View source for B17593, Requests Relief from Requirements of 10CFR50.55a(g)(5) for Performing Required ISI of Certain Class 2 Components IAW ASME Section XI for Mnps,Unit 3.Rev 2 to Relief Request IR-9,encl

{{Adams
| number = ML20198J662
| issue date = 12/21/1998
| title = Requests Relief from Requirements of 10CFR50.55a(g)(5) for Performing Required ISI of Certain Class 2 Components IAW ASME Section XI for Mnps,Unit 3.Rev 2 to Relief Request IR-9,encl
| author name = Bowling M
| author affiliation = NORTHEAST NUCLEAR ENERGY CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000423
| license number = 
| contact person = 
| document report number = B17593, NUDOCS 9812300235
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 8
| project = 
| stage = Request
}}

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g h Northeast                                                                  Rope Feny RddRoute 156), Wetuford, Cr 06385 j$ Nucl:arEn:rgy                                                           waistone Nuclear Power Station Nonheast Nuclear Energy Company P.o. Box 128 i
                         .                                                      Waterford, Cr 06385-0128 (860) 447-1791 Fax (860) 444-4277                                 i l
The Northeast Utilities System DEC 21 1998                        !
Docket Nos. 50-423 B17593 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Re: 10CFR50.55a(g)
Millstone Nuclear Power Station, Unit No. 3 Inservice Test Program Revised Reauest for Relief From ASME Section XI Northeast Nuclear Energy Company (NNECO) hereby requests relief from the requirements of 10CFR50.55a(g)(5) for performing the required in-service Inspection (ISI) of certain Class 2 components in accordance with the American Society of                                                l Mechanical Engineers (ASME) Section XI for Millstone Nuclear Power Station, Unit No.
3.
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Relief Request IR-9' was previously evaluated and granted interim relief in the NRC Safety Evaluation Report (SER) dated Feb. 8,1991 provided that the licensee demonstrated that the proposed alternative examination, including procedures and                                              .
instrumentation was capable of detecting O.D. flaws. IR -9, Revision 1, was submitted                                         I with the conditions of the NRC SER incorporated and was subsequently approved4.
Revision 1 of the Relief Request specifically stated the ultrasonic technique and examination angle used. IR-9, Revision 2 (Attachment 2) has been revised to reflect the actual state of the art ultrasonic technique using 40 degree Refracted Longitudinal-                                      l Wave search units to obtain the full volume Ultrasonic Test (UT) examination of the                                           l weld a d, base n tal of the Nozzle-to-SafeEnd welds (Cat. B-F) from the nozzle bore.
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    ' J. F. Opeka letter to V. S. Noonan, License Condition 2.C.5 -ISI Program, dated May 22,1986
* J. F. Stolz letter to E. J. Mroczka, First Ten Year Program Plan and Inservice Inspection Relief Requests, Millstone Nuclear Power Station, Unit No. 3 (TAC No. 60385), dated February 8,1991
* E. J. Mroczka to U. S. Nuclear Regulatory Commision, Millstone Nuclear Power Sation, Unit No.3,                             I Inservice Inspection Program Summary Report And Request For Relief From ASME Section XI (TAC No.
60385), dated October 30,1991
* J. F. Stolz letter to J. F Opeka, Millstone Nuclear Power Station , Unit No. 3 - Review Of Firts Ten-Year               l Interval inservice inspection Program Summary Report, Revision 3 And Request For Relief, dated March                   q munLSS.3o                                                                                                             h'   I 9812300235 981221                  I                                                                                     Il PDR     ADOCK 05000423 i' P                          PDR

    .        'U.S. Nucle:r Regulatory Commission B17593\ Pcg3 2 This technique was demonstrated on April 3,1995, prior to the performance of the onsite e'xamin 8tions as a condition of the SER.
Additionally, the SafeEnd-to- pipe welds ( Cat. B-J) have been deleted from this Relief Request. Since they were not selected for examination during the First inspection Interval they are not required as part of this Relief.
A detailed relief description and weld examination summary are provided in Attachment
: 2. If you have any questions concerning this submittal, please contact Mr. D. W.
Dodson at (860) 447-1791, extension 2346.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY Martin L. Bowling       j Recovery Of5cer - Technical Services Attachments:
: 1. NNECO's commitments for relief from ASME Section XI Code requirements
: 2. Request for relief from ASME Section XI cc: H. J. Miller, Region l Administrator W. M. Dean, Director, Millstone Project Directorate W. D. Lanning, Director, Millstone inspections J. P. Durr, Chief, inspections Branch J. W. Andersen, NRC Project Manager, Millstone Unit 3 A. C. Cerne, Senior Resident inspector, Millstone Unit 3

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Docket Nos. 50-423 B17593         )
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I l-                                 Millstone Nuclear Power Station, Unit No. 3 Reaulatory Commitments l-I i,
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U.S. Nucber R::gulatory Commission B17593\ Attachment 1 \ Page 1 l
Attachment 1 Regulatory Commitments                                    ,
The following table identifies those actions committed to by NNECO in this document.
Please notify the Director, Regulatory Affairs at the Millstone Nuclear Power Station of   !
any questions regarding this document or any associated regulatory commitments.             j Number                          Commitment                              Due            j N/A                              None                                 N/A           )
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1 Docket Nos. 50-423
                                                                                     .B17593 l.
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i-t Attachment 2 Millstone Nuclear Power Station, Unit No. 3 Inservice inspection Program Roauest for Relief From ASME Section XI i
: i.                                                                          December 1998 l
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  .    'U.S. Nucisar Regulatory Commission B17593\ Attachmsnt 2 \ Pega 1 Attachment 2 Millstone Nuclear Power Station Unit 3 Relief from In-service Inspection Reauirements Relief Reauest:        IR-9, Rev. 2 Code Class:                    1 Examination Category:          B-F, Pressure Retaining Dissimilar Metal Welds
      ' Item No.:       B5.10 Code Reauirements:
Section XI of the ASME B&PV Code,1983 Edition, with Addenda through the Summer of 1983, requires that a volumetric and surface examination be performed on nozzle to safe-end welds greater than 4-inch nps.
Code Relief Reauest:
Pursuant to 10CFR50.55a(g)5(iii), relief is requested from performing the in-service surface examination of the nozzle to safe-end welds greater than 4-inch nps on the Reactor Vessel.
Reason for Relief:
The Millstone Unit 3 reactor vessel is a four-loop PWR. There are eight nozzle to safe-end welds for item B5.10, in the in-service inspection program. The purpose of this relief is to perform a full volumetric ultrasonic examination in lieu of a surface examination in order to reduce exposure. The reactor vessel nozzles have a permanent mirror type insulation installed which covers the OD surface of these welds.
The exposure received from the removal and reinstallation of this insulation and performing the surface examination is estimated to be 2.5 man-rem per weld.
The ultrasonic examination of these welds will be performed during the third inspection period from the ID surface using the remote immersion method. NNECO believes that any failure of the weld will be induced from the ID surface and that the ultrasonic examination from this surface shall be sufficient to detect any indications.
NNECO believes that the proposed ultrasonic examination will prove to be adequate to detect flaws in the listed items. NNECO believes that the ultrasonic exam will assist in reducing the exposure rates, without losing the ability to detect flaws in the reactor vessel nozzle to safe-end and safe-end to pipe welds.
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        .U.S. Nucl=r Regulatory Commission                                                                    !
B17593\ Attachment 2 \ Page 2                                                                        l Proposed Alternative Examinations A. The subject welds received a full volume volumetric examination from the ID surface               i in accordance with ASME Section XI and Section IWA-2240. This examination                        l l
consisted of 40 degree refracted longitudinal wave search units manipulated and l            scanned in four directions to obtain full volumetric coverage of the weld and 1/2 inch           ;
l            of base material on each side of the O.D. weld fusion lines. This alternative volumetric examination was demonstrated prior to performing the examinations.                    ,
The demonstration included the ability to detect OD flaws with the actual procedure              i r            and instrument used in the proposed examination.
B. in-Service System Leakage Tests will be performed per Code Case N-408-1 as granted by NRC correspondence dated January 18,1995.
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    ,   'U.S. Nucle r Regulatory Commission
!        B17593\ Att: chm:nt 2 \ Paga 3 TABLE 1 Code Cateaory B-F/B-J Welds                                      ;
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Zone            Weld          Code                            Exam Number      identification   Cateaory         Material Type    Anale     Techniaue           I 12          302-121-C '      B-F       29" SA508/CL2         40     Refracted SA182/F316                   Longitudinal           I Wave.
12           301-121-C        B-F       27% SA182/F316        40     Refracted SA508/CL2                    Longitudinal Wave.
13           302-121-D        B-F       29" SA508/CL2         40     Refracted SA182/F316                   Longitudinal Wave.
13          301-121-D        B-F       27% SA182/F316        40     Refracted SA508/CL2                    Longitudinal Wave.
14          302-121-A        B-F       29" SA508/CL2         40     Refracted SA182/F316                  Longitudinal Wave.
14          301-121-A        B-F       27% SA182/F316        40     Refracted SA508/CL2                   Longitudinal           l Wave.
15          302-I21-B        B-F       29" SA508/CL2         40     Refracted SA182/F316                  Longitudinal Wava.                   I 15          301-121-B        B-F       27% SA182/F316        40     Refracted SA508/CL2                    Longitudinal Wave.
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