ML051370314

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Relief Request B-5, Response to Request for Additional Information
ML051370314
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 05/11/2005
From: Devincentis J
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 05-37
Download: ML051370314 (72)
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Text

{{#Wiki_filter:Entergy Nuclear Northeast Entergy Nuclear Operations, Inc. Vermont Yankee P.O. Box 0500 J9 tTY~I B 185 Old Ferry Road 1 ~E terffl< Brattleboro, VT 05302-0500 Tel 802 257 5271 May 11,2005 BVY 05-37 U.S. Nuclear Regulatory Commission ATMN: Document Control Desk Washington, DC 20555

Subject:

Vermont Yankce Nuclear Power Station License No. DPR-28 (Docket No. 50-271) Relief Request B-S, Response to Rertuest for Additional Information By letter dated October 1, 20031, Vermont Yankee Nuclear Power Station (VY) submitted Relief Request B-5. Relief Request B-5 proposed relief for identified weld examinations from the Third Interval where the required "essentially 100%" examination coverage was impractical due to physical obstructions and limitations imposed by design, geometry, and materials of construction of the subject components. On January 19, 20052, The NRC submitted a Request for Additional Information regarding RI-01. Accordingly, the following Attachments provide the response to the request for additional information. There are no commitments contained within this letter. Please feel free to contact me at (802) 258-4236, if there are any questions regarding this subject. Sincerely, //lam s M. eVincentis Manager, Licensing Vermont Yankee Nuclear Power Station Attachments (16) cc: USNRC Region I Administrator (w/6 a d z ) USNRC Resident Inspector - VY < A/ M'a') USNRC Project Manager - VY Vermont Department of Public Service Reference VY Letter to USNRC, BVY 03-89, "Supplement 2 to Fourth-Interval Inservice Inspection (ISI) Program Plan - Submittal of Relief Request RI-OI," dated October 1, 2003. 2 Reference USNRC Letter to VY, NVY 05-05, "Request for Additional Information - Relief Request B-5 (TAC No. MC0959)," dated January 19, 2005.

ATTACHMENT 1 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Restatement of Questions and General Response to Questions ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

BVY 05-37 / Attachment I I Page i of 5 On January 19, 20053, The NRC submitted a Request for Additional Information regarding Relief Request B-5. The Staff questions are restated below: Question 1: Provide a technical basis for each component listed in Table RR-B-5 describing in detail the examination limitation, and discuss whether other [supplemental] examinations may be used to increase or supplement the limited examinations. The technical basis should include a cross-sectional sketch of the weld indicating ultrasonic coverage(s) and details of the weld and base metal materials. The technical basis should confirm, where applicable, that the examinations that were performed were qualified under Appendix VIII of Section XI. Question 2: Indicate what degradation mechanism(s) is most likely to occur in this weld and a basis for whether the achieved examination coverage could reasonably be expected to detect this degradation. Response to Questions: The questions above are requesting various related pieces of information. To summarize and explain the responses, please see below: Description of Examination Limitation The description of each limitation is described in Table I which follows. Use of Supplemental Examinations The use of supplemental examinations to enhance the inspection results is discussed in Notes 3, 8 and 9 of Table 1. Provide Cross-Sectional Coverage Sketches Coverage sketches, in addition to coverage calculations are provided on the sketches. Provide Details of the Weld and Base Materials Involved The base materials for the subject areas are identified on the coverage sketches. Weld materials are identified on the sketches where dissimilar metals are joined. Confirm, where applicable, that examinations were performed per Appendix VIII of Section Xl Table 1, Note I identifies the components which were examined per ASME Section V, Articles 4 & 5 and USNRC Reg. Guide 1.150. It is noted that additional non-code scanning angles or techniques would have 3 Reference USNRC Letter to VY, NVY 05-05, "Request for Additional Information - Relief Request B-5 (TAC No. MC0959)," dated January 19,2005.

BVY 05-37 / Attachment I / Page 2 of 5 provided little or no relevant additional data. Performance of such examinations would have significantly increased radiation dose with little or no enhancement in safety. Indicate Most Likely Degradation Mechanism The most likely degradation mechanisms are discussed in Notes 3, 8 and 9 in Table I below. Achieved Coverage will Detect Degradation Mechanism Statement of acceptable coverage to detect degradation mechanism is discussed in Notes 3, 8 and 9 in Table I below. TABLE 1 COMPONENTS WITH LESS THAN "ESSENTIALLY 100%" COVERAGE Section XI Component Exam Category System Component Examination Limitation Notes Description Coverage Item No. Number Percent B-D RPV Vessel-to-Nozzle Weld proximity to nozzle . UT. B3.90 NIA (Recirculation) blend radius limits scanning 50.4% See notes 1, 2, 3 & 4 to one side B-D RPV Vessel-to-Nozzle Weld proximity to nozzle UT B3.90 NIB (Recirculation) blend radius limits scanning 50.4% See notes 1, 2, 3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N2A (Recirculation) blend radius limits scanning 51.6% See notes 1, 2, 3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N2B (Recirculation) blend radius limits scanning 51.6% See notes 1, 2, 3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N2C (Recirculation) blend radius limits scanning 51.6% See notes 1, 2, 3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N2D (Recirculation) blend radius limits scanning 51.6% See notes 1, 2, 3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N2E (Recirculation) blend radius limits scanning 51.6% See notes 1, 2, 3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N2F (Recirculation) blend radius limits scanning 51.6% See notes 1, 2, 3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N2G (Recirculation) blend radius limits scanning 51.6% See notes 1, 2, 3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N2H (Recirculation) blend radius limits scanning 51.6% See notes 1, 2, 3 & 4 to one side BVY 05-37, Attachment, Page 2 of 5

BVY 05-37 / Attachment 1 / Page 3 of 5 B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N2J (Recirculation) blend radius limits scanning 51.6% See notes 1, 2,3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N2K (Recirculation) blend radius limits scanning 51.6% See notes 1, 2,3 & 4 to one side B-D RPV Vessel-to-Nozzle Weld proximity to nozzle UT B3.90 N3A (Main Steam) blend radius limits scanning 51.6% See notes 1, 2, 3, 4 & 5 to one side B-D RPV Vessel-to-Nozzle Weld proximity to nozzle UT B3.90 N3B (Main Steam) blend radius limits scanning 51.6% See notes 1, 2,3,4 & 5 to one side B-D RPV Vessel-to-Nozzle Weld proximity to nozzle UT B3.90 N3C (Main Steam) blend radius limits scanning 51.6% See notes 1, 2,3, 4 & 5 to one side B-D RPV Vessel-to-Nozzle Weld proximity to nozzle UT B3.90 N3D (Main Steam) blend radius limits scanning 51.6% See notes 1, 2, 3, 4 & 5 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N4A (Feed Water) blend radius limits scanning 63.3% See notes 1, 2, 3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N4B (Feed Water) blend radius limits scanning 63.3% See notes 1, 2, 3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N4C (Feed Water) blend radius limits scanning 63.3% See notes 1, 2, 3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N4D (Feed Water) blend radius limits scanning 63.3% See notes 1, 2, 3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 NSA (Core Spray) blend radius limits scanning 67.1% See notes 1, 2, 3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N5B (Core Spray) blend radius limits scanning 67.1% See notes 1, 2, 3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N6A (Head Spray) blend radius limits scanning 52.5% See notes 1, 2, 3 & 4 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 N6B (Head Spray) blend radius limits scanning 52.5% See notes 1, 2, 3 & 4 to one side B-D RPV Vessel-to-Nozzle Weld proximity to nozzle UT B3.90 N7 (Head Vent) blend radius limits scanning 49.1% See notes 1, 2 & 3 to one side B-D RPV Vessel-to-Nozzle Weld proximity to nozzle UT B3.90 N8A (Jet Pump Instr.) blend radius limits scanning 65.9% See notes 1, 2, 3 & 4 to one side B-D RPV Vessel-to-Nozzle Weld proximity to nozzle UT B3.90 N8B (Jet Pump Instr.) blend radius limits scanning 65.9% See notes 1, 2, 3 & 4 to one side

BVY 05-37 / Attachment 1 / Page 4 of 5 B-D RPV Vessel-to-Nozzle Weld proximity to nozzle UT B3.90 N9 (CRD - Capped) blend radius limits scanning 61.6% See notes 1, 2 & 3 to one side B-D RPV Nozzle-to-Vessel Weld proximity to nozzle UT B3.90 NIO (SLC) blend radius limits scanning 42.8% See notes 1, 2 & 3 to one side. Additional partial limitation due to RPV Support Skirt B-D RPV Nozzle Inner Radius Support skirt UT B3.I00 NIO-IR (SLC) 88.3% See notes 1, 2 & 3 B-F RPV Nozzle-to-Safe-end Flange bolting & surface UT See note 2, 9 & 10 B5.10 N6A-SE (Head Spray) depression 58% B-F RPV Nozzle-to-Safe-end Flange bolting UT See note 2, 9 & 10 B5.10 N6B-SE (Head Spray) 89.9% B-H RPV Bottom Head-to-OD of weld inaccessible due PT B8.10 SUPPORT Support Skirt to biological shield wall and 50% See note 6, 8 & 10 SKIRT insulation B-J Core Spray Valve-to-Pipe Pipe to valve configuration UT See note 7, 9 & 10 B9.11 CS4B-MF5 l(one-sided exam) 38.6% B-J RHR Pipe-to-Valve Pipe to valve configuration UT See note 2, 9 & 10 B9.11 RH28-12 (one-sided exam) 82.5% B-J RHR Valve-to-Elbow Elbow to valve configuration UT See note 2, 8 & 10 B9.1 I RH29-10 (one-sided exam) & branch 82.1% connection obstruction B-J RHR Valve-to-Pipe Pipe to valve configuration UT See note 2, 8 & 10 B9.1I1 RH32-8 (one-sided exam) & OD 73.8% surface configuration B-K Recirc 8 Lug Welds Pipe clamp on bottom of PT See note 8 & 10 B10.10 RR-89,90 shear lugs 77.8% B-Q CRD CRD Housing-to-Two I" diameter support rods UT See note 2, 9 & 10 B14.10 02-27HF Flange 85.2% B-O CRD CRD Housing-to-Two I" diameter support rods UT See note 2, 9 & 10 B 14.10 02-27SH Flange 85.2% B-O CRD CRD Housing-to-Two I" diameter support rods UT See note 2, 9 & 10 B14.10 26-03HF Flange 85.2% B-O CRD CRD Housing-to-Two 1" diameter support rods UT See note 2, 9 & 10 B14.10 34-39HF Flange 85.2% C-A RHR RHR Heat Exch. Flange geometry & 12 UT See note 2, 9 & 10 C 1.10 A-HTEX 10-Shell-to-Flange welded attachments 80.2% 4 l C-C RHR RHR Heat Exch. Limited access between shell MT See note 8 & 10 C3.10 A-RHR-CC-Welded Support and floor 80.1% 4 C-F-2 Condensate Pipe-to-Valve Valve configuration UT See note 2, 7, 8 & 10 C5.51 CT27-S30 84.5% C-F-2 Feedwater Valve-to-Pipe Valve configuration (one-UT See note 2, 7, 8 & 10 C5.51 FW-17-S5 sided exam) 79.8% C-F-2 RHR Valve-to-Pipe Weld OD profile UT See note 2, 7, 8 & 10 C5.51 RH3D-S206 configuration (limited 79.0% circumferential scan)

BVY 05-37 / Attachment 1 / Page 5 of 5 NOTES

1. This examination was performed in accordance the requirements of ASME Section V, Articles 4

& 5 and USNRC Reg. Guide 1. 150. Additional non-code scanning angles or techniques would have provided little or no relevant additional data. Performance of such examinations would have significantly increased radiation dose with little or no enhancement in safety.

2. A copy of the examination report with cross-sectional sketches and coverage calculations are attached. Sketches have been modified to include identification of component materials.
3. Flaws within the examination area would most likely have initiated from existing fabrication related discontinuities. No discontinuities of reportable size have been recorded for this component during construction or baseline examinations. This area is subjected to minimal residual and operational stress. To date, for the industry, no cracking has been reported in this area. The NDT critical flaw size for the Vermont Yankee RPV is 1/4 t (approximately 1.3").

Vermont Yankee believes that the examinations that were performed on this area would have detected a flaw of this size.

4. Examination limitations identical for all components in this Item Number; Coverage calculations performed for one, apply to all items in the Category
5. Coverage for the N3A, B, C & D nozzle to vessel welds are identical to N2A-K. See plots for N2A-K.
6. Access to ID surface only.
7. Appendix VIII examination
8. Flaws within the examination area would most likely have initiated from service induced fatigue or corrosion. No discontinuities of reportable size have been recorded for this component during construction or baseline examinations. Vermont Yankee believes that the examinations that were performed on this area would have detected service induced flaws in the accessible areas.
9. Flaws within the examination area would most likely have initiated from service induced fatigue or IGSCC. No discontinuities of reportable size have been recorded for this component during construction or baseline examinations. Vermont Yankee believes that the examinations that were performed on this area would have detected service induced flaws in the accessible areas.
10. Additional non-code scanning angles or techniques would have provided little or no relevant additional data. Performance of such examinations would have provided little or no enhancement in safety.

ATTACHMENT 2 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Coverage Sketches - NIA & NiB Nozzle to Vessel ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

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ATTACHMENT 3 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Coverage Sketches - Nozzles N2A, B, C, D, E, F, G, H, J & K ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

ATTACHMENT 4 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Coverage Sketches - Nozzles N4A, B, C & D, N5A & I} ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

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ATTACHMENT 5 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Coverage Sketches - Nozzles N6A & B ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

ATTACHMENT 6 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Coverage Sketches - N7 Nozzle to Vessel ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

ATTACHMENT 8 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Coverage Sketches - Nozzles N8A & B ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

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ATTACHMENT 7 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Coverage Sketches - N9 Nozzles ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

Data sheet: 8061-02-003 Page 4 of 8 Weld N,ozzle to Vessel Weld Coverage Obstruction: Nozzle blend configuration Base Material: 68.73% complete Weld Material: 55% complete Dimensions for coverage calculation Iron Drawing # 5920-246 taken from Chicago Bridge and 'rOW CGwvvt (croqxlcl usf-,oqS°1A-x)'0. Dsi-60°Px~lal leo il t ? s4,,,w )toF¢;*rCt lsm C o°% Czrscw 706Ge c to.T.0 /7 _w GI.6%) Reviewer: C4 p Level: Date: __Z__ __Z__O_

ATTACHMENT 9 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Coverage Sketches - Nozzle NI0 ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

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ATTACHMENT 10 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Coverage Sketches - Nozzles N6A & B ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

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ATTACHMENT 11 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Coverage Sketches - Weld No. CS4B-MF5 ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

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ATTACHMENT 12 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Coverage Sketches - Welds No. RH28-12, RH 29-10 & RH 32-8 ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

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ATTACHMENT 13 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Coverage Sketches -8 lug welds / hanger #RR-89, 90 ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR PONVER STATION DOCKET NO. 50-271

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ATTACHMENT 14 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Coverage Sketches - CRD welds 34-39HF, 26-03HF, 02-27SH & 02-27HF ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

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ATTACHMENT 15 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Coverage Sketches - HTEX 10-4 ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

YA-UT-1 INUCLE~AR SERVICES DIVSION REVISION 12 of 12 R1NSERVICE INSPECTION PROCEDUE q ( YANKE IPA_ EVALUATION REPORT .4 - Lur - d , -8 4 PLANT: V Y OUTAGE: SPA'W & q ZRA IN ISI.RPV-10+ REV.: ° SYSTEM: . IH PR COHPONEHT/WELD NO.: T E) I O0 EN: ? 1N LOCATION: R LI EC c Reference (Applicable Code Paragraphs) ___ 'SKETC$ (A'+/-AL). t4,LID LErJ&rH 143 C4

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NUCLEAR SERVICES DIVISION IINSERVICE INSPECTION PROCEDURE REVISION PAGE YA-UT-1 9 12 of 12 I. _____________________ EVALUATION REPORT /$- vr-,.-I-PLANT: V Y OUTAGE: SeR1teN R DRAWING: ISI-RPV-104-REYV. 1 °_'O SYSTEM: ki. H R COHPONENT/IWELD NO.: P T EA ( I 0 4-EN: " If LOCATION: P B L. I E c Z Reference (Applicable Code Paragraphs) 'SKETCH B (AXIL) A -EL ID L EW H = 1 4 3 w'C 1.*4 EXArn AE A (A-B-C-D)

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YA-UT-1 I N LlPROCEDURE 9 0 NUJCLEAR SERVICES DWISION REVISION 12 of 12 INSERVICE INSPECTION PACE EVALUATION REPORT PLANT: V Y OUTAGE: SAPI A c-q g SYSTEM: R 14 A. COMPONENT/WELD NO.: HTEX LOCATION: R B L tE CJ n YO - V7- >- DRAWING: 11-JIeAV-0+ tO REV.: 0 EN: P /A Reference (Applicable Code Paragraphs)

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ATTACHMENT 16 TO BVY 05-37 Relief Request B-5, Response to Request for Additional Information Coverage Sketches: A-RHR-CC-4, CT27-S30, FW17-S5, RH3DS206, RC3-S15 & CU54-16 ENTERGY NUCLEAR OPERATIONS, INC. VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

Y L KE NUCLEAR SERVICES DISION INSERVICE INSPECTION PROCEDURE REVISION PAGE YA-UT-1 9 11 of 12 PrA 6V(. It s o SUPPLEMENTAL DATA SHEET PLANT: V L OUTAGE: ZA SYSTEM: rfiK 1T XPOMENT/YELD NO. LOCATION: M/c (§OA/64 m /K .-Mu-I-q f Fzv REV.: 6 EN: _ Examination Detai 17.5 1.0 J.0 Tr7,rA LW10flI is/Sketch: I a.- 2,S'/o SO7LI14'aOr 4R6/ X 2.q 1I~q:Z: /9,72a% £CAA QU,96 k Ak S ,D LEVEL I / EXAMINER ~COG. `NG.W;AM AENCT 7 ( t A/A DATE DATE JJ/4 DATE _-30_76 DATE DATE ISI COORDINATOR (If ASHE XI Exam) CtJ4?? U OA (Oational) ANIT (Dational) R65\\9 FORM 3 I j

Ultrasonic Examination Supplemental Report Sheet Component ID C 27-- S O System: C-Is Data Sheet No: 9a8;(8 'lf9

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20 0 - C00C4 ProcedureNo: NE ~30SLk Rev: C> Page 3 of ASME Section Xl coverage is the inner 1/3 T and 1/4" from each weld toe (see NE 8054, Fig. 1). Procedure NE 8054 required coverage is the inner 1/3 T and 1/2" from each weld toe. For the purpose of calculated coverage, the ASME code coverage requirement volume was used. The examination was limited due to the pipe to valve configuration allowing examination from the pipe side only. i A 1 1/2 Vee examination was performed perpendicular to the weld from the pipe side in order to obtain complete coverage in the axial direction. Width of the area to be examined is 1.3". Width of the area covered during the examination was 0.9". N ICA L 6r";R 0.9" - 1.3" = 69% Circumferential coverage. 69% + 69% + 100% + 100% = 338% (percent coverage of Cs \\examination in four directions). f 338%. 4 = 84.5% Coverage of the required code volume. AS~ COKsAOD Examiner: LS S7K/CrtL4 Level: ig Date: Sf( ° ( Examiner: ffA / 1 CiL Level: Z Date: Reviewer: U p s Date: Hi IL. 0 ( Reviewer: 3i (A-Date: V/IA ANII: Date: ///- H/7-0

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