ML110960361

ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations Performed in the Third 10-Year Inspection Interval

ML110960361
Person / Time
Site:	Millstone
Issue date:	03/30/2011
From:	Price J Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
11-137
Download: ML110960361 (158)

Text

Dominion Nudear Connecticut, Inc.

5000 Dominion Boulevard, Glen Allen, Virginia 23060 Oe t iir Web Address: www.dom.com March 30, 2011 U.S. Nuclear Regulatory Commission Serial No.11-137 Attention: Document Control Desk NSS&L/MLC RO Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2 ASME SECTION XI INSERVICE INSPECTION PROGRAM RELIEF REQUESTS FOR LIMITED COVERAGE EXAMINATIONS PERFORMED IN THE THIRD 10-YEAR INSPECTION INTERVAL The Millstone Power Station Unit 2 (MPS2) third 10-year interval for the inservice inspection program concluded on March 31, 2010. During this interval the components identified in Attachments 1 through 10 received less than the required examination coverage. Accordingly, pursuant to 10 CFR 50.55a(g)(5)(iii), Dominion Nuclear Connecticut, Inc. requests relief on the basis that the required examination coverage was impractical due to physical obstructions and limitations imposed by design, geometry and materials of construction of the subject components.

Attachments 1 through 10 contain the specific relief requests and the individual basis for the request. These relief requests have been reviewed and approved by the station's Facility Safety Review Committee.

If you have any questions or require additional information, please contact Wanda Craft at (804) 273-4687.

Sincerely, J. an rice Vi e Pesident - Nuclear Engineering 46(-47

Serial No.11-137 MPS2 Limited Exam Relief Requests Page 2 of 2 Attachments:

1. Relief Request RR-89 Examination Category B-A, Pressure Retaining Welds in Reactor Vessel.

2. Relief Request RR-89 Examination Category B-D, Full Penetration Welds of Nozzles in Vessels - Inspection Program B.

3. Relief Request RR-89-71, Examination Category B-J, Pressure Retaining Welds in Piping.

4. Relief Request RR-89-72, Examination Category C-A, Pressure Retaining Welds in Pressure Vessels.

5. Relief Request RR-89-73, Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels.

6. Relief Request RR-89-74, Examination Category C-C, Integral Attachments of Vessels, Piping, Pumps, and Valves.

7. Relief Request RR-89-75, Examination Category C-F-i, Pressure Retaining Welds in Austenitic Stainless Steel High Alloy Piping.

8. Relief Request RR-89-76, Examination Category C-F-2, Pressure Retaining Welds in Carbon or Low Alloy Steel Piping.

9. Relief Request RR-89-77, Examination Category R-A, Risk Informed Piping Examinations.

10. Relief Request RR-89-78, Examination Category B-P, All Pressure Retaining Components.

Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 J. D. Hughey NRC Project Manager, Mail Stop 08-BlA U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

Serial No.11-137 Docket No. 50-336 ATTACHMENT 1 RELIEF REQUEST RR-89-69 EXAMINATION CATEGORY B-A PRESSURE RETAINING WELDS IN REACTOR VESSEL DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

--Inservice Inspection Impracticality--

1. ASME Code Components Effected:

ASME Code Class: Code Class 1 Examination Category: B-A, Pressure Retaining Welds in Reactor Vessel Item Numbers: B1.11, Shell Welds - Circumferential B1.12, Shell Welds - Longitudinal B13.21, Head Welds - Circumferential B13.22, Head Welds - Meridional Component Identification: Listed in Table 1 Material: SA-533-65, GR. B, CL. 1 carbon steel with internal stainless steel cladding.

2. Applicable Code Addition and Addenda ASME Section XI, 1989 Edition, No addenda

3. Applicable Code Requirement

ASME Section Xl, 1989 Edition, Examination Category B-A requires volumetric examination of 100% of the weld volume as defined in ASME Section Xl Table IWB-2500-1 and shown in Figures IWB 2500-1, IWB-2500-2 and IWB-2500-3. The alternative requirements of ASME Section Xl, Code Case N-460, approved for use in Regulatory Guide 1.147, Rev. 15, allows credit for essentially 100% coverage of the weld provided greater than 90% of the required volume has been examined.

4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the essentially 100%

volumetric examination coverage requirement for the subject welds. Due to the design of the reactor pressure vessel (RPV), geometric configuration and permanent obstructions limit the volumetric examination coverage of the subject welds.

During the third 10-year RPV examination, the best available technology was used in performing the automated ultrasonic examination from the inside surface of the RPV.

The examinations were performed with equipment, procedures and personnel qualified in accordance with the requirements of ASME Section Xl, Appendix VIII, 1995 Edition Page 1 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 thru 1996 Addenda, as implemented by the Performance Demonstration Initiative (PDI) program.

The examination of the six (6) lower head meridional welds were limited due to obstructions from the flow skirt that is permanently attached to the inside of the RPV.

Additionally, three (3) of these meridional welds are also limited due to the obstruction of the core support lugs that are permanently attached to the RPV. The examination of the lower shell to lower head weld was limited due to the obstructions from the core barrel stabilizer and core support lugs that are permanently attached to the inside of the RPV.

The examination of two (2) of the lower and middle shell longitudinal welds, and the middle shell-to-lower shell weld were limited due to the obstructions from the permanent surveillance specimen holder tubes.

These noted permanent obstructions on the inside surface of the RPV prevent achieving the essentially 100% examination coverage required by Code. Due to the high dose rates in the area, attempts to improve examination coverage from the outside surface of the RPV would result in a significant increase in the radiation exposure to personnel without a commensurate increase in the level of quality and safety.

Isometric drawings, coverage calculations, limitation sketches and flaw evaluation summaries are provided in this attachment.

5. Burden Caused by Compliance To increase examination coverage on the subject welds requires a significant design modification or replacement of components with a different design to eliminate the noted obstructions. This is impractical due to the cost, additional radiation exposure and impact to plant equipment.

6. Proposed Alternative and Basis for Use The subject welds received a volumetric examination on the accessible portions of the welds to the maximum extent practical given the limitations caused by the geometric configuration and permanent obstructions. Additionally, a visual (VT-2) examination was performed at the end of each refueling outage during the system leakage tests as required by Section XI, IWB-2500-1, Category B-P.

Based upon the examination volumes that were obtained with acceptable results and the visual (VT-2) examination performed each refueling outage, it is reasonable to conclude that service-induced degradation would be detected. Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject welds.

Page 2 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69

7. Period for Which Relief is Reauested The relief is requested for the third 10-year inspection interval for Millstone Unit 2, which began on April 1, 1999 and ended March 31, 2010.

TABLE 1- Examination Category B-A Welds with Limited Volumetric Coverage Weld Code Item Configuration Comments Ultrasonic Identification Number Examination Coverage Attained (%)

BHV-1 B13.22 Lower Head Meridional Limited examination due to 53.3 Weld (30 Deg.) obstruction caused by the permanent flow skirt within close proximity of the weld.

No recordable indications were detected.

BHV-2 B1.22 Lower Head Meridional Limited examination due to 43.4 Weld (90 Deg.) obstructions caused by the permanent flow skirt and core support lug within close proximity of the weld.

No recordable indications were detected.

BHV-3 B1.22 Lower Head Meridional Limited examination due to 53.3 Weld (150 Deg.) obstruction caused by permanent flow skirt within close proximity of the weld.

No recordable indications were detected.

BHV-4 B1.22 Lower Head Meridional Limited examination due to 43.4 Weld (210 Deg.) obstructions caused by permanent flow skirt and core support lug within close proximity of the weld.

No recordable indications were detected.

BHV-5 B1.22 Lower Head Meridional Limited examination due to 53.3 Weld (270 Deg.) obstruction caused by permanent flow skirt within close proximity of the weld.

No recordable indications were detected.

Page 3 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 TABLE 1- Examination Category B-A Welds with Limited Volumetric Coverage (continued)

Weld Code Item Configuration Comments Ultrasonic Identification Number Examination Coverage Attained (%)

BHV-6 B13.22 Lower Head Meridional Limited examination due to 43.4 Weld (330 Deg.) obstructions caused by permanent flow skirt and core support lug within close proximity of the weld.

No recordable indications were detected.

HS-1 B13.21 Lower Shell to Lower Limited examination due to 72.5 Head Weld obstruction caused by core barrel stabilizers and permanent core support lugs within close proximity of the weld.

Three recordable subsurface indications were detected and evaluated as acceptable in accordance with ASME Section Xl, IWB-3510-1.

LSL-1 B1.12 Lower Shell Longitudinal Limited examination due to 76.8 Weld (90 Deg.) obstruction caused by permanent surveillance specimen holder tubes within close proximity of the weld.

No recordable indications were detected.

MSL-1 B1.12 Middle Shell Longitudinal Limited examination due to 39.1 Weld (90 Deg.) obstruction caused by permanent surveillance specimen holder tubes within close proximity of the weld.

No recordable indications were detected.

SC-2 B13.11 Middle Shell to Lower Limited examination due to 82.6 Shell Weld obstruction caused by permanent surveillance specimen holder tubes within close proximity of the weld.

Five recordable subsurface indications were detected and evaluated as acceptable in accordance with ASME Section Xl, IWB-3510-1.

Page 4 of 55

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 A

ARE VA Domiiioti-TWS Weld Number: oW15

.Component ID: BHV-1 Item Number: Bi.22

Description:

LOWER HEAD MERIDIONAL WELD (300)

Examination Procedure: 54-ISI-801-02 Results: No Recordable Indications Status: Acceptable Data Analysts: S. Breiholz, UT Level 11 V. Zado, UT. Level. Il 51-9077940-000 Section F Page 73 of 105 Page 7 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 MILLSTONE-2 EXAMINATION COVERAGE FOR WELD: W15, W17, W19 MERIDIONALS Customer Number BHV-1, BHV-3, & BHV- 5 Scan Plan Drawing Number: 8022562D Sheets 11 and 12 WELD VOLUME COVERAGE OBTAINED: 53.3%

Zone Coverage Obtained Inner 15%T: 49.8% Outer85%": 54.0%

Examination Volume Definition Weld Length: 72.19 in.

Area Measurement Volume Calculation Inner 15%T 3.54 sq. in. Inner 15%T 255.6 cu. in.

Outer 85%T 20.56 sq. in. Outer 85%T 1484.2 cu. in.

Limitations Limits scan by: Compensation(s)

Flow Skirt Axial/Circ. Extent None Examination Coverage Calculations INNER 15%T Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg) Direction (sq. in) (in) (cu. in) (cu. in,) Examined Limited Limitations 1 70L/45L Up/Down 3.54 24.08 85.2 85.2 100.0% No 2 70L/45L Up/Down 0.00 32.85 0.0 116.3 0.0% Yes Flow Skirt 3 70LU45L CW/CCW 3.54 22.04 78.0 78.0 100.0% No 4 70L/45L CW/CCW 0.00 39.63 0.0 140.3 0.0% Yes Flow Skirt 5 70L/45L Down 3.54 15.26 54.0 54.0 100.0% No 6 70L/45L CW 3.54 10.52 37.2 37.2 100.0% No Totals: 254.5 511.1 49.8%

OUTER 85%T Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Enbrv # (del.) Direction (s(7 in) (in.) (cu. in.) (cu. in) Examined Limited Limitations 1 45L/45S Up/Down 20.56 24.08 495.1 495.1 100.0% No 2 451-/45S Up/Down 0.00 32.85 0.0 675.4 0.0% Yes Flow Skirt 3 45L/45S CW/CCW 20.56 25.04 514.8 514.8 100.0% No 4 45L/45S CW/CCW 0.00 33.63 0.0 691.4 0.0% Yes Flow Skirt 5 45LJ45S. Down. 20.56 15.26 313.7 313.7 100.0% No 6 45L/45S CW 20.56 13.52 278.0 278.0 100.0% No Totals: 1601.6 2968.5 54.0%

Entries 1, 2, 3, and 4 are values for dual sided coverage below the Flow Skirt Entries 5 and 6 are values for single sided coverage above the Flow Skirt Page 17 of 20 Page 8 of 55

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 A

AREVA TWS Weld Number: W16 Component ID: BHV-2 Item Number: B1.22

Description:

LOWER HEAD MERIDIONAL WELD (900)

Examination Procedure: 54-ISI-801-02 Results: No Recordable Indications Status: Acceptable Data Analysts: S. Breiholz, UT Level II V. Zado, UT Level III 51-9077940-000 Section F Page 75 of 105 Page 11 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 MILLSTONE-2 EXAMINATION COVERAGE FOR WELD: W16, W18, W20 MERIDIONALS Customer Number BHV-2, BHV-4, & BHV- 6 Scan Plan Drawing Number: 8022562D Sheets 11 and 12 WELD VOLUME COVERAGE OBTAINED: 43.4%

Zone Coverage Obtained Inner 15%T: 43.6% Outer 85%T: 43.4%

Examination Volume Definition Weld Length: 72.19 in.

Area Measurement Volume Calculation nner 15%/T 3.54 sq. in. Inner 15%T 255.6 cu. in.

Duter 85%T 20.56 sq. in. Outer 85%T 1484.2 cu. in.

Limitations Limits scan by: Compensation(s)

Flow Skirt Axial/Circ. Extent None Support Lugs. Axial/Circ. Extent Examination Coverage Calculations INNER 15%T Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent

.._nty # (deg.) Direction (sq. in.) (in.) (Cu.in.) (cu. in.) Examined Limited Limtations 1 70LU45L Up/Down 3.54 24.08 85.2 85.2 100.0% No 2 70L/45L UplDown 0.00 32.85 0.0 116.3. 0.0% Yes Flow Skirt 3 70L/45L CW/CCW 3.54 22.04 78.0 78.0 100.0% No 4 70LU45L CW/CCW 0.00 39.63 0.0 140.3 0.0% Yes Flow Skirt 5 70U45L Down 1.76 15.26 26.9 54.0 49.7% Yes Support Lug 6 701/45L CW 3.12 10.52 32.8 37.2 88.1% Yes Support Lug Totals: 222.9 511.1 43.6%

OUTER 85%T Exam. Area Length Volume Volume Angie Beam Examined Examined Examined Required Percent

._ntry# (deg.) Direction (sq.in.) (in.) (cu. in.) (cu. in.) Examined Limited Limitations 1 45L/45S Up/Down 20.56 24.08 495.1 495.1 100.0% No 2 45L/45S Up/Down 0.00 32.85 0.0. 675.4 0.0% Yes Flow Skirt 3 45U45S CWiCCW 20.56 25.04 514.8 514.8 100.0% No 4 45L/45S CW/CCW 0.00 33.63 0.0 691.4 0.0% Yes Flow Skirt 5 45U45S Down 0.00 15.26 0.0 313.7 0.0% Yes Support Lug 6 45L145S CW 20.50 13.52 277.2 278.0 99.7% Yes Support Lug Totals: 1287.1 2968.5 43.4%

Entries 1, 2, 3, and 4 are values for dual sided coverage below the Flow Skirt Entries 5 and 6 are values for single sided coverage above the Flow Skirt 51-9077940-000 Section E, Tab 2 Page 18 of 20 Page 12 of 55

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69

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ARr;VA TWS Weld Number: W17 Component ID: BHV-3 Item Number: B13.22

..Description: LOWER HEAD MERIDIONAL WELD (150o)

Examination Procedure: 54-1SI-801-02 Results: No Recordable Indications Status: Acceptable Data Analysts: H. Bezlaj, UT Level Ill.

S. Breiholz, UT Level 11 51-9077940-000 Section F Page 77 of 105 Page 15 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 MILLSTONE-2 EXAMINATION COVERAGE FOR WELD: W15, W17, W19 MERIDIONALS Customer Number BHV-1, BHV-3, & BHV- 5 Scan Plan Drawing Number: 8022562D Sheets 11 and 12 WELD VOLUME COVERAGE OBTAINED: 53.3%

Zone Coverage Obtained Inner 15%T: 49.8% Outer 85%T: 54.0%

Examination Volume Definition Weld Length: 72.19 in.

Area Measurement Volume Calculation Inner 15%T 3.54 sq. in. Inner 15%T 255.6 cu. in.

Outer 85%T 20.56 sq. in. Outer 85%T 1484.2 cu. in.

Limitations Limits scan by: Compensation(s)

Flow Skirt Axial/Circ. Extent None Examination Coverage Calculations INNER 15%T Exam. Area Length volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg) Direction (sq. in) (ih.) (cu. inj (cu. in) Examined Lirmited Limitations 1 70L/45L Up/Down 3.54 24.08 85.2 85.2 100.0% No 2 70LU45L Up/Down 0.00 32.85 0.0 116.3 0.0% Yes FlowSkirt 3 70L/45L CW/CCW 3:54 22.04 78.0 78.0 100.0% No 4 70U45L CW/CCW 0.00 39.63 0.0 140.3 0.0% Yes Flow Skirt 5 70L/45L Down 3.54 15.26 54.0 54.0 100.0% No 6 70L/45L CW 3.54 10.52 37.2 37.2 100.0% No Tota.s 254.5 511.1 49.8%

OUTER 85%T Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg) Direction (sq. in) (in) (cu. in) (cu. in) Examined Limited Limitations 1 45U45S Up/Dawm 20.56 24.08 495.1 495.1 100.0% No 2 451.45S Up/Down 0.00 32.85 0.0 675.4 0.0% Yes Flow Skirt 3 45LU45S CW/CCW 20.56 25.04 514.8 514.8 100.0% No 4 45L/45S CW/CCW 0.00 33.63 0.0 691.4 0.0% Yes Flow Skirt 5 45L/45S. Down 20.56 15.26 313.7 313.7 100.0% No 6 45L/45S CW 20.56 13.52 278.0 278.0 100.0% No Totals: 1601.6 2968.5 54.0%

Entries 1, 2, 3, and 4 are values for dual sided coverage below the Flow Skirt Entries 5 and 6 are values for single sided coverage above the Flow Skirt Page 17 of 20 Page 16 of 55

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 A

AREVA TWS Weld Number: W18 Component ID: BHV-4 Item Number: B1.22

Description:

LOWER HEAD MERIDIONAL WELD (2100)

Examination Procedure: 54-ISI-801-02 Results: No Recordable Indications Status: Acceptable Data Analysts: S. Breiholz, UT Level II V. Zado, UT Level III 51-9077940-000 Section F Page 79 of 105 Page 19 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 MILLSTONE-2 EXAMINATION COVERAGE FOR WELD: W16, W18, W20 MERIDIONALS Customer Number BHV-2, BHV-4, & BHV- 6 Scan Plan Drawing Number: 8022562D Sheets 11 and 12 WELD VOLUME COVERAGE OBTAINED: 43.4%

Zone Coverage Obtained

.Inner 15%T: 43.6% Outer 85%T: 43.4%

Examinaion Volume Definition Weld Length: 72.19 in.

Area Measurement vouma Calculation Inner 15%T 3ý.54 sq. in. IlVn-ner1 15%T 255.6 cu. in.

Outer 85%T 20.56 sq. in. Outer 85%T 1484.2 cu. in.

Limitations Limits scan by: Compensation(s)

Flow Skirt Axial/Circ. Extent None Support Lugs. AxiaVCirc. Extent W -v~in-*i-nt'~ ~ A*-lldln INNER 15%T Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry# (dea.) Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined Limited Limiations 1 70U45L Up/Down 3.54 24.08 85.2 85.2 100.0% No 2 70U45L Up/Down 0.00 32.85 0.0 116.3 0.0% Yes Flow Skirt 3 70U45L CWICCW 3.54 22.04 78.0 78.0 100.0% No 4 70U45L* CWlCCW 0.00 39.63 0.0 140.3 0.0% Yes Flow Skirt 5 70U45L Down 1.76 15.26 26.9 54.0 49.7% Yes Support Lug 6 70U45L CW 3.12 10.52 32.8 37.2 88.1% Yes Support Lug Totals: 222.9 511.1 43.6%

OUTER 85%T Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (dog.) Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined Limited Limitations 1 45L/45S UplDown 20.56 24.08 495.1 495.1 100.0% No 2 45L/45S Up/Down 0.00 32.85 0.0 675.4 0.0% Yes Flow Skirt 3 45L/45S CW/CCW 20.56 25.04 514.8 514.8 100.0% No 4 45L/45S CW/CCW 0.00 33.63 0.0 691.4 0.0% Yes Flow Skirt 5 45L/45S Down 0.00 15.26 0.0 313.7 . 0.0% Yes Support Lug 6 45LU45S CW 20.50 13.52 277.2 278.0 99.7% Yes Support Lug Totals: 1287.1 2968.5 43.4%

Entries 1, 2, 3, and 4 are values for dual sided coverage below the Flow Skirt Entries 5 and 6 are values for single sided coverage above the Flow Skirt 51-9077940-000 Section E, Tab 2 Page 18 of 20 Page 20 of 55

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 A

AREVA WDOmndlion-TWS Weld Number: W19 Component ID: BHV-5 Item Number: B1.22

Description:

LOWER HEAD MERIDIONAL WELD (2700)

Examination Procedure 54-1SI-801-02

.Results: No Recordable Indications Status: Acceptable Data Analysts: S. Breiholz, UT Level It..

V. Zado, UT Level .111'

..1 51-9077940-000 Section F Page 81 of 105 Page 23 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 MILLSTONE-2 EXAMINATION COVERAGE FOR WELD: W15, W17, W19 MERIDIONALS Customer Number BHV-1, BHV-3, & BHV-5 Scan Plan Drawing Number: 8022562D Sheets 11 and 12 WELD VOLUME COVERAGE OBTAINED: 53.3%

Zone Coverage Obtained Inner 15%T: 49.8% Outer 85%T: 54.0%

Examination Volume Definition Weld Length: 72.19 in.

Area Measurement Volume Calculation Inner 15%T 3.54 sq. in. Inner 15%T 255.6 cu. in.

Outer 85%T 20.56 sq. in. Outer 85%T 1484.2 cu. in.

Limitations Limits scan by: Compensation(s)

Flow Skirt Axial/Circ. Extent None Examination Coverage Calculations INNER 15%T Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent E.ntry # (deg.) Direction (sq. in.) (in.) (cu.in) (cu. in.) Examined Limited Limitations 1 70L/45L Up/Down 3.54 24.08 85.2 85.2 100.0% No 2 70L/45L Up/Down 0.00 32.85 0.0 116.3 0.0% Yes Flow Skirt 3 70UJ45L CW/CCW 3:54 22.04 78.0 78.0 100.0% No 4 70LU45L CW/CCW 0.00 39.63 0.0 140.3 0.0% Yes Flow Skirt 5 70L/45L Down 3.54 15.26 54.0 54.0 100.0% No 6 70L/45L CW 3.54 10.52 37.2 37.2 100.0% No Totals: 254.5 511.1 49.8%

OUTER 85%T Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.) (in) (cu.in.) (cu. in) Examined Limited Limitations 1 45L145S Up/Down 20.56 24.08 495.1 495.1 100.0% No 2 45L/45S Up/Down 0.00 32.85 0.0 675.4 0.0% Yes Flow Skirt 3 45LU45S CW/CCW 20.56 25.04 514.8 514.8 100.0% No 4 45LJ45S CW/CCW 0.00 33.63 0.0 691.4 0.0% Yes Flow Skirt 5 45L/45S Down 20.56 15.26 313.7 313.7 100.0% No 6 451J45S CW 20.56 13.52 278.0 278.0 100.0% No Totals: 1601.6 2968.5 54.0%

Entries 1, 2, 3, and 4 are values for dual sided coverage below the Flow Skirt Entries 5 and 6 are values for single sided coverage above the Flow Skirt Page 17 of 20 Page 24 of 55

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 A

AREVA TWS Weld Number: W20 Component ID: BHV-6 Item Number: B1.22

Description:

LOWER HEAD MERIDIONAL WELD (3300)

Examination Procedure: 54-ISI-801-02 Results: No Recordable Indications Status: Acceptable Data Analysts: S. Breiholz, UT Level II V. Zado, UT Level III 51-9077940-000 Section F Page 83 of 105 Page 27 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 MILLSTONE-2 EXAMINATION COVERAGE FOR WELD: W16, W18, W20 MERIDIONALS Customer Number BHV-2, BHV-4, & BHV- 6 Scan Plan Drawing Number: 8022562D Sheets 11 and 12 WELD VOLUME COVERAGE OBTAINED: 43.4%

Zone Coverage Obtained Inner 15%T: 43.6% Outer 85%T: 43;4%

Examination Volume Definition Weld Length: 72.19 in.

Area Measurement Volume Calculation Inner 15%T 3.54 sq. in. Inner 15%T 255.6 cu. in.

Outer 85%T 20.56 sq. in. Outer 85%T 1484.2 cu. in.

Limitations Limits scan by: Compensation(s)

Flow Skirt Axial/Circ. Extent None Support Lugs Axial/Circ. Extent Examination Coverage Calculations INNER 15%T Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry# (deg.) Direction (sq. in.) (in.) (cu. in.) icu. in.) Examined Limited Limlations 1 .70LU45L Up/Down 3.54 24.08 85.2 85.2 100.0% No 2 70U/45L Up/Down 0.00 32.85 0.0 116.3 0.0% Yes Flow Skirt 3 70U45L CWICCW 3.54 22.04 78.0 78.0 100.0% No

.4 70L/45L CW/CCW 0.00 39.63 0.0 140.3 0.0% Yes Flow Skirt 5 70U45L .Down 1.76 15.26 26.9 54.0 49.7% Yes Support Lug 6 70L/45L CW 3.12 10.52 32.8 37.2 88.1% Yes Support Lug Totals: 222.9 511.1 43.6%

OUTER 85%T Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Fndn, i ida,* ni,'a,'tinn, (.*n in ) iin I fr-i in ir-rJ in sEam~inad Linited L.eimtinns 1 45L145S Up/Down 20.56 24.08 495.1 495.1 100.0% No 2 451-45S Up/Down 0.00 32.85 0.0. 675.4 0.0% Yes Flow Skirt 3 45L/45S CW/CCW 20.56 25.04 514.8 514.8 100.0% No 4 45L/45S CW/CCW 0.00 33.63 0.0 691.4 0.0% Yes Flow Skirt 5 45U45S Down 0.00 15.26 0.0 313.7 0.0% Yes Support Lug 6 45U45S CW 20.50 13.52 277.2 278.0 99.7% Yes Support Lug Totals: 1287.1 2968.5 43.4%

Entries 1, 2. 3, and 4 are values for dual sided coverage below the Flow Skirt Entries 5 and 6 are values for single sided coverage above the Flow Skirt 51-9077940-000 Section E, Tab 2 Page 18 of 20 Page 28 of 55

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 A

AREVA TWS Weld Number: W04 Component ID: HS-1 Item Number: B1.21

Description:

LOWER SHELL TO LOWER HEAD CIRC. WELD Examination Procedure: 54-ISI-801-02 Results: 3 Recordable Indications Status: Acceptable Data Analysts: H. Bezlaj, UT Level III S. Breiholz, UT Level II M. Key, UT Level III V. Zado, UT Level III 51-9077940-000 Section F Page 25 of 105 Page 31 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 A

AR EVA A0.11. .1. 1.1

~ f~' Z4~

Customer: Dominion Plant: Millstone Unit: 2 Weld: W04 Flaw No.: 1 Outage: 2R18 Detection Files: B8113_19.59.06 Sizina Files: B8113,19.59.06 Transducer Beam, Angle/Mode Dir.. Min. (dog.) Max. (.) Total (deg.) Mn. (in.) Max. (in) Total (In.)

450. L Alpha - 224.5 224.8 0.3 3.7 3.8 0.1 Estimate of Flaw Length: (Calculate the average of all length values which are considered credible)

Length: 0.442 In. 0.280 deg.

Estimate of Flaw Depth: (Calculate the average of all depth values which are considered credible)

Depth (flaw height): 0.090 In.

Radius of Curvature@ Indication: 86.87 in.

Depth of Flaw at Max. Amp.: 3.56 In.

Max. Amp.: 28 %

Max. Location: X. 97.08

• Y= 224.51 Nominal Walt ThIckness: (Measured) 4.68 In.

Nominal Clad Thickness: 0.31 In.

Evaluation: S = 0.85 2a = 0.09 a- 0.04 Y :1.00 1_= 0.44 all. 0.10 I 1 4 I a/%

aft= 1.0% min. 0.10 2.50 Maximum Allowable art 2.5 % max. 0.18 2.90 Acceptance Standard: IW1-3510-1 Disposition: SUBSURFACE FLAW ACCEPTABLE Comments:,

Ths, Indication Is located within the weld and is Indicative of a fabrication anomaly.

This Indication was not recorded durng the previous examination IThsscan Is perpendicular to the weld on the vessel shell.

Pettormed by: Michael W Key Level; III Qate: 04122=08 Reviewed by: Michael G Hacker M Level: Ill , Date: 04/23108 51-9077940-000 Section F Page 26 of 105 Page 32 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69

.A AREVA Customer: Dominion Plant: Millstone Uhit: 2 Weld: W04 Flaw No.: 2 Outage: 2R18 Detection Fifes: 88113_19.59.06 Slzlna Fifes: B8113 19.59.06 , , ,

Transducer Beam Angle/Mode Dir. Min. (deg.) Ma- (deg. Total (deg.) Min. (In. Max. (in) Total (in.)

450. L Alpha - 228.3 228.8 0.5 3.0 3.2 0.2 Estimate of Flaw Length: (Calculate the average of all length values which are considered credible)

Length: 0.815 In. 0-520 deg.

Estlmate of Flaw Depth: (Calculate the average of all depth values which are considered credible)

Depth (flaw height): 0.180 In.

Radius of Curvature@ Indication: 86.87 In.

Depth of Flaw at Max. Amp.: 2.97 In.

Max. Amp.: 19%

Max. Location: X= 97.13 ° Y= 228.67 Nominal Wall Thickness: (Measured) 4.68 In.

Nominal Clad Thickness: 0.31 In.

Evaluation: S= 1.50 2a - 0.18 a- 0.09 Y= 1.00 L= 0.82 a/L- 0.11 ./I a&L  %

a/t- 2.1% ml. 0.10 2.50 Maximum Allowable aet: 2.8 % max. 0.15 2.90 Acceptance Standard: IWB-3510-1 Dlsp*,siton: SUBSURFAqE FLAW ACCEPTABLE Comments:

This Indicajtor Is located within the weld and Is indlcative of a fabrication anomaly.

This Indlcatlion was not recorded during the previous examination is scan Is perpen*:lcular to the weld on the vessel shell.

Performed.by: Michael W Key Level: IIlI Date: -04/22/08 9Reviewed by; Michael G Hacker Level: . III Date: 04/23/08 51-9077940-000 Section F Page 27 of 105 Page 33 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 A &

AREVA 0-4 W;19" A 5FI/a AID JJ Customer: Dominion Plant* Millstone Unit, 2 Weld: W04 Flaw No.: 3 Outage: 2R18 Detection Files: B811322.58.44 Sizin Files: 88113 22.58.44 Transducer Boom An le/Mode Dir. MIA. (dog.) Max, (deg.) Total (deg. Min. (in.) Max. (In) Total (In.)

4V- S Alpha - 91.2 92.3 1.1 3.5 3.6 0.1 Estimate of Raw Length: (Calculate the average of all length values which are considered credible)

Length: 1.656 In. 1.050 deg.

Estimate of Flaw Depth: (Calculate the average of all depth values which are considered credible)

Depth (flaw height): 0.100 in.

Radius of Curvature@ Indication: 86.87 in.

Depth of Flaw at Max. Amp.: 3.50 In.

Max. Amp.: 45 %

Max. Location: X= 91.88 ' Y= 98.49 Nominal Wail Thickness: 4.68 in.

Nominal Clad Thickness: 0.31 in.

Evaluation: S. 1.08 2a = 0.10 a= 0.05 Y= 1.00 L,- 1.66 a/l- 0.03 a/L a4 %

a/t.. 1.1 % mi. 0.00 2.00 Maxlmum Allowable a/t 2.1% ma. 0.05 2.20 cceptance Standard: iWS-3510-1

'DisDosrtdon: SUBSURFACE FLAW ACCEPTABLE C~omments:

This Indicatiop is located within the weld and Is Indicative of a fabrication anomaly.

This Indication was notrecorded during the previous examination

,Thi scan Is perpendicular to the weld on the vessel shell.

Performed br . Michael W Key Level: III Date: 04/22/08 lReviewed by. Michael G Hacker Level: III Date: 04/23/08 51-9077940-000 Section F Page 28 of 105 Page 34 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69

... :MILLSTONE-2 EXAMINATION COVERAGE FOR WELD:. W04 LWR SHELL-TO-LWR . HEAD SI .

CuatomerN mbr'  : ..

Scan Plian raving Number. ' U8022592SheetS 8, 9.and.12

'WELD;VOLUME COVERAGi lOBTAINED: .72.5%

.. ,.'inner15%T: 60.0% .':".*: CoVer*9e:Obtained

.' Zoine.Outei .5%T""713% . .*°.

'EasrmlnatiohVolume Definition V' *idLeneli: 546.01 in.

..iner 1 ** AreaMeasurement Volume Calculation 4357.2:. i "..

1156T *-. . 7.96 slin. 1 ' .ar . .%T 4357.2 CU.'i.

terST. *33.82 sqin. Outer..%T 15466.1 cu. In.

" i:mtations

- . Limits acan by  : Compensatlon(s)

Core BamelStabilizers M"dal and ClrScans not posaibiaaBa None Core Lugs Slight limitabionin the circ 'scan directli;. None

-. . .: ExamnatonCvaragCatculations.

INNER 15%T Exam A.es. Lenh. V4oume voluIr-e A,- .. Beam Examnd. JEamined Examkied Required..".. ont

• Ent#. .de4 . De ".i(sq.

/ in-) in.),. (cul in.),.(,.I Examined Limited Lijmtations '

70U45L 7*98n'7 388.12 .3097.2 972*. .. 100.0% :NQ. .

2(e) 7.1U45L CVOCCW 7...98" . 7 20 199 2.9.. 00. No 2(b) 70L45L CWICC.W 621 .151 23 9i9 1 1206.8 7.7.8% ... Yea. C.B. Stab.&-Core Lug 70U451 Down 06.8 157.89 .. :0 12600 .0.0% Yea C.B. StabilIzers

• 4. 701245L .C.CW m:.I0 146.96 . :0.0 . i172.7 0."0% Yea C.B. StabCore*Lug -

5 .70145L CWCW 5.99a 10.62 . . '. 64.7 75.0% ..... Yes. CABStabili.e -

::: .:  ::::i :ToB*s 5939.22:: *81.3* 686% '

0.J OU TER 8S%T

. . .Exam. ArS' Length Volume Volumes.

Angle Beam Examind Eismkied Examnined -Required. Percent

nF#...do.) Direct6.n (sq ;).. .. n.) - (c.u.. .) .(&.u in.); Examined " Rmied Umdetron. ..

". 41455 Dow, 33.82 3,.12 .1312:2, .. 312.2-..00% No 2 15

46U458 CWCCW .3382 ý99.09 1U34:8:! .913495.9l 100-0% No

3. 49.45 6D(w* 0.00.. .1 0.0 . 53398 00% .. Ye.. : .C..Stabizems-.

4 451U45S CYWCCCW 0.00 93.68. 0.0 : ,,3170 ', 6 0% Yes CA Stab&CoreLug 5 461245 CWCCW 8.46 93.0 448.8 1995.2 2 -Ys- C .....

rbltafs: 2v0ow3 389$3.1 73.^%

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Section E, Tab 2 Page 7of20 Page 35 of 55

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 A

AR EVA TWS Weld Number: W12 Component ID: LSL-1 Item Number: B1.12

Description:

LOWER SHELL LONGITUDINAL WELD (900)

Examination Procedure: 54-ISI-801-02 Results: No Recordable Indications Status: Acceptable Data Analysts: S. Breiholz, UT Level I1 51-9077940-000 Section F Page 66 of 105 Page 39 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 MILLSTONE-2 EXAMINATION COVERAGE FOR WELD: W12 LOWER LONG SEAM @ 90 Degrees CustomerNumber LSL-1 Scan Plan Drawing Number: 8022562D Sheets 13 and 14 WELD VOLUME COVERAGE OBTAINED: 76.8%

Zone Coverage Obtained Inner 15%T: 77.1% Outer 85%T: 76.7%

Examination Volume Definition Weld Length: 98.00 in.

Area Measurement Volume Calculation nhter 15%T 12.22sq.In. inner 15%T 1197.6 Ot in.

Duter 85%T 72.67 sq. in. Outer 85%T 7121.7 cu, In.

Umltatlons ULmitsscan by: Compensation(s)

SSHT Reduction to adial/idr scans due to SSHTs None Examination Coverage Calculations INNER 15%T Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq.in.) (in.) (cu. In.) (cu. in.) Examined Limited Limitations 1 70U45L Up/Down 1222 71.07 868.5 868.5 100.0% No 2 70U45L CW/CCW 1222 69.02 843.4 843.4 100.0% No 3 70U45L Up/Down 0.00 26.93 0.0 329.1 0.0% Yes SSHT 4 70U45L CW/CCW 4.69 28.98 135.9 354.1 38.4% Yes . SSHT Totals: 1847.8 2395.1 77.1%

OUTER 85%T Exam. Area Length . Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.) (in-) (cu. in.) (cu. in,) Examined Limited Limitations I 45L/45S UpfDown 72.67 71.07 5164.7 5164.7 100.0% No 2 45UJ45S CW[CCW 7267 69.02 5015.7 5015.7 100.0% No 3 451145S Up/Down 0.00 26.93 0.0 1957.0 0.0% Yes SSHT 4 45L145S CWICCW 25.84 28.98 748.8 2106.0 3.5,6% Yes . SSHT Totals: 10929.2 14243.3 76.7%

SSHT - Survellance Specrnen Holder Tubes K

51-9077940-000 Section E, Tab 2 Page 15 of 20 Page 40 of 55

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 A

AREVA TWS Weld Number: W09 Component ID: MSL-1 Item Number: B1.12

Description:

MIDDLE SHELL LONGITUDINAL WELD (900)

Examination Procedure: 54-ISI-801-02 Results: No Recordable Indications Status: Acceptable Data Analysts: S. Breiholz, UT Level II 51-9077940-000 Section F Page 60 of 105 Page 43 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 MILLSTONE-2 EXAMINATION COVERAGE FOR WELD: W09 MID LONG SEAM @ 90 Degrees Customer Number MSIL-1 Scan Plan Drawing Number: 80225620 Sheets 13 and 14 WELD VOLUME COVERAGE OBTAINED: 39.1%

Zone Coverage Obtained Inner 15%T: 40.0% OutergS%T: 39.0%

Examination Volume DefinItion WeldLength: 98.00 in.

Area Measurement lVolume Calculation Inner 15%T 12.22 sq. In. Ilnner t%T 1197.6 cu. i.

Outer 85%T 72.67 sq. In. Outer 65%T 7121.7 cu. in.

Umitastons Limits scan by: Compensation(s)

SSHT Reduction to axiallcintscans due to SSHTs None Examination Coverage Calculations INNER 15%T Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Enry # (dei.) Direction (sq. in.) (in.) (on. In.) (Cu. in.) Examined Limfied Limitations 1 .70U45L UplDown 12.22 28-06 318.5 318.5 100.0% No 2 70LU45L CWICCW 12.22 24.01 293.4 293.4 100.0% No 3 70L145L UplDown 0.00 71.94 0.0 879.1 0.0% Yes SSHT 4 70U45L CW/CCW 4.69 73.99 347.0 904.2 38.4% Yes SSHT Totals: 958.9 2395.1 40.0%

OUTER 85%T Exam. Ama Length Volume Volume

. Angle_- Bee-nExaminedExamined xamkned.- Requiremd-Pecent Eflny# (dog.) Dinschon (sq. In.) (in) (ou. in.) (cu. in.) Examined Limited Limitations 1 45U456 Up/Down 7267 26.06 1893.8 1893.8 100.0% No 2 451-45S CW/CCW 72.67 24.01 1744.8 1744.8 100.0% No 3 45L/45S UpiDown 0.00 71.94 0.0 5227.9 0.0% Yes SSHT 4 46U45S CWA/CCW 25.84 73.99 1911.9 537e.9 35.6% Yes SSHT Totals: .6550.5 14243.3 .3.0% .*'..

SSHT - Surveillance Specimen Holder Tubes 51-9077940-000 Section E, Tab 2 Page 12 of 20 Page 44 of 55

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 A

AR EVA TWS Weld Number: W03 Component ID: SC-2 Summary Number: B1.11

Description:

MIDDLE SHELL TO LOWER SHELL CIRC. WELD Examination Procedure: 54-ISI-801-02 Results: 5 Recordable Indications Status: Acceptable Data Analysts: H. Bezlaj, UT Level III S. Brelholz, UT Level II V. Zado, UT Level Ill 51-9077940-000 Section F Page 18 of 105 Page 47 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 AR EVA AREVA NP INC.

Customer: Dominion Plant: Millstone Unit: 2 Weld: W03 Flaw No.: 1 Outage: 2R18 Detection Files: 88110_06.13.40 Sizint Files: B8110 08.12.42 Transducer Beam Angle/Mode Dir. Mn. (den.) Max. (deg.) Totrl (deI.) MIn.) Max. (In) Total (In.)

4,A*-S Z- -38.98 -3700 1.98 1.90. 2.08 0.18 l o- S Z+ -39.38 -g7.00 2.38 1.79 2.02 0.23 L Z+- -39.47 -38.16 3.31 1.60 1.81 0.21 Estimate of Flaw Length: (Calculate the average of all length values which are considered credible)

Length: 3.967 In. 2.557 deg.

Estimate of Flaw Depth: (Calculate the average of all depth values which are considered credible)

Depth (flaw height): 0.207 In.

Radius of Curvature@ Indication: 86.90 In.

Depth of Raw at Max. Amp.: 2.01 In.

Max. Amp.: 110%

Max. Location: X= -39.12' Y= -230.5 NomInal Wall Thickness: 9.00 In.

Noftnihal Clad Thickness: 0.31 In.

Evaluation: S= 1.29 2a= 0.21 a= 0.10 Y= 1.00 .

IL = 3.97 a/L= 0.03 a/n= 1.2 % 14. Q.00 2.00 Maximum Allowable a/& 2.1 % max. 0.05 2.20-Acceptance Standard: IWB-3510-1

)lsPOfltion: SUBSURFACE FLAW , ACCEPTABLE

_mments:

This Indication was recorded durinQ the previous examination This scan Is perpendicular to the weld on the vespel shell.

11h1sIndication Is IoeateO1within the weld and is indicative of 4 fabrication anomaly..

'erfgrmed by: . Michael*G Hacker Level: IIl Date: 04/19108 RevieYwed byv: Michael W Key . - Level: III . Date: 04/20108 51 -9077940-000 Section F Page 19 of 105 Page 48 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 A ~

. . . E..

AREVA A -A 1.11 Customer: Dominion Plant: Millstone Unit: 2 Weld: W03 Flaw No.: 2 Outage: 2R18 Detection Files: B8110_08.13.40 Sizln Flies: 88110 08.12.42 Transducer Beam Angle/Mode oir. Min, (deg.) Max. (degj Total (deg. Mn. I Max. (In) Total (in.)

1 45 -S 45*- L Z+

Z+

-39.11

-39.33

-36.20

-36.30 7303 2.91 2. 1 2.32 2.55 2.45 0.14 0.13 Estimate of Flaw Length: (Calculate the average of all length values which are considered credible)

Length: 4.629 In. 2.970 deg.

Estimate of Flaw Depth: (Calculate the average of all depth values which are considered credible)

Depth (flaw height): 0.135 It.

Radius of Curvalure@ Indication: 86.90 In.

Depth of Flaw at Max. Amp.: 2.41 in.

Max. Amp.: 45 %

Max. Location: X= -38.18

• Y= -230.81 Nominal Wall Thickness: 9.00 In.

Nominal Clad Thickness: 0.31 In.

Evaluation: S= 2.01 2a= 0.14 a= 0.07 Y =- 1.00 L. 4.63 a/L= 0.01 al. , 518%

a/l= 0.8% min. 0. 0 2.00_

Maximum Allowable a/t: 2.1 % max. 0.05 2.20 Acceptance Standard: IWB-3510-1 Disposition: SUBSURFACE FLAW ACCEPTABLE a rommentse ...

iThsIndication was recorded duftng the prevyous examination This scan Is perpendlguler to the weld on the vessel shell.

ihisIndIcalton Is lcasteo within the weld ani Is Indicative of a fabrication anomaly.

Performned by - Michae!,G Hacker Level: III Date: 04/19/08 iReviewed by:.

• Michael W Key Level: 11l Date: 04/20/08 51-9077940-000 Sectioh F Page 20 of 105 Page 49 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 A

AR EVA 1- -~ ~ ~

Customer Dominion Plant: Millstone Unit: 2 Weld: WO3 Flaw No.: 3 Outage: 2R18 Detection Files: B8110.06.13.40 Sizina Files: B8110 08.12.42 Transducer Bieamn AngtelMode Dir. Kin. (deg.) Max. (deg.) Total (deg.) Min. (in.) Max (In) rota! (In.)

45*- L Z+ -40.66 -40.39 0.27 1.88 1.96 0.08 Estimate of Flaw Length: (Calculate the average of all length values which are considered credible)

Length: 0.418 In. 0.270 deg.

Estimate of Flaw Depth: (Calculate the average of all depth values which are considered credible)

Depth (flaw height): 0.080 In.

Radius of Curvature@ Indication: 86.90 In.

Depth of Raw at Max. Amp.: 1.88 In.

Max. Amp.: 16%

Max. Location: X= -40.521 Y= -230A93 Nominal Wall Thickness: 9.00 In.

Nominal Clad Thickness: ... ... - 0.31 In.

Evalualion: S = 1.57 2a = 0.08 a= 0.04 Y= 1.00 L= 0.42 8/= 0.10 1 at 1a,%

a/t 0.5% Min. 0.10 2.50 Maximum Allowable at: 2.5 % max. 0.15 2.90 Acceptance Standard: IWB-3510-1 Disposition: $UBSURFACE FLAW ACCEPTABLE Comments:

This Indication was recorded during, the previous examination This scan Li permendlcLular to the weld on the vessel shen.

ihisindication Is located within the weld and is Indicative of a fabrication anomaly.

erfortmed by: Michael G elacker Level: . II Date: 04/19108 hRevlewad by: , Michael W Key Level: III Date: 04/20108 51-9077940-000 Section F Page 21 of 105 Page 50 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 A

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Customer: Dominion Plant: Millstone Unit, 2 Weld: W03 Flaw No.: 4 Outage: 2R18 Detection Flies: B8110_06.13.40 Sizinq Files: B8110 08.12.42 Transducer Beami Angfe/Mode Dir. MI . (de. Max. (deg.) Total (deg.) Min. (In.) Max. fin) Total (In.)

45°- L Z+ -41.71 -41.32 0.39 1.68 1.82 0.16 Estimate of Flaw Length: (Calculate the average of all length values which are considered credible)

Length: 0.604 In. 0.390 deg.

Estimate of Flaw Depth: (Calculate the average of all depth values which are considered credible)

Depth (flaw height): 0.160 In.

Radius of Cur'vature@ Indication: 86.90 in.

Depth of Flaw at Max. Amp.: 1.81 In.

Max. Amp.: . 19%

Max. Location: X= -41.45

• Y= -230.83, NormInal Wall Thickness: 9.00 In.

Nominal Clad Thickness: 0.31 In.

Evaluation: S= 1.35 2a= 0.16 a= 0.08 Y. 1.00 L= 0.60 F r ul X1 a/L= 0.13 Val. ah %

alt= 0.9% min. 0.1 2.50 Maximum Allowable ath: 2.8 % max. 0.15 2.90 Acceptanca Standard: IWB-3510-1 Disoosltion: , SUBSURFACE FLAW ACCEPTABLE Comments::

This Indfcation was iecoed during the previous examination This scaon Is perpendigular to Mo Weld on the vessel shell.

This Indicatiol Islocated within the weld and Is Indicative of a fabrication anomaly.

Performed by: Michael G Hacker Level: III Date: 04/19/08 Reviewed by: Michael W Key Level: III Date: 04/20/08 51-9077940-000 Section F Page 22 of 105 Page 51 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69 A

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Customer: Dominion Plantf Millstone Unit" 2 Weld: W03 Flaw No.: 5 Outage: 2R18 Detection Files: B811006.13.40 Sizing Files: B8110 08.12.42 Transducer Beam Angel/Mobde Dir. Mm. (deg.) Max. [deg.) Totali(deg.) Mn. (In.) Max. (in) Tota 17n.)

70*- L Z+ -39.65 -36.21 3.44 1o07 1.15 0.08 Estimate of Flaw Length: (Calculate the average of ali length values which are considered credible)

Length: 5.283 In. 3.440 deg.

Estimate of Raw Depth: (Calculate the average of all depth values which are considered credible)

Depth (IRawheight): 0.080 in.

Radius of Curvature@ Indication: 86.90 In.

Depth of Flaw at Max. Amp.: 1.09 In.

Max. Amp.: 158 %

Max. Location: X= -37.64 o Y= -230.49" Nominal Wall Thickness: 9.00 in.

Nominal Clad Thickness: 0.31 In.

Evaluation: S= 0.76 2a= 0.08 a0 0.04 Y =. 1.00 L. 5.28 a/L= 0.01 A t%

aft= 0.5% Mltn. 0.00 2.00 Maximum Allowable all: 2.0 % thax. 0.05 2.20 Acceptance Standard: IWB-3510-1 Disposition! SUBSURFACE FLAW ACCEPTABLE Is Indicationrwas recorded during the previous examination Is Vcan Is perpendicular to the weld on the vessel shell.

Is Indication Is located within the weld and Is Ilrdicatlve of a fabrication anoffialy.

PerforMd by: Michael G Hacker Level: III Date: 04/19/08 Reviewed by: Michael W Key Level: III Date: 04/20/08.

51-9077940-000 Section F Page 23 of 105 Page 52 of 55

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-69

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MILLSTONE-2 EXAMINATION COVERAGE FOR WELD: W03 MIDDLE SHELL TO LOWER SHELL Customer Number, 5C-2 Scan Plan Diaving Number: 8022562 Sheets 6 and 7 WELD VOLUME COVERAGE OBTAINED: 82.6%

Zone Cover*gea ObtaIned Inner 1*%T: . 82.9% .Out0 85%T: 82.6%.

S"..".'* Examlnai*ot Volume Defniionr.

• Weld Lenqth: 540.01 in.

Area Measurement Volume C onculatlon IlineT 15%T 12.78 sq. in. r"e1rI*"1T . 6978.0 du. Fri.

Outer 85%T " 72.40 . in. Outer 85%T . ,. : 39531.1 6. In.

LlmItations Li"m"Uts can by: - Compensatlon(s)

SSHT . Reduction to axlaicirc sbans due to SSHr"s None Examination Coverage Calculations INNER 15%T Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Peren . "

Direction (sq, In.) 0.)~ (a.'.in.) (i.In) Eand Limited Limitations ExT'v do 1 701.45 Up 12.78 438.17 5500.8 5599.8 100.0% NO 2 70U45L Up 8.56 5.31 45.8 67.9 67.0% Yes SSHT 3 70U45L Up

• 0.00 102.52 0.0 1310.2 0.0%. Yet SSHT 4 70U45L Down 12.78 *438.17 559.8 5599.8 t00.0%* No 8 70U45L Doin 8.56 5.31 . 45.5 87.9 V7.0% ' Yes SSHT 8 70145L Down 0.00 102.82 0.0 1310.2 0.0% Yes SSWT 7 701145L CW 12.78 463.80 6927.4 5927.4 100.0% No 70U45L CW 0.00 82.20 0.0 1050.5 0.0% Yes SSHT (7 j 5 10 70U45L 70U45L

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.COw 12.78 0.00 463.80 82.20 8927.4

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No Yes SSHT Totals: 23145.3 2791U.5 82.9%

OUTER 81%T "

Exam. , Area Length Volume Volume Angle Beam Examined Examined Examined Required . Perent Entry# (deg.) Dhdieon (sq. in.) A(in,) cu.in.)" (c. in.) Examined "Limited Limitations 1 45L145S Up 72.40 458.17 1725.5 31723.5 108.0% No 2 45U145S Up 48.51 5.31 257.6 384.4 67.0% Yes SSHT 3 4611458 Up 0.00 102.52 " 0.0 7422.4 0.0% Yed SSHT 4 451145S Down 72.40 43*8.17 31723.5 31723.5 100.0% 'No 468456 0DoIn 48.51 5.31 257.6 384.4 67.0% 'Ye SSHT 6 458/456 Down 0.00 102.52 0.0 7422.4 0.0% Yes SSHT 7 .461.45S CI 72.40 448.63 32480.8 32480.8 100.0% NO 8 48U45S .CW 54.30 15.17 823.7 1098.3 75.0% .

8 45U45S CW 0.00 82.20 0.0 *

• 81.3 0.0% Yes SSHT 10 458145S CCW 72.40 448.63 32480.8 32480.8 100.0% No 11 4 44t8 COW 5430 15.17 823.7 f0§8.3 75.0%

12 45U45S COW 0.00 82.20 .0.0 .. 5951.3 0.0% . Yet SSHT

. . Totals: 130571.3 15812f.6 82.6%

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Serial No.11-137 Docket No. 50-336 ATTACHMENT 2 RELIEF REQUEST RR-89-70 EXAMINATION CATEGORY B-D FULL PENETRATION WELDS OF NOZZLES IN VESSELS - INSPECTION PROGRAM B DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-70 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

--Inservice Inspection Impracticality--

1. ASME Code Components Effected:

ASME Code Class: Code Class 1 Examination Category: B-D, Full Penetration Welds of Nozzles in Vessels -

Inspection Program B Item Numbers: B3.130, Steam Generator, Nozzle-to-Vessel Welds Component Identification: Listed in Table 1 Material: SA308, CL.3 carbon steel with internal stainless steel cladding

2. Applicable Code Addition and Addenda ASME Section XI, 1989 Edition, No addenda

3. Applicable Code Requirement

ASME Section Xl, 1989 Edition, Examination Category B-D requires volumetric examination of 100% of the weld volume as defined in Table IWB-2500-1 and shown in Figure IWB-2500-7. The alternative requirements of ASME Section XI, Code Case N-460, approved for use in Regulatory Guide 1.147, Rev. 15, allows credit for essentially 100% coverage of the welds provided greater than 90% of the required volume has been examined.

4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the 100% volumetric examination coverage requirement of the subject welds due to the geometric configuration which limit the volumetric coverage that can be obtained.

The subject steam generator nozzle-to-vessel welds were examined with a manual ultrasonic technique using pulse echo ultrasonic instruments and transducers. The best available technology was used to achieve the maximum examination coverage practical. Limitations imposed by the nozzle configuration preclude obtaining 100%

Page 1 of 10

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-70 coverage. This configuration with the nozzle outside radius and outside diameter taper are within close proximity of the weld and prevents scanning in these areas. This limits the circumferential, axial scan and straight beam coverage that can be obtained.

No alternative methods or advanced technologies were considered capable of increasing the ASME code coverage.

Isometric drawing, coverage calculations and limitation sketches are provided in this attachment.

5. Burden Caused by Compliance To increase examination coverage on the subject welds would require a significant design modification or replacement of components with a different design to eliminate the noted obstructions which is considered impractical due to the cost, additional radiation exposure and impact to plant equipment.

6. Proposed Alternative and Basis for Use The subject welds received a volumetric examination utilizing the best available techniques on the accessible portions of welds to the extent practical. Additionally, a visual (VT-2) examination was performed at the end of each refueling outage during the system leakage tests, as required by Section XI, Table IWB-2500-1, Category B-P.

Based upon the examination volumes that were obtained with acceptable results and the visual (VT-2) examinations performed during each refueling outage, it is reasonable to conclude that service-induced degradation would be detected. Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject welds.

7. Duration of Proposed Alternative The relief is requested for the third 10-year inspection interval for Millstone Unit 2, which began on April 1, 1999 and ended March 31, 2010.

Page 2 of 10

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-70 TABLE 1- Examination Category B-D Welds with Limited Volumetric Coverage Weld Code Configuration Examination Angle Comments Ultrasonic Identification Item and Wave Mode Examination Number Coverage

__N(%)

SG-1-NH-2-A B3.130 Cold Leg Nozzle to 00 Longitudinal Wave Scan limitations due to the 54 Hemisphere. 30' Shear Wave configuration of the nozzle with 450 Shear Wave its outside radius and outside 600 Shear Wave diameter taper that restrict the scanning in these areas.

One recordable indication was detected and evaluated as acceptable internal geometry.

SG-1-NH-4-A B3.130 Hot Leg Nozzle to Hemisphere. 00 Longitudinal Wave Scan limitations due to the 56 450 Shear Wave configuration of the nozzle with 600 Shear Wave its outside radius and outside diameter taper'that restrict the scanning in these areas.

One recordable indication was detected and evaluated as acceptable internal geometry.

SG-1-NH-5-A B3.130 Cold Leg Nozzle to 00 Longitudinal Wave Scan limitations due to the 55 Hemisphere. 300 Shear Wave configuration of the nozzle with 450 Shear Wave its outside radius and outside 600 Shear Wave diameter taper that restrict the scanning in these areas.

One recordable indication was detected and evaluated as acceptable internal geometry.

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Serial No.11-137 Docket No. 50-336 ATTACHMENT 3 RELIEF REQUEST RR-89-71 EXAMINATION CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-71 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

--Inservice Inspection Impracticality--

1. ASME Code Components Affected:

ASME Code Class: CodeClass 1 Examination Category: B-J, Pressure Retaining Welds in Piping Item Number: B9.1 1, NPS 4 or Larger - Circumferential Welds Component Identification: Listed in Table 1 Material: Listed in Table 1

2. Applicable Code Addition and Addenda ASME Section Xl 1989 Edition, No Addenda Austenitic piping welds with single-side access subject to ultrasonic examination with Supplement 2 of Appendix VIII to the 1995 Edition with 1996 Addenda of ASME Section XI.

3. Applicable Code Requirement

ASME Section Xl, 1989 Edition, Examination Category B-J requires 100%

volumetric examination coverage for circumferential piping welds. The alternative requirements of ASME Section Xl, Code Case N-460, approved for use in Regulatory Guide 1.147, Rev. 15, allows credit for essentially 100%

coverage of the weld provided greater than 90% of the required volume has been examined.

10 CFR 50.55a(b)(2)(xv)(A), requires the following examination coverage criteria when applying Supplement 2 of Appendix VIII:

(1) Piping must be examined in two axial directions and when examination in the circumferential direction is required, the circumferential examination must be performed in two directions, provided access is available.

(2) Where examination from both sides is not possible, full coverage credit may be claimed from a single side for ferritic welds. Where examination from Page 1 of 8

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-71 both sides is not possible on austenitic welds, full coverage credit from a single side may be claimed only after completing a successful single sided Appendix VIII demonstration using flaws on the opposite side of the weld.

10 CFR 50.55a(b)(2)(xvi)(B) requires that examinations performed from one side of a stainless steel pipe weld must be conducted with equipment, procedures, and personnel that have demonstrated proficiency with single side examinations. To demonstrate equivalency to two sided examinations, the demonstration must be performed to the requirements of Appendix VIII as modified by this paragraph and §50.55a(b)(2)(xv)(A).

4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the 100%

volumetric examination coverage requirement for austenitic piping welds with single side access.

The manual ultrasonic scanning techniques were performed using pulse-echo ultrasonic instruments and transducers qualified in accordance with ASME Section Xl, Appendix VIII as implemented by the Performance Demonstration Initiative (PDI).

There are currently no PDI-qualified single side examination procedures that demonstrate equivalency to two-sided examination procedures on austenitic piping welds. Current technology is not capable of reliably detecting or sizing flaws on the far side of an austenitic weld for configurations common to domestic nuclear applications.

PDI Performance Demonstration Qualification Summary (PDQS) certificates for austenitic piping list the limitation that single side examination is performed on a best effort basis. The best effort qualification is provided in place of a complete single side qualification to demonstrate that the examiners qualification and the subsequent weld examination is based on application of the best available technology.

When the examination area is limited to one side of an austenitic weld, examination coverage does not comply with 10 CFR 50.55a(b)(2)(xv)(A) and proficiency demonstrations do not comply with 10 CFR 50.55a(b)(2)(xvi)(B) and full coverage credit may not be claimed.

Based on the configuration limited to single-sided access, relief is requested from complying with the 100% required examination coverage for the piping welds listed in Table 1. Note that examination coverage listed was obtained during Page 2 of 8

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-71 examination with no credit taken for the far side of each weld. The ASME code-required volume of these welds was interrogated ultrasonically to the maximum extent possible. No alternative methods or advanced technologies were considered capable of increasing the ASME code coverage.

Coverage calculations and limitation sketches are provided in this attachment.

5. Burden Caused by Compliance Compliance with the Code requirements would require extensive modification or replacement of components with a design that would allow examination from both sides of the weld which is considered impractical due to cost, additional radiation exposure and impact to plant equipment.

6. Proposed Alternative and Basis for Use The subject welds received a volumetric examination to the maximum extent practical using the best available techniques, as qualified through the PDI for Supplement 2 with demonstrated best effort for single-sided examination, from the accessible side of the weld. Additionally, a surface examination was performed with 100% coverage obtained and a visual (VT-2) examination was performed each refueling outage during the system leakage tests as required by Section Xl, Table IWB-2500-1, Category B-P.

Based on the volumetric coverage that was obtained with acceptable results, the surface examination obtaining 100% percent coverage with acceptable results, and the visual (VT-2) examination performed each refueling outage, it is reasonable to conclude that service-induced degradation would be detected.

Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject welds.

7. Duration of Proposed Alternative Relief is requested for the third 10-year inspection interval for Millstone Unit 2, which began on April 1, 1999 and ended March 31, 2010.

Page 3 of 8

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-71 Table 1- Examination Category B-J Welds with Limited Volumetric Coverage Weld Item Configuration Examination Angle Limitations and Results Ultrasonic Surface Exam Identification Number Material and Wave Mode Examination Results Coverage BSI-C-1 025 B9.11 12" Valve-To- 450 and 700 Shear Wave Limited examination from the elbow side 50 Liquid penetrant Elbow 60' Longitudinal Wave only due to the taper of the valve within examination close proximity of the weld. There is not performed obtaining Type 316 sufficient distance from the weld to the 100% coverage. No Stainless Steel valve to perform any scanning on the recordable valve side of the weld. indications detected.

No recordable indications were detected.

BSI-C-1027 B9.11 12" Pipe-To- 450 and 70' Shear Wave Limited examination from the pipe side 50 Liquid penetrant Valve 600 Longitudinal Wave only due to the taper of the valve within examination close proximity of the weld. There is not performed obtaining Type 316 sufficient distance from the weld to the 100% coverage. No Stainless Steel valve to perform any scanning on the recordable valve side of the weld. indications detected.

No recordable indications were detected.

BSI-C-1029 B9.11 12" Valve-To- 450 and 70' Shear Wave Limited examination from the pipe side 50 Liquid penetrant Pipe 600 Longitudinal Wave only due to the taper of the valve within examination close proximity of the weld. There is not performed obtaining Type 316 sufficient distance from the weld to the 100% coverage. No Stainless Steel valve to perform any scanning on the recordable valve side of the weld. indications detected.

No recordable indications were detected.

BSI-C-401 0 B9.11 12" Valve-To- 450 Shear Wave Limited examination from the pipe side 50 Liquid penetrant Pipe 60' Longitudinal Wave only due to the taper of the valve within examination close proximity of the weld. There is not performed obtaining Type 316 sufficient distance from the weld to the 100% coverage. No Stainless Steel valve to perform any scanning on the recordable valve side of the weld. indications detected No recordable indications were detected.

Page 4 of 8

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-71

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Page 5 of 8

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-71 ATTACHM~ft1I COVERAGE CALCUIA1NDT HE Plan  ;/Igroxh --. Unit Z. AWO Number A Z63O'9 System W Par~o 9f Ara ~ ý)rn4 0oqmvonnt ID RSz- <~ 7 047 - si;oet a_____DataSheet COMPOnemp esotlpon.- PIP 7-0 VAt' V,9 Cahbaftl Data -Shdet#________

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-71 ATTAORPAFNT I I CO2VIRAGE CAjLCIU lNDTASHE PLW Pz1it biý Unit .AWO~urhber /I12ý-,03 nof7q-4 Systemag of Are Moid a

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-71

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Serial No.11-137 Docket No. 50-336 ATTACHMENT 4 RELIEF REQUEST RR-89-72 EXAMINATION CATEGORY C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-72 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

--Inservice Inspection Impracticality--

1. ASME Code Comrponents Affected:

ASME Code Class: Code Class 2 Examination Category: C-A, Pressure Retaining Welds in Pressure Vessels Item Numbers: C1.10, Shell Circumferential Welds C1.30, Tube Sheet-to-Shell Welds Component Identification: Listed in Table 1 Material: SA 515 GR 70 carbon steel with internal stainless steel cladding.

2. Applicable Code Addition and Addenda ASME Section Xl, 1989 Edition, No Addenda

3. Applicable Code Requirement

ASME Section Xl, 1989 Edition, Category C-A requires volumetric examination of 100% of the weld length as defined in Table IWC-2500-1 and shown in Figures IWC 2500-1 and IWC-2500-2. The alternative requirements of ASME Section Xl, Code Case N-460, approved for use in Regulatory Guide 1.147, Rev. 15, allows credit for essentially 100% coverage of the welds provided greater than 90% of the required volume has been examined.

4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the 100% volumetric examination coverage requirement of the subject welds due to the geometric configuration and permanent obstructions which limit the volumetric coverage that can be obtained.

The shutdown cooling heat exchanger tube sheet-to-shell weld (SIAC-Al) and the flange-to-shell weld (SIAC-A2) were examined with a manual ultrasonic technique using the best technology available to achieve the maximum examination coverage practical. The examinations were performed using pulse echo ultrasonic instruments and transducers. No alternative methods or advanced technologies were considered capable of increasing the ASME code coverage.

Page 1 of 8

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-72 The position of the heat exchanger tube sheet flange limits the examination coverage of the subject tube sheet-to-shell weld. The tube sheet is located within close proximity to the weld and does not provide sufficient distance from the weld to allow complete axial scanning on that side of the weld. The scanning coverage on the tube sheet side of the weld was limited for the axial scans in both directions; 96.9 % with scanning from the shell side and 26.1% while scanning from the tube sheet side.

The position of the heat exchanger channel cover flange limits the examination of the subject flange-to-shell weld to scanning from the shell side only. The flange is located within close proximity to the weld and does allow sufficient distance for any axial or circumferential examination scanning from the flange side of the weld.

Additionally, the location of this flange limits the axial scan from the shell side to 88%.

Isometric drawing, coverage calculations and limitation sketches are provided in this attachment.

5. Burden Caused by Compliance To increase examination coverage on the subject welds would require a significant design modification or replacement of the component with a different design to eliminate the noted obstructions. This option to meet the 100% Code examination requirement is considered impractical due to the cost, increased radiation exposure, and impact to plant equipment.

6. Proposed Alternative and Basis for Use The subject welds received a volumetric ultrasonic examination using the best available techniques on the accessible portions of welds to the maximum extent practical. Additionally, a visual (VT-2) examination was performed each inspection period during the system leakage tests as required by Section Xl, Table IWC-2500-1, Category C-H.

Based upon the examination volumes that were obtained with acceptable results and the visual (VT-2) examinations performed each inspection period, it is reasonable to conclude that service-induced degradation would be detected. Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject welds.

7. Duration of Proposed Alternative The relief is requested for the third 10-year inspection interval for Millstone Unit 2, which began on April 1, 1999 and ended March 31, 2010.

Page 2 of 8

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-72 TABLE 1- Examination Category C-A Welds with Limited Volumetric Coverage Weld Code Configuration Examination Angle Comments Ultrasonic Identification Item and Wave Mode Examination Number Material Coverage (%)

SIAC-Al C1.30 Tube Sheet to Shell Weld 450 - Shear Wave Limited examination due to the 80.75 location of the tube sheet that obstructs the axial scans on that side of the weld. Five recordable indications were detected that were evaluated as acceptable geometry caused by internal reinforcing plate and weld root geometry.

SIAC-A2 C1.10 Flange to Shell Weld 450 - Shear Wave Limited examination from the shell side only due to the location of the flange that obstructs any examination from that side of the weld.

Five recordable indications were detected that were evaluated as acceptable ID geometry caused by internal reinforcing plate and weld root geometry.

Page 3 of 8

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-72

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Serial No.11-137 Docket No. 50-336 ATTACHMENT 5 RELIEF REQUEST RR-89-73 EXAMINATION CATEGORY C-B PRESSURE RETAINING NOZZLE WELDS IN VESSELS DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-73 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

--Inservice Inspection Impracticality--

1. ASME Code Components Affected:

ASME Code Class: Code Class 2 Examination Category: C-B, Pressure Retaining Nozzle Welds in Vessels Item Numbers: C2.21, Nozzle-to-Shell (or Head) Welds Component Identification: Listed in Table 1 Material: SA533, GR B carbon steel

2. Applicable Code Addition and Addenda ASME Section Xl, 1989 Edition, No Addenda

3. Applicable Code Requirement

ASME Section Xl, 1989 Edition, Category C-B requires volumetric examination of 100% of the weld length as defined in Table IWC-2500-1 and shown in Figure IWC 2500-4. The alternative requirements of ASME Section Xl, Code Case N-460, approved for use in Regulatory Guide 1.147 Rev. 15, allows credit for essentially 100% coverage of the welds provided greater than 90% of the required volume has been examined.

4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the essentially 100% volumetric examination coverage requirement of the subject welds due to the geometric configuration and permanent obstructions which limit the volumetric coverage that can be obtained.

The subject welds were examined with manual ultrasonic scanning techniques using the best technology available to achieve the maximum examination coverage practical. The examination was performed using pulse echo ultrasonic instruments and transducers. No alternative methods or advanced technologies were considered capable of increasing the ASME code coverage.

Page 1 of 9

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-73 The steam generator feedwater nozzle-to-shell weld was examined from the shell side. The shell side examination was restricted due to the location of a permanently welded insulation retaining ring located within close proximity of the weld that limited the axial scanning. No examination could be performed from the nozzle side due to the nozzle configuration which precludes any meaningful examination results from that side of the weld.

The steam generator main steam nozzle-to-head weld was examined from the head side of the weld. The examination from the head side was restricted by the location of six permanently welded insulation retaining lugs that limited the coverage that could be obtained in the areas of these lugs. No examination could be performed from the nozzle side due to the nozzle configuration which precludes any meaningful examination results from that side of the weld.

Weld isometric drawing, coverage calculations and limitation sketches are provided in this attachment.

5. Burden Caused by Compliance To increase examination coverage on the subject welds would require removing the permanently welded retaining lugs and ring and then reattaching them by welding following examination completion. This option to meet the 100% Code examination requirement is considered impractical due to the increased radiation exposure and impact to plant equipment.

6. Proposed Alternative and Basis for Use The subject welds received a volumetric examination using the best available techniques on the accessible portions of welds to the extent possible.

Additionally, a visual (VT-2) examination was performed each inspection period during the system leakage tests as required by ASME Section XI, Table IWC-2500-1, Category C-H.

Based upon the examination volumes that were obtained with acceptable results and the visual (VT-2) examination performed each inspection period, it is reasonable to conclude that service-induced degradation would be detected.

Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject welds.

7. Duration of Proposed Alternative The relief is requested for the third 10-year inspection interval for Millstone Unit 2, which began on April 1, 1999 and ended March 31, 2010.

Page 2 of 9

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-73 TABLE 1- Examination Category C-B Welds with Limited Volumetric Coverage Weld Code Configuration Examination Angle Comments Ultrasonic Identification Item and Wave Mode Examination Number Coverage (%)

SG-1-FW-1 C2.21 Steam Generator No. 1 0' Longitudinal Wave Limited examination from the 74.7 Feed Water Nozzle to 450 and 600 Shear Wave shell side due to permanently Shell Weld welded insulation retaining ring within close proximity of the weld. No recordable indications were detected SG-2-MS-1 C2.21 Steam Generator No. 2 00 Longitudinal Wave Limited examination from the 56.3 Main Steam Nozzle to 450 and 600 Shear Wave head side due to six Head Weld permanently welded insulation retaining lugs within close proximity of the weld.

No recordable indications were detected Page 3 of 9

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-73

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Serial No.11-137 Docket No. 50-336

. ATTACHMENT 6 RELIEF REQUEST RR-89-74 EXAMINATION CATEGORY C-C INTEGRAL ATTACHMENTS OF VESSELS. PIPING. PUMPS. AND VALVES DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-74 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

--Inservice Inspection Impracticality--

1. ASME Code Components Affected:

ASME Code Class: Code Class 2 Examination Category: C-C, Integral Attachments of Vessels, Piping, Pumps, and Valves Item Numbers: C3.20, Piping Component Identification: MSR-2 pipe restraint lug attachment welds within the Main Steam System Material: A155, GR KCF-70 carbon steel A516, GR 70 carbon steel

2. Applicable Code Addition and Addenda ASME Section Xl, 1989 Edition, No Addenda

3. Applicable Code Requirement

ASME Section Xl, 1989 Edition, Examination Category C-C requires surface examination of 100 % of the weld length as defined in Table IWC-2500-1 and shown in Figure IWC 2500-5 for the subject welds. The alternative requirements of ASME Section Xl, Code Case N-460, approved for use in Regulatory Guide 1.147, Rev. 15, allows credit for essentially 100 % coverage of the welds provided greater than 90 % of the required surface has been examined.

4. Impracticality I I of Compliance I

Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the essentially 100% surface examination coverage requirement of the subject welds due to the geometric configuration and obstructions caused by the pipe rupture restraint support members which limit the surface examination coverage that can be obtained.

Page 1 of 7

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-74 A magnetic particle surface examination of the subject welds was performed to the maximum extent practical with the limitations caused by the obstruction of the support members of a pipe rupture restraint that are in close proximity of the welds.

The subject attachment welds consist of the welds associated with a set of four lugs that are welded to the piping pressure boundary to restrict the restraint movement. Each lug is welded on all four sides. The examination of the attachment welds for these four lugs is restricted due-to the location of the restraint members that limit the access for examination and the coverage that can be obtained. Alternative non-destructive examination (NDE) methods were considered, however, due to the limited access to these areas, it was determined that they would not provide any meaningful results.

The aggregate coverage calculated for the set of all four lugs was 75.5%.

The support design drawing and limitation sketch is provided for reference in this attachment.

5. Burden Caused by Compliance To increase the examination coverage, the support members of the pipe rupture restraint would need to be disassembled and removed. The removal of this large complex restraint would require a significant effort that is considered impractical due to the the impact to plant equipment.

Note that later editions of the code allow the examination surface to be limited to the portions that are accessible without removal of support members. Reference ASME Section Xl, 2004 Edition, Figure IWC 2500-5.

6. Proposed Alternative and Basis for Use The subject welds received a surface examination using the best available techniques on the accessible portions of welds to the extent practical.

Additionally, a visual (VT-2) examination was performed each inspection period during the system leakage tests as required by ASME Section Xl, Table IWC-2500-1, Category C-H.

Based upon the surface examination coverage that was obtained with acceptable results and the visual (VT-2) examination performed each inspection period, it is reasonable to conclude that service-induced degradation would be detected.

Therefore, these proposed alternatives provide an acceptable level of quality and Page 2 of 7

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-74 safety by providing reasonable assurance of structural integrity of the subject welds.

7. Duration of Prooosed Alternative The relief is requested for the third 10-year inspection interval for Millstone Unit 2, which began on April 1, 1999 and ended March 31, 2010.

TABLE 1- Examination Category C-C Welds with Limited Volumetric Coverage Identification Code Configuration Comments Ultrasonic Number Item Examination Number Coverage MSR-2 C3.20 MSR-2 lug attachment Limited examination due to 75.5 welds restraint members within close proximity to a portion of the weld of each of the (4) lugs.

No recordable indications were detected.

Page 3 of 7

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-74 L0 *BEM~T It2YWt -

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Page 4 of 7

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-74 MTELQE!IýKF T PA4..WT .0

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number; RR-89-74 GOMDEbW EET S~~rH Sydtm -AA At- &MI'4-O pwkq ecm1dcg 17p..

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Page 6 of 7

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-74 GB4ERJSKIrCSHEET

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Serial No.11-137 Docket No. 50-336 ATTACHMENT 7 RELIEF REQUEST RR-89-75 EXAMINATION CATEGORY C-F-1 PRESSURE RETAINING WELDS IN AUSTENITIC STAINLESS STEEL HIGH ALLOY PIPING DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

--Inservice Inspection Impracticality--

1. ASME Code Comrnonents Affected:

ASME Code Class: Code Class 2 Examination Category: C-F-i, Pressure Retaining Welds in Austenitic Stainless Steel High Alloy Piping Item Number: C5.1 1, Piping Welds > 3/8 in. Nominal Wall Thickness for Piping > NPS 4 in. - Circumferential welds C5.21, Piping Welds > 1/5 in. Nominal Wall Thickness for Piping > NPS 2 in. and < 4 in. -

Circumferential welds Component Identification: Listed in Table 1 Material: Listed in Table 1

2. Applicable Code Addition and Addenda ASME Section Xl 1989 Edition, No Addenda Austenitic piping welds with single-side access subject to ultrasonic examination with Supplement 2 of Appendix VIII to the 1995 Edition with 1996 Addenda of ASME Section XI.

3. ADDlicable Code Reauirement ASME Section XI, Examination Category C-F-1 requires 100% volumetric examination coverage for circumferential piping welds. The alternative requirements of ASME Section Xl, Code Case N-460, approved for use in Regulatory Guide 1.147, Rev. 15, allows credit for essentially 100% coverage of the weld provided greater than 90% of the required volume has been examined.

10 CFR 50.55a(b)(2)(xv)(A), requires the following examination coverage criteria when applying Supplement 2 of Appendix VIII:

Page 1 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 (1) Piping must be examined in two axial directions and when examination in the circumferential direction is required, the circumferential examination must be performed in two directions, provided access is available.

(2) Where examination from both sides is not possible, full coverage credit may be claimed from a single side for ferritic welds. Where examination from both sides is not possible on austenitic welds, full coverage credit from a single side may be claimed only after completing a successful single-sided Appendix VIII demonstration using flaws on the opposite side of the weld.

10 CFR 50.55a(b)(2)(xvi)(B) requires that examinations performed from one side of a ferritic or stainless steel pipe weld must be conducted with equipment, procedures, and personnel that have demonstrated proficiency with single-side examinations. To demonstrate equivalency to two-sided examinations, the demonstration must be performed to the requirements of Appendix VIII as modified by this paragraph and §50.55a(b)(2)(xv)(A).

4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the essentially 100% volumetric examination coverage requirement for austenitic piping welds with single-side access.

Manual ultrasonic scanning techniques were performed using pulse-echo ultrasonic instruments and transducers qualified in accordance with ASME Section Xl, Appendix VIII as implemented by the Performance Demonstration Initiative (PDI).

There are currently no PDI qualified single-side examination procedures that demonstrate equivalency to two-sided examination procedures on austenitic piping welds. Current technology is not capable of reliably detecting or sizing flaws on the far side of an austenitic weld for configurations common to domestic nuclear applications.

PDI Performance Demonstration Qualification Summary (PDQS) certificates for austenitic piping list the limitation that single-side examination is performed on a best effort basis. The best effort qualification is provided in place of a complete single-side qualification to demonstrate that the examiner's qualification and the subsequent weld examination is based on application of the best available technology.

When the examination area is limited to one side of an austenitic weld, examination coverage does not comply with 10 CFR 50.55a(b)(2)(xv)(A) and Page 2 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 proficiency demonstrations do not comply with 10 CFR 50.55a(b)(2)(xvi)(B) and full coverage credit may not be claimed.

The ASME code required volume of these welds was interrogated ultrasonically to the maximum extent possible. No alternative methods or advanced technologies were considered capable of increasing the ASME code coverage Based on the configuration limited to single-sided access, relief is requested from complying with the essentially 100% required examination coverage for the following piping welds listed in Table 1. Note that examination coverage listed was obtained during examination with no credit taken for the far side of each weld in which examination from that side could not be performed.

Coverage calculations and limitation sketches are provided in this attachment.

5. Burden Caused by Compliance Compliance with the Code requirements would require extensive modification or replacement of components with a design that would allow examination from both sides of the weld. This option to meet the 100 % Code examination requirement for coverage is considered impractical based on the cost, additional radiation exposure and impact to plant equipment.

6. Proposed Alternative and Basis for Use The subject welds received a volumetric examination to the maximum extent practical using the best available techniques, as qualified through the Performance Demonstration Initiative (PDI) for Supplement 2 with demonstrated best effort for single-sided examination, from the accessible side of the weld.

Additionally, a visual (VT-2) examination was performed each inspection period during the system leakage tests as required by Section Xl, Table IWC-2500-1, Category C-H.

Based on the volumetric coverage that was obtained with acceptable results and the visual (VT-2) examination performed each inspection period, it is reasonable to conclude that service induced degradation would be detected. Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject welds.

7. Period for Which Relief is Requested The relief is requested for examinations performed during the third 10-year inspection interval for Millstone Unit 2, which began on April 1, 1999 and ended March 31, 2010.

Page 3 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 Table 1- Examination Category C-F-1 Welds with Limited -Volumetric Coverage Weld Number Code Item Configuration Examination Angle Limitation and Results Ultrasonic Surface Number and Wave Mode Examination Examination Material Coverage results

(%)

HSI- CF-316 C5.21 4 " Pipe-To-Valve 450 and 700 Shear Wave Examination limited to the pipe 44.75 Liquid penetrant side only due to taper of the valve examination Type 316 Stainless within close proximity of the weld. performed Steel There is not sufficient distance obtaining 100%

from the weld to the valve to coverage. No perform any scanning on the valve recordable side of the weld. indications Additional limitation on the pipe detected.

side due to a support located within close proximity of the weld limiting pipe side axial scan in the area of this support.

One recordable indication was detected and evaluated as acceptable root geometry.

HSI- CF-351 C5.21 3" Valve-To-Tee 450 and 700 Shear Wave Examination limited to the tee side 43.5 Liquid penetrant only due to taper of the valve examination Type 304 Stainless within close proximity of the weld. performed Steel There is not sufficient distance obtaining 100 %

from the weld to the valve to coverage. No perform any scanning on the valve recordable side of the weld. indications Additional limitation on the tee side detected.

due to the inside radius of the tee limiting the tee side axial scan in this area.

No recordable indications were detected.

Page 4 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 Table 1- Examination Category C-F-1 Welds with Limited Volumetric Coverage Weld Number Code Item Configuration Examination Angle Limitation and Results Ultrasonic Surface Number and Wave Mode Examination Examination Material Coverage results

(%)

HSI- CF-C-01 4 C5.11 6" Pipe-To-Valve 450 and 700 Shear Wave Examination limited to the pipe 50 Liquid penetrant 600 Longitudinal Wave side only due to taper of the valve examination Type 316 Stainless within close proximity of the weld. performed Steel There is not sufficient distance obtaining 100%

from the weld to the valve to coverage. No perform any scanning on the valve recordable side of the weld. indications No recordable indications were detected.

detected.

HSI- CF-E-050 C5.1 1 6" Pipe-To-Tee 450 Shear Wave Examination limited to the pipe 50 Liquid penetrant 700 Longitudinal Wave side only due to taper of the tee examination Type 316 Stainless within close proximity of the weld. performed Steel There is not sufficient distance obtaining 100%

from the weld to the tee to perform coverage. No any scanning on the tee side of the recordable weld. indications No recordable indications were detected.

detected.

HSI- CF-E-057 C5.1 1 6" Pipe-To-Valve 450 Shear Wave Examination limited to the pipe 50 Liquid penetrant 600 Longitudinal Wave side only due to taper of the valve examination Type 316 Stainless within close proximity of the weld. performed Steel There is not sufficient distance obtaining 100%

from the weld to the valve to coverage. No perform any scanning on the valve recordable side of the weld. indications No recordable indications were detected.

detected.

Page 5 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 Table 1- Examination Category C-F-1 Welds with Limited Volumetric Coverage Weld Number Code Item Configuration Examination Angle Limitation and Results Ultrasonic Surface Number and Wave Mode Examination Examination Material Coverage results

(%)

SI-CF-B-023 C5.11 10" Pipe-To-Elbow 450 Shear Wave Examination limited on the pipe 77.8 Liquid penetrant side of the weld due to location of examination Type 304 Stainless a permanent box type restraint performed Steel within close proximity of the weld obtaining 100%

that restricted the scanning in the coverage. No area of this restraint, recordable No recordable indications were indications detected. detected.

SI-CF-C-01 1 C5.1 1 6" Valve-To-Pipe 45 0and 600 Shear Wave Examination limited to the pipe 50 Liquid penetrant side only due to taper of the valve examination Type 304 Stainless within close proximity of the weld. performed Steel There is not sufficient distance obtaining 100%

from the weld to the valve to coverage. No perform any scanning on the valve recordable side of the weld. indications No recordable indications were detected.

detected.

SI-CF-D-01 3-1 C5.1 1 6" Tee-To-Pipe 450 Shear Wave Examination limited to the pipe 50 Liquid penetrant 600 Longitudinal Wave side only due to taper of the tee examination Type 316 Stainless within close proximity of the weld performed Steel There is not sufficient distance obtaining 100%

from the weld to the tee to perform coverage. No any scanning on the tee side of the recordable weld. indications No recordable indications were detected.

detected.

Page 6 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 Table 1- Examination Category C-F-1 Welds with Limited Volumetric Coverage Examination Angle Limitation and Results Ultrasonic Surface and Wave Mode Examination Examination Material Coverage results

(%)

3" Pipe-To-Tee 45 0and 700 Shear Wave Examination limited to the pipe 50 Liquid penetrant side only due to taper of the tee examination Type 316 Stainless within close proximity of the weld. performed Steel There is not sufficient distance obtaining 100%

from the weld to the tee to perform coverage. No any scanning on the tee side of the recordable weld. indications No recordable indications were detected.

detected. I SI-CF-F-046-1 I I 6" Tee-To-Pipe 450 Shear Wave Examination limited to the pipe 45.25 Liquid penetrant 700 Longitudinal Wave side only due to taper of the tee examination Type 316 Stainless within close proximity of the weld. performed Steel There is not sufficient distance obtaining 100%

from the weld to the tee to perform coverage. No any scanning on the tee side of the recordable weld. indications Additional limitation on the pipe detected.

side due to the location of two weldolets within close proximity of the weld that limited the pipe side axial scan in these areas.

No recordable indications were detected.

Page 7 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 Table 1- Examination Category C-F-1 Welds with Limited Volumetric Coverage Weld Number Code Item Configuration Examination Angle Limitation and Results Ultrasonic Surface Number and Wave Mode Examination Examination Material Coverage results

(%)

SI-CF-F-051 C5.1 1 6" Pipe-To-Valve 45 0and 600 Shear Wave Axial scan limited to the pipe side 75 Liquid penetrant 600 Longitudinal Wave only due to the taper of the valve examination Type 316 Stainless within close proximity of the weld. performed Steel There is not sufficient distance obtaining 100%

from the weld to the valve to coverage. No perform any axial scanning on the recordable valve side of the weld. indications Circumferential scans were detected.

performed on both the pipe and valve.

No recordable indications were detected.

450, 600 and 700 Shear Examination limited to the pipe Liquid penetrant SI-CF-F-052 C5.21 3" Tee-To-Pipe Wave side only due to taper of the tee 50 examination within close proximity of the weld. performed Type 316 Stainless There is not sufficient distance obtaining 100%

Steel from the weld to the taper of the coverage. No tee to perform any scanning on the recordable tee side of the weld. indications No recordable indications were detected.

I I_ I detected.

Page 8 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 Table 1- Examination Category C-F-1 Welds with Limited Volumetric Coverage Weld Number Code Item Configuration Examination Angle Limitation and Results Ultrasonic Surface Number and Wave Mode Examination Examination Material Coverage results

(%)

SI-CF-X-69 C5.1 1 12" Pipe-To-Valve 60 °and 700 Shear Wave Examination limited to the pipe 48.75 Liquid penetrant side only due to taper of the valve examination Type 304 Stainless within close proximity of the weld. performed Steel There is not sufficient distance obtaining 100%

from the weld to the valve to coverage. No perform any scanning on the valve recordable side of the weld. indications No recordable indications were detected.

detected.

SI-CF-X-82 C5.1 1 12" Pipe-To-Valve 45°and 700 Shear Wave Examination limited to the pipe 50 Liquid penetrant side only due to taper of the valve examination Type 304 Stainless within close proximity of the weld. performed Steel There is not sufficient distance obtaining 100%

from the weld to the valve to coverage. No perform any scanning on the valve recordable side of the weld. indications No recordable indications were detected.

I detected.

Page 9 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant MILLS*-.,.. Unit z AWONumber, . *.. .

system t4'-1 Percentage of Area Examined L' .- 7 S.,

Component ID t *- , Examination Data Slneet 20* 0- -0o -7 componentDescription 'JA-Vrt- Pipe CaIlbation Data Sheet# *S-_, -

Procedure Noz*.m.-*bu-r--v a.Rev 0 Pap " ofZ Calculation Type Surface Q1 Voiumettlc Cverage .quln calculation I I Sketch Area

, .. . c .c .CA#JL5 *o...

ExamIner Comrnent9 U1f-Ad Mg~~b t- .APenvz

ýr- PTAJTI3")jýL2Arg .' Feaft'1

'-JE ~ zý<l'2 Okz:4 -!SeAL bV)A ,A41=) MaJpJ. -q

$3lATb '4qS AK SAM-C~IT$%

MYZ. ;t4 AI.WEeWAA,5.t I-LI*,a g'%.99 te1ALCULA'flt )A.. n~t&A-.- 19-5" W%- I6fiv"11 1LI,,r'~~JC~5

-7~9 1 r UE0-A. FA &( :Mt AVA 1. V.A 311 Igo lbrA&'i tllo% L WIJa iu.JJ~ I~~IS Qw -~. .

Page 10 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 ATTACHMENT I

.COVERAGECALCULATION DATA SHEET Plant AlIIL L-:51n S . Unit  ;- AWONumber A4U-o7-o04491 System 1-AZ Percentage of Area Examined .. t5 'I-ComponentiD I4sD.. c. j,- ;". Examlnatlon Data Sheet.# All-o--ozo ComponentDesciptilon. -'r- JALjF_ _ Calibration Data Sheet# i- t0o*,0!bo ProcedureNo a.*.b.iA-B*,3 o,.Rev 0 Page 9 of Calculation Type Surface LI Volumetdo _ _ _... _ _

Coverage Calculation I Equation I Sketch Area

-M F_ -bj.1_,V *- sA.A.

SoCArQitA(I-o ') - 1 4L*

QJAL'JC 15 0S C %A ~C A~ r 0

-ca-AL Co-JEQAC-C3~

Exafilner Comme~ns

• 7ILP u~e~i.cuA LJAr

-AL AYA AtIAI ' Ir-

""~D 'J1r~eAWM!JS.

~XTIL a .1'

_.? AM LA I YrATLO ,Q a. N,- FJUA t ~ j.ý ZJih0¶1A SC MMUL~~.

r

• ý . e _ktnt, I ..-

Page 11 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75

• 'ATTACHMENT 1 COVERAGE CALCUIATI014 DATA SHEEýT Plan Uni AWO Wnfber /h.Z o(tS5.2 Sw"-____________

1-S Pemnage of AreaExamined Component ID 1HST - e- F C,- 014 . Examlnaton.Data Sheet #______

ComponentjDesoption -PIPE- MT VALV6c Camlbaion Data Sh"et#________

Procedure No, MI& -Rev, o06-o i Page' .. .Of .. 2!7 zo Coverage CalcukatiQnlEqmdton/I.letbh4eAm

• -'fC4A CIe VALVCS:Ar. 0%

Apni,5.1row PIPE ~j.2 &&.2*A /M66 q%'~tL 5AiJ VALOt %/W" nrt &ec aoa0.4:S IEXmh~ftWC6Mmonts. E r-A-*i,-I* VIA L.:*A Ak II.

Page 12 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 ATTACHMENT I COVERAGE. CALCULATION DATA SHEET Plant ALL-STOo' Unit .* AWO Number M*a.0o-O*236l System MS" Percentage of Area Examined" . d Component ID Us..cv--o5O Examlnation Data Sheet #

Component Description ,' fie-, Calibration Data Sheet #

ProcedureNo.Mp-pt).XJT_. T _ Rev ooo--ot Page*to of Calculation Type. Surface - Volumeb Coverage Calculation I Equation I Sketch Area q SPCW5YAXIAL 6CA41 buC Ta.flOQ4044 LJ(W'> Io

-ME SMb AXIALM SCAm 0

.-rce stb ic acM ________

To¶? C 'O- I .+/'

= ,50"/-

E~Ine omns"C~r~t "~ "'EU *~"%nA(A

" "~A~

i "~ f'J~

Page 13 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 I.

Weld No.

HSI-CF-E-057

\ / E Note: Single side access from the pipe side only.

50 percent coverage obtained.

Page 14 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75

'ATTACHM~fT 1 COVERAGE CALCULWPIN DIATA SKEET Plant MILL,,;21NE3 Unit '7 AWO Number M m %5-5, SystemR V-% /=pt3 Z-09 Peroentage pf Area -Examined -7

'-7.

.ComponentiD -C-l-O. ExaminationData Sheet # 2 0'4-O-OQ3 (r Component.Desorlpilon 10' PIPF--FLBQW Callbetlon Data Sheet # ~aig -0(<3L Pedue~o~i9-P~-~Y-ai~v 0page, .L...f-

,A: IAt- SCAtA vjP5T -S iss "wcLc W :sreu 5"C",

MIrfAL 60S 00sT 0; ,R SCAIA UP,'5- (CLQ(C1Xi '55.I*I - &V4elCS-TC CIQC*CA) l3T CCLa /ccu) %00,-

- r-7.la -VTAL covEtA&C- AC14 IEJEO p CLS'OL3 ExaminertC6mmeflts <~ suvE-rJAa-b AA1SC~e ~

-r- 0L0, Sidn.

Page 15 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 VIA$neiNuclea Energ Procedur No Pge o system  ?=:QZJE: ':-09 Exami.Data Sheet 0 Z4OI1-03 SCAW~ UMITATIOOS 0'3 '.PS'r-AM (-PtPF,)5IbE

?40 SCA63 O..j pipe sibc 5V' CCQ. FROM lC...I 3.-75* c,) FmoM rbt. .e~ LnV: M L.Ei-

-MyALt vp$r SCM-I "0i SCAO 014 PF StbF -roAL A QVA CvA I TOC FL4 Page 16 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75

,.,.,i.

• . . . * .* .. * . . . .. . ;... ,.- ,.. 2 - ..- .

. * * - ~ ,.. -, -'.*.. . .. . * - , ' *t.

• =*: * *..**' .. '..'..*....,..-

. ".,..**4.

, " ". . - ... *.. ._* .."*  :., .... ' . "J'

- ---------------- -ATTACHMENT I COVERAGE CALýCULAXnoN R~ATA SHEET P~antkA'u~t un ?. WO Number 147.-L5,4 G40 SyeMPItatD 61-. . .5i.Enn~wtu Oft ShOM erni d9~QfpU

-C P~~nftNI ~AL EET. R P M nftr a Dat a ShOO tS rA*t~fo Tm Sufaft oed2 efttwalchulal I auknIsetw Aa qA,.S o C t.-. r 7- 01.7S L& w I7.

A614E(AbSýmaezp_

kteva sol E2~m~nmrcominenta Page 17 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75

• . .I-_..___.

.. _ .. - .. ....... ...... .... "..-* - -* ."....... -= .. . .. . .

ATTACHMENT I COVERAGE CALdCULATION DATA SHEET plant JTJL t mF- .uni t AWO Number. fn-M2-4-7g system H -% Pereantae bf Area Ecamr 2/

nadL50 ..

ComponentiD 5SX-!tC....j.- ExaMtnon~atafteetf aL-01-10df 2 COMpOnwdtDesculptuonM F. Pr Calibration Data Sheet 42 FpcoadprvNoXYlPM:P-:jXZQ-R.vV 0.3 page o..O.2 Calmult"o TYpe surrfic'6't] Volumetut _ _ __ _ __ _ __ _ __ _ __ _

Coverage Calculation I ffguation I Sketch Are SCAN'I KL~Tcy 107- AX. DM5T 25%

k93 CM2C~ CSW 17-XAA~

Ex~aminer~ouet A *Sr'"l=r-Page 18 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant P¶ILLTQM~E n....Z Unt AWONuniber M;-o4-02-021 System -~sb 4:"'iJ, A-ale Percentage ofArea Mxaimined so-[

ComponentlD sc- . Examination Data Sheet# Alt -Ok 12(

Component Description S' 2 PE-T calibration Data Sheet . 01A ProoedureNo.MN9- -.oT--) -RevR 3 Page of~

Calculation Typo Surface [I voiumatticm covepeCalculationlIEuaflon I Sketch Area PIPEC S~ AXIAL ýICAN. 1004 TOS 6:0Z A)II CAhI0-

'TM MbE 3AJ c)

-VCJTAL.00YEZA-C -,; Sul Exam~inerCommwents." ,e)A IT  : '51Nr, pLu -Mt C6 ,rJeI~cj io Page 19 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant ,mL,-!osr Unit ' AWO Number /tA- 0-7 -. 1* *9 3 System 1tJ,*./ z/ X.;-3.i Percentage of Area Examined 5. '5I" Component ID si.-c-- o'4*- Examination Data Sheet#  ; aOs:

Component Description -rr-' - P% . Calibration Data Sheet.#

• l'- ci O o' .

Procedure Nol 4rAA-Ov-r-kotdRoev 0 Page Of 5 O,

Calculation Type Surface 0 Volumetric Coverage Calculation I Equatlon I Sketch Area 3o' l' 0 "W.*. ~~ Ol ~ ~ V r-.**,*.AJ

,~ ~ ~ " . . ~

-ME 5%br.eC Io 5CAF4 TfdTAL COVI~eA&C

/ . . ' ' . . . . . . .7 Examiner CommrentswTljvAxtoji AT 't e

%-W~ r WLt$0LEtAr Lq l,,GrAjj " AJ Q5 ."MiM LI4 'TATIO'J dse rfl~~t~~ ~ P~E 5IF, AYAAA, MAuP. 0-aI C:ltr. CA-h) LW-tA41M e%.

g3QrAJ nJf rvaI* e~~.~Q- -

Page 20 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75

~i.

Weld No.

SI-CF-F-051 Ov~rmen00'eO/L CO,1Cj*&O Ito 1: L"

• .J., -

l Page 21 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant AILL ;,rCg Unit a AWONumber mav 6- o'4jozi .

System r 4n E Percentage Of Area Examined 5o /,

ComponentlD s"T - ;-osF Examtnation Data Sheet#41 - O0 Component Descilption _S' fkeE-*TF-C Calibration Data Sheet# - -or- 0 a ,

Procedure No.* p-pbr..Or.. Revooo-o3 Page oof "

Calculation TyM Su,1raoe.E VOIUM!TrC~

Coverage Calculation I Equation I Sketch Area VYPST A~'AI,= .. :t too-L vp c%..C Ar 5.CAQ0 Vf5 rCIItC .$CA!4 %00-

"-'TAL- CvERA&C "7. 4 2*o00 7. q 50/.

aExafninier cotments -70 AXICtAL Q ~~EQjIr AAII F.~ FAp0 Page 22 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75 ATTACHMENT 1 'C M 9 COVERAGE CALCULATION DATA SHEET Plant mLL5T.r,-

• Unit  : AWO Number AA -- o01.. O'4jO" System ba: ,4 MOW 1-10 Percentage of Area Examined __ .'_

Component ID -.. c ).- , Examination Data Sheet#0 11. 0%- 0.49I Component Description i.a, Pip.-,JALJy Calibration Data Sheet . " -oi-

ý01.1

• Procedure No._p e pb-r-cJ-ra. Rev o00.-03 Page Li of L(

Calculation Type Surface [] Volumetdsc ff.

Coverage Calculation I Equation I Sketch Area

• PElJ A L* V*

UPSI'C tA S-AF4 too ". CcO/ 5.*A

~~s A~lA1SCA"~C 0 EWn et .ieo .1 < Z4 Ea inr Comet i-C -T

• 1

• 1 Page 23 of 24

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-75

......... . . .. .. I . . . L J

a.

• Weld No.

SI-CF-X-82 Gom~70ý S' Co P ~rr F'10 Skatc or Maxcr

.4 I'; p&

I.

43-0 0%*G~w~

TqpvmS Too1 0

______e Was 1)~~ ~~~~ae OoePoOsCInua imm OdMuI 2)B4 Fld~t a--p SO be 1,eE01 abaeApas W . .

Page 24 of 24

Serial No.11-137 Docket No. 50-336 ATTACHMENT 8 RELIEF REQUEST RR-89-76 EXAMINATION CATEGORY C-F-2 PRESSURE RETAINING WELDS IN CARBON OR LOW ALLOY STEEL PIPING DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-76 Relief Requested.

In Accordance with 10 CFR 50.55a(g)(5)(iii)

--Inservice Inspection Impracticality--

1. ASME Code Components Effected:

ASME Code Class: Code Class 2 Examination Category: C-F-2, Pressure Retaining Welds in Carbon or Low Alloy Steel Piping.

Item Numbers: C5.81, Pipe Branch Connections of Branch Piping -

Circumferential Weld Component Identification: Listed in Table 1 Material: A155, GR KCF-70 carbon steel

2. Applicable Code Addition and Addenda ASME Section Xl, 1989 Edition, No Addenda

3. Applicable Code Requirement

ASME Section Xl, 1989 Edition, Examination Category C-F-2 requires 100% surface examination coverage for circumferential piping branch connection welds. The alternative requirements of ASME Section Xl, Code Case N-460, approved for use in Regulatory Guide 1.147, Rev. 15, allows credit for essentially 100% coverage of the weld provided greater than 90% of the required volume has been examined.

4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the essentially 100%

surface examination coverage requirement of the subject weld due to the geometric configuration and obstructions caused by the pipe rupture restraint support members which limit the surface coverage that can be obtained.

Magnetic Particle surface examination of the subject weld was performed to the maximum extent practicable with the limitations caused by the obstruction of the support members that are in close proximity of the weld.

The use of liquid penetrant examination was considered as an alternative to increase the coverage, however, due to the close proximity of the support members to the Page 1 of 4

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-76 subject weld, it was determined that no meaningful results could be obtained. There were no other alternative methods or advanced technologies that were considered capable of increasing the ASME code coverage.

The support design drawing and limitation sketch is provided for reference in this attachment.

5. Burden Caused by Compliance To increase the examination coverage, the pipe rupture restraint would need to be disassembled and removed. The removal of this large complex restraint would require a significant effort that is considered to be impractical due to the impact to plant equipment.

6. Proposed Alternative and Basis for Use The subject weld received a surface examination using the best available techniques on the accessible portions of weld to the extent practical. Additionally, a visual (VT-2) examination was performed each inspection period during the system leakage tests as required by ASME Section Xl, Table IWC-2500-1, Category C-H.

Based upon the surface examination coverage that was obtained with acceptable results and the visual (VT-2) examination performed each period, it is reasonable to conclude that service induced degradation would be detected. Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject welds.

7. Duration of Proposed Alternative The relief is requested for the third 10-year inspection interval for Millstone Unit 2, which began on April 1, 1999 and ended March 31, 2010.

TABLE 1- Examination Category C-F-2 Weld with Limited Surface Examination Coverage Weld Number Code Item Configuration Comments Surface Number Examination Coverage MSB-CG-16 C5.81 Sweepolet-to-Pipe Limited accessibility due to the 61.5 obstruction from the pipe rupture restraint support members that are within close proximity to the weld.

No recordable indications were detected.

Page 2 of 4

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-76

'LD PLAN-MS R-2.

Page 3 of 4

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-76 I

I Page 4 of 4

Serial No.11-137 Docket No. 50-336 ATTACHMENT 9 RELIEF REQUEST RR-89-77 EXAMINATION CATEGORY R-A RISK INFORMED PIPING EXAMINATIONS DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-77 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

--Inservice Inspection Impracticality--

1. ASME Code Components Affected:

ASME Code Class: Code Class 1 Examination Category: R-A, Risk Informed Piping Examinations Item Number: R1.20, Elements Not Subject to a Damage Mechanism Component Identification: Listed in Table 1 Material: Listed in Table 1

2. Applicable Code Addition and Addenda ASME Section Xl 1989 Edition, No Addenda Austenitic piping welds with single-side access subject to ultrasonic examination with Supplement 2 of Appendix VIII to the 1995 Edition with 1996 Addenda of ASME Section XI.

3. Applicable Code Requirement

The examination requirements for Class 1 piping welds are governed by the Risk-Informed Inservice Inspection program that was approved by the NRC in a Safety Evaluation dated April 1, 2005 (ADAMS Accession No. ML050740463).

This program was developed in accordance with the Westinghouse Owners Group Topical Report WCAP-14572, Revision 1-NP-A. The WCAP Table 4.1-1, Examination Category R-A, Risk-Informed Piping Examinations, requires 100%

of the weld to be examined. The alternative requirements of ASME Section Xl, Code Case N-460, approved for use in Regulatory Guide 1.147, Rev. 15, allows credit for essentially 100% coverage of the weld provided greater than 90% of the required volume has been examined.

10 CFR 50.55a(b)(2)(xv)(A), requires the following examination coverage when applying Supplement 2 of Appendix VIII:

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-77 (1) Piping must be examined in two axial directions and when examination in the circumferential direction is required, the circumferential examination must be performed in two directions, provided access is available.

(2) Where examination from both sides is not possible, full coverage credit may be claimed from a single side for ferritic welds. Where examination from both sides is not possible on austenitic welds, full coverage credit from a single side may be claimed only after completing a successful single-sided Appendix VIII demonstration using flaws on the opposite side of the weld.

10 CFR 50.55a(b)(2)(xvi)(B), requires that examinations performed from one side of a stainless steel pipe weld must be conducted with equipment, procedures, and personnel that have demonstrated proficiency with single-side examinations. To demonstrate equivalency to two-sided examinations, the demonstration must be performed to the requirements of Appendix VIII as modified by this paragraph and §50.55a(b)(2)(xv)(A).

4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the 100 %

volumetric examination coverage requirement for austenitic piping welds with single-side access.

The manual ultrasonic scanning techniques were performed using pulse-echo ultrasonic instruments and transducers qualified in accordance with ASME Section Xl, Appendix VIII as implemented by the Performance Demonstration Initiative (PDI).

There are currently no PDI qualified single-side examination procedures that demonstrate equivalency to two-sided examination procedures on austenitic piping welds. Current technology is not capable of reliably detecting or sizing flaws on the far side of an austenitic weld for configurations common to domestic nuclear applications.

PDI Performance Demonstration Qualification Summary (PDQS) certificates for austenitic piping list the limitation that single-side examination is performed on a best effort basis. The best effort qualification is provided in place of a complete single-side qualification to demonstrate that the examiners qualification and the subsequent weld examination is based on application of the best available technology.

When the examination area is limited to one side of an austenitic weld, examination coverage does not comply with 10 CFR 50.55a(b)(2)(xv)(A) and Page 2 of 16

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-77 proficiency demonstrations do not comply with 10 CFR 50.55a(b)(2)(xvi)(B) and full coverage credit may not be claimed.

The ASME code required volume of these welds was interrogated ultrasonically to the maximum extent possible. No alternative methods or advanced technologies were considered capable of increasing the ASME code coverage.

Based on the configuration limited to single-sided access, relief is requested on complying with the 100 % required examination coverage for the piping welds listed in Table 1. Note that the examination coverage listed was obtained during examination with no credit taken for the far side of each weld.

Coverage calculations and limitation sketches are provided in this attachment.

5. Burden Caused by Compliance Compliance with the Code requirements would require extensive modification or replacement of components with a design that would allow examination from both sides of the weld which is considered to be impractical due to cost, additional radiation exposure and impact to plant equipment.

6. Proposed Alternative and Basis for Use The subject welds received a volumetric examination to the maximum extent practical using the best available techniques, as qualified through the Performance Demonstration Initiative (PDI) for Supplement 2 with demonstrated best effort for single-sided examination from the accessible side of the weld.

Additionally, a visual (VT-2) examination was performed at the end of each refueling outage during the system leakage tests as required by ASME Section Xl, Table IWB-2500-1, Category B-P.

Based on the volumetric coverage that was obtained with acceptable results, and the visual (VT-2) examination performed each refueling outage, it is reasonable to conclude that service induced degradation would be detected. Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject welds.

7. Duration of Proposed Alternative Relief is requested for the third 10-year inspection interval for Millstone Unit 2, which began on April 1, 1999 and ended March 31, 2010.

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-77 Table 1- Examination Category R-A Welds with Limited Volumetric Coverage Weld Item Configuration Examination Angle Comments Ultrasonic Identification Number Material and Wave Mode Examination Coverage (%)

BPV-C-5025A R1.20 2.5" Valve-To-Pipe 450 and 700 Shear Wave This was a preservice examination 50 associated with a new weld. Limited Type 316 Stainless examination from the pipe side only due Steel to the taper of the valve within close proximity of the weld. There is not sufficient distance from the weld to the valve to perform any scanning on the valve side of the weld.

No recordable indications were detected.

BPV-C-5043A R1.20 2.5" Valve-To-Pipe 450 and 70' Shear Wave This was a preservice examination 50 associated with a new weld. Limited Type 316 Stainless examination from the pipe side only due Steel to the taper of the valve within close proximity of the weld. There is not sufficient distance from the weld to the valve to perform any scanning on the valve side of the weld.

No recordable indications were detected.

BPV-C-5049A R1.20 2.5" Pipe-To-Valve 450 and 700 Shear Wave This was a preservice examination 50 associated with a new weld. Limited Type 316 Stainless examination from the pipe side only due Steel to the taper of the valve within close proximity of the weld. There is not sufficient distance from the weld to the valve to perform any scanning on the valve side of the weld.

One recordable indication was detected and evaluated as acceptable weld root geometry.

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-77 Table 1- Examination Category R-A Welds with Limited Volumetric Coverage Weld Item Configuration Examination Angle Comments Ultrasonic Identification Number Material and Wave Mode Examination Coverage (%)

BPV-C-5051 A R1.20 2.5" Pipe-To-Valve 450 and 700 Shear Wave This was a preservice examination 50 associated with a new weld. Limited Type 316 Stainless examination from the pipe side only due to Steel the taper of the valve within close proximity of the weld. There is not sufficient distance from the weld to the valve to perform any scanning on the valve side of the weld.

One recordable indication was detected and evaluated as acceptable weld root geometry.

BSI-C-1013 R1.20 12" Elbow-to-Valve 450 and 70c Shear Wave Limited examination from the elbow side 50 600 Longitudinal Wave only due to the taper of the valve within Type 316 Stainless close proximity of the weld. There is not Steel sufficient distance from the weld to the valve to perform any scanning on the valve side of the weld.

No recordable indications were detected.

BSI-C-2011 R1.20 12" Elbow-To-Valve 450 Shear Wave Limited examination from the elbow side 50 600 Longitudinal Wave only due to the taper of the valve within Type 316 Stainless close proximity of the weld. There is not Steel sufficient distance from the weld to the valve to perform any scanning on the valve side of the weld.

No recordable indications were detected.

BSI-C-3012 R1.20 12" Valve-To-Elbow 450 Shear Wave Limited examination from the elbow side 50 600 Longitudinal Wave only due to the taper of the valve within Type 316 Stainless close proximity of the weld. There is not Steel sufficient distance from the weld to the valve to perform any scanning on the valve side of the weld.

No recordable indications were detected.

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-77 Table 1- Examination Category R-A Welds with Limited Volumetric Coverage Weld Item Configuration Examination Angle Comments Ultrasonic Identification Number and Wave Mode Examination Material Coverage (%)

BSI-C-4010A R1.20 12" Valve-To-Pipe 450 and 700 Shear This was a preservice examination 50 Wave. associated with a new weld. Limited Type 316 Stainless 600 Longitudinal Wave examination from the pipe side only due to Steel the taper of the valve within close proximity of the weld. There is not sufficient distance from the weld to the valve to perform any scanning on the valve side of the weld.

Recordable indications were detected and evaluated as acceptable counterbore geometry and an embedded fabrication flaw outside UT examination area was evaluated as acceptable in accordance with IWB-3514.

BSI-C-4011 Ri1.20 12" Pipe-to-Valve 450 Shear Wave This was a preservice examination 50 600 Longitudinal Wave associated with a new weld. Limited Type 316 Stainless examination from the pipe side only due to Steel the taper of the valve within close proximity of the weld. There is not sufficient distance from the weld to the valve to perform any scanning on the valve side of the weld.

Recordable indications were detected and evaluated as acceptable counterbore and root geometry.

BSI-C-4012 R1.20 12" Valve-To-Elbow 450 Shear Wave Limited examination from the elbow side 50 600 Longitudinal Wave only due to the taper of the valve within Type 316 Stainless close proximity of the weld. There is not Steel sufficient distance from the weld to the valve to perform any scanning on the valve side of the weld.

No recordable indications were detected.

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-77 Millstone Unit 2 Ultrasonic Weld Thickness Profile

[Reference ID: IPFV-C- 025ZA Palo Pkg.: 17048Page of f~]

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Profile Area VAU WA eit4 Th'lrlI~ ~ O V64.0.1 rGM~r1deA*A TV Note: Single side access from the pipe side only. 50 percent coverage obtained Page 7 of 16

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-77 Millstone Unit 2 Ultrasonic Weld Thickness Profile IReferenlc 0:rnBýy44O3aA Data Pkcg.,71-9 Page: L]o ~

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Note: Single side access from the pipe side only. 50 percent coverage obtained Page 9 of 16

Serial No.11-137 Docket. No. 50-336 10 CFR 50.55a Request Number: RR-89-77 l~onHeight: Crown Width: O- via., Weld Length: Z L' LOng 08nl:

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-77 ATTACHMENT i COVERAGE CALCULATION DATA SHEET Plant $I.L*TO*r. Unit Z - AWO Number .

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-77

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-77 BSI-C-4010A Coverage QUALIFIED COVERAGE ACHIEVED

- 0.82 Sq. In. (50%)

PIPE VALV Ii I..

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-77 BSI-C-4011 Coverage

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- 0.749 Sq. In. (72.1%)

PIPE Page 15 of 16

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number: RR-89-77 COVERAGA CALCLAllON DAASET Plan rn/11*rg&4 Unit2 I,AWONuftebr System .*Z. Pererfg r~ea Vm5ndA

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Serial No.11-137 Docket No. 50-336 ATTACHMENT 10 RELIEF REQUEST RR-89-78 EXAMINATION CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-78 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

--Inservice Inspection Impracticality--

1. ASME Code Components Affected ASME Code Class: Code Class 1 Examination Category: B-P, All Pressure Retaining Components Item Number: B15.11, Reactor Vessel, Pressure Retaining Boundary

Description:

Pressure Testing Requirements for the Reactor Pressure Vessel (RPV) Flange Leak-Off Piping Component Identification: NPS 1 in. RPV Flange Seal Leak-Off Piping

2. Applicable Code Edition and Addenda

ASME Section Xl, 1989 Edition, No Addenda, with the alternative requirements of ASME Code Case N-498-4, approved for use in Regulatory Guide 1.147, Rev. 15.

3. Applicable Code Requirement

The 1989 Edition of ASME Section XI, Table IWB-2500-1, Examination Category B-P, requires all pressure retaining components to be subject to a system hydrostatic test in accordance with IWB-5222. ASME Code Case N-498-4 allows a system leakage test at or near the end of each inspection interval as an alternative to the 10-year system hydrostatic test required by Table IWB-2500-1. The boundary subject to test pressurization during the leakage test conducted at or near the end of each inspection interval shall extend to all Class 1 pressure retaining components within the system boundary with a test pressure not less than the pressure corresponding to 100% rated reactor power.

4. Impracticality of Code Compliance The Reactor Pressure Vessel (RPV) head flange seal leak detection piping is shown in Figures 1 and 2 of this attachment. The piping is separated from the reactor coolant pressure boundary by one passive membrane, which is an o-ring located on the inner vessel flange. A second o-ring is located on the outside of the tap in the vessel flange. Failure of the inner o-ring is the only condition under which this line is pressurized. Therefore, the line is not expected to be pressurized during the system pressure test following a refueling outage.

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-78 The configuration of this piping precludes system pressure testing while the vessel head is removed because the configuration of the vessel tap coupled with the high test pressure prevents the tap in the flange from being temporarily plugged or connected to other piping. The opening in the flange is smooth walled, making the effectiveness of a temporary seal very limited. Failure of a temporary test seal could possibly cause ejection of the device used for plugging or connecting to the vessel flange.

The configuration also precludes pressurizing the line externally with the head installed. The top head of the vessel contains two grooves that hold the o-rings.

The o-rings are held in place by a series of retainer clips that are housed in recessed cavitieý in the flange face. If a pressure test were to be performed with the head on, the inner o-ring would be pressurized in a direction opposite to its design function.

This test pressure would result in a net inward force on the inner o-ring that would tend to push it into the recessed cavity that houses the retainer clips. The thin o-ring material would likely be damaged by the inward force.

5. Burden Caused by Compliance The RPV flange seal leak-off line would only be pressurized in the event of a failure of the inner O-ring. Purposely failing or not installing the inner o-ring in order to perform a pressure test would require subsequently installing a new o-ring set with the time and radiation exposure associated with removing and reinstalling the RPV 2 head a second time to replace the o-rings.

This option is considered to be impractical due to the cost, increased radiation exposure and impact to outage duration.

6. Proposed Alternative and Basis for Use For each refueling outage during the third 10-year interval, a visual (VT-2) examination was performed on the unpressurized subject piping as part of the Class 1 leakage test.

If the inner o-ring should leak during the operating cycle, it would be identified by an increase in temperature of the leak-off line above ambient temperature because this is an indication of o-ring seal leakage. This increased temperature would actuate an alarm in the Control Room, which is closely monitored by procedure and directs operator actions allowing identification of the leakage and any further compensatory actions, if required. This leakage would be collected in the primary drain transfer tank.

Additionally, the flange seal leak-off line is essentially a leakage collection/detection system and the line would only function as a Class 1 pressure boundary if the inner o-ring fails, thereby pressurizing the line. If any significant leakage did occur in the leak-off line piping itself during this time of pressurization, it would exhibit boric acid Page 2 of 5

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-78 accumulation and be discernable during the VT-2 visual examination that was performed unpressurized each refueling outage.

Based upon the above, it is reasonable to conclude that service induced degradation would be detected. Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject piping.

Future pressure testing of this line will be performed in accordance with the fourth interval relief request RR-04-08, which was approved on January 18, 2011, (ADAMS Accession no. ML103640257).

7. Duration of Proposed Alternative Relief is requested for the third 10-year inspection interval for Millstone Unit 2, which began on April 1, 1999 and ended March 31, 2010.

8. Precedents A similar request for relief was previously approved for Limerick Generating Station, Units 1 and 2 by letter dated January 27, 2009 ADAMS Accession No. ML090060218.

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Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-78 Figure 1:

REACTOR PRESSURE VESSEL HEAD FLANGE LEAK-OFF LINE CONFIGURATION Page 4 of 5

Serial No.11-137 Docket No. 50-336 10 CFR 50.55a Request Number RR-89-78

- Ifr"4 Flcrt,§ I ttJ

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504 Dioiil -.A" Detail 'A" Vessel Flanqe Sectional View Figure 2 REACTOR PRESSURE VESSEL HEAD FLANGE LEAK-OFF LINE DETAILS Page 5 of 5