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Response to Request for Additional Information Regarding Relief Requests 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, & 2R2-011 for the Second 10-Year Inservice Inspection Program
	ML092740063
Person / Time
Site:	Harris
Issue date:	09/24/2009
From:	Corlett D; Progress Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	HNP-09-095, TAC ME0166, TAC ME0608, TAC ME0609, TAC ME0610, TAC ME0612, TAC ME0613, TAC ME0614, TAC ME0615
	Download: ML092740063 (173)
	v • d • e

Progress Energy Serial: HNP-09-095 SEP 2 4 2009 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, AND 2R2-011 FOR THE SECOND 10-YEAR INSERVICE INSPECTION PROGRAM (TAC NOS.

ME0608, ME0609, ME0610, ME0166, ME0612, ME0613, ME0614, AND ME0615)

References:

1. Letter from D. H. Corlett to the Nuclear Regulatory Commission (SERIAL:

HNP-08-045), "Second Ten-Year Interval Inservice Inspection Program - Final Documentation Including Requests for Relief in accordance with 10 CFR 50.55a," dated February 05, 2009

2. Letter from M. Vaaler, Nuclear Regulatory Commission, to C. L. Burton, "Request for Additional Information Regarding Relief Requests 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, and 2R2-011 For The Second 10-Year Inservice Inspection Program (TAC NOS. ME0608, ME0609, ME0610, ME0611, ME0612, ME0613, ME0614, and ME0615),"

dated July 21, 2009 Ladies and Gentlemen:

On July 21, 2009, Harris Nuclear Plant (HNP) received a request from the NRC (Reference 2) for additional information needed to facilitate the review of proposed Second 10-Year Inservice Inspection Interval Relief Requests 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, and 2R2-01 1. HNP submitted this original request as Serial: HNP-08-045 (Reference 1).

Per discussions with Marlayna Vaaler (NRC HNP Project Manager), HNP was allowed an extension to the September 18, 2009, response date specified in Reference 2. Accordingly, the Enclosures to this letter provide the requested additional information for the Relief Requests.

This document contains no new or revised Regulatory Commitments.

Please refer any questions regarding this submittal to me at (919) 362-3137.

Progress Energy Carolinas, Inc.

-T Harris Nuclear Plant P.O. Box 165 New Hill, NC 27562

,i 10'

HNP-09-095 Page 2 Sincerely, D. H. Corlett Supervisor - Licensing/Regulatory Programs Harris Nuclear Plant DHC/kms

Enclosures:

1. HNP's Response to the Request for Additional Information Regarding Relief Request 13R-02 for the Third 10-Year Inservice Inspection Interval

2. Inservice Inspection Relief Request 2R1-0 18 Response to Request for Additional Information

3. Inservice Inspection Relief Request 2R1-019 Response to Request for Additional Information

4. Inservice Inspection Relief Request 2R1-020 Response to Request for Additional Information

5. Inservice Inspection Relief Request 2R1-021 Response to Request for Additional Information

6. Inservice Inspection Relief Request 2R1-022 Response to Request for Additional Information

7. Inservice Inspection Relief Request 2R2-009 Response to Request for Additional Information

8. Inservice Inspection Relief Request 2R2-010 Response to Request for Additional Information

9. Inservice Inspection Relief Request 2R2-011 Response to Request for Additional Information cc:

Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. L. A. Reyes, NRC Regional Administrator, Region II Ms. N. C. Ritchie-Slaughter, Harris Plant Authorized Nuclear Inservice Inspector Ms. M. G. Vaaler, NRC Project Manager, HNP to SERIAL: JINP 09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, AND 2R2-011 FOR THE SECOND 10-YEAR INSERVICE INSPECTION PROGRAM Summary Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc.,

(PEC) (licensee) submitted Relief Requests (RRs) 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, and 2R2-01 1, for the Harris Nuclear Plant (HNP). The proposed RRs are for the second 10-year inservice inspection (ISI) interval, in which the licensee adopted the 1989 Edition of the ASME Code,Section XI, No Addenda, as the Code of Record.

The proposed RRs request relief in accordance with Title 10 of the Code of Regulations (10 CFR) Section 50.55a(g)(5)(iii) from applicable requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," related to inspection of welds with limited coverage in ASME Code examination Categories B-F, B-A, B-D, B-B, C-A, C-B, and C-A. The ASME Code requires that 100 percent of the examination volumes or surface areas described in ASME Code,Section XI, Tables IWB-2500 and IWC-2500, be inspected during each interval., The licensee stated that 100 percent of the ASME Code-required volumes or surface areas are impractical to obtain at HNP.

10 CFR 50.55a(g)(5)(iii) states that when licensees determine that conformance with ASME Code requirements is impractical at their facility, they shall submit information to support this determination. The U.S. Nuclear Regulatory Commission (NRC) will evaluate such requests based on impracticality, and may impose alternatives, giving due consideration to public safety and the burden imposed on the licensee.

Pacific Northwest National Laboratory and the NRC have reviewed the information submitted by the licensee and have determined the following information is required to complete the evaluation.

Request 1:

General - Information Required on All Requests for Relief In all cases, the licensee has provided only general information regarding the impracticality of obtaining ASME Code-required volumetric or surface examinations, as applicable. Statements such as "physical obstructions and geometric surface conditions," "design configurations," or "inner diameter counterbore and root configuration," are inadequate to explain the bases for not obtaining the ASME Code-required examination volumes. No sketches with dimensional information showing the causes of limited accessibility have been included.

Please submit detailed and specific information to support the bases for limited examination in all requests for relief in order to demonstrate impracticality. Specifically:

a)

Include descriptions (written and/or sketches, as necessary) of the interferences present Page 1 of 5

Enclosure I to SERIAL: HNP 09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE-NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, AND 2R2-011 FOR THE SECOND 10-YEAR INSERVICE INSPECTION PROGRAM for applied nondestructive examination (NDE) techniques.

b)

As applicable, describe NDE equipment (ultrasonic scanning apparatus), details of the listed obstructions (size, shape, proximity to the weld, etc.) to demonstrate accessibility limitations, and discuss whether alternative methods or advanced technologies could be employed to maximize ASME Code coverage.

c)

Fully clarify the wave modality and insonification angles used for all ultrasonic examinations.

d)

Provide cross-sectional coverage plots to describe the ASME Code volumes examined.

e)

If not included, state whether any indications were discovered as a result of these examinations, and how these indications have been dispositioned.

Response

The requested information is summarized in the following

Enclosures:

2R1-018 2R1-019 2R1-020 2R1-021 2R1-022 2R2-009 2R2-010 2R2-011 Request 2:

Request for Relief 2R2-010, ASME Code,Section XI, Examination Category C-B, Item C2.21, Nozzle-to-Shell Weld The licensee has requested relief from the requirement to examine 100 percent of the ASME Code-required inspection volume for two Boron Injection Tank nozzle-to-vessel welds:

II-BIT-01NTHW-03 and II-BIT-01NTHW-04.

a)

Please state whether the inspection techniques used to examine these welds included refracted longitudinal waves.

Response

Shear waves were used in all angle beam exams and longitudinal waves used in the 0 degree exam, as follows:

45 degree shear - V2 V 60 degree shear - V2 V 0 degree - longitudinal Page 2 of 5

Enclosure I to SERIAL: HNP 09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS 2R1-018, 2R1-019, 2R1-020, 2R1-024, 2R1-022, 2R2-009, 2R2-010, AND 2R2-011 FOR THE SECOND 10-YEAR INSERVICE INSPECTION PROGRAM b)

Please state the material used (austenitic or ferritic steel) and the wall thickness for each of these components.

Response

The material used is alloy steel - ASTM A 204 Standard Specification for Pressure Vessel Plates, Alloy Steel, Molybdenum with a 1.732" Thickness Request 3:

Request for Relief 2R1-018, ASME Code,Section XI, Examination Category B-F, Item B5.130, NPS 4 or Larger Dissimilar Metal Butt Welds a)

The licensee has requested relief from the requirement to examine 100 percent of the ASME Code-requiredinspection volume for the following dissimilar metal welds on the primary coolant system:

RVNOZCI-N-05SE Inlet Nozzle DM weld at 95 degrees RVNOZBI-N-03SE Inlet Nozzle DM weld at 215 degrees RVNOZAI-N-01SE Inlet Nozzle DM weld at 335 degrees It is unclear from the licensee's submittal why inlet nozzle welds RVNOZCI-N-05SE and RVNOZBI-N-03SE were not included in the previous 10-year ISI request for relief.

Please submit information explaining why these welds were not included previously.

Response

As discussed in Section 8.1 ("Changes in Circumstances") of Relief Request Submittal (SERIAL: HNP-08-045), these examinations were performed by a different vendor during the first interval, resulting in different coverage limitations. Additionally, the second interval UT inspections were performed with examination personnel and examination procedures qualified to ASME Code, Appendix VIII, as administered by the EPRI Performance Demonstration Initiative (PDI). This improved method of examination also results in differing coverage limitations.

b)

Please provide more detailed information on the ultrasonic testing (UT) inspections performed (i.e., probe type, incident angle, geometrical interference, scanned coverage, etc).

Response

Information is provided in Enclosure 2 of this response.

c)

Please explain how the "Combined UT [Ultrasonic] Coverage Total Percentage" in Sections 6.1, 6.2, and 6.3 of 2R1-018 is obtained.

Page 3 of 5

Enclosure I to SERIAL: 14NP 09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, AND 2R2-011 FOR THE SECOND 10-YEAR INSERVICE INSPECTION PROGRAM

Response

The Combined UT coverage totals as provided in Sections 6.1, 6.2 and 6.3 of 2R1-018 were obtained from averaging the individual (CCW, CS, UP, DOWN) 700 Longitudinal Wave Dual Scans as follows :

RVNOZC1-N-05SE: (69.15 + 69.15 + 100 + 100)/4 = 84.58 RVNOZBI-N-03SE: (76.67 + 76.67 + 100 + 100)/4 = 88.34 RVNOZA1-N-01SE: (70.29 + 70.29 + 100 + 100)/4 = 85.15 d)

Please provide information regarding when the ultrasonic testing inspection for each weld was performed (e.g., what ASME Code criteria were required - Appendix VIII or Section V)?

Response

'As discussed in Section 6.1 for RVNOZC1-N-05SE, Section 6.2 for RVNOZBl-N-03SE and Section 6.3 for RVNOZAI-N-OISE of the Relief Request Submittal (SERIAL:

HNP-08-045), UT examinations were performed with examination personnel and examination procedures qualified to ASME Code, Appendix VIII, as administered by the EPRI Performance Demonstration Initiative (PDI).

e)

Please provide more detailed information on the eddy current inspection methods performed, the inner diameter surface conditions of the affected welds, and an assessment of the ability to perform the eddy current testing exam effectively on these types of surface conditions.

Response

The Eddy Current procedure (provided separately) contains this information.

Request 4:

Request for Relief 2R1-022, ASME Code,Section XI, Examination Category B-B, Item B2.40, Pressure Retaining Welds in Vessels Other than Reactor Vessels The licensee has requested relief from the requirement to examine 100 percent of the ASME Code-required inspection volume for steam generator tubesheet-to-head weld II-SG-001 SGA-TSTHW-06-1.

HNP is a 3-loop pressurized water reactor plant; there are three steam generators, each containing a tubesheet-to-head weld. The ASME Code states that "the examination may be limited to one vessel among the group of vessels performing similar functions."

Please clarify whether all three steam generator tubesheet-to-head welds were examined.

Because the licensee was unable to meet the ASME Code-required inspection volume on tubesheet-to-head weld II-SG-00 1 SGA-TSTHW 1, if the other tubesheet-to-head welds were examined, please describe whether the same coverage area limitations apply to these similar welds on the remaining two steam generators.

Page 4 of 5

Enclosure I to SERIAL: HNP 09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, AND 2R2-011 FOR THE SECOND 10-YEAR INSERVICE INSPECTION PROGRAM

Response

All three of HNP's steam generators have the same configuration and associated limitation. Since this examination category only requires one examination per similar vessel, only one of the steam generators was examined. Additionally, these steam generators were new in 2001.

Page 5 of 5 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-018 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Examination Category B-F, Item B5.130, NPS 4 or Larger Dissimilar Metal Butt Welds RAI REQUEST

RESPONSE

I a Description (Reference Relief Request submittal HNP-08-045 Section 1.0). Welds are Cold leg elbow to nozzle weld.

I a Sketch Information follows in Enclosure.

la Interference/Obstruction (Reference Relief Request submittal HNP-08-045 Section 5.0). Volumetric examination for the subject welds at HNP is restricted due to geometric surfaces (inner diameter surface counter-bore and root configuration) which limit accessibility and make the 100 percent volumetric examination impractical for these areas.

lb NDE Equipment The following procedures are provided separately:

PDI-ISI-254-SE WDI-STD-146 WDI-STD-088 lb Alternative Methods (Reference Relief Request submittal HNP-08-045 Section 6.0). To supplement the UT, areas of limitation were fully scanned using eddy current testing (ET), which is effective in detecting surface breaking flaws. This combination of UT and ET further validates that the proposed alternative provides an acceptable level of quality and safety, since these completed examinations would have detected any existing patterns of degradation.

lc Wave Modality/ Insonification Information follows in Enclosure ("70' Longitudinal Angles Wave Dual Scan").

I d Cross Sectional Coverage Plots to Information follows in Enclosure.

describe the ASME Code coverage le Results of the Examination No indications detected.

Indications / No Indications

__________________________________________________ I Page 1 of 10 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-018 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 3a It is unclear from the licensee's (Reference Relief Request submittal.HNP-08-045 submittal why inlet nozzle welds Section 8.1). During the first interval, these RVNOZCI N 05SE and RVNOZBI-examinations were performed by a different vendor N-03SE were not included in the using different equipment, resulting in different previous 10 year ISI request for coverage limitations. In addition, the second relief. Please submit information interval UT Examinations were performed with explaining why these welds were not examination personnel and examination procedures included previously, qualified to ASME Code, Appendix VIII, as administered by the EPRI Performance Demonstration Initiative (PDI).

3b Please provide more detailed Information follows in Enclosure.

information on the ultrasonic testing (UT) inspections performed (i.e.,

probe type, incident angle, geometrical interference, scanned coverage, etc).

3c Please explain how the "Combined An averaging method is used.

UT [Ultrasonic] Coverage Total Percentage" in Sections 6.1, 6.2, and 6.3 of 2R1 -018 is obtained.

3d Please provide information regarding (Reference Relief Request submittal HNP-08-045 when the ultrasonic testing inspection Sections 6.1, 6.2 and 6.3). UT examinations were for each weld was performed (e.g.,

performed with examination personnel and what ASME Code criteria were examination procedures qualified to ASME Code, required - Appendix VIII or Section Appendix VIII, as administered by the EPRI V)?

Performance Demonstration Initiative (PDI).

3e Please provide more detailed Eddy Current procedure provided separately:

information on the eddy current WDI-STD-146 inspection methods performed, the inner diameter surface conditions of the affected welds, and an assessment of the ability to perform the eddy current testing exam effectively on these types of surface conditions.

Page 2 of 10 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-018 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

RVNOZCI-N-05SE IWB-2500-8 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

MATERIAL B-F B5.130 84.58 %

SS/CS ELBOW TO REACTOR VESSEL NOZZLE PDI-ISI-254-SE WDI-STD-146 WDI-STD-088 PDI TECHNIQUE USED:

YES 700 LONGITUDINAL WAVE DUAL SCAN SCAN

% VOLUME LIMITATION ACHIEVED CCW 69.15%

ELBOW TO NOZZLE WELD ID COUNTER-BORE AND ROOT CONFIGURATION CW 69.15%

ELBOW TO NOZZLE WELD ID COUNTER-BORE AND ROOT CONFIGURATION UP 100%

DOWN 100%

EDDY CURRENT SCAN SCAN

% VOLUME LIMITATION ACHIEVED CCW 100%

CW 100%

The coverage achieved was the maximum extent practical with the elbow to nozzle weld ID counter-bore and root configuration obstructions in place and the results are representative of the entire weld.

UT COMBINED COVERAGE = 84.58 %

EXAMINATION RESULTS: NO INDICATIONS Page 3 of 10 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63

-INSERVICE INSPECTION RELIEF REQUEST 2R1-018 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

RVNOZBI-N-03SE IWB-2500-8 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

MATERIAL B-F B5.130 88.34 %

SS/CS ELBOW TO REACTOR VESSEL NOZZLE PDI-ISI-254-SE WDI-STD-146 WDI-STD-088 PDI TECHNIQUE USED:

YES 700 LONGITUDINAL WAVE DUAL SCAN SCAN

% VOLUME LIMITATION ACHIEVED CCW 76.67%

ELBOW TO NOZZLE WELD ID COUNTER-BORE AND ROOT CONFIGURATION CW 76.67%

ELBOW TO NOZZLE WELD ID COUNTER-BORE AND ROOT CONFIGURATION UP 100%

DOWN 100%

EDDY CURRENT SCAN SCAN

% VOLUME LIMITATION ACHIEVED CCW 100%

CW 100%

The coverage achieved was the maximum extent practical with the elbow to nozzle weld ID counter-bore and root configuration obstructions in place and the results are representative of the entire weld.

UT COMBINED COVERAGE = 88.34 %

EXAMINATION RESULTS: NO INDICATIONS Page 4 of 10 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-018 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

RVNOZAI-N-O0SE IWB-2500-8 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

MATERIAL B-F B5.130 85.15 %

SS/CS ELBOW TO REACTOR VESSEL NOZZLE PDI-ISI-254-SE WDI-STD-146 WDI-STD-088 PDI TECHNIQUE USED:

YES 700 LONGITUDINAL WAVE DUAL SCAN SCAN

% VOLUME LIMITATION ACHIEVED CCW 70.29%

ELBOW TO NOZZLE WELD ID COUNTER-BORE AND ROOT CONFIGURATION CW 70.29%

ELBOW TO NOZZLE WELD ID COUNTER-BORE AND ROOT CONFIGURATION UP 100%

DOWN 100%

EDDY CURRENT SCAN SCAN

% VOLUME LIMITATION ACHIEVED CCW 100%

CW 100%

The coverage achieved was the maximum extent practical with the elbow to nozzle weld ID counter-bore and root configuration obstructions in place and the results are representative of the entire weld.

UT COMBINED COVERAGE = 85.15 %

EXAMINATION RESULTS: NO INDICATIONS Page 5 of 10 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-018 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION WELD CONFIGURATION IDENTIFICATION SHEET WELD DOWN SCAN DIRECTION ELBOW SIDE NOZZLE FLOW TO VESSEL Page 6 of 10

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A)

Reactor Vessel Weld Results Summary RVNOZCI-N-05SE, including:

Analysis Log # SE-95-1 ET Analysis Log # SE-95-1 Data Acquisition Log # SE-95-1 RPV Coverage Estimate Breakdown NOZ @ 950 B)

Reactor Vessel Weld Results Summary RVNOZCI-N-03SE, including:

Analysis Log # SE-215-1 ET Analysis Log # SE-215-1 Data Acquisition Log # SE-215-1 RPV Coverage Estimate Breakdown NOZ @ 2150 C)

Reactor Vessel Weld Results Summary RVNOZCI-N-01SE, including:

Analysis Log # SE-335-1 ET Analysis Log # SE-335-1 Data Acquisition Log # SE-335-1 RPV Coverage Estimate Breakdown NOZ @ 3350 Page 10 of 10 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-018 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ATTACHMENT A WesDyne International Reactor Vessel Weld Results Summary RVNOZC1-N-05SE (5 Pages)

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(,mddyy)

WN95SEPARDETIN N-05SEý 25.51's 00 4'

18 0

ESO 418/08 1

CHANNEL-1 WN95SEPARDETIN N-O5SE 125;51' 5

171 0

ESO 418/06 1746 CHANNEL 2 WN85SEPRPDETIN N-O5SEw 0

114-74!

347 14 0

ESO.

4/18/06 184Z CHANNEL,1 WN95SEPRPDEMIN

."N'0SE 0$

114.74.

.34 7 12!

0

16 4/18106 1842 CHANNEL.2 Form 12A4 IPDI-SI-254-SE, Rem 2

SHEARON HARRtIS #1

'DI RECTION / ORIENTATION kPV COVERAGE ESTIMATE IBREAKDOWNS PARALLEL SCANS PERP.-SCANS IN/ OUT ITEMIAREA INLET NOZZLEDM WELD' 956 WEELDNO.

-RVNOZCI-'N-SE-.

Exa mihation Probes BEAM W70 Dual

ET DiRECTiON r:__...._

Examiotni Vokmb Ex~mna Itn Swf~ce WELD LVOLUME WEL VOLUME WELD VOLUME cw

.15 100 cw::

cw 69J15 loG-up 100 o

DOWN 100 UT Combined Coverage = 84.58%*

UT:& ET ComblnediCoverage 1,00%.

Ciro Scsns limited as per pm~csdure.POOS due to ID Couoe-o~ an o!c iUrain

,ET used' u

to psurp6emnt-Ls~m, fr uIl ov~erage.

ANALYSTYS to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-018 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ATTACHMENT B WesDyne International Reactor Vessel Weld Results Summary RVNOZB1-N-03SE (5 Pages)

WesDyne International Reactor Vessel Weld Results. Summary SHEARON HARRIS UNIT 11 WELDL NO.

RVNOZBI-N-3SE DESCRTION INLET NOZZLE, DM WELD LIMI'TATIONS

NO

,.. I.

'YE'SWF--

Coverage = 88.34%

Weld Configur-ation RESU1TS IRf1 NO. OF INDICATIONS 0 STATUS N/A EXAi DOCUMENTATION INDICATION DOCUMENTATION IANALYSIS LOG

[]ACQUISITIO-N LOG:

[]SCAN PRINTOUT D ASSSES NT SHEET

]PA.RAGON HARD COPY L]OTHER (Specify) 7] -COVERAGE BREAKDOWN ccc~4~

WESDYNE ANALYST

lESDyvnE

Page,

, of ANALYSISLOG #

SEI-21i54 utility: [Progress Energy iPiant:

TShearon I arra Procedure No:

PD-ISI-254-SE Unit:

I

'Outage:

RFO-13 Procedure Rev.

Ir4TLET-DM Exam. Surface:

I D Weld No: [RVNOZBI-N-03SE tWe1dType:~ I A*Aplicable Sensitivity Calibration Data Sheet No:

SE-01,^.

4cqui,,3ition Log No: I SE215-1 j PARAGON Anal. Reease:1 6A~6 UT. Examiner Signaturfe:

Dte:

4-1S Data File Name, UT BoaWAngle I N1Ill

~

RI, Examiner ID 1 Date Channel Beam Direction R

Comm.. t. L t"

Resolution :/Com m-ents I Lim itations*

.WN215-SE-PFA-DET-IN 1I 70(

CCW X

"SW 4*18/06 WN21 5-SE-PAR-DET-IN 2

70'1 /W XCSW 4118?06

'WN2,I5-SE-PRP-DET-1N I

70 IN CSW 4118106 WN215-SE-PRP-DET-IN.

2 70'/ OUT X

CSW 4118/06 Ff-r!-n 12~ 5D M81-264-SE, Revý 2

mwasco ETAnalySiS 1Lg: SE 215-1 Proc No.WDIST 4$...

Pe 4RevO.

No.:% ".

"i,ýity Call islton Log Nc ýSE2,11-1

" A p p i c a b i~e :s o n i i 6t raJ a tio n D a tg S h e e t 'N o : E T -11.

= A r q lb t o g N o E

5 -

ET am Si r

L Ill..

Date: 4-19-6 "

-Data ET

'ET Probe Scan

NI RI RI:

Examiner ID 1 Data File Name Probe Dirction Resoltlon 1Comments I LImItations

No.

,WN216S.ERT EIRM NX CSW 14-19,40 WN2 S;PARDEIN 2CIRC X

CSW 14-119-06 WN2 SSEPRPDETIN, T

AXIAL X

CSW 4-19-00

'WN2I6SEPRPEN...

2:

AXIAL

.CSWI 4-49-00 form, 12.-5

lMJWE6DYPEi

'Page 1 -of I

DATA ACQUISITION LOG #

SEM2I51 Utliy '..rgress;ýEnergy.

-at*,Shearoq'.

Harr!;

t.Unit,: 1,.pOutage :,e.N.

Proced 6m M : ý: PFDWI4S-25" Ei

.r

.Rev...

2 Applicable SensitivcCalibraon DataSheet No:

-Ol ----

_UTExam_

itiatui_

_1 11, Date:

4-1,806

.ati File Name

'e N6.

index Scan Total #

"AVto Gain

.Date Time Comments StLart

'Start o

inl Ai Sweqpsý. Amplitude k

fmidy)

W21:5SE-.PARDETiN 8NO3SE 125251" 0"

,5 8

0.

S 4-18-06 22 CHANNEL I W

.215-SE-.ARDIETN N-03SEt 125.51j 0

-54' 9

0 OS 4,-1,6`

22:28 CHANNEL 2.:

DN2iN:EPRP i

,N.,0'SE' 0

1

.411.74" 034 515 " 4-18-06 23:21 CHANNýEL1 WN25I1SE;7RP.DEI' N-.3SEC

'0

1i.74*

346

.1",1 0

S 4-1

28-06,

2,21 CHANNEL 2,

,--P D, E T

-I-N:

§ E,

~~~

~

L..

Form 124. PDiI-SIR-25SE,.Rev. 2

SHEARON HARRIS #1 DIRECTION / ORIENTATION RPV; COVERGE ESTIMATEl *BREAKDOWN0,S PARALLEL SCANS PERP,RSCANS

,CCW/Cw

.IN 1/OUT ITE=M, A ARE A INLET NOZZLE, DM-WELD.02150 WELDiNO.

RVNOZB IN-O3SE.

Examination Probes BEAM 700 Dual

=ET D I

_.RECTIO N

ExaftiwminIovom

ýEimin-atlan s~tfac9l :WELD VOLUME WELD VOLUME

-WELD VOLUME

'ccw h610

,c~w

!*76.67 100

'UP 100-DOWN 100 UT Combined Coverage 88.34%

UT & ET Combined Coverage, i=00 Circ,Scans limited as'per procedure'.PDQS due to I D Counter-borezand Rbot configuration.

ET used. to: supplemernt exam for fufl coverage,.

ANALYST_____________

to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-018 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ATTACHMENT C WesDyne International Reactor Vessel Weld Results Summary RVNOZA1-N-01SE (5 Pages)

WesDyne Intemrational ReactorVessel Weld Results Summary SHEARON HARRI$UNEIT WELD NO.

RVNOOZAI-N-iSE INLET NOZZLE DMWLD

-R35 LIMITATIONS

NG YES~J

'Coveralge = 854i 59/o Weld Configuration I SUILTS NO. OFVINDICATiONS r0 STATUS' N/A 8Ek..M..DQCUMENTATION ANALYSIS LOGI wACQUiSITION LOG ZAS SESSMEi-NT SHEET ZPARAGON HAiRD COPY-Z OTER ('specify)

[~]

COVERAE BEKDýOWN WESDYNE-ANALYST

Y~DyflE Page I, of

-4 ANALYSIS LOG4# :SE-33541 Uti'ty:,

P:ro9ress Energy 'Plat:

Shea-onI rris Unit:

I

. Outage:" RF 3

ProcedureNo; N

PDI-iSI-254SE

ýProcedure RevZNo.:

2 Wetd No: I RVNQZA-N-OsE:

WeldType:

INLET-DM Exam. Surface; IDi Applicable Sensitifity Calibration Data hetNO:Acquiton LogNo:

S.-335A1 PARAGON Anal R

6 UT Examiner Signature:

__Level:

Ill Date:. 4-I81.06 Data FieName "

UT "Beam'Anglel Ni H

Ri' RI ExaminerIDl Date

...channel BeamDireton Resolution I Comment. I Limitations.

No,.

O..Q,=.,CW~CC~aj WN3354SE-PAR-DEiTiN

1.

70' COW X :.SAS 18!06 WN335-SE-PAR-DET-IN 2:

1 CW x

SAS 4118106 WN*335SEpPRP0DET-iN

....... 10I IN WOW

.AS 4118/06 WN335-SE-PRP-IDET-I' 2

.709 1 OUT XSA4/86

.t.

Form 12.5 POI-IS1-254JSEf Rev. 2'

-WwEDynlii

.ET.Anal sfs log:.Sg335-1 oUtiit:i Progress Erergy Nant: Slic-iron liarris u nit: I, Cute clkis

_9 1: -

ý.

Prmo~dtireNwo, WDI-STD-146 Proc~.dJw. Rev. No.: 61 Weld No.: RVNOZAl44.-OiSl Weld Tj*O6:,J NLETDM'WELD AT 336*

Appllcable SonsItlvity Ca~lfbratfn Data Sheet Vo: ET-1 Acquisitlen Log. N w: SE33$4l aT Wxminer Sfgnaturi.,

0 -~

fit.l blate: 44-186 Dataer E~wbecan I

RIRi xamlnerlWO/ate

Fi le Nasme Probe Dr'

~

nRslto Cmet i~ain No2~

-Coittntil~iitaioI WN335SEPAROETINA.

I cIRC X

s i.ýo WN336SEPAROETINA 2

CIRC X

CW 1 4-18j-06 W?433$SEPRPDETIN.

1AiWAL X

GSW /4-18-06 WN3,358EPRPOETIN:

Z:AXIAL kX iiw: I 4A-18

,Eortni' 12-5

RWR PyIna, pa, 96, I

of I

DATA ACQUISITION LOG #

SE336-,

Utility:

ProgressHEnergy nPlant hearon Harrs Uni I

Outage:

RFO-13 Procedure No. : PDl-8l-i254-sE.

Procedure Rev. No.

2.

.Applicabl6eS.

S iIvity Cal i.rao.S Data. Sheet, N.:....

UT Eamier igntur:

____________Levjel:

HI Date:

4-80 DatalFlieName Weld No.

I"I(ex SCan

'Total #

AVE' "Gain Date Time Comments Start Start-of.

Signal

'Adj..

Sweepsn:. AmplitudeO dB

}

(mm-d

~

~

d )

c

)dd!*

,/y 0.

WN335SEPARDEiNA.

N-ISE 122.49' 0

52 17 0

CSW.418-06.

0600.CHANNELI-WN336SEPARDEINA N -18*

122,491-06 5-,62 i4 b0.

0'SW 4.-IS-O6,S 0800,CHANNELI2 WN335SEPRPDEIN N-OISE I0 I+

14774*

.48 7

0 DS 4-18-0 0730 ;CHANNEL 1.

WN335SEPRPDEIN

. N-OISE

0.

114.74" 348 12 0

DS

-44M806 0730,CHANNEL2 JJ]JJ*

,sJ*J*

Form 12.4. PDI-iSI,-24+SE Rev.- 2

SHEARON HARRIS #1 DIRECTION-fORIENTATION RPV COVERAGEtEsTI MAVT E BREKDOWNS PAPALLEL,SCANS PERP,*. SCANS IN.!OUT ITEM/ AREA INLETVNOZZLE DM WELD @ 3350 WELD NO, RVNOZAI.N-O1 SE:

ExaminatiOn Probes BEAM 70"' Dual

'ET D I R E C T I O N Exm~tin okmeExrnnaIa Sfa&WELD VOLUME:

WEfLD

VOLUME, WELD VOLUME ccw J029 00 cw 70.29 100 u-ico:

DOWN UT Combined Coverage = 85 5%

UT & ETCombined iCooverage = 100%

CircScans limited as per procedurePDQS due t ID-D Couiter-bore and.Ro'ot-"config~umtion; ET. used to su6IemeIntexam rfor fulroverage,,

ANALYSJ T to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-019 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Examination Category B-A, Item BI.ll and B1.21, Circumferential Shell/Head Welds RAI REQUEST

RESPONSE

1 a Description (Reference Relief Request submittal HNP-08-045 Section 1.0). Welds are Lower shell to lower circumferential shell weld and lower head circumferential weld.

l a Sketch Information follows in Enclosure.

la Interference/Obstruction (Reference Relief Request submittal 1HNP-08-045 Section 5.0). The limitation for Reactor Vessel Lower Head to Lower Shell Circumferential Weld STHW-RV-04 was due to the four core support lugs integrally attached to the reactor vessel. The limitation for Reactor Vessel Lower Head Circumferential Weld CHW-RV-17 was due to peripherally located Bottom Mounted Instrumentation (BMI) tubes integrally attached to the reactor vessel.

lb NDE Equipment The following procedure is provided separately:

PDI-ISI-254 l b Alternative Methods (Reference Relief Request submittal HNP-08-045 Section 6.0). HNP is proposing to volumetrically UT examine the RPV pressure retaining welds STHW-RV-04 and CHW-RV-17 to the maximum extent possible in accordance with the Inservice Inspection Program schedule. A significant portion of the subject welds have been examined, obtaining 83.9% for weld STHW-RV-04 and 81.77% for weld CHW-RV-17. In addition, the subject welds are subject to visual (VT-2) system Leakage test during each refueling outage.

lc Wave Modality/ Insonification Information follows in Enclosure ("45' Angles Longitudinal Wave Dual Scan", "45' Longitudinal Wave Single Element Scan", "45' Shear Wave Scan").

ld Cross Sectional Coverage Plots to Information follows in Enclosure.

describe the ASME Code coverage Page 1 of 13 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-019 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION le Results of the Examination Information follows in Enclosure.

SIndications / No Indications Page 2 of 13 to SERIAL: 1HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-019 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

STHW-RV-04 IWB-2500-8 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

B-A Bl.1l 83.90 %

CS/CS CIRCUMFERENTIAL SHELL WELD PDI-ISI-254 MATERIAL YES 450 LONGITUDINAL WAVE DUAL SCAN SCAN

% WELD

% VOLUME LIMITATION VOLUME ACHIEVED ACHIEVED CCW 75.56%

84.41%

FOUR CORE SUPPORT LUGS INTEGRALLY ATTACHED TO THE REACTOR VESSEL CW 75.56%

84.41%

FOUR CORE SUPPORT LUGS INTEGRALLY ATTACHED TO THE REACTOR VESSEL UP 79.11%

79.11%

FOUR CORE SUPPORT LUGS INTEGRALLY ATTACHED TO THE REACTOR VESSEL DOWN 79.11%

79.11%

FOUR CORE SUPPORT LUGS INTEGRALLY ATTACHED TO THE REACTOR VESSEL Page 3 of 13

'Enclosure 3 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-019 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 450 LONGITUDINAL WAVE SINGLE ELEMENT SCAN SCAN

% WELD

% VOLUME LIMITATION VOLUME ACHIEVED ACHIEVED CCW 82.04%

84.41%

FOUR CORE SUPPORT LUGS INTEGRALLY ATTACHED TO THE REACTOR VESSEL CW 82.04%

84.41%

FOUR CORE SUPPORT LUGS INTEGRALLY ATTACHED TO THE REACTOR VESSEL UP 79.11%

79.11%

FOUR CORE SUPPORT LUGS INTEGRALLY ATTACHED TO THE REACTOR VESSEL DOWN 79.11%

79.11%

FOUR CORE SUPPORT LUGS INTEGRALLY ATTACHED TO THE REACTOR VESSEL 450 SHEAR WAVE SCAN SCAN

% WELD

%VOLUME LIMITATION VOLUME ACHIEVED ACHIEVED CCW 82.04%

84.41%

FOUR CORE SUPPORT LUGS INTEGRALLY ATTACHED TO THE REACTOR VESSEL CW 82.04%

84.41%

FOUR CORE SUPPORT LUGS INTEGRALLY ATTACHED TO THE REACTOR VESSEL UP 100%

97.46%

FOUR CORE SUPPORT LUGS INTEGRALLY ATTACHED TO THE REACTOR VESSEL DOWN 100%

97.46%

FOUR CORE SUPPORT LUGS INTEGRALLY ATTACHED TO THE REACTOR VESSEL The coverage achieved was the maximum extent practical with the four core support lug obstructions in place and the results are representative of the entire weld.

UT COMBINED COVERAGE = 83.90 %

EXAMINATION RESULTS: ONE RECORDABLE INDICATION ALLOWABLE PER ASME SECTION XI 1989, IWB-3510-1 Page 4 of 13

C" EQUIPMENr TAG IRC-EO9I TL ~.

-Fi OF 71~-

~~

PIPE~

-N WELD 4

A V cj ~ H~

~v Akr.:R z

da-M I]IE MM EL Hz L P4 WP-W-U Z

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U I,0-0 0,0 re 0

P.,_

c-d OUNDEON n E n e rgy F.U-i TUR I

OMrogreM)

5 REACIOR VESSEL WY 1-ISI-RV-1 m

OULE L

p I

NLET Lop 3 OTLET'Loop -3 INLET:Loop:2 OUTLET Loo 2 INLET Loop 1:

25-9 4

1 6

335, CO I~ r 6

0 60 2

0 V-O~

121C6, C-4 u~

Z

(:)

33.19

~Q 0RV-07

RY708,

-7 65 0

S 1150' IELD W)

MV-04 MOMNM 10 RV I

)RV 16 1VS

~

4 R3 RV -2 ILl RV-7 105*

165*

225 25.

(:: W oo SHE-ARON HARRIS CQL.

WesDlyne, 1nte~r.nationial.

TfW V ess et RottbUt EXAM!PROGR'Am"PLAN 1m AMMS HEE~T 1 OF 2

N ON ON cj~

C

~1.)

0 0

"SCANS IB ETV/EEN: LUGS-:

33T3O19 TO. TOP:

78:5 R:

SUPREEN ANGULAR SCANNING DOUNDARIES AREA BETWEEN PERP SCANS PARALLEL SCANS 0'

90 9.4' - 80V

-i":'79,0?

0*

9%4BO

- 170.6-1010" -169.0'-

.180'

- 270': 1894'. - 260,6 191,0 **

25o9.0 270

- 30'

'27,94- - 350.6 2SL0 7:349,0' z

z 0Y ZQ OF Noteý Performi scons between si.por fu~ ' fir Expand the lbelqw' scans, If necess dry,. to 324,0 TOP.:PERP cove.1ge.

326o0, TOP PAR LLEL

ýNOMINAL.

POSITI.ON OF,SUPPOR.T LUGS,-

C' 0.180ý,27.0-80.9W 7...8 9ý ýBOTTOiM PARALLEL

'78,0V BOTTOM PERP 0

323i5O

.vESSEL W'ýELD-Cb AV-1

-SHEARFON HARRIS' -

CQL

,caiw~i &AI4 ribOTOIPO[W W esDyne Internationa.(

INE IX SIZEt PARALLEL SCANS 015i PERP SCANS = 8,365-7LIOWER SHELL 7T LOWER: HEAD'. CIRC EXAM PRBGRAM PLAN AUD110OWN INI[SHEET 19. OF 2 3 UNUES OMWU NOM I

ON ON 0

-:2 C

0 U

SCANS BE-LV '~LUGS&

zo oDz 0

0J H

0 HO

SUPREEM ANCGULAR<,

SCANNINGý Bý)UNUARIES LUG EPSAS PRLE SCANS

0.

350' IV`

348!

12' 90..

8

-w

41001,

'78*

C 18V 170-2 18 192ý18 2701 2W_

28'2 z

33O~95 r

00 VE~

32.150

~SSEL I-SrHW-Rv-04.

WELD SHEAPtIN HARRIS CQL WesDyne 'ThternotionoA CALMLATIIIN OFl EICTT13:POSITION, ME-lD S IZE PoRALLEL & RERP,SCANS -- 036.

I TM.LOWER SHELL TO LOWER'HEAD.CIR'C EXA0M PROGRýAMPLAN ALL DUM~2SIONS IN INCMISSHEET 20-OF 23 I

to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-019 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

CHW-RV-17 IWB-2500-8 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

B-A B1.21 81.77 %

CS/CS CIRCUMFERENTIAL HEAD WELDS PDI-ISI-254 MATERIAL YES 450 LONGITUDINAL WAVE DUAL SCAN SCAN

% WELD

% VOLUME LIMITATION VOLUME ACHIEVED ACHIEVED CCW 88.15%

88.15%

PERIPHERALLY LOCATED BOTTOM MOUNTED INSTRUMENTATION (BMI) TUBES INTEGRALLY ATTACHED TO THE REACTOR VESSEL CW 88.15%

88.15%

PERIPHERALLY LOCATED BOTTOM MOUNTED INSTRUMENTATION (BMI) TUBES INTEGRALLY ATTACHED TO THE REACTOR VESSEL UP 75.38%

75.38%

PERIPHERALLY LOCATED BOTTOM MOUNTED INSTRUMENTATION (BMI) TUBES INTEGRALLY ATTACHED TO THE REACTOR VESSEL DOWN 75.38%

75.38%

PERIPHERALLY LOCATED BOTTOM MOUNTED INSTRUMENTATION (BMI) TUBES INTEGRALLY ATTACHED TO THE REACTOR VESSEL Page 9 of 13 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-019 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 450 LONGITUDINAL WAVE SINGLE ELEMENT SCAN SCAN

% WELD

% VOLUME LIMITATION VOLUME ACHIEVED ACHIEVED CCW 88.15%

88.15%

PERIPHERALLY LOCATED BOTTOM MOUNTED INSTRUMENTATION (BMI) TUBES INTEGRALLY ATTACHED TO THE REACTOR VESSEL CW 88.15%

88.15%

PERIPHERALLY LOCATED BOTTOM MOUNTED INSTRUMENTATION (BMI) TUBES INTEGRALLY ATTACHED TO THE REACTOR VESSEL UP 75.38%

75.38%

PERIPHERALLY LOCATED BOTTOM MOUNTED INSTRUMENTATION (BMI) TUBES INTEGRALLY ATTACHED TO THE REACTOR VESSEL DOWN 75.38%

75.38%

PERIPHERALLY LOCATED BOTTOM MOUNTED INSTRUMENTATION (BMI) TUBES INTEGRALLY ATTACHED TO THE REACTOR VESSEL Page 10 of 13 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-019 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 450 SHEAR WAVE SCAN SCAN

% WELD

% VOLUME LIMITATION VOLUME ACHIEVED ACHIEVED CCW 88.15%

88.15%

PERIPHERALLY LOCATED BOTTOM MOUNTED INSTRUMENTATION (BMI) TUBES INTEGRALLY ATTACHED TO THE REACTOR VESSEL CW 88.15%

88.15%

PERIPHERALLY LOCATED BOTTOM MOUNTED INSTRUMENTATION (BMI) TUBES INTEGRALLY ATTACHED TO THE REACTOR VESSEL UP 75.38%

75.38%

PERIPHERALLY LOCATED BOTTOM MOUNTED INSTRUMENTATION (BMI) TUBES INTEGRALLY ATTACHED TO THE REACTOR VESSEL DOWN 75.38%

75.38%

PERIPHERALLY LOCATED BOTTOM MOUNTED INSTRUMENTATION (BMI) TUBES INTEGRALLY ATTACHED TO THE REACTOR VESSEL The coverage achieved was the maximum extent practical with the bottom mounted instrumentation tube obstructions in place and the results are representative of the entire weld.

UT COMBINED COVERAGE = 81.77 %

EXAMINATION RESULTS: ONE RECORDABLE INDICATION ALLOWABLE PER ASME SECTION XI 1989, IWB-3512-1 Page 11 of 13

0 z

0 z0 P-q 0

cj*

z TO. CLAD C

IDEAL SCAN. BOUNDARIES ADJUST PER ýBMifPENETRATION JINTERFERENCE;

[SHEARON HARRIS CQL IV!e.sDyrneý !;h~-. er~ndtion'dt 0

Pci INOEX SIZE:

PARALLEL & PERP-SCANS, =ý P036' 7ic.lvoues'n of perp~an4.PmrateI Positions

.L0WER HEAD CIR*'"

EXAKM PROGRAM PLAN AUl. OMESN IN INCE K-ir

. ET2a F 3

tr~

aN ON 0

cj~

0 0

gEOULIPMEBqT TAG jjýC===

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C:

W P K 2713 -------

=Pit

ýýP, C NU-N!,

RMOM-N-03 wz-ta NOZ44 0

DProgress Energy pwur SHAO RS - U I NUL REACTOR VESSEL to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1 -020 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Examination Category B-A, Item B1.30, Shell to Flange Weld, and Item B 1.40, Head to Flange Weld RAI REQUEST

RESPONSE

l a Description (Reference Relief Request submittal HNP-08-045 Section 1.0). Welds are Vessel Flange to Upper shell weld and Vessel Flange to Head weld.

la Sketch Information follows in Enclosure.

Ia Interference/Obstruction (Reference Relief Request submittal HNP-08-045 Section 5.0). The limitation that reduces the amount of UT examination coverage for Vessel Flange to Upper Shell Weld FTSW-RV-01 is the vessel configuration at the flange. The limitations for the Vessel Flange to Head Weld FTHW-RV-18 is due to the component configuration (flange directly adjacent to the weld) and the vessel head lifting lugs.

lb NDE Equipment The following procedures are provided separately:

PDI-ISI-254 (FTSW-RV-01)

WDI-STD-146, WDI-STD-088 (FTHW-RV-18) lb Alternative Methods (Reference Relief Request submittal 14NP-08-045 Section 6.0). HNP is proposing to volumetrically UT examine the RPV pressure retaining welds FTSW-RV-0 1 and FTHW-RV-18 to the maximum extent possible in accordance with the Inservice Inspection Program schedule. In addition, the subject welds are subject to visual (VT-2) system Leakage test during each refueling outage. For FTHW-RV-18 Vessel Flange to Head Weld, the Code required MT Examination was also performed in accordance with the ASME Code Section XI.

1 c Wave Modality/ Insonification Information follows in Enclosure ("45' Longitudinal Angles Wave Dual Scan", 45' Longitudinal Wave Single Element Scan", "45' Shear Wave Scan",

"Longitudinal Wave Manual Scans from Flange Face", 0' Longitudinal Wave Scan", 450 and 600 Shear Wave 1/2 Vee Scan").

Id Cross Sectional Coverage Plots to Information follows in Enclosure.

describe the ASME Code coverage

_ I

_ ~I _

,Page 1 of 16 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 1NSERVICE INSPECTION RELIEF REQUEST 2R1-020 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION I e Results of the Examination No indications detected.

Indications / No Indications Page 2 of 16 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-020 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

FTSW-RV-01 IWB-2500-4 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

MATERIAL B-A B 1.30 87.5 %

CS/CS VESSEL FLANGE TO UPPER SHELL WELD PDI-ISI-254 WDI-SSP-1063 YES 450 LONGITUDINAL WAVE DUAL SCAN SCAN

% WELD

% VOLUME LIMITATION VOLUME ACHIEVED ACHIEVED CCW 100%

50%

VESSEL CONFIGURATION AT THE FLANGE CW 100%

50%

VESSEL CONFIGURATION AT THE FLANGE UP 100%

100%

DOWN 100%

100%

450 LONGITUDINAL WAVE SINGLE ELEMENT SCAN SCAN

% WELD

% VOLUME LIMITATION VOLUME ACHIEVED ACHIEVED CCW 100%

50%

VESSEL CONFIGURATION AT THE FLANGE CW 100%

50%

VESSEL CONFIGURATION AT THE FLANGE UP 100%

100%

DOWN 100%

100%

Page 3 of 16 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-020 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 450 SHEAR WAVE SCAN SCAN

% WELD

% VOLUME LIMITATION VOLUME ACHIEVED ACHIEVED CCW 100%

50%

VESSEL CONFIGURATION AT THE FLANGE CW 100%

50%

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00, 60 in, 60 out, 120 out and 160 out LONGITUDINAL WAVE MANUAL SCANS FROM FLANGE FACE SCAN

% WELD

% VOLUME LIMITATION VOLUME ACHIEVED ACHIEVED DOWN 100%

100%

The coverage achieved was the maximum extent practical due to the vessel configuration at the flange and the results are representative of the entire weld.

UT COMBINED COVERAGE = 87.5 %

EXAMINATION RESULTS: ONE RECORDABLE INDICATION ALLOWABLE PER ASME SECTION XI 1989, IWB-3510-1 Page 4 of 16

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SýHLET eSn &JF 23-to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-020 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

FTHW-RV-18 IWB-2500-5 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

MATERIAL B-A B1.40 71.7 %

CS/CS HEAD TO FLANGE WELD ISI-210-T WDI-STD-146 WDI-STD-088 PDI TECHNIQUE USED:

YES 450 and 600 SHEAR WAVE 11/2 VEE SCAN SCAN

% VOLUME LIMITATION ACHIEVED CIRCUMFERENTIAL 65%

VESSEL HEAD CONFIGURATION AT THE SCAN FLANGE AXIAL SCAN 85%

VESSEL HEAD CONFIGURATION AT THE FLANGE UT COMBINED COVERAGE = 71.7 %

EXAMINATION RESULTS: NO INDICATIONS Page 9 of 16 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-020 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REACTOR VESSEL TOP HEAD TO FLANGE WELD MATERIAL AND WELD IDENTIFICATION SHEET HEAD FLANGE FLANGE SA-508 CLASS 2a WELD HEAD SA-508 CLASS 2a Page 10 of 16 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-020 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FTHW-RV-18 SKETCH "A" S UpPLEIMEN7EAL U1LTRAS4ONIC.! SHIEET PACE 4jCEi~

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SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-020 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FTHW-RV-18 COVERAGE CALC.

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SUMMARY

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DA-Lt~qjkAfi Page 16 of 16 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-021 RESPONSE TO REQUEST FOR ADDITIONAL.INFORMATION Examination Category B-D, Item B3.110, Pressurizer Nozzle-to-Vessel Welds RAI REQUEST

RESPONSE

la Description (Reference Relief Request submittal HNP-08-045 Section 1.0). Welds are Pressurizer Nozzle to Head Welds.

Ia Sketch Information follows in Enclosure.

I a Interference/Obstruction (Reference Relief Request submittal HNP-08-045 Section 5.0). Nozzle to vessel welds are not conducive to two-sided volumetric examinations due to nozzle configurations.

lb NDE Equipment Information follows in Enclosure.

l b Alternative Methods (Reference Relief Request submittal HNP-08-045 Section 6.0). HNP is proposing to volumetrically UT examine the pressurizer nozzle welds NTHW-08/-09/-10/-i 1/-12/-13 to the maximum extent possible in accordance with the Inservice Inspection Program schedule. In addition, the welds are subject to visual (VT-2) tests during each refueling outage.

lc Wave Modality/ Insonification Information follows in Enclosure ("0' Longitudinal Angles Wave Scan", "45' and 600 Shear Wave 1/2 Vee Scan",).

I d Cross Sectional Coverage Plots to Information follows in Enclosure Attachments 1 describe the ASME Code coverage through 5.

le Results of the Examination No indications detected.

Indications / No Indications Page 1 of 14 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-021 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

NTHW-08 IWB-2500-8 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

B-D B3.110 66%

CS/CS PRESSURIZER NOZZLE-TO-VESSEL WELD ISI-210-T MATERIAL YES 450 and 600 SHEAR WAVE 1/2 VEE SCAN SCAN

% VOLUME LIMITATION ACHIEVED PARALLEL SCAN 79.6%

NOZZLE TO SHELL CONFIGURATION AND THE PRESSURIZER HEATER OBSTRUCTIONS AXIAL SCAN 38.7%

NOZZLE TO SHELL CONFIGURATION AND THE PRESSURIZER HEATER OBSTRUCTIONS The coverage achieved was the maximum extent practical with the nozzle to shell configuration and the pressurizer heater obstructions in place and the results are representative of the entire weld.

UT COMBINED COVERAGE = 66 %

EXAMINATION RESULTS: NO INDICATIONS NDE EQUIPMENT: STAVELEY, SONIC-136, WITH KBA 1.0", 2.25MHZ, LONGITUDINAL 00, KBA 0.5" x 1.0", 2.25MHZ, SHEAR 450 AND KBA 0.5" x 1.0",

2.25MHZ, SHEAR 600 Page 2 of 14 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1 -021 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PRESSURIZER SURGE NOZZLE TO HEAD WELD CONFIGURATION IDENTIFICATION SHEET PRESSURIZER SURGE PRESSURIZER HEAD NTHW-08 WELD Page 3 of 14 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-021 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

NTHW-09 IWB-2500-8 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

B-D B3.110 67.14 %

PRESSURIZER NOZZLE-TO-VESSEL WELD ISI-210-T MATERIAL CS/CS YES 00 LONGITUDINAL WAVE SCAN SCAN

% VOLUME LIMITATION ACHIEVED 66.31%

NOZZLE TO SHELL CONFIGURATION 450 SHEAR WAVE 1/2 VEE SCAN SCAN

% VOLUME LIMITATION ACHIEVED 67.85%

NOZZLE TO SHELL CONFIGURATION 600 SHEAR WAVE 'A VEE SCAN SCAN

% VOLUME LIMITATION ACHIEVED 67.26%

NOZZLE TO SHELL CONFIGURATION The coverage achieved was the maximum extent practical with the nozzle to shell configuration and the results are representative of the entire weld.

UT COMBINED COVERAGE = 67.14 %

EXAMINATION RESULTS: NO INDICATIONS NDE EQUIPMENT: STAVELEY, SONIC-136, WITH AEROTECH 1.0", 2.25MHZ, LONGITUDINAL 0°, KBA 0.5" x 1.0", 2.25MHZ, SHEAR 450 AND KBA 0.5" x 1.0",

2.25MHZ, SHEAR 600 Page 4 of 14 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-021 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PRESSURIZER NOZZLE TO HEAD WELDS CONFIGURATION IDENTIFICATION SHEET

'LE PRESSURIZER HEAD NTHW-09 WELD Page 5 of 14 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-021 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

NTHW-10 IWB-2500-8 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

B-D B3.110 67.14 %

PRESSURIZER NOZZLE-TO-VESSEL WELD ISI-210-T MATERIAL CS/CS YES 00 LONGITUDINAL WAVE SCAN SCAN

% VOLUME LIMITATION ACHIEVED 66.31%

NOZZLE TO SHELL CONFIGURATION 450 SHEAR WAVE 1/2 VEE SCAN SCAN

% VOLUME LIMITATION ACHIEVED 67.85%

NOZZLE TO SHELL CONFIGURATION 600 SHEAR WAVE 1/2 VEE SCAN SCAN

% VOLUME LIMITATION ACHIEVED 67.26%

NOZZLE TO SHELL CONFIGURATION The coverage achieved was the maximum extent practical with the nozzle to shell configuration and the results are representative of the entire weld.

UT COMBINED COVERAGE = 67.14 %

EXAMINATION RESULTS: NO INDICATIONS NDE EQUIPMENT: STAVELEY, SONIC-136, WITH AEROTECH 1.0", 2.25MHZ, LONGITUDINAL 00, KBA 0.5" x 1.0", 2.25MHZ, SHEAR 450 AND KBA 0.5" x 1.0",

2.25MHZ, SHEAR 600 Page 6 of 14 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1 -021 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PRESSURIZER NOZZLE TO HEAD WELDS CONFIGURATION IDENTIFICATION SHEET (TYPICAL)

PRESSURIZER HEAD NTHW-10 WELD Page 7 of 14 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-021 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

NTHW-11 IWB-2500-8 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

B-D B3.110 67.14%

CS/CS PRESSURIZER NOZZLE-TO-VESSEL WELD ISI-210-T MATERIAL YES 00 LONGITUDINAL WAVE SCAN SCAN

% VOLUME LIMITATION ACHIEVED 66.31%

NOZZLE TO SHELL CONFIGURATION 450 SHEAR WAVE 1/2 VEE SCAN SCAN

% VOLUME LIMITATION ACHIEVED 67.85%

NOZZLE TO SHELL CONFIGURATION 600 SHEAR WAVE 1/2 VEE SCAN SCAN

% VOLUME LIMITATION ACHIEVED 67.26%

NOZZLE TO SHELL CONFIGURATION The coverage achieved was the maximum extent practical with the nozzle to shell configuration and the results are representative of the entire weld.

UT COMBINED COVERAGE = 67.14 %

EXAMINATION RESULTS: NO INDICATIONS NDE EQUIPMENT: STAVELEY, SONIC-136, WITH AEROTECH 1.0", 2.25MHZ, LONGITUDINAL 00, KBA 0.5" x 1.0", 2.25MHZ, SHEAR 450 AND KBA 0.5" x 1.0",

2.25MHZ, SHEAR 600 Page 8 of 14 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R 1-021 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PRESSURIZER NOZZLE TO HEAD WELDS CONFIGURATION IDENTIFICATION SHEET (TYPICAL)

PRESSURIZER HEAD NTHW-1 1 WELD Page 9 of 14 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-021 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

NTHW-12 IWB-2500-8 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

B-D B3.110 67.14%

CS/CS PRESSURIZER NOZZLE-TO-VESSEL WELD ISI-210-T MATERIAL YES 00 LONGITUDINAL WAVE SCAN SCAN

% VOLUME LIMITATION ACHIEVED 66.31%

NOZZLE TO SHELL CONFIGURATION 450 SHEAR WAVE '1/2 VEE SCAN SCAN

% VOLUME LIMITATION ACHIEVED 67.85%

NOZZLE TO SHELL CONFIGURATION 600 SHEAR WAVE 1/2 VEE SCAN SCAN

% VOLUME LIMITATION SCAN_

ACHIEVED 67.26%

NOZZLE TO SHELL CONFIGURATION The coverage achieved was the maximum extent practical with the nozzle to shell configuration and the results are representative of the entire weld.

UT COMBINED COVERAGE = 67.14 %

EXAMINATION RESULTS: NO INDICATIONS NDE EQUIPMENT: STAVELEY, SONIC-136, WITH AEROTECH 1.0", 2.25MHZ, LONGITUDINAL 00, KBA 0.5" x 1.0", 2.25MHZ, SHEAR 450 AND KBA 0.5" x 1.0",

2.25MHZ, SHEAR 600 Page 10 of 14 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-021 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PRESSURIZER NOZZLE TO HEAD WELDS CONFIGURATION IDENTIFICATION SHEET (TYPICAL)

PRESSURIZER HEAD NTHW-12 WELD Page 11 of 14 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-021 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

NTHW-13 IWB-2500-8 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

B-D B3.110 67.14 %

CS/CS PRESSURIZER NOZZLE-TO-VESSEL WELD ISI-210-T MATERIAL YES 00 LONGITUDINAL WAVE SCAN SCAN

% VOLUME LIMITATION ACHIEVED 66.31%

NOZZLE TO SHELL CONFIGURATION 450 SHEAR WAVE A VEE SCAN SCAN

% VOLUME LIMITATION ACHIEVED 67.85%

NOZZLE TO SHELL CONFIGURATION 600 SHEAR WAVE 'A VEE SCAN SCAN

% VOLUME LIMITATION ACHIEVED 67.26%

NOZZLE TO SHELL CONFIGURATION The coverage achieved was the maximum extent practical with the nozzle to shell configuration and the results are representative of the entire weld.

UT COMBINED COVERAGE = 67.14 %

EXAMINATION RESULTS: NO INDICATIONS NDE EQUIPMENT: STAVELEY, SONIC-136, WITH AEROTECH 1.0", 2.25MHZ, LONGITUDINAL 00, KBA 0.5" x 1.0", 2.25MHZ, SHEAR 450 AND KBA 0.5" x 1.0",

2.25MHZ, SHEAR 600 Page 12 of 14 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-021 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PRESSURIZER NOZZLE TO HEAD WELDS CONFIGURATION IDENTIFICATION SHEET (TYPICAL)

PRESSURIZER HEAD NTHW-13 WELD Page 13 of 14 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-021 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ATTACHMENTS:

A.

Supplemental Ultrasonic Sheets NTHW-08 B.

Supplemental Ultrasonic Sheets NTHW-09 C.

Supplemental Ultrasonic Sheets NTHW-10 D.

Supplemental Ultrasonic Sheets NTHW-II E.

Supplemental Ultrasonic Sheets NTHW-12 F.

Supplemental Ultrasonic Sheets NTHW-13 Page 14 of 14 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR IOWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-021 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ATTACHMENT A Supplemental Ultrasonic Sheets NTHW-08 (4 Pages)

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I 1119A12 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-022 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Examination Category B-B, Item B2'.40, Tubesheet-to-Head Weld RAI REQUEST

RESPONSE

1 a Description (Reference Relief Request submittal HNP-08-045 Section 1.0). Welds is Tubesheet-to-Head Weld.

la Sketch Information follows in Enclosure.

I a Interference/Obstruction Information follows in Enclosure.

l b NDE Equipment Information follows in Enclosure.

l b Alternative Methods (Reference Relief Request submittal HNP-08-045 Section 6.0). HNP is proposing to volumetrically UT examine the steam generator Tubesheet-to-head weld, II-SG-00l SGA-TSTHW-06-1, to the maximum extent possible in accordance with the Inservice Inspection Program schedule. In addition, the subject weld will be subject to system pressure tests during each refueling outage.

ic Wave Modality/ Insonification Information follows in Enclosure (00 Longitudinal, Angles 45' Shear, 60' Shear).

I e Results of the Examination No indications detected.

Indications / No Indications 4a Please clarify whether all three All three of the steam generators have the same steam generator tubesheet-to-head configuration / limitation.

welds were examined. Because the Since B-B, B2.40 Note 1 only requires one per licensee was unable to meet the similar vessel, the examination was performed on one ASME Code-required inspection of the three steam generators.

volume on tubesheet-to-head weld (Note: These steam generators were new in 2001).

II-SG-001 SGA-TSTHW-06-1, if the other tubesheet-to-head welds were examined, please describe whether the same coverage area limitations apply to these similar welds on the remaining two steam generators.

Page 1 of 6 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-022 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

II-SG-001SGA-TSTHW-06-1 ASME CATEGORY:

B-B IWB.2500-6 ASME ITEM NUMBER:

% CRV ACHIEVED:

WELD BASE METAL TUBESHEET TO HEAD WELD B2.40 70.106%

74.20%

CS/CS NDEP-0450 MATERIAL NO BASE METAL AND WELD METAL VOLUME COVERAGE SCAN

% VOLUME

% WELD LIMITATION ACHIEVED VOLUME ACHIEVED 00 72.74%

76.6%

Lower lateral support pads 450 73.38%

68.852%

Lower lateral support pads 600 76.48%

64.867%

Lower lateral support pads TOTAL 74.2%

70.106%

Lower lateral support pads The coverage achieved was the maximum extent practical with the four lower lateral support pad obstructions in place and the results are representative of the entire weld.

UT COMBINED COVERAGE:

Total base metal volume coverage 74.20 %

Total weld volume coverage 70.11 %

EXAMINATION RESULTS: NO RECORDABLE INDICATIONS NDE EQUIPMENT: STAVELEY, SONIC-136, WITH KBA 1.0", 2.25MHZ, LONGITUDINAL 00, KBA 0.5" x 1.0", 2.25MHZ, SHEAR 450 AND KBA 0.5" x 1.0",

2.25MHZ, SHEAR 600 Page 2 of 6

ON ON cr~

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0 ITEM NO ESCRIPTION MTRIAL SPEC.

01 CHANtiEL EAD S NC~

02 TUBE PlATE PLATE.-5 CL. 3o OZ STUB BARREL,

-533 TPE-B CL. 2 LOWER SHELL BARREL SA-533 TYPE B C. 2 0S LOWER SHELt. ARREL 'T SA-533 TYPE 8 a., 2 05r MTAMMITON CONE SA-508 CL. 30, 67 UPPER SHELL B

'RRELI SA-533 TYPE B CL 2 Be UPPER SHELL BARREL V

5-533 TYPC B CL. 2 09 UPPE'R HEKR (WtT"4 INTI.PL NOZZLE) SA-505 CL. 30 in FEEOYAT ER INLET NOZZLE 16$ 0.0.

SA-53 CL3ý It AUXEL1ARY FEEOWATER NOZ2ZLE?ý O.X. SA-OU CL, 4.

12 SECONAIDY SNE WWAYS (2)

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SUMMARY

WELD MATERIAL Determination of Percent Coverage for UT Examinationsl

-Vessels.

Srte/.t "6fP I

I prooedure:

Noep-om5 Out age No,.:

tttPO.12:-

summar No:'

H-03M4 Prcur Re,:._

0 Ragot Ito.:

UT-04-1t23_

Workacopec, lim Work OdrN.,________

ae:4, "of:

B Scn 76.600

% L00X t0000 ON lmolegh10 76.m0

!%6toal Ordag Scan I 76.600

%,Length X MA0O0 % Volume oJeU)thiAQ10-76.4600 % total for Scan 1 S

2a.

2 76.00o Length X 5*.840

% volume of feth I 100,.0

ý=

f s4

5.

% total for Suan 2 Scan 3 76.600

% Le..th x 100.000 vol t%

total for Stan3 Scan 4 76.600

%Legqth X 100.000

% voWume Oa laengh 9100 29 70

% total for Scan 4 Add totals and diie by# scans =

58.02

%tn*bo ltior454 og bftl do Sor Scan I 76.00

%LbnglhX

'N00

%volUrreotlajngih I 00 76.(60 ltowalfor Soa I 70 76.0

%Lanth X 36.730

% Voltaottength10.0 29.667'

%t l61otrr ean 2

Scan 3 76.000

% LeVngth X

100.000

%vtueo length / 100v 700

% tota for-Sc-an 3

Sa4 76.800

%A ongthX

10 0,00

% votlumeof "nth j100=

M4.0

% total forScan 4 Ad.d touta anw divide liy, a.

a

64. 6

%total for

de.g Add totals lor eachý angle and scan required and fdivite by # ot angles to determi no; 70A106 */,Total for comjaleta examn Note.

&rVpptmentolt covearag pa uy be achweed by use ot ofter angles I

/ methods., When used, the coverage tot votrert not obta ired w

,th angls as noted above that be calaed and added to ttotat to provIde th percenltotal for thb ornpqla Site Foltd Suppervsor."Ot:

,/

at 7thu Dmierrot hsa OA Record Page 4 of 6 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R1-022 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION II-SG-001SGA-TSTHW-06-1 COVERAGE

SUMMARY

BASE MATERIAL Supplemental RepOrt

(~U E~Report No.:

UT04Y-023 pawe.5

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Limitation'Record

.SumrneryNo N.0384 Deecrpttor of birfftattorr:

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Page 6 of 6 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-009 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Examination Category C-A, Item C1.1O, Shell Circumferential Welds RAI REQUEST

RESPONSE

I a Description (Reference Relief Request submittal HNP-08-045 Section 1.0). Weld is Pressure Retaining Welds in Pressure Vessels.

la Sketch Information follows in Enclosure.

la Interference/Obstruction (Reference Relief Request submittal HNP-08-045 Section 5.0). Weld configuration (flange to shell) and obstructions (flange bolting) prevent 100 percent volumetric examination to be performed during inservice inspection activities.

lb NDE Equipment Information follows in Enclosure.

lb Alternative Methods (Reference Relief Request submittal HNP-08-045 Section 6.0). HNP is proposing to volumetrically UT examine the restricted areas of Weld RHRACSW-02 to the maximum extent possible in accordance with the Inservice Inspection Program schedule. In addition, this weld is subject to visual (VT-2) system leakage testing during each refueling period. To supplement the volumetric examination, a 70 degree 1/2/ vee shear wave UT examination was performed. A code compliant surface examination (PT) was also performed, although not required by code.

Ic Wave Modality/ Insonification Information follows in Enclosure ("45' Shear Wave Angles 3/4 Vee Scan").

Id Cross Sectional Coverage Plots to Information follows in Enclosure.

describe the ASME Code coverage le Results of the Examination Information follows in Enclosure.

Indications / No Indications Page 1 of 11 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-009 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

II-RHR-01RHRA-CSW-02 IWC-2500-1 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

C-A SHELL CIRCUMFERENTIAL WELDS CI.10 66.50 SS/SS ISI-21 IT MATERIAL NO 450 SHEAR WAVE % VEE SCAN SCAN

% WELD REQUIRED LIMITATION VOLUME ACHIEVED AXIAL 96.01%

FLANGE TO SHELL WELD CONFIGURATION AND TOWARD INTERFERENCE FROM THE CLOSE PROXIMITY OF FLANGE THE FLANGE CONNECTION BOLTING AXIAL 38.63%

FLANGE TO SHELL WELD CONFIGURATION AND TOWARD INTERFERENCE FROM THE CLOSE PROXIMITY OF SHELL THE FLANGE CONNECTION BOLTING CIRC 31.37%

FLANGE TO SHELL WELD CONFIGURATION AND FLANGE INTERFERENCE FROM THE CLOSE PROXIMITY OF SIDE THE FLANGE CONNECTION BOLTING CIRC 100%

FLANGE TO SHELL WELD CONFIGURATION AND SHELL INTERFERENCE FROM THE CLOSE PROXIMITY OF SIDE THE FLANGE CONNECTION BOLTING The coverage achieved was the maximum extent practical with the four core support lug obstructions in place and the results are representative of the entire weld.

A 700 shear wave, 1/22 vee examination was performed from both sides of the weld for additional coverage but was not listed on the coverage calc.

UT COMBINED COVERAGE = 66.50 %

EXAMINATION RESULTS: GEOMETRIC INDICATION NOTED (ROOT GEOMETRY), NO RECORDABLE INDICATION NDE EQUIPMENT: STAVELEY, SONIC-136, WITH KBA 0.375", 2.25MHZ, SHEAR 450 AND KBA 0.375", 2.25MHZ, SHEAR 700 Page 2 of 11 to SERIAL: FINP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-009 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION DATA SHEET 211-98-001 PAGE 11 OF 12 COMPONENT DRAWING PAM66 OF

62-WL6'tP4' AII&AA-C SWJ-OL JIrA~L poF qq.v IMs P~F~1 AIC5 WCLLI'0 VAl-IA4S Page 3 of 11 to SERIAL: 1HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-009 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION DATA SHEET 211-98-001 PAGE 10 OF 12 INTERFERENCE MEASUREMENT DRAWING

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SUMMARY

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DAT (1~e.co; Page 10 of I1 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-009 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION DATA SHEET,211-98-001 PAGE 1 OF 1 NDE REPORT

SUMMARY

S" nAROLINA L

OHPR &oImGpnT COMrANY te x

in No.m) me NDE REPORT/SUMMAARY Iae____O U-RI4R-0IRHRA-*CSW..02:

Procedure(s) ISI.21 IT Per the ISI Program Plan, Interval 2. Pe*iod L Outage I (RFO-8), ultrasonic examinations (UT) were performed on the subJect weld. These.exminations rmeet the requirement-of ASME.Section Xl, 1989 Ed, and re acceptable to the evaluation critena of-IWA.3000.

This e**d onlyreqtihtesa U-r cxal*nation. A code compliant FP was also perfor*ed. No indication swaer.edetcted The, LIT exams were performed us;ing 'procedure. techniques and personnel that meet the requirements of Appe-ndix III of ASMI3, Section XL. A 451, sheatr wavc. V'ý vec eXAM wasý performed from both sides. For additional coverage. a 7W Vi vee. shear wave was used to scan on both sides of the welds. Examination is incomplete, Scanning was limited due to the flange' to shell weld configuration and interfere*e from the close promimity of the flangeconnection bolting. Total volume of weld and base material coverage was calculate* to be 66.5%.

Co'verge plots and calculations are attached.

Cud i;~2~

0> 1 millEt 1 e; em Page 11 of.11 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-010 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION.

Examination Category C-B, Item C2.21, Nozzle-to-Shell Weld RAI REQUEST

RESPONSE

la Description (Reference Relief Request submittal HNP-08-045 Section 1.0). Weld BIT-O1NTHW-03 is the Outlet Nozzle to Head Weld located on the top of the Boron Injection Tank and Weld BIT-O1NTHW-04 is the Inlet Nozzle to Head Weld located on the bottom of the Boron Injection Tank.

la Sketch Information follows in Enclosure.

I a Interference/Obstruction (Reference Relief Request submittal HNP-08-045 Section 5.0). Nozzle to vessel welds are not conducive to two-sided volumetric examinations due to nozzle configurations.

lb NDE Equipment Information follows in Enclosure.

lb Alternative Methods (Reference Relief Request submittal HNP-08-045 Section 6.0). HNP is proposing to volumetrically examine the pressure retaining nozzle to vessel welds BIT-OINTHW-03 and BIT-O1NTHW-04 to the maximum extent possible in accordance with the Inservice Inspection Program schedule using Ultrasonic (UT) Examination. A significant portion of the subject welds have been examined, obtaining greater than 75 percent coverage for each nozzle to shell weld. In addition, the welds are subject to visual (VT-2) tests during each refueling outage.

ic Wave Modality/ Insonification Information follows in Enclosure ("0' Longitudinal Angles Wave Scan", 450 Shear Wave 1/2 Vee Scan", 600 Shear Wave 1/22.Vee Scan").

1 d Cross Sectional Coverage Plots to Information follows in Enclosure.

describe the ASME Code coverage le Results of the Examination No indications detected.

Indications /No Indications Page 1 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-010 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 2a Please state whether the All angle beam exams used shear waves, only the 0 inspection techniques used to degree exam used longitudinal waves.

examine these welds included 45 degree shear -

Y2 V refracted longitudinal waves.

60 degree shear - V2 V 0 degree longitudinal 2b Please state the material used Material used is alloy steel - ASTM A 204 Standard (austenitic or ferritic steel) and Specification for Pressure Vessel Plates, Alloy Steel, the wall thickness for each of Molybdenum (Austenitic); 1.732" Thickness these components.

Page 2 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-010 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

II-BIT-01NTHW-03 II-BIT-01NTHW-04 ASME CATEGORY:

IWC-2500-4 PRESSURE RETAINING NOZZLE WELDS IN VESSELS ASME ITEM NUMBER:

% CRV ACHIEVED:

0 DEGREES 45 DEGREES 60 DEGREES C-B C2.21 77.14%

100%

58%

73.43%

SS/SS NDEP-0448 MATERIAL NO 00 LONGITUDINAL WAVE SCAN SCAN

% VOLUME LIMITATION ACHIEVED 100%

450 SHEAR WAVE 1/2 VEE SCAN SCAN

% VOLUME LIMITATION ACHIEVED CIRCUMFERENTIAL 100%

SCAN HEADSIDE CIRCUMFERENTIAL 100%

SCAN NOZZLE SIDE AXIAL SCAN 0%

NOZZLE TO SHELL CONFIGURATION TOWARD HEAD AXIAL SCAN 32%

NOZZLE TO SHELL CONFIGURATION TOWARD NOZZLE I II Page 3 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEFREQUEST 2R2-010 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 600 SHEAR WAVE 1/2 VEE SCAN SCAN

% VOLUME LIMITATION ACHIEVED CIRCUMFERENTIAL 100%

SCAN HEADSIDE CIRCUMFERENTIAL 100%

SCAN NOZZLE SIDE AXIAL SCAN 0%

NOZZLE TO SHELL CONFIGURATION TOWARD HEAD AXIAL SCAN 93.7%

NOZZLE TO SHELL CONFIGURATION TOWARD NOZZLE I II The coverage achieved was the maximum extent practical with the nozzle to shell configuration and the results are representative of the entire weld.

UT COMBINED COVERAGE = 77.14 %

EXAMINATION RESULTS: NO INDICATIONS NDE EQUIPMENT: STAVELEY, SONIC-136, WITH KBA 0.75", 2.25MHZ, LONGITUDINAL 00, KBA 0.5" DIA., 2.25MHZ, SHEAR 450 AND KBA 0.5" DIA.,

2.25MHZ, SHEAR 600 Page 4 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-010 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION BORON INJECTION TANK NOZZLE TO HEAD WELD CONFIGURATION IDENTIFICATION SHEET TYPICAL FOR BOTH THE INLET NOZZLE AND THE OUTLET NOZZLE NOZZLE SHELL I

WVLLU Page 5 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-010 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION II-BIT-01NTHW-03 COVERAGE

SUMMARY

Detelrmination of Percent COverage for SUTT Examinations Vessels S

"f/011 I'P SrnrNo~;~

t-01353

.Wonks9qjpe'F oS Proceduro

ýWe~cide No.:,

B0aP 5rert N;,ý

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'S..n 100.000

%!Length Xý 100.000..

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. 142i.

S~,ptonenntovorge toybe achieved by.use of other angtoe~yrnthocts~hn Thist-b-rhent I.

Oflcr

Date,

'10/22/2004 Page 6 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-010 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION II-BIT-OINTHW-03 ULTRASONIC SKETCH B

Supplp!emental Report:

'A.~port N-'

WTý04-0031 f~g: 3:

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Sit0Roqvf(w-Edjwin U. Si6k:

Iot 10/23/2004, other.. N/A Le-ef N/A ANit Resvitw.

L-ey'JbneS AM11 aet-10123/ 2004,

.Cnn-e, V ELXVLOCATIONWAND UII4ENS64DS TAKENM FROM 0RAWiN0 C 1219OE77 SHMEYT2.

ifs DomentIs.o.O&floco.-O Page 7 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-010 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION II-BIT-01NTHW-04 COVERAGE

SUMMARY

Dete-mination E

of Perce nt Coverage fr zUT'*Examinations - Vessels Siek/ nit.:..

p.

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PmoCedur Ro.-r NO0EP-0448.

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ýs equr0nddvd'ty#onla to detannine s6pptenelioeoereite civdayue to tatt gtt"d -hn uethe'coevrae0Olor-lurnenot cblaied~wth~aglaeaS~ntedaavO haltbececuiaedan addd lahe ttait prcidolhc.percntlolat fort,,arp~l Site Field SupolvlaoT:,

Ww-laiW

VBlee, Th1.onel saARcr Dol 1022/00 Page 8 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-010 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION II-BIT-01NTHW-04 ULTRASONIC SKETCH

ýSupplemental Report Ftepo.

No.

ýUY-04-G00 page:

-.2.Z

. of, ".3 S.uonotary No:;, H-0113S4 Eeeio:~B~g~.

no.

Le ti it-poE R'Eo.

>alh~

oe~U.L~JI Dte 10/22)2004 ExoeYinobr;'

N/A

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Bick Dote 0)23 004

.Qthe ~

~

Y

"/

ee:NAAn oiw.

e-y J.... ANII Date;: 10)2320041 This Dec..n*ient Is e OA Record.

Page 9 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-011 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Examination Category C-C, Item C3.30, Pumps Integrally Welded Attachments RAI REQUEST

RESPONSE

Ia Description (Reference Relief Request submittal HNP-08-045 Section 1.0). Welds II-CSIP-ICSIP-A-WAI, II-CSIP-ICSIP-A-WA2, II-CSIP-1CSIP-A-WA3 and IICSIP-I CSIP-A-WA4 are integral attachments for the support legs located on the bottom of the Charging Safety Injection Pump.

la Sketch Information follows in Enclosure.

la Interference/Obstruction (Reference Relief Request submittal HNP-08-045 Section 5.0). Due to the restricted access caused by the configuration of the components, structural support steel limits, access to one side of the welded attachment, 100 percent surface examinations are limited.

lb NDE Equipment Information follows in Enclosure.

lb Alternative Methods No additional alternative methods or advanced technologies have been employed.

I c Wave Modality/ Insonification Penetrant Examination.

Angles ld Cross Sectional Coverage Plots to Information follows in Enclosure.

describe the ASME Code coverage le Results of the Examination No recordable indications.

Indications / No Indications Page 1 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-011 -

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

II-CSIP-1CSIP-A-WA1 IWC-2500-5 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

C-C C3.30 77.10%

SS INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS AND VALVES NDEP-0201 MATERIAL NO LIQUID PENETRANT EXAMINATION

% VOLUME LIMITATION ACHIEVED 77.1%

FLANGE MATING SURFACE AND STRUCTURAL STEEL The coverage achieved was the maximum extent practical with the pump fillet weld configuration and the results are representative of the entire weld&

UT COMBINED COVERAGE = 77.14 %

EXAMINATION RESULTS: NO RECORDABLE INDICATIONS NDE EQUIPMENT: MAGNAFLUX MATERIALS Page 2 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-011 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION II-CSIP-1CSIP-A-WA1 COVERAGE

SUMMARY

Srnn ir No i'

1-p "1' Supplemental

Repcrrt fio0o0tw N0 w

P-o4-ooz2 Page,:

2 JF

'2.

Sketch or Photo:

v:\\Sr.aeU~,aoeart-tNP_0atetflataSheot3ofo~PT-04~002tif

--I

.- ~;"

L.

L 1,rI

ýý

'ý-

z

&-c--

mwon mrCSK--WA I~aai.,~t~o rotpitot

~tottato1, rota eaai is QA Step Page 3 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-011 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

II-CSIP-iCSIP-A-WA2 IWC-2500-5 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

C-C C3.30 82.35%

SS INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS AND VALVES NDEP-0201 MATERIAL NO LIQUID PENETRANT EXAMINATION

% VOLUME LIMITATION ACHIEVED 82.35%

STRUCTURAL STEEL The coverage achieved was the maximum extent practical with the pump fillet weld configuration and the results are representative of the entire weld.

UT COMBINED COVERAGE = 82.35%

EXAMINATION RESULTS: NO RECORDABLE INDICATIONS NDE EQUIPMENT: MAGNAFLUX MATERIALS Page 4 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 1NSERVICE INSPECTION RELIEF REQUEST 2R2-011 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION II-CSIP-1CSIP-A-WA2 COVERAGE

SUMMARY

'Su pplementa*ti Rep6ot Ropoftl No.;

PIT*G4-003 I

go; 2i ot.

2

~.,rcro8,y No.;

14-01 859 Sketch ~

~

.0 4,40 Photo;-iý66 1:.hrdtdal-$Ih~t~aaho tlOP-6"03.t 594P.5-A p~t

'retare~nui,.27.65V6a Page 5 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-011 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

II-CSIP-iCSIP-A-WA3 IWC-2500-5 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS AND VALVES C3.30 80%

SS NDEP-0201 MATERIAL NO LIQUID PENETRANT EXAMINATION

% VOLUME LIMITATION ACHIEVED 80%

STRUCTURAL STEEL The coverage achieved was the maximum extent practical with the pump fillet weld configuration and the results are representative of the entire weld...

UT COMBINED COVERAGE = 80%

EXAMINATION RESULTS: NO RECORDABLE INDICATIONS NDE EQUIPMENT: MAGNAFLUX MATERIALS Page 6 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 1NSERVICE INSPECTION RELIEF REQUEST 2R2-011 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION II-CSIP-1CSIP-A-WA3 COVERAGE

SUMMARY

-G-NGI AJN 00 0 Supplemental Report FAoporiNo,~~To-

~no00,:.N0.: H-01860 Skatahor F'hata:

~V,\\S~

dlddoa\\HNP *O0~OaSheetj.ifo\\PT)~'0O~Wit FensitL.lass oi~ia..

'Fa0~j eaIan0a,..,s-e~

'7.0'.'

-.- ~.0" 4.00" 5-4,00".2Z00" 1.0" 5.00".5- ~00" (t1~~s-~s-.

IoI.o0.o.~fl~3a0S) ~.

175" (w.11 IdOh -o.50" 101.

.sId~) -52.S0"~

ftncauw.pKata pCS.flIflSStOfl ann:

.75"('.s-s-Id e.Sdth) -- ~1.O' (50",~e,,oo, ens-a s-Itba.

10 at e.s-Id) X GOO" (I.,gh at

- 0. ea.apl000

,.~s-ai.satIa..

.- en>.= 10.50" 10.S0" ~s-5 2.SO's- =.20 -

20w. h.s-o..,pIs-t e80~

eenpD.t..

Th~e~a~a~s.,1. '10A 05N5-O,-5 Page 7 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-011 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMPONENT ID:

ASME CODE FIGURE:

CONFIGURATION:

PROCEDURES:

PDI TECHNIQUE USED:

II-CSIP-1CSIP-A-WA4 IWC-2500-5 ASME CATEGORY:

ASME ITEM NUMBER:

% CRV ACHIEVED:

C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS AND VALVES C3.30 75%

SS NDEP-0201 MATERIAL NO LIQUID PENETRANT EXAMINATION

% VOLUME LIMITATION ACHIEVED 75%

FLANGE MATING SURFACE AND STRUCTURAL STEEL The coverage achieved was the maximum extent practical with the pump fillet weld configuration and the results are representative of the entire weld.

UT COMBINED COVERAGE = 75%

EXAMINATION RESULTS: NO RECORDABLE INDICATIONS NDE EQUIPMENT: MAGNAFLUX MATERIALS Page 8 of 9 to SERIAL: HNP-09-095 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST 2R2-011 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION II-CSIP-1CSIP-A-WA4 COVERAGE

SUMMARY

G.-

Ii..

Gr-

<:04'b

ý I

'Supplemental RepOrt-Ftop.r1 N5.ý PT-04-005ý P~goZ 2 of 2

s'S.6mnly N-.

"-016q1' Skotcti:or-:Phote:

.V:~Shaed'.5ddsaN-lNPOata'd1IstonAMFO-i 2WtT-04+OOS;tit

~

L.4.i~~,0J

~

7^

.V

.')4

.7S."

n.-t$d~:

fl-CS.-XCSIr..A.-WA.4 rota.

c,~asntnat1en V.75" (,,.eld.,Idtb -.-. 50" aith.'

alda) = 50.75"'

lfleCfl.nICte C,.OpflbtIOfl

area,

1.

275" (~..Id srtdlh) -s-1.0" (.50"ao.ara.ithar

.54,.

of,.,aR.j~'X 6.00~ (Ie.s~0.

~f i,.,aoOSpIat. ~,.atataatio..

~

10.50

2.

.40" X 5.50"-

Total ia.oo=plate a,......kaal1an~rea.=32.70" ~

~a.aaIatad oerraota.,a~

1Z.7O~

50.75"'

=.254)2 = ZS.00~I~

.pI~ta 75.00'A, ao.apiala.

TbIsOdcurrsent is a OA>Rocerd Page 9 of 9

v t e Letter Sequence Response to RAI
TAC:ME0166, (Approved, Closed) TAC:ME0608, (Open) TAC:ME0609, (Open) TAC:ME0610, (Open) TAC:ME0612, (Open) TAC:ME0613, (Open) TAC:ME0614, (Open) TAC:ME0615, (Open)
Initiation Acceptance... Administration Questions Answers 24 September 2009 Results Approval Other:
MONTHYEAR2009-09-24 [Table View]

HNP-09-095, Response to Request for Additional Information Regarding Relief Requests 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, & 2R2-011 for the Second 10-Year Inservice Inspection Program

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HNP-09-095, Response to Request for Additional Information Regarding Relief Requests 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, & 2R2-011 for the Second 10-Year Inservice Inspection Program

Text

References:

Enclosures:

Response

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