Unit 2

    CC'Mr. J. Ted Enos, Managar Mr. Charles B. Brinknar, ManagerNuclear Engineering and Licensing Washington Nuclear Operations

    j Arkansas Power & Light Company C-E Power Systens.! P. O. Box 551 7910 Woodmont Avenue ,

    | Little Rock, Arkansas 72203 Suita 1310i Bethesda, Maryland 7081a

    Mr. James M. Levina, Director |,

    Sito Nuclaar Operations Mr. Frank Wilson, DirectneArkanses Nuclear Ona Division of Environmental HealthP. O. Box 608 ProtectionRussellville, Arkansas 72801 Department of Health

    Arkansas Departnent of HealthMr. Nicholas S. Reynnits 4815 Wast Markham StreatBishop Liberran, Cook, Purcell Little Rock, Arkansas 7?201*1200 Seventeenth Street, N.W.Suite 700 Hnnorable Willitm Abe-vsthy ,Washington, D.C. 20036 County Judoa of Pope Count'y ,,

    Pope County Courthouse |Regional Adninistrator, Renien IV Russelville, Arkansas 72801U.S. Nuclear Pagulatory CommissionOffice of Executive Director fn*

    Operations611 Pyan Plaza Drive, Suite 1000Arlirgton, Texas 76011

    Senior Resident IrSpector", U.S. Nuclear Regulatory Commissioni 1 Nuclear Plant Road

    Pussellville, Arkansas 72801'

    : Ms. Greta Dieus, Director iDivision of Er"ironmental Health i<

    Protectice !*

    Arkansas Department of Health !4815 West Markam Street !Little Rock, Arkansas 72201 !

    Mr. Robert B. BorsumBabcock & Wilcox,Nuclear Power Generation Division'Suite 220, 7910 Woodmont Avenue ,Rethesda, Maryland 20814

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    ; -2-' code case states that---wher perfomina ultrasonic examinatiers in accordance

    with either Appendix ! or Appendix III of Section XI, Division 1 if automatedultrasenic examination systems are used, the time peried between calibrationchecks required by I-4230 or III-3330 may be extended to 17 hr. ard naed notbe coincident with a change of operator personnel.

    ,

    AP&L request of March 1, 1988 stated that the application ef Code Case N-234would result in a reduction of approximataly 36 hours in the outage criticalpath time required for the examination and, consistent with health physicsALARA objectives, a reduction of radiation exposure of perternel perfoming theexaminatier. Application of Code Case N-234 is in accordarce with the provi-siens of 10 CFR 50.55a(a)(3)(1) in that calibration checks of 12 hours duringuse of the automated ultrasonic examination 'ystens would provide er acceptablelevel of quality and safety. Further, usino the 'our hour calibration irtervalswould increase personnel radiation exposure with no compensating increase inthe level of oue14ty and safety.

    ,

    The staff has detemined in acccedance with the provisiers of 10 CFR 50.55a(a)(3)that your request for authorization for use of Code Case N-?34 for the ultrasonicexamination of the reactor vessel at previously described provides an acceptablelevel of cuality and safety, and that requiring the four hcur calibration checkswould result ir increased radiation exposure without a comparsating increase inthe systens level of quality and safety.

    This letter shall serve as authori7ation of your request to use Code Case N-234in lieu of currently perferring the four hour calibration checks as part of theinservice inspection of the reactor vcssel in accordance with Apperdix I ofSection XI o' the ASME Code. ,

    The Comiscion hereby authorizes this use of ASME Code Case N-734 for thisportion of reactor vessel inservice inspection program pursuert to 10 CFR50.55a(a)(3) and finds that this use (1) provides an acceptabla level ofouality and safety, (2) that compliance with th* present requirements would

    i

    increase radiation axposure not compensated by the resultant increase in Iquality ard safety, and (3) is authorized by law asd will not endanger life orproperty or the comon defense and security and is otherwise ir the publicinterest.

    Sincerely,

    Jose A. Calvo, DirectorProject Directorate - IVDivision of Peactor Projects - III,

    IV, V and Special Projectscc: See next page

    DISTRIRUTIONDocket File NRC PDR Local PDR PD4 ReadingDR4A/J. Collins J. Calvo P. Noonar G. DickOGC-Bethesda E. Jordan J. Partlow ACRS (10)PD4 Plart File C. Harbuck I*See previous cercurrence i

    *PD4/LA *PDA/PM *EMTB OGC PD4/D/MPNoonan GDick:sr /) ,y 5 JCalvo03/03/88 03/03/88 03/03/88 03/ /88 03//o/88 i

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    code case states that---when perfoming ultrasonic examinations in accordancewith either Appendix I or Appendix III of Section XI, Division 1, if automatedultrasonic examination systems are used, the time period between calibrationchecks required by I-4230 or III-3330 may be extended to 12 hr. and need not ,be coincident with a change of operator personnel.

    AP&L request of March 1,1988 stated that the application cf Code Case N-234would result in a reduction of approxinately 36 hours in the outage critical 'path time required for'the examination and, consistent with health physicsALARA objectives, a reduction of radiation exposure of personnel p;rfoming the !examinatien. Application of Code Case N-234 is in accordance with the provi- ;siens of 10 CFR 50.55afa)(3)(1) in that calibration checks of 12 hours duringuse of the automated ultrasonic examination rystens would provide an acceptablelevel of quality and safety. Further, using the four hour calibration intervalswould increase personnel radiation exposure with no compensating increase inthe level of quality and safety.

    ,

    The staff has detemined in accordance with the provisiens of 10 CFR 50.55a(a)(3)that your request for authorization for use of Code Case N-234 for the ultrasonicexamination of the reactor vessel as previously described provides an acceptablelevel of cuality and safety, and that requiring the four hour calibration checkswould result in increased radiation exposure without a comparsating increase inthe systens level of quality and safety.

    This letter shall serve as authoriration of your request to use Code Case N-234in lieu of currently perfoming the four hour calibration checks as part of theinservice inspection of the reactor vessel in accordance with Apperdix ! of ;Section XI of the ASME Code. ;

    ,

    The Comission hereby authorizes this use of ASME Code Case N-234 for thisportion of reactor vessel inservice inspection program pursuant to 10 CFR ,50.55a(a)(3) and finds that this use (1) provides an acceptable level of :quality and safety, (2) that compliance with the present requirements wouldincrease radiation exposure not compensated by the resultant increate in

    ,

    quality ard safety, and (3) is authorized by law snd will not endanger life or |property or the comon defense and security and is otherwise in the public :interest.

    Sincerely, ,i

    Jose A. Calvo, Director iProject Directorate - IVDivision of Peactor Projects - III,

    ,

    IV, V and Special Projectscc: See next page !

    !

    DISTRIBUTION |'|fDoctetJ11e. NRC POR Local PDR PD4 Reading |"

    DR4A/J. Collins J. Calvo P. Noonar G. Dick*

    OGC-Bethesda E. Jordan J. Partlow ACRS(10)PD4 Plant File C. Harbuck ,*See previous cercurrence

    OGC[ PD4/D/M*PD4/LA *PD4/PM *EMTBPNoonan GDick:sr /) ;/ < JCalvo03/03/88 03/03/88 03/03/P8 03/ /88 03/ /c/R8

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    code case states that---when performirg ultrasonic examinations in accordance -

    ! with either Appendix ! or Appendix III of Section XI, Division 1, if automated4 ultrasonic examination systens are used, the time period between calibration :; checks required by I-4230 or 111-3330 may be extended to 12 hr. and need not i

    i be coincident with a change of operator personnel. ;

    AP&L' request of March 1, 1988 stated that the application of Code Case N-234 )would result in a reduction of approximately 36 hours in the outage critical !path time required for the examination and, consistent with health physics ;.ALARA objectives, a reduction of radiation exposure of personnel performing the |

    ; examination. Application of Code Case N-234 is in accordance with the provi-sions of 10 CFR 50.55(a)(3)(1) in that calibration checks of 12 hours duringuse of the automated ultrasonic examination systens would provide an acceptable

    j level of quality and safety. Further, using the four hour calibratien intervals |!would increase personnel radiation exposure with ro compensating increase in

    |the level of cuality and safety. j

    1

    The staff has detemined in accordance with the provisions of 10 CFR 50.55a(a)(3)ithat your request for authorization for use of Code Case N-234 for the ultrasonic iexamination of the reactor vessel as previously described provides an acceptable !'level of quality and safety, and that requiring the four hour calibration checks !:

    i would result in increased radiation exposure without a compensating increase in :the systers level of quality and safety.' .

    This letter shall serve as authorization of your request to use Code Case N-234"in lieu of currently perfoming the four hour ca.libration checks as part of the .'

    '

    ! inservice inspection of the reactor vessel in accordance with Appendix ! ofSection XI of the ASME Code, f'

    .

    The Comissier hereby authorizes this use of ASME Code Case N-?34 for this; portion of reactor vessel inservice inspection program pursuant to 10 CFRi 50.55a(a)(3) and finds that this use (1) provides an acceptable level of i; quality and safety. (?) that compliance with the present requirements would !| increase radiation expcsure not compensated by the resultant increase ini quality and safety, and (3) is euthorized by law and will not endanger life or '

    i property or the comon defense and security and is otherwise in the public |i interest. >] 'Sircerely, .

    '

    :

    Jose A. Calvo, Director'Project Directorate - IVi

    2 Division of Reactor Projects - III,

    i IV, V and Special Projectscc: See next page

    ! DISTRIBUTION| Docket File .NPC PDR Local PDP PD4 Reading; DR4A/J. Collins J. Calvo P. Nooran G. Dickj OGC-Bethesda E. Jordan J. Partlow ACRS (10)

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    ! PD4 Plent file C. Harbuck

    PD4/LAPNoonan (h k/PMh OGC PD4/D

    A ek:sr O(WWT JCalvo i403j/88 03/63/88 03/3/88 03/ /88 03/ /88 i

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