ML032810440

To Fourth-Interval Inservice Inspection (ISI) Program Plan, Submittal of Relief Request RI-01

ML032810440
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	10/01/2003
From:	Devincintis J Entergy Nuclear Operations, Entergy Nuclear Vermont Yankee
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 03-89
Download: ML032810440 (10)

Text

{{#Wiki_filter:Entergy Entergy Nuclear Vermont Yankee, LLC Entergy Nuclear Operations, Inc. 185 Old Ferry Road Brattleboro, VT 05302-0500 October 1, 2003 BVY 03-89 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271) Supplement 2 to Fourth-Interval Inservice Inspection (ISI) Program Plan - Submittal of Relief Request RI-01 On April 1, 2003, Vermont Yankee Nuclear Power Station (VY) submitted to the NRC a revised Inservice Inspection (ISI) Program' as required by IOCFR50.55a(aX3Xi). The subject submittal contained a number of relief requests for NRC review and approval. The attached Relief Request has also been identified as warranting NRC review and approval. Accordingly, attached for your review and approval in parallel with our Fourth-Interval ISI Program Review is Relief Request RI-01 "Reactor Internals." This submittal requests to implement various BWRVIP Guidelines in lieu of select ASME Section Xl requirements. Attachment I identifies the commitments contained within this letter. Attachment 2 contains Relief Request RI-01. If you have any questions on this transmittal, please contact Mr. Thomas B. Silko at (802) 258-4146. Sincerely, James M. DeVincintis Manager, Licensing Attachments cc: USNRC Region I Administrator USNRC Resident Inspector - VY USNRC Project Manager - VY Vermont Department of Public Service I Reference VY Letter to USNRC, dated April 1,2003, BVY 03-28, "Fourth-interval Inservice Inspection Program Plan and Fourth-interval Inservice Inspection Pressure Test Program and Request for Approval of ISI Relief Requests." 14& 4

Docket No. 50-271 BVY 03-89 Vermont Yankee Nuclear Power Station Supplement 2 to Fourth-Interval Inservice Inspection (ISI) Program Plan - Submittal of Relief Request RI-Ol List of Commitments

SUMMARY

OF VERMONT YANKEE COMMITMENTS BVY NO.: 03-89 The following table Identifies commitments made In this document by Vermont Yankee. Any other actions discussed in the submittal represent intended or planned actions by Vermont Yankee. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Licensing Manager of any questions regarding this document or any associated commitments. COMMITMENT COMMITTED DATE I OR "OUTAGE" None I N/A

Docket No. 50-271 BVY 03-89 Vermont Yankee Nuclear Power Station Supplement 2 to Fourth-Interval Inservice Inspection (ISI) Program Plan - Submittal of Relief Request RI-O1 Relief Request RI-01

LICENSEE/UTILITY NAME - Entergy Nuclear Operations, Inc. PLANT NAME, UNIT - Vermont Yankee 10-YEAR INTERVAL - Fourth Interval REQUEST FOR RELIEF No. RI-01 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i) - Alternative Provides Acceptable Level of Quality and Safety -

1. ASME Code Component(s) Affected ASME Section XI, Class 1, Examination Categories B-N-I and B-N-2, Code Item Nos. B13.10, Vessel Interior, B13.20, Interior Attachments within Beitline Region, B 13.30, Interior Attachments beyond Beltline Region, and B 13.40, Core Support Structure

2. Applicable Code Edition and Addenda

1998 Edition with Addenda through 2000

3. Applicable Code Requirements

ASME Section Xl requires the examination of components within the Reactor Pressure Vessel. These examinations are included in Table IWB-2500-1 Categories B-N-I and B-N-2 and identified with the following item numbers: B13.10 Examine accessible areas of the reactor vessel interior each period by the VT-3 method. B 13.20 Examine interior attachment welds within the beltline region each interval by the VT-I method. B 13.30 Examine interior attachment welds beyond the beltline region each interval by the VT-3 method. B1 3.40 Examine surfaces of the core support structure each interval by the VT-3 method. These examinations are performed to assess the structural integrity of components within the boiling water reactor pressure vessel.

4. Reason for Request

To avoid unnecessary inspections and to conserve radiological dose, while still maintaining an adequate level of quality and safety for examination of the affected welds.

5. Proposed Alternative In lieu of the requirements of ASME Section Xl, 1998 Edition, 2000 Addenda, the proposed alternative described in the enclosure shall be used.

BVY 03-89, Attachment 2, Page I of 6

Vermont Yankee will examine components within the reactor vessel in accordance with BWRVIP Guideline requirements. The particular guidelines that are applicable to those components are: BWRVIP-1 8 "BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines" BWRVIP-25 "BWR Core Plate Inspection and Flaw Evaluation Guidelines" BWRVIP-26 "BWR Top Guide Inspection and Flaw Evaluation Guidelines" BWRVIP-38 "BWR Shroud Support Inspection and Flaw Evaluation Guidelines" BWRVIP-41 "BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines" BWRVIP-47 "BWR Lower Plenum Inspection and Flaw Evaluation Guidelines" BWRVIP-48 "Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines" BWRVIP-76 "BWR Core Shroud Inspection and Flaw Evaluation Guidelines" The attached Table compares present ASME Category B-N-I and B-N-2 requirements with the above current BWRVIP Guideline requirements applicable to Vermont Yankee. In addition, the requirements of BWRVIP-94, "Program Implementation Guideline," will be followed. BWRVIP-94 states that where guidance in existing BWRVIP documents has been supplemented or revised by subsequent correspondence approved by the BWRVIP Executive committee, the most current approved guidance will be implemented. Therefore, the attached Table only represents a current comparison. Basis for Use BWRs now examine reactor internals in accordance with BWRVIP guidelines. These guidelines have been written to address the safety significant vessel internal components and to examine these components using appropriate methods and reexamination frequencies. The NRC has agreed with the BWRVIP approach in principal and has issued Safety Evaluations for these guidelines (see References below). Therefore, use of these guidelines, as an alternative to the subject Code requirements, provides an acceptable level of quality and safety and will not adversely impact the health and safety of the public.

6. Duration of Proposed Alternative

It is proposed to use the alternative for the duration of the Vermont Yankee Fourth Ten-Year Interval (September 1, 2003 through August 31, 2013).

7. References I. Letter USNRC to BWRVIP, dated April 27, 1998, "Final Supplement to the Safety Evaluation of the BWRVIP, BWRVIP-07 Report"

2. Letter USNRC to BWRVIP, dated September 15, 1998, "Safety Evaluation of the BWRVIP, BWRVIP-06 Report"

3. Letter USNRC to BWRVIP, dated September 29, 1999, "Final Safety Evaluation of 'BWRVIP, BWR Top Guide Inspection and Flaw Evaluation Guidelines (BWRVIP-26),' EPRI Report TR-107285, December 1996"

4. Letter USNRC to BWRVIP, dated September 29, 1999, "Final Safety Evaluation of 'BWRVIP, BWR Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines (BWRVIP-48),'

EPRI Report TR-108724"

5. Letter USNRC to BWRVIP, dated October 6, 1999, "Staff Reevaluation of Table I in the BWRVIP-07 Report" BVY 03-89, Attachment 2. Page 2 of 6

6. Letter USNRC to BWRVIP, dated October 13, 1999, "Final Safety Evaluation of 'BWRVIP, BWR Lower Plenum Inspection and Flaw Evaluation Guidelines (BWRVIP-47),' EPRI Report TR-108727"

7. Letter USNRC to BWRVIP, dated December 2, 1999, "Final Safety Evaluation of BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines (BWRVIP-18)"

8. Letter USNRC to BWRVIP, dated December 19, 1999, "Final Safety Evaluation of BWRVIP,

'BWR Core Plate Inspection and Flaw Evaluation Guidelines (BWRVIP-25)' EPRI Report TR-107284, December 1996"

9. Letter USNRC to BWRVIP, dated July 24, 2000, "Final Safety Evaluation of the 'BWRVIP, BWR Shroud Support Inspection and Flaw Evaluation Guidelines (BWRVIP-38),' EPRI Report TR-108823"

10. Letter USNRC to BWRVIP, dated February 4, 2001, "Final Safety Evaluation of the 'BWRVIP, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines (BWRVIP-41)"'

I1. Letter USNRC to BWRVIP, dated August 20, 2001, "Final Safety Evaluation of the 'BWRVIP, Shroud Vertical Weld Inspection and Evaluation Guidelines (BWRVIP-63) BVY 03-89, Attachment 2, Page 3 of 6

Comparison of ASME Category B-N-i and B-N-2 Requirements With BWRVIP Guidance Requirements ASME Item Component ASME Exam ASME ASME Applicable BWRVIP BWRVIP BWRVIP Frequency No. Table Scope Exam Frequency BWRVIP Exam Exam IWB-2500-1 Document Scope B13.10 Reactor Vessel Interior Accessible VT-3 Each period BWRVIP-18, Per VY Program Procedure PP 7027 Areas 25,26, 38,41, See Attached Table I (Non-specific) 47,48, 76 B13.20 Interior Attachments Within Accessible VT-I Each 10-BWRVIP-48 Riser Brace EVT-I 100% in first 12 Beitline - Riser Braces Welds year Table 3-2 Attachment years, 25% during Interval each subsequent 6 years Lower Surveillance Specimen BWRVIP-48 Bracket VT-3 Each 10-year Interval Holder Brackets I Table 3-2 Attachment I I B13.30 Interior Attachments Beyond Accessible VT-3 Each 10-BWRVIP-48 Bracket VT-3 Each 10-year Interval Beitline - Steam Dryer Hold-Welds year Table 3-2 Attachment down Brackets Interval Guide Rod Brackets BWRVIP-48 Bracket VT-3 Each 10-year Interval Table 3-2 Attachment Steam Dryer Support Brackets BWRVIP48 Bracket EVT-1 Each 10-year Interval Table 3-2 Attachment Feedwater Sparger Brackets BWRVIP-48 Bracket EVT-1 Each 10-year Interval Table 3-2 Attachment Core Spray Piping Brackets BWRVIP-48 Bracket EVT-I Every 4 Refueling Table 3-2 Attachment Cycles Upper and Middle Surveillance BWRVIP-48 Bracket VT-3 Each 10-year Interval Specimen Holder Brackets Table 3-2 Attachment Shroud Support (Weld H9) BWRVIP-38 Weld H9 EVT-1 or Maximum of 6 years 3.1.3.2, UT for EVT-I, Maximum Figure 3-5 of 10 years for UT Shroud Support Legs (H12 (Rarely BWRVIP-38 Not Not Not Required Welds) Accessible) 3.2.3 Required Required B13.40 Integrally Welded Core Support Accessible VT-3 Each 10-BWRVIP-38 Welds H8, EVT-1 or Maximum 6 years for Structure - Shroud Support Surfaces year 3.1.3.2, H9 UT EVT-l, 10 years for Interval Figure 3-5 UT Shroud BWRVIP-76 Welds HI, EVT-1 or Maximum 10 years 2.2.1 H2 UT BWRVIP-76

Vertical, EVT-I or Maximum 6 years for Figure 3-3 Ring Seg.

UT one-sided EVT-I, 10 Welds years for UT Below H2 BWRVIP-76 Tie-rod VT-3 All four within 10 3.5 Repair years NOTE: This Table provides only an overview of the requirements. For more details, refer to ASME Section XI. Table IWB-2500-1. and the appropriate BWRVIP document. BVY 03-89, Attachment 2, Page 4 of 6

Table 1 Outage Year 195 1996 1998 19 2001 2002 2004 2005 2007 2008 2010 2011 Reactor Internal Component Outage RFO18 RFO19 RF020 RFO21 RF022 RF023 RF024 RFO25 RF026 RF027 RFO 28 RF029 Control Rod Drive Guide Tube Body Welds EVTI (4) EVTI (I) EVTI EVT-I (IN) _ Conrol Rod Drive Guide Tube Lg and Pin VT3 VT3 VT3 VT3 VT-3 VT3 Core Plate Rim Hold-Down Bolts VT3 VT3 (W0lo) VT3 (50%) VT-3 (50%1s) VT-3 (50%!.) UT Core Shroud Horizontal Welds (Hl-H3) UT EVTI EVTI Core Shroud Horizntal Welds (H4-H7) UT Core Shroud Vertical Welds UT/ET EVTI EVI Core Shroud TG/CP Ring Segment Welds UT/ET EVTI EVI Core Shroud Flange Ring Segment Welds Core Shroud Tie-Rod Repair VT3 (all) VT3 (all) Vi3 (all) VT3 (2) VT3 (2) Core Shroud Support Welds (HS, H9) UT/ET UT or EVTI Core Shroud Support Access Hole Cover VT VT MUVTI EVT EVTI ET) EVTI Core Shroud Support Annulus Floor vr3T3 VT3 m m m VT3 VT3 VT3 m m Core Spray Thermal Sleeve Welds (Hidden) UT Core Spray Piping Welds (except P9) MVTI UT EVTI EVTI EVTI EVTI EVTI EVTI EVTI EVTI EVTI Core Spray P9 Welds UT UT UT Core Spray Sparger Large Circ Welds CSVTI CSVTI MVI EVTI EVTI EVI EVTI Core Spray Sparger Nozzle Welds CSVTIl CSVTIl VT3 VTI (50Y) VTI (50%) VTI (500/.) VTI (50%) Core Spray Piping Brackets MYTI MVTI EVTI EVTI Core Spray Sparger Brackets CSVTI CSVTI VT3 VTI VTI VTI Core Spray Sparger Tee-Box Repair (Old) V3 m m m Feedwater Sparger Tee Welds MVTI MVTI VTI VTI VTI VTI Feedwater Sparger End Bracket Attachment MVI MVTI VTI EVTI VTI VTI VTI Feedwater Sparger Piping and Brackets VT3 VT3 VT3 VT3 VT3 VT3 Feedwater Nozzle Inner Radii UT UT UT(l) UT Guide Rods VT3 Incore Dry Tubes MVT] (3) VTI,3 2) VT,3 (2) VT],3 (5) VTI,3 (5) VT],3 (5) VF1,3 (5) Integrally Welded Core Support Structures VT3 Jet Pump Beams UT UT (500/e) UT UT Jet Pump Thermal Sleeve Welds (Hidden) UT UT (50%fe) Jet Pump Riser Welds (RS-I, RS-2, RS-3) UT UT (flaws) EVT-I UTorEVTI EVT-I (flaws) (5f)(flaws) Jet Pump Riser Welds (RS-4, RS-5, RS-8) MVT (OY.) EVT (50%) = EVT (25%) Jet Pump Riser Brace Welds VT (50Y) VT (50Y) MVT (500) EVi (50%) EVT (251%) Jet Pump Inlet Bolted Connection Vm) (50%) m (50%) VT3 (50%Y) VT3 (50%/6)I VT3 (25/6)_ Jet Pump Restrainer Wedges VT (50%1) VT (50/) VT (50%s) VT] (50%) VTI (50) VT] (50%) VTI(250/v-Jet Pump Restrainer Setscrews VT (50%) VT (5 00%) VT (5 001) m (50%O) m (50%) m (50% I V73 (50%) Jet Pump Mixer/Diffuser Welds (above shell) UT (000/0) Jet Pump Diffuser/Adapter Welds (below UT (100%) UT (4 flaws) EVT-I (4 UT or EVTI shell) __flaws) (50%) Jet Pump Sensing Unes VT(50°/) VT5 0%) IVT(50%) I VI) (50%) V3 (50%/.) m 13(50%) m (50%) Lower Plenum (CRD, Core Shroud Support) W H E N A C C E S S I B L E LowerPlenum(CorePlate,IncoreSLC) W H E N A C C E S S I B L E Miscellaneous Vessel Internal Attachments EVIVI,3 Orificed Fuel Support Castings VT3 V3 SLC Nozzle-to-Safe End Weld I EVI2* I EVT2* EV12* PT I UT BVY 03-89, Attachment 2, Page 5 of 6

Outage Year 1995 1996 1998 1999 2001 2002 2004 2005 2007 2008 2010 2011 Reactor Internal Component Outage RFO18 RFO19 RFO20 RFO21 RF022 l RF023 RF024 RF025 RF026 RF027 RFO 28 RF029 Steam Dryer VT VT (faws) VT _3 Steam Dryer Support Bracket ___UT-flaw VT3UT-flaw Steam Separitor/Shroud Head VT3 MT3 _3 Steam Separator Hold-down bolts 3_ Top Guide Aligner Assemblies VT3 (2) VT1 (2) Top Guide Hold-down Assemblies MvT (4) VTI (2) VTI (2) VTI (2) VTI (2) Top Guide Bolts (Rim and Cover Plate) _VT 73 Top Guide Grid Beams VT VT MVT1 VTI Vessel Cladding UT (aut) UT (man) Table Key Standard Print Italics UT UT (aut or man) ET PT VT EVT1 EVT2-VT1 VT3 CSVT1 or MVT1 (IN) (all, number, %, or flaw) = Inspections mandated by ASME, BWRVIP, or NRC commitments = Inspections recommended for Risk-to-Generation purposes = Ultrasonic Testing performed or planned = Either automated or manual Ultrasonic Testing = Eddy Current Testing performed or planned = Penetrant Testing performed or planned = Visual Testing performed or planned = EVT-1; Enhanced Visual Test to look for cracking; 1/2 mi wire resolution with cleaning assessment = Enhanced Leakage Inspection (direct view of component during pressure test) = VT-1; Visual Test to look for cracks, wear, corrosion, etc.; resolution required: 1/32" black line = VT-3; Vsual Test to determine general mechanical/structural condition; no resolution requirements = CSVT-1 or MVT-1; Core Spray Visual Test or Modified VT-1, no longer a defined test method; 1 mil wire resolution = If necessary (to complete minimum number of inspections not performed in previous outage) = Perfomn inspection on all components, limited number (or percentage) of components, or just flawed components BVY 03-89, Attachment 2, Page 6 of 6}}