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Relief Request B-5, Response to Request for Additional Information
	ML051370314
Person / Time
Site:	Vermont Yankee
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)
	v • d • e

{{#Wiki_filter:Entergy Nuclear Northeast Entergy Nuclear Operations, Inc. Vermont Yankee P.O. Box 0500 J9

 ~E1     terffl<      B tTY~I                                                              185 Old Ferry Road 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

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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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NUCLEAR SERVICES DIVISION PROCEDURE a 2I 7KE INSERVICE INSPECTION PAGE IY , RU SUPPLENEXTAL DATA SHEET 5 SILO (. s 8. -33 PL&NT: V Y OUTAGE: Sifi L- 'RS5 DRAWING: REV.: _° SYSTEM: P.H A COMPONENTIVELD NO.: RE)I - 3 7- - EN: _J/jq LOCATION: D L,' Examination Detai1s/Sketch: S If. TC- F (60'AL FL FLO AVERMCE CAOSS SLCrcO,4 Pok THE CC FOLLO".IW AOLCA5: 34'CW TO 40c -- +/- TO &2 *c-

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DATE 4-_-_ 6 DATE AJ/i4 TS? COORDINATOR (If ASME XI Exam) - DATE 10 _ _5 DATE -

ANTI (Optional) DATE ______ R6559 FORtt 3 III

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

(yI PROCEDURE NUCLEAR SERVICES DMSION REVISION YA-PE-1 YANKEE INSERVICE INSPECTION PAGE 0 11 nf 11 YPPE-141 LIOUID PENETRANT EXAMINATION REPORT PLANT Vg y,&&4_OUTAGE 42/2d~Z DPAWING j/-d72,O-d/2-2 e e&, C4&. REV. n SYSTEMe jr A - WEELD N LOCATION AP, CZ W /* PI

                                                       -    20 -,                         _--

EXAMINATION DETAILS PROCESS: Solvent Removable Color Contrast Temperature verified between 60-F and 125F eyes 0 No

Haterial:-C-fhf~tt/irr-SM ~Thermometer SIN /2?RA-26 Surface Condition:, 0 As-Velded Around 0 Machined 0 Other MATERIALS: Manufacturer Designation Batch No.

Precleaner: __________ZX C __A_-_ , Penetrant: JM ct - C9 Remover: t U Developer: yk - C2. Post-Cleaner: _c-ep-w< 2.,9 4 EXAMINATION/DETAILS/SKETCH 2/ k,, LAY,727-2 C A0 t. 1A

     -- ,9r1,01 I_          - A   --                &~L 21 k ,#                                               41                9 4  .,

14A/1 a - 2

Y/ Ya ACCEPTANCE CRITERIA ASME XI 17 ASME III NX-5000 a ASME III NX-2500 0 ANSI B31.1 0 Other A1 .

1 NU I.,AI Un KtLUKU: Ind. No. Size Location Accept Reject Comments -

                                                                .-                                                     . 0 0

O.E 0 E3 0 [3 0 tc n

                                                                                                                                             /3Z 0

- -Yr/ 9: Date: 9-29 1

FWI IN£Rv j4a-, L.4 JJ.fl A, /tna d_ ( I,- Iov al

                                                             -..              . 9..%/A                                                     Date:    A31A -

Cog. Eng7/Exaxm Agency ISI Coordinator (ifASME XI Exam) Date: 7 {(' OA (Optional) ,. _ Q A3 t4 Date: 114-,. ANII (Optional) l/- X Date: FORM 1 I bt I Re-,- 63 Yu

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

YA-UT-1 PROCEDURE 9 NUCLEAR SERVICES DIVISION REVISION 11 of 12 WPf -. INSERVICE INSPECTION PAGE REEE i, ^ . ._ ^ SUPPLEHEHTAL DATA SHEET / piul-a-as PARa 7-PLANT: 1kyM )G&plf)CeOUTAGE: J ( D DRAVIHG: _ REV.: 0 SYSTM:8e PI () CONPONEKT/IELO NO. :lTC; f-OO4T hFAI&^ 3' / LOCATIOH: Deg LAxZ K2w (lUdee kPv W6105 I) Examination Details/Sketch: 1 P-4 Il(2) 1 y i Iocaed @I 0o pi 49001-_ nv4L~,- ce 2 ch -i pOe 1 ~ CJka er pOJ "L. 0qr ti~ ef-D

                                                  .--,a)           F 41+,             p19er(         iem 1

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                            " q-11 2-"
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                                                                               - (0.q51 i03pIee il IV--                                                                               &q.n1 Smplehek Uj                          U Pmrallel S-e- oa-SILcIed Woc 3.4 L2WJAncd                              Urfe ni bolh -di ronE.

I S.( o Z( inQ.rr pJe -

                                                       *X2(p :Y. 78t                8i :32X Cfoi'mpleke EXAMINER                       A      &/                 1(9                  LEVEL                     DATE        ____

COG. ENG.,BqA HAGENCY A IDATE AP ISI COORDINATOR (If ASHE XI Exam) ___ DATE9_____ 9 OA (Ootionall 4Ur4A DATE - _ _

                                                '                        _-_                           DATE Cove-
                                                                      °55<-~    t)                    1-39/A-=i0i FORH 3

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 ZRAIN ISI.RPV-10+ REV.: ° _ ly"(e SYSTEM: . IH PR COHPONEHT/WELD NO.: T E) IO0 EN: ? 1N LOCATION: R LI ECc Reference (Applicable Code Paragraphs) ___ __ __ __ __ __

    'SKETC$            (A'+/-AL)     .       t4,LID     LErJ&rH                143

C4 .
EXAri AitEA (A-8c-CP) 2.. 4 X 0. ' - I2.q I1a, NOTE: THIS skErc kePAeSER,.T5 131.4 oF 1+3 oF wrELD L1E4CTJ-1 L4 P B

CS FL AOrC-C D T-0 PlItECTION AL CoVEAA&E: .f5 [7 (.7x I.2)+ (.5X'-q)+(5X.s5)4 (.z573s.40J . 92. In" (.6'ITnt oF 1.-1ZIA XY(137?4' f 143LE6TP)= 41i631. 04,J DIAE~cvlo`AL CoVEAA6E: .5(.2x.7) + (.4-x(c.o) +.(.2~k.g) +s )'. 81 n7 SOY. (-SftIWL OF .qZ .) x (13a.4' o 143"Lenary) r 2.0. SC V. Ek TCH A: 41.63 , 4 I o.56. - z. I'ii. A x0AL -cA v COG. ENG./EXAH AGENCY I- A DATE _JI_ JSI COORDINATOR (If ASHE XI Exam) \IJ. LA-A.4.---- DATE ___2 ' OA Motional) _ h I DATE AJ14 AN[I (Optional) DATE /- 3 <,v I. R65%9 FORM 4

YA-UT-1 PROCEDURE 9 NUCLEAR SERVICES DIVISION REVISION 12 of 12 IINSERVICE INSPECTION PAGE

 *YAJEE
  -              S I. _____________________

EVALUATION REPORT /$- vr-,.-I-1 PLANT: V Y OUTAGE: SeR1teN R DRAWING: ISI-RPV- 104- REYV. °_'O SYSTEM: H ki. R COHPONENT/IWELD NO.: P T EA( I0 4- EN: " If LOCATION: P B L.I Ec Z Reference (Applicable Code Paragraphs)

     'SKETCH        B   (AXIL)A              -EL ID L EW   .      H = 14 3

w'C - 1.*4 EXArn AE A (A-B-C-D) 2. 4' X 04.§ I/7 1 IO.

fJMOE T41-5 S&fETCM RF-PESEPrJ5 3.G' OF 14-3" f wELD LOtC-rv (12 ITS N 0.3 wicE) X CC, sL. AU SF rODiPRfcTiorJAL COVE1ZAGE: . 1;5fX.2-5) + (.2).x 65) t (.1/K.2)l .O 7 4 Ih-(.ooq4 0P I, 2.¶hl) (3.6' CF 143w LE7NG&-A): 0. 12 1. ONE DIP.ECTIOAL CoVEFAAGE . s(. 5 Io) 4 (.ZS X- 1.2) + C .35-.i) - O. 735Jnw S01. - 35)4 DF I. qZ I?) (3. 6 0 F 143" LEP4Gr) O. 61/. SkETcm- B : 0.12 ', + O. 61 cx.3 0.73% AXIAL CI V COG. ENG-/EXAH AGFNCY gJ/A DATE _____1A ISI COORDINATOR (If ASME XI Exam.) °/l DATE _____;_

                                                 =P , - - " , " - -  N, OA (Ootional)                                                                                                   DATE    t'/A ANtI (Octional)                   (I                                                                            DATE _--7-ff R6S\9 FORM 4

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

   *SkETCl4      IC    (Ca^C)

t.,ELD LEiG Tt 143' " cW 1 .4
ExAm SULAiFACE = Z. 4 X 14 3* 343.2 I CS FLA N Gt W'ELD-4 - - -

L

                                                                                               -2.,

EXAM uR.FACE 4' S4ELL PROBE IF$Vs; I l ( P)xlr Pr. S e E je 1rFr.l _1 _- _ Cs

                                                            -X       -i 5,4t#=C- AR-EA            O8STAkUCrED         = X   X   Y x     ie oF     )4ur5

1.5 X .:5 XL CI,.L SkETC14 C: ( 313.2. tYo - I -) ( 3473.7. 1) - ( 7. 31F %, C14 C CA V COG. ENG./EXAM AGENCY A r DATE __ _A ISI COORDINATOR (If ASHE XI Exam) DATE 3____

OA (Optional) DATE .41z ANTI (Optional) vf1 4-DATE Z-3

/~-

R65\9 FORM 4

YA -UT-1 lfJCI3 NULARSRICSDVIIN SERVIC0ES5DM SI N PROCEDURE lREVISION 912 of 12 INSERVICE INSPECTION PAGE 0 - */ 0 L.-7 ID I kJ A .- - _ .- (,. EVALUATIOH REPORT 'I "t 1)7- S PLANT: V / OUTAGE: _tR_ I__' _E DRAWING: s-gsv ,0j REV.:° SYSTEM: R14 1ZR COMPONEN T/WELD NO.: Irx E H IO EN: tJ I P LOCATION: RAB LPJ EC A Reference (Applicable Code Paragraphs) Co V AFG-E C5-if-r1AA-Y S kETCH .'A A'XIAL cov~iA&5 - G2. I' % Sk~r-cj4 -B AxiAL COVERZF&r - o. 73%/. TorAL (A') - 6 .I¶qZ /. SkETCH C Cjac Cov ERAJ&G = 17. 36 */. ToTA L CA V t ( A(t 0/ Z- t 6 2.. q I % 4*)I 7.3 /2L = g0. 1-5-/ COG. ENG./EXAH AGENCY /dI DATE _____ ISI COORDINATOR (If ASNE XI Exam) P/A DAT DATE 3 27v §'3 OA (Oational) DATE __)_/_ _ ANTI (Optional) DATE

3 2 R65\9 FORM 4

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

YA-UT-1 PROCEDURE 9 . Y L KE NUCLEAR SERVICES DISION REVISION 11 of 12 INSERVICE INSPECTION PAGE PrA 6V(. s o It .-Mu- I-q f Fzv SUPPLEMENTAL DATA SHEET PLANT: V L OUTAGE: ZA REV.: 6 SYSTEM: rfiK 1T XPOMENT/YELD NO. EN: _ LOCATION: M/c (§OA/64 m /K Examination Detai is/Sketch: 17.5 1.0 J.0 Tr7,rA LW10flI

                          <                                   a.-

I 2 ,S'/o SO7LI14'aOr 4R6/ X 2.q 1I~q:Z: /9,72a% £CAA EXAMINER QU,96 k Ak 7 S ,D LEVEL I / DATE

     ~COG.   `NG.W;AM AENCT                                 (t A/A                               DATE       JJ/4 ISI COORDINATOR (If   ASHE XI Exam)          CtJ4??         U                              DATE    _-30_76 OA (Oational)                                                                              DATE   _    _   _   _

ANIT (Dational) DATE 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  ;eC Work Order No:          - 0       20 - 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". L 6r";R NICA 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

Ultrasonic Examination Supplemental Report Sheet ComponentiD: I - System: 1 . . Data Sheet No: gQ5/ O/ -On P Work Order No: Procedure No: NJ ? 8S 4 Rev; O Page s oo 2 A1,O ,1 , 'S Exmnr t'-. C)/ Leel .. J Dae . 'S2. .Q .

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Reiwr ;.!A DCPate:~ 8 S1 ANi): ,-z-j /

                                                     ;-                 Date: :
                                                                                 .          . .\.          .

Ultrasonic Examination Supplemental Report Sheet Component ID: ( jq - SZO)(o Systm: Data Sheet No: G:)Y I Work Order No: D- Procedure No: P6 ¶54 Rev: 0 Page __ of . AS M6 Sec-<-- ( eJo XI P ISiLt /tJI%6n 13T 0C) 'Af" Th-ov . 6ACH LBj&ix T06 (S&e M6 ,4:OS ), Peas ~ OV~i~W~ ISITtj IIb~ K(T p t D 'c'i je

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                                                                     /     / AW&          )   I0-,A  CthE rIroF 0 V--ro Ag -4o CO06Rw VZ.4w                W~e'Alft t D-m t:           Th15i~C 4o ITli       lcJeTz' C 6AtIP          cT-,1  X 64s A-()p                      /            -A7'e-                     12-!'-SCO(       CztcUW^F*o          E4\T~rL        (bfrI4c

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                                       -t4                                                        M     M-*rtJ lt4 FoX            l CS                                                        7-               5            . °£4Gu~j         gU      p<, & oFT-{ (~QL2&                       4iRi bEDd Examiner: \U"tforA).L                                    P.Si(CI4AAJ               >       Level:__;IL_      Date:   £4-   (8  -

Examiner: _ Level: L4 Date: Reviewer: C9, Date:_______ Reviewer: A/Pr Date: ANII: - Date: 219

                 'v   1'--

Ultrasonic Examination Supplemental Report Sheet Component 1__R_3-5__) Sse:___ Data Sheet No:Sc2 ; ' * /

JJ WorkOrder N -- O0O ProcedureNo: M L: fOs. Rev: 0 Page of a 4S~26*&101 ,~1 o vciA-c?(F is 71*j- 6 I/, -r yq~ ~~ro~(~ 1~c j~' j,

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                               *,7             IC,                                  2 2-                                    v&g-Examiner:.                                       I--  *  /

JI / Level: _ Date: V-u- a Examiner: (FiA Level: L/A- Date: N/A Reviewer: _________ Date:______ Reviewer: i______; _Date: _ _ _ _ ANII: ________ Date: _ ____

_ _ I _. -j I - A

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.1 YA-UT-1 PROCEDURE 9 NUCLEAR SERVICES DIVISION REVISION 11 of. 12 INSERVICE INSPECTION PAGE VA- tT-;7 -00;? SUPPLEMENTAL DATA SHEET ivr1- 7010S-300 PLANT: v Y OUTAGE: P.F - Z I HG: REV.: 2. SYSTEH: R uV C COMPONENT/14ELD HO. CIUS 4

                                                                                         -                          EH:      kJ IA LOCATION:    IRB    2.5.2 Examination Details/Sketch:                                F L 0   U.     ,

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e .04-1? oF 4172. W 25 Y. I AXIAL CoVEEZRC-E= £ 2. + - 6 4. 5 'A T,,j avevr,3 i-c;i,,, Gverv_ ),

                             =(crew. i.zcv)-/,z I ..     = 6-,,,,%                                 ..

7 EXAHIHER , v 1_7 - - LEVEL W DATE l1-Z-' I COG. EHG./EXAH AGENCY /A -. DATE ISI COORDINATOR (If ASHE XI Exam' Lzr ___ __ - _ _ _--_ __ :_ _- _ _ DATE _____ _ OA (Ontlonal) nr.P DATE ANtI (ODtional) DATE IV tt7SV> 6' R65\9 r FORM 3}}

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