ML18151A720

Requests Relief from Certain Requirements of ASME Section XI Code Associated W/Partial ISI Exams Conducted During 1996 Refueling Outage,Per 10CFR50.55a(g)(5)(iii)

ML18151A720
Person / Time
Site:	Surry
Issue date:	01/02/1997
From:	Saunders R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-606, NUDOCS 9701060258
Download: ML18151A720 (40)

Text

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CATEGORY 1 REGULATO.INFORMA~!ON DISTRIBUTION tt~TEM (RIDS)

ACCESSION NBR:9'7G'l060258 DOC.DA'I'E: 97/01/02 NOTARIZED: NO FAC!~:so~2si Surry Power Station, Unit *, Virginia Electric & Powe AU'iH. NAME AUTHOR AFFI'.'LIAT'EON SAUNDE~S,rt.F.

vfrginia Power (Virginia Electric & Power Co.)

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

DOCKET #

• 05000281

SUBJECT:

~~-ts Rei~ests relief from certain requirements of ASME Section XI Code associated w/partial ISI exams conducted during 1996 refueling outage,per 10CFR50.55a(g)(5)(iii).

DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ~l ENCL _l SIZE:~'3..._,~,.,,__~~

TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code -

GL-89-04 NOTES:

RECIPIENT ID CODE/NAME PD2-l LA EDISON,G.

EXTERNAL: LITCO ANDERSON NRC PDR NOTES:

COPIES LTTR ENCL l

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1 NOTE TO ALL "RIDS" RECIPIENTS:

RECIPIENT ID CODE/NAME PD2-l PD AEOD/SPD/RAB NRR/DE/EMEB OGC/HDS2 RES/DET/EMMEB NOAC PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-S(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 14 05000281 COPIES LTTR ENCL 1

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VIRGINIA ELECTRIC AND PowER COMPANY RICHMOND, VIRGINIA 23261 January 2, 1997 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 Serial No.96-606 NL&OS/GDM R1 Docket No.

50-281 License No.

DPR-37 ASME SECTION XI INSERVICE INSPECTION PROGRAM RELIEF REQUESTS During the 1996 refueling outage for Surry Power Station Unit 2, the inservice inspection examinations for the first period of the third ten year inspection interval were completed. The examinations were conducted in accordance with the requirements of the 1989 Edition of ASME Section XI.

Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from certain requirements of the ASME Section XI Code associated with partial examinations conducted during the 1996 Surry Unit 2 refueling outage. Relief Requests SR-018 through SR-024 are attached and provide the basis of this request. These relief requests have been reviewed and approved by the Station Nuclear Safety and Operating Committee.

If you have any questions or require additional information concerning these requests, please contact us.

Very truly yours, R. F. Saunders Vice President - Nuclear Engineering and Services Attachments 9701060258 970102 PDR ADOCK 05000281 G

PDR

cc:

U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.

Atlanta, Georgia 30323 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station

ASME SECTION XI ISI PROGRAM RELIEF REQUESTS REC'D W/LTR DTD Ol/02/97.... 9701060258

.. NOTICE -

THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE INFORMATION &

RECORDS MANAGEMENT BRANCH.

THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUSTBERETURNEDTOTHE

• RECORDS & ARCHIVES SERVICES

.SECTION, T5 C3. PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE(S) FROM DOCUMENT FOR REPRODUCTION MUST BE REFERRED TO FILE PERSONNEL.

- NOTICE -

Virginia Electric & Power Company Surry Power Station Unit 2 Third Ten Year Interval Request for Relief No. SR-018 I.

Identification of Component:

Weld No.

Weld 1-01 Weld 1-01 Weld 1-01 Line No.

2"-CH-397-1502 2"-CH-395-1502 2"-CH-393-1502 Drawing No.

Class 11548-WMKS-RC-1225 1

11548-WMKS-RC-1123 1

11548-WMKS-RC-1024 1

The above welds are socket welds in the reactor coolant pump seal injection piping lines.

II.

Code Requirements:

For Surry Unit 2, Relief Request SR-008 was used for weld selection of Class 1 pressure retaining welds in piping in conjunction with ASME Section XI, 1989 Edition, Table IWB-2500-1, Notes 1 (b) and 2 of Category B-J. Relief Request SR-008 was approved by NRC Letter 95-480, dated 8-30-95. The relief request requires that all terminal ends of piping runs connected to vessels and pumps be examined.

The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.40 requires an OD surface examination of the weld and adjacent base metal as defined.by Figure IWB-2500-8, (socket weld).

Ill.

Code Requirement From Which Relief Is Requested:

Relief is requested from performing the Code-required surface examination on the above identified reactor coolant system piping.

IV.

Basis for Relief:

The components listed above are terminal ends on. seal injection piping connected to the reactor coolant pumps. The welds are completely inaccessible due to their closeness to the pump flange (i.e., they are underneath the flange.

The attached picture shows the configuration.)

However, when the reactor coolant pump main flange is disassembled, the weld is accessible for examination. However, disassembly of the pump would cause a burden without a compensating increase in quality and safety.

All terminal end welds are

V.

scheduled for examination.

Therefore, substitution with another weld is not feasible.

However, another weld will be selected for examination in order to ensure that 25% of examination category B-J welds will be examined.

Proposed Alternate Requirement:

It is proposed that the substitution with another weld be counted as meeting the Code requirements. In addition:

1.

A visual (VT-2} examination will be performed during the normally scheduled system leakage test each refueling outage.

2.

Technical Specifications require that the reactor coolant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

3.

The containment atmosphere particulate radioactivity is checked every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.

If a reactor coolant pump main flange is disassembled, thereby making the weld accessible for examination, the weld will be examined consistent with Code requirements.

The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.

SR-018 - Picture

11548-WMKS-RC-1225 FL. EL. l-l3'-6'. \\.. -

'-. 2' X 3/4' RED.

2"-CH-Jql-1502-2" X 3/4'/

RED.

!FLANGE BDLTINJ I ~ STUDS RED.

REACTOR COOL~NT 2' X 11/2'

~NUTS DIIMP FLAN(.EA

~

/

F~ / ~

ITfil /~

[Efil

/1t_EL.14"-'li/4' 1-01

11548-WMKS-RC-1123

'10" SW ELL 4 STUDS* I" DIA. -....

REACTOR COOLANT

~

2-RC-P-18

[

FLANGE BOLTING}

B NUTS I FLANGE A I ~

"~

[rnJ "mil

'*'10" SW ELL

....._2' X 3/4" RED

~

• /'Ii. EL.17"*8 3/4'

' 90" !:W ELL

D FLANGE BOLTING\\

4 STUDS 8 NUTS 2" X 3/4' RED.

11548-WMKS-RC-1024

'10" SW EL~

LC

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cse 2*CH*J4~

Virginia Electric & Power Company Surry Power Station Unit 2 Third Ten Year Interval Request for Relief No. SR-019 I.

Identification of Component:

11.

111.

Weld No.

Weld 4-11 BC Line No.

3"-RC-335-1502 Drawing No.

11548-WMKS-0124A 1 Weld 4-11 BC is a branch connection piping weld.

Code Requirements:

1 The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.32 requires an OD surface examination of the weld and adjacent base metal as defined by Figure IWB-2500-11. The Code does not allow any limitations to the required surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 1 O percent.

Code Requirement From Which Relief Is Requested:

Relief is requested from performing the Code-required surface examination on the above identified reactor coolant system piping.

IV.

Basis for Relief:

The weld listed above is covered by a reinforcement pad/saddle weld, which totally covers the examination area described in the Code.

Therefore, examination coverage cannot be achieved due to the configuration of the piping.

This weld is a branch connection and, as such, all welds of this type are scheduled for examination.

Therefore, substitution with another weld is not feasible.

V.

Proposed Alternate Examination:

It is proposed that a surface examination performed on the fillet weld of the reinforcement pad be substituted for the Code surface examination. In addition:

1.

A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refueling outage.

2.

Technical Specifications require that the reactor coolant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

3.

The containment atmosphere particulate radioactivity is checked every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.

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Virginia Electric & Power Company Surry Power Station Unit 2 Third Ten Year Interval Request for Relief No. SR-020 I.

Identification of Components:

Weld No.

Weld 1-05DM Weld 1-06DM Line No.

29 11-RC-301-2501 R 31 11-RC-308-2501 R Drawing No.

Class 11548-WMKS-RC-12-1 1

11548-WMKS-RC-10-1 1

Weld 1-05DM is a nozzle-to-safe end weld on the steam generator on the reactor coolant piping on loop 11A 11

• Weld 1-06DM is a nozzle-to-safe end weld on the steam generator on the reactor coolant piping on loop 11C 11 II.

Code Requirements:

The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-F, item number B5.70 requires an OD surface examination of the weld and adjacent base metal and a volumetric examination of the weld and adjacent base metal (interior one-third volume) as defined by Figure IWB-2500-8. The Code does not allow any limitations to the required volumetric or surface examinations.

Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 1 O percent.

Ill.

Code Requirement From Which Relief Is Requested:

Relief is requested from fully performing the Code-required volumetric examination on the above identified reactor coolant piping.

IV.

Basis for Relief:

The components listed above have been examined to the extent practical as required by the Code. However, full volumetric coverage could not be achieved due to joint configuration and material characteristics.

Coverage of the volumetric and surface examinations is detailed in Tables SR-020-1 and SR-020-

2. Figure SR-020-1 is provided as graphic detail of the limitations experienced.

Substitution with another weld is not feasible because all welds in this Category and Item must be examined.

V.

Proposed Alternate Examination:

It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements. In addition:

1.

A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refueling outage.

2.

Technical Specifications require that the reactor coolant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

3.

The containment atmosphere particulate radioactivity is checked every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.

Table SR-020-1 Surry Unit 2 Examination Coverage Estimates (Piping) 11548-WMKS-RC-12-1 Category B-F, Item 85.70 UT Scan Coverage %

Weld No.

1-05DM 2

0 5

28 UT Scan Direction Definitions 7

55 8

55 Surface Coverage%

100 2 - axial scan, 180 degrees from isometric flow direction.

5 - axial scan, the same direction as the isometric flow.

Reason For Partial Weld is limited by the nozzle geometry, surface condition and limited surface preparation on the pipe side of the weld. The surface on the pipe side of the weld, which is a cast elbow, is machined for a distance of approximately three inches from the edge of the weld. Ultrasonic examination is limited to this machined area of the pipe and weld since the nozzle side is in the rough as-cast condition.

The use of alternate angles would not have improved volumetric coverage.

Because of the use of the longitudinal wave form only Y2 node examinations were possible.

7 - circumferential scan, clockwise rotation when viewing in the direction of isometric flow.

8 - circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow.

Table SR-020-2 Surry Unit 2 Examination Coverage Estimates (Piping) 11548-WMKS-RC-10-1 Category B-F, Item 85.70 UT Scan Coverage %

Weld No.

1-06DM 2

28 5

0 UT Scan Direction Definitions 7

55 8

55 Surtace Coverage%

100 2 - axial scan, 180 degrees from isometric flow direction.

5 - axial scan, the same direction as the isometric flow.

Reason For Partial Weld is limited by the nozzle geometry, surtace condition and limited surtace preparation on the pipe side of the weld. The surtace on the pipe side of the weld, which is a cast elbow, is machined for a distance of approximately three inches from the edge of the weld. Ultrasonic examination is limited to this machined area of the pipe and weld since the nozzle side is in the rough as-cast condition.

The use of alternate angles would not have improved volumetric coverage.

Because of the use of the longitudinal wave form only 1h node examinations were possible.

7 - circumferential scan, clockwise rotation when viewing in the direction of isometric flow.

8 - circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow.

Figure Search Unit Search Unit Elbow Rough OD Surface Hatched area is volume examined.

-020-1 45* Beam Angle Longitudinal Wave Nozzle I

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~l Exam. Volume

IOIJ*5l j _6'*RC*Jl7*1502* I -- --

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f7 J/2"*RC*J03*2501R*!

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<NOTE 71 11548-W-MKS-RC-12-1 J

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Virginia Electric & Power Company Surry Power Station Unit 2 Third Ten Vear Interval Request for Relief No. SR-021 I.

Identification of Component:

II.

II I.

IV.

Weld No.

Weld 2-30 Line No.

4"-RC-315-1502 Drawing No.

11548-WMKS-0125A 1 1

Weld 2-30 is on pressurizer spray piping from reactor coolant cold leg on loop "C" to the pressurizer.

Code Requirements:

The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.11 requires an OD surface examination of the weld and adjacent base metal and a volumetric examination of the weld and adjacent base metal (interior one-third volume) as defined by Figure IWB-2500-8. This weld is not a terminal end or dissimilar metal weld, but is included in the examination category as additional piping welds to ensure that 25% of the reactor coolant piping is examined. The Code does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent.

Code Requirement From Which Relief Is Requested:

Relief is requested from fully performing the Code-required surface examination on the above identified reactor coolant piping.

Basis for Relief:

The component listed above has been examined to the extent practical as required by the Code. However, full surface coverage could not be achieved due to interferences from an adjacent pipe support. The required volumetric examination had limitations, but they where less than 10%. Coverage of the volumetric and surface examinations is detailed in Table SR-021-1. Picture SR-021-1 is provided as graphic detail of the limitations experienced. Substitution with another weld of the same size would not necessarily improve the examination coverage since this weld is representative of plant design and similar geometric conditions are expected.

V.

Proposed Alternate Examination:

It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements. In addition:

1.

A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refueling outage.

2.

Technical Specifications require that the reactor coolant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

3.

The containment atmosphere particulate radioactivity is checked every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.

Weld No.

2-30 UT Scan Table SR-021-1 Surry Unit 2 Examination Coverage Estimates (Piping) 11548-WM KS-0125A 1 Category B-J, Item 89.11 Surface Coverage % Coverage %

Reason For Partial 93.3 81 A whip restraint located on the piping and on the pipe side with the weld extending across the weld to the weld toe prevents 100% surface examination. The whip restraints (4 total) are located at o*, 90°, 180° and 270°. Each restraint at the pipe is 0.500" in length.

SR-021-Picture

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Virginia Electric & Power Company Surry Power Station Unit 2 Third Ten Year Interval Request for Relief No. SR-022 I.

Identification of Component:

Weld No.

Weld 2-06 Component 2-SI-P-1A Drawing No.

11548-WMKS-SI-P-1A Weld 2-06 is a pump casing weld on the safety injection pump 02-SI-P-1 A.

2 II.

Code Requirements:

The 1989 Edition of ASME Section XI Table IWC-2500-1, examination category C-G, item number C6.10 requires an OD or ID surface examination of the weld and adjacent base metal as defined by Figure IWC-2500-8. The Code does not allow any limitations to the required surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent.

Ill.

Code Requirement From Which Relief Is Requested:

Relief is requested from fully performing the Code-required surface examination on the above identified safety injection pump casing weld.

IV.

Basis for Relief:

V.

The component listed above has been examined to the extent practical as required by the Code. Approximately sixty-three (63) percent of the required examination was completed. Full surface coverage could not be achieved due to interferences from an adjacent wall, bolting and the pump casing support. Figure SR-022-1, pictures SR-022-1, SR-022-2 and SR-022-3 are provided as graphic detail of the limitations experienced. Substitution with another weld is not feasible because the "B" pump has the same limitation. Disassembly of the pump would cause a burden without a compensating increase in quality and safety.

Proposed Alternate Examination:

It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.

The proposed alternative examination will ensure that the overall level of plant quality and safety will not be compromised.

Figure SR-022-1 Wal I 02-SI-P-lA Flange

~

We Id 2-06

/).

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Support Structure

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SR-022 Picture

SR-022 Picture

SR-022 Picture

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Virginia Electric & Power Company Surry Power Station Unit 2 Third Ten Vear Interval Request for Relief No. SR-023 I.

Identification of Component:

Weld No.

10NIR 11NIR Component 2-RC-E-2 2-RC-E-2 Drawing No.

11548-WMKS-RC-E-2 11548-WMKS-RC-E-2 1

1 NI R's 10 and 11 are nozzle inside radius sections integrally cast to the top of the pressurizer.

II.

Code Requirements:

The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-D, item number B3.120 requires a volumetric examination of the nozzle inside radius section as defined by Figure IWB-2500-?(d). The Code does not allow any limitations to the required volumetric examinations.

Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent.

Ill.

Code Requirement From Which Relief Is Requested:

Relief is requested from fully performing the Code-required volumetric examination on the above identified pressurizer nozzle inside radius sections 1 ONIR and 11 NIR.

IV.

Basis for Relief:

The components listed above have been examined to the extent practical as required by the Code. However, full volumetric coverage could not be achieved due to inherent interferences from a rough and bumpy surface, which causes the ultrasonic search unit to lose contact and change angles.

• The use of alternate angles would not have improved volumetric coverage. The nozzles are integrally cast to the pressurizer, therefore, weld contour preparation (grinding or weld buildup and grinding) prior to examination will result in vessel wall reduction and is not recommended. The reduction in coverage is approximately ninety-five (95) percent.

Picture SR-023-2 (NIR-11) is provided as graphic detail of the pressurizer nozzles, and is representative of existing conditions.

Substitution with another nozzle inside radius section is not feasible because all of the pressurizer nozzle inside radius sections must be examined.

V.

Proposed Alternate Examination:

It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements. In addition,

1.

The nozzle inside radius sections will be visually examined from the inside using direct or remote techniques prior to the end of the inspection interval.

2.

A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refueling.

3.

Technical Specifications require that the reactor coolant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

4.

The containment atmosphere particulate radioactivity is checked every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.

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,l Virginia Electric & Power Company Surry Power Station Unit 2 Third Ten Year Interval Request for Relief No. SR-024 I.

Identification of Component:

Weld No.

Weld 1-03 Line No.

29"-RC-307-2501 H Drawing No.

11548-WMKS-RC-10-1 1

Weld 1-03 is on the reactor coolant (hotleg) piping on loop "C" from the reactor vessel to the steam generator.

II.

Code Requirements:

The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category 8-J, item number 89.11 requires an OD surface examination of the weld and adjacent base metal and a volumetric examination of the weld and adjacent base metal (interior one-third volume) as defined by Figure IWB-2500-8. This weld is not a terminal end or dissimilar metal weld, but is included in the examination category as additional piping welds to ensure that 25% of the reactor coolant piping is examined. The Code does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent.

Ill.

Code Requirement From Which Relief Is Requested:

Relief is requested from fully performing the Code-required volumetric examination on the above identified reactor coolant piping.

IV.

Basis for Relief:

The component listed above has been examined to the extent practical as required by the Code. However, full volumetric coverage could not be achieved due to joint configuration. Coverage of the volumetric and surface examinations is detailed in Table SR-024-1. Figure SR-024-1 is provided as graphic detail of the limitations experienced.

Substitution with another weld of the same size would not necessarily improve the examination coverage since this weld is representative of plant design and similar geometric conditions are expected.

V.

Proposed Alternate Examination:

It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements. In addition:

1.

A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refueling outage.

2.

Technical Specifications require that the reactor coolant system leak rate be limited to one gallon per minute unidentified* leakage. This value is calculated at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

3.

The containment atmosphere particulate radioactivity is checked every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The proposed alternative examinations stated above will ensure that the overall

. level of plant quality and safety will not be compromised.

Figure SR-024-1 Table SR-024-1 Surry Unit 2 Examination Coverage Estimates (Piping) 11548-WMKS-RC-10-1 Category 8-J, Item 89.11 UT Scan Coverage %

Weld No.

1-03 2

0 5

7 100 25 UT Scan Direction Definitions 8

25 Surface Coverage %

Reason For Partial 100 Pipe to valve configuration prevented scanning from the 2 side, (valve side ).

A 60° supplemental examination was performed to increase examination coverage. The use of alternate angles would not have improved volumetric coverage. Because of the use of the longitudinal wave form, only Y2 node examinations were possible.

2 - axial scan, 180 degrees from isometric flow direction.

5 - axial scan, the same direction as the isometric flow.

7 - circumferential scan, clockwise rotation when viewing in the direction of isometric flow.

8 - circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow.

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Figure SR-024-1 Search Unit Va. Ive lv10V-259LJ 29"-RC-307-2501R 45

• Beam Angle 60" Beam Angle Exam.

Volume

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