NRC 2013-0012, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Lnservice Inspection Program Interval Response to Request for Additional Information
| ML13035A018 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/01/2013 |
| From: | Meyer L Point Beach |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NRC 2013-0012, TAC M9905 | |
| Download: ML13035A018 (8) | |
Text
NEXT ENERCVr
/+- POINT BEACH February I , 2013 NRC 2013-0012 10 CFR 50.55a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant Unit 1 Docket 50-266 Renewed License No. DPR-24 10 CFR 50.55a Request, Relief Request 1-RR-4 Re-Examination of the Unit 1 Reactor Pressure Vessel lndication on the
" A lnlet Nozzle Weld Fifth Ten-Year lnservice lnspection Program Interval Response to Request for Additional lnformation
References:
(1) NextEra Energy Point Beach, LLC letter to NRC, dated November 9, 2012, 10 CFR 50.55a Request, Relief Request 1-RR-4 Re-Examination of the Unit 1 Reactor Pressure Vessel lndication on the " A lnlet Nozzle Weld Fifth Ten-Year lnservice Inspection Program Interval (ML12318A125)
(2) NextEra Energy Point Beach, LLC letter to NRC, dated December 14,2012, Supplement to 10 CFR 50.55a Request, Relief Request 1-RR-4 Re-Examination of the Unit 1 Reactor Pressure Vessel lndication on the " A lnlet Nozzle Weld Fifth Ten-Year lnservice lnspection Program Interval (MLI2349A364)
(3) NRC e-mail to NextEra Energy Point Beach, LLC, dated January 18, 2013, Point Beach Nuclear Plant, Unit 1 - Draft Request for Additional lnformation for Relief Request 1-RR-4 (TAC No. M9905)
In Reference (I), supplemented by Reference (2), NextEra Energy Point Beach, LLC (NextEra) requested that the Nuclear Regulatory Commission (NRC) grant relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code),Section XI, 2007 Edition with Addenda through 2008 for the re-examination of the Point Beach Nuclear Plant (PBNP) Unit 1 reactor pressure vessel (RPV) " A lnlet Nozzle Weld RC-32-MRCL-Alll-03. Relief was requested on the basis that alternative methods would provide an acceptable level of quality and safety.
Via Reference (3), the NRC determined additional information was required to enable the staff's continued review of Relief Request 1-RR-4. Enclosure 1 contains the NextEra response to the NRC staff's request for additional information.
This letter contains no new Regulatory Commitments and no revisions to existing Regulatory Commitments.
NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241
Document Control Desk Page 2 If you have questions or require additional information, please contact Mr. Michael Millen, Licensing Manager, at 9201755-7845.
In accordance with the provisions of 10 CFR 50.91, a copy of this submittal has been provided to the designated Wisconsin Official.
Very truly yours, NextEra Energy Point Beach, LLC Larry Meyer Site Vice President Enclosure cc: Regional Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW Mr. Mike Verhagan, Department of Commerce, State of Wisconsin
ENCLOSURE I NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT UNIT 1 RELIEF REQUEST 1-RR-4 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION The NRC staff determined that additional information was required (Reference 3) to enable the continued review of the Point Beach Nuclear Plant (PBNP) Relief Request 1-RR-4 (References 1 and 2). The following information is provided by NextEra Energy Point Beach, LLC (NextEra) in response to the NRC staff's request.
By letter dated November 9, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12318A125), as supplemented by letter dated December 14, 2012 (ADAMS Accession No. MLl2349A364), NextEra Energy Point Beach, LLC (the licensee) submitted Relief Request (RR) I-RR-4 requesting the use of alternate root mean square (RMS) error criteria for sizing flaws that is greater than the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Case N-695, "Qualification Requirements for Dissimilar Metal Piping Welds," at the Point Beach Nuclear Plant Unit I.
The NRC staff has reviewed and evaluated the information provided by the licensee and determined that the following information is needed in order to complete its review of the relief request.
While the inspection procedure is described as having a depth-sizing RMS Error of 0.212 inches, no information is stated about the detection and length sizing capabilities of the inspection procedure. Has the inspection procedure passed the Appendix Vlll detection and length sizing requirements of ASME Code Case N-695?
NextEra Response The inspection procedure has passed the Appendix Vlll detection and length sizing requirements of ASME Code Case N-695. The Electric Power Research Institute Specific Details of Qualification for this procedure is included in Attachment 1 to this Enclosure.
Page 1 of 2
References NextEra Energy Point Beach, LLC letter to NRC, dated November 9, 2012, 10 CFR 50.55a Request, Relief Request 1-RR-4 Re-Examination of the Unit 1 Reactor Pressure Vessel lndication on the " A lnlet Nozzle Weld Fifth Ten-Year lnservice lnspection Program Interval (ML12318A125)
NextEra Energy Point Beach, LLC letter to NRC, dated December 14, 2012, Supplement to 10 CFR 50.55a Request, Relief Request 1-RR-4 Re-Examination of the Unit 1 Reactor Pressure Vessel lndication on the "A"lnlet Nozzle Weld Fifth Ten-Year lnservice lnspection Program Interval (ML12349A364)
NRC e-mail to NextEra Energy Point Beach, LLC, dated January 18, 2013, Point Beach Nuclear Plant, Unit 1 - Draft Request for Additional Information for Relief Request 1-RR-4 (TAC NO.M9905)
Page 2 of 2
ATTACHMENT I NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT UNIT 1 RELIEF REQUEST 1-RR-4 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ELECTRIC POWER RESEARCH INSTITUTE SPECIFIC DETAILS OF QUALIFICATION 3 Pages Follow
ELECTRIC POWER RESEARCH 1NSTiTUTF Performance Demonstration Initiative Program Printed: 21-Sep-12 PERFORMANCE DEMONSTRATlONPROGRAM In Accordance with the PDI Implementation of Section XI, Appendix Vm PDQS No: 722 Specific Detail of Qualifications Owner: TB[I Southwest Technologies, Inc.
Procedure: ISwT-PDI-AUT11 ;Revision: 2; Addenda: 0 Automated Inside Surface Ultrasonic Examination of Piping Welds Using Phased Array PDQSRev: 0 .4nalysis SW TypelRev: ULTRAVISION, 1.1 Q5 Date of bsue: 18-Sep-12 Operator SW TypelRcv: UltmVjsion 1.1Q5 Hardware: m E C Tomoscan Ill Scan Application: Fully-Autominic Category: Piping Edrufncc: Inside Ranges Demonstrated:
I Date:
~iubinm:
MaxDiam:
07-Jun- 12 27.50 MinThick:
29.00 MarThick:
2.340 2.540 I1 Dnte:
MinDiam:
MaxDiam:
07-Sun-12 27.50 MiiThick:
50.00 MaxThick:
2.400 5.200 I
Material: Austenilic without IGSCC I Material: Dissimilar Metal Examina,tion: Detection Access: Double Sided Weld Condition: Ground Flush I Examination: Detection Access: Double Sided Weld Condition: Gmund Flush i
1 i
Weld Condition: As Welded Weld Condition: As Welded Examination: h g t h Sizing Examination: Length Sizing Access: Double Sided Access: Double Sided
\Veld Condition: Ground Flush Weld Condition: Ground Rush I I Weld Condition: As Welded I Weld Condition: As Welded Page 1 of 3
ELECTRIC POWER RESEARCH INSTITUTE Performance Demonstration Initiative Program Printed: 21Sep-12 PERFORMANCE DEMONSTRATIONPROGRAM In Accordance with the PDI Implementation of Section XI, Appendix VlTI PDQS No: 722 Specilic Detail of Qualifications Owner: IHI Southwest Technologies, Inc.
Procedure: ISwT-PDI-AUT11; Revision: 2; Addenda: 0 Automated Inside Surface Ultrasonic Examination of Piping Welds Using Phased Array PDQS Rev: 0 . M y s i s SW TypeiRev: ULTRAVISION, 1.1 Q5 Date of Issue: 18-Sep12 Operator SW Type/Rev: UlhaVision, 1.145 Hardware: ZETEC Tomoscan TLl Scan Application: Fully-Automatic Category: Piping ExrmSurfnw: Inside I
---- - --. - - - 1 Wh& "Length Sizingnis indicated, the 0.750 RMS acceptance criteria per the PDIProgmm Description has been achieved.
1 When 'Through Wall Sizingt'is indicated, the 0.125 RMS acceptance criteria per the PDI Program Description Iws been a t h i e d . -- - --.
[ Tolerances for field applicntions as follows:
1 Diameter Lower: ,500"can be subncted &om the minimum diameter delnonstrated 1 Upper Diametersgwtatban 21"need not be demonstrated.
Thickness: Lower: 0.100" can be submcted from the minimum thickness demonsated for both austenitic and fenitic 15% of the~ninimumthickness demonstratedfor dissimilar metal welds 1 Upper. 1.000" can be added to the mximum thiclcness demonstrated for ferritic material.
0.500" can be addedto the maximum thicknes demousbated for austenitic material.
I _ _ 25% of the lnaxinum thickness demonstrated for dissimilar metal welds 1 . - ------ - - _---A
~omments: I See Table 1 for III~ procedure for list of qualified seiu-ch unit instrument combinations.
2 Detection, length and depth sizing of embedded flaws has not been demansmied during ihis qualification.
3 11edian~etersnoted on this document are inside diameters.
4 The tllickness values shown on this PDQS exclude the clad tlzickncsswhere applicable.
5 For both Supplement 2 and 10 the term "As Welded" deiued under weld condition in the dissimilarmetal weld qualifications rerm to the fcniic base metal clad collditiolr and the mot condition of the closure weld ~ o ~ g u r a t i o n s .
6 Candidates qualified to earlier versions of this procedure rue also qualified to utilize thisversion wi&out requalificarion,withhl the b u n & of their personnel PDQS.
7 The Appendix WI demonshation requirements applicable to thisprocedure do no contain provisions to dr~nonstratesizing of axial flaws. When required, the techniques described for circumfemntial flaw sizing shall be used for axial flaw sizing.
Limitations: 1 This procedu~dcandidateis nor qualified for examinationsperformed from the cast stainless steel side o f a comnponeut 2 This procedurdcandidatcis not qualified for depth sizing Page 2 of 3
ELECTRIC POWER RESEARCH INSTlTUTE Performance Demonstration Initiative Program Printed:
PERFORMANCE DEkdONSTRAndN'PROGRAM In Accordance with the PD1 Implementation of Section XI, Appendix VIII PDQS No:
Specific Detail of Qualif~cations Owner: IHI Southwest Technologies, Inc.
Procedure: ISwT-PDI-AUT11; Revision: 2; Addenda: 0 Automated Znside Surface Ultrasonic Examination of Piping Welds Using Phased Array PDQS Rev: 0 Analysis SW T>pe/Rev: ULTRAVISION, 1.1 Q5 Date of Issue: 18-Sep-12 Operator SW Typacv: Ultravision, 1.145 Hardware: ZETEC Tornoscan m Scan Application: FuUy-Automatic Category: Piping Ejamsmrface: Inside The above procedure has met the requirements of The Performance Demonstration Initiative's Implementation of The American Society of Mechanical EngineersBoiler and Pressure Vessel Code,Section XI, Appendix VIII, as stated in this document.
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~e&nce Demonstration Initiative Piping and Bolting Supervisor/LevelIII
'~erformanceDemonstration Initiative Piping Project Manager Page 3 of 3