Text

Inservice Inspection Activities - 90-Day Report
	ML070380368
Person / Time
Site:	Salem
Issue date:	01/30/2007
From:	Joyce T; Public Service Enterprise Group
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	LR-N07-0016
	Download: ML070380368 (57)
	v • d • e

! ",

7*,...,¸

\\

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC January 30, 2007 LR-N07-0016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555-001 Salem Nuclear Generating Station Unit 2 Facility Operating License No. DPR-75 NRC Docket No. 50-311

SUBJECT:

Inservice Inspection Activities Day Report This letter submits the ninety (90) day report for Inservice Inspection (ISI) activities conducted at the Salem Generating Station Unit No. 2 during the fifteenth refueling outage. This report is submitted in accordance Article IWA-6000 of Section Xl of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, 1998 Edition, 2000 Addenda.

The enclosures to this letter are as follows:

Salem Unit 2, 2R15 Final Outage Report Salem Unit 2, ISI Examination Plan and Results Salem Unit 2, Reactor Coolant Pump (RCP) Flywheel Inspection Plan and Results Salem Unit 2, IWE Examination Plan and Results Salem Unit 2, Owners Activity Report Should you have any questions regarding this submittal, please contact E. H. Villar at (856) 339-5456.

Sincerely, Thomas P. Joyb-e "

Site Vice President - Salem Enclosures (5) 95-2168 REV. 7/99

January 30, 2007 Page 2 LR-N07-0016 C

Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Project Manager - Salem U.S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Salem (X24)

Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625 Mr. Milton Washington Chief Inspector NJ Department of Labor Division of Public Safety, Occupational Safety and Health Bureau of Boiler and Pressure Vessel Compliance P. O. Box 396 101 South Broad Street Trenton, NJ 08625-0392

.4~

-~

LR-N07-0016 Salem Unit 2, 2R15 Final Outage Report With Appendices

SALEM UNIT 2 (RFO#1 5) ISI FINAL

SUMMARY

REPORT ABSTRACT This report represents an accumulation of information pertaining to the In-Service Inspection (ISI) activities conducted during Salem Unit 2 fifteenth Refueling Outage (RFO#1 5). ISI/

nondestructive examinations (NDE) exams were conducted in accordance with the Salem Unit 2 ISI Program Long Term Plan.

ISI/NDE examinations were completed of selected Salem Generating Station Unit 2 Class 1, Class 2, Class 3, and Class MC components. PSEG-Nuclear LLC (PSEG), Areva, Team Industrial Services and Wesdyne personnel performed these examinations during the period from October 10, 2006'through November 01, 2006 (21 days).

These examinations constituted the fifteenth (15 th) outage overall and the second outage of the first period of the third interval (3 rd Interval 1st Period, 2 nd Outage 3-1-2) at Salem Unit 2 Third 10-year Inspection Interval of operation. This final report covers the time period between breaker closure after RFO#1 4 (May 11, 2005) until breaker closure after RFO#1 5 (November 1, 2006).

ISI/NDE exams were completed in accordance with American Society of Mechanical Engineers (ASME)Section XI 1998 up through and including Edition 2000 Addenda.

Ultrasonic testing requirements were completed in accordance with ASME Xl Appendix VIII as amended by 10CFR50.55a Final Rulemaking. Other ISI/NDE examinations were conducted using Visual (VT), Magnetic Particle (MT), Liquid Penetrant (PT), and Manual Ultrasonic (UT), nondestructive examination techniques.

Containment IS[ examinations were conducted in accordance with ASME Section XI IWE/IWL 1998 Edition up through and including 1998 Addenda as amended by the Nuclear Regulatory Commission's Safety Evaluation Report (SER). These examinations constituted the first outage of the third period of the first interval at Salem Unit 2 marking the beginning of the third period of scheduled exams of the First 10- year Inspection Interval.

This report also contains augmented examinations required by Salem Unit 2 Technical Specifications (TS), and commitments made in response to Nuclear Regulatory Commission (NRC) Regulatory Guides, Circulars, Bulletins, and selective preventive maintenance examinations.

Page: ii

-3 SALEM UNIT 2 (RFO#1 5) ISI FINAL

SUMMARY

REPORT TABLE OF CONTENTS PAGE FINAL

SUMMARY

REPORT WITH APPENDICES A B S T R A C T....................................................................................................

ii TA B LE O F C O N T E N T S........................................................................................

iii I.

SUMMARY

REPORT A.

A pplicable docum ents................................................................................

1 B.

ISI Section XI (Vol. & Surface.) Examinations Performed...

........ 2 C.

ISI Section XI RPV IVVI Visual Exams.......................................... 3 D.

ISI Section XI Visual Examinations on Valves and Bolting.................... 3 E.

ISI Section XI Visual Examination of Component Supports................. 4 F.

ISI Section XI Visual Examination of Containment Integrity...................

4 G.

ISI Section XI System Leakage Examinations.......................................

4 H.

RCP Flywheel Examination per USNRC Regulatory Guide 1.14.......5 I.

Risk Informed Break Exclusion Region RI-BER......................................

5 J.

Augmented Bolted Connection exams per ISI Code Case N533-1......

5 K.

Augmented System Leakage Test per NUREG - 0578.......................... 5 L.

Additional Augmented Examinations Performed............................. 6 M.

Preservice Examinations on Various Bolting Materials..............

7 N.

Preservice Examinations on Various Piping Welds................................

7

0.

Preservice Examinations on Various Component Supports...................

7 P.

Preservice Examinations on IWE/IWL components.......................... 7 Q.

Erosion / Corrosion UT Thickness Program.....................

8 R.

Functional Testing of Snubbers per T.S. 4.7.9(C)............................... 8 S.

Explanation of the Outage ISI Examination Plan Format.................. 10 T.

List of Acronym's...............

12 Page: iii

A4 SALEM UNIT 2 (RFO#1 5) ISI FINAL

SUMMARY

REPORT

11.

APPENDICES VOLUME 1 A

ISI Exam Plan (S2RFO#15, Rev. 1, 11/17/2006) Pages 1 Thru 165 B

ISI Exam Results (S2RFO#15, Rev. 1, 11/17/2006) Pages 1 Thru 16 C

ISI Flywheel Exam Plan (S2RFO#15, Rev. 0, 11/17/2006) Page 1 D

ISI Flywheel Exam Results (S2RFO#15, Rev. 0, 11/17/2006) Page 1 E

ISI IWE Exam Plan (S2RFO#15, REV. 1 11/17/2006) Pages 1 Thru 80 F

ISI IWE Exam Results (S2RFO#15, REV. 1 11/17/2006) Pages 1 Thru 11 G

Examination Allocation Percentage Review (11/17/2006)

H Class 1, 2 & 3 Exam Limitations Greater Than 10% for the 3rd Interval, 1st Period, 1 st Outage (S2RFO#1 5),

I Revision Data Report for the Second Ten Year Inspection Interval (S2RFO#1 5,)

J PSEG Notifications, Listed by Summary Number (S2RFO#1 5)

K S2RFO#15 OAR Report (Code Case N-532)

L PSEG / Vendor Correspondence (S2RF0#1 5)

M PSEG / VENDOR NDE Procedure Listing N

Certificates of Vendor Personnel Qualifications 0

Consumables Material Certifications P

Equipment Certifications Page: iv

4 SALEM UNIT 2 (RFO#1 5) ISI FINAL

SUMMARY

REPORT II.

APPENDICES (CONT'D VOLUME 2 Q

PSEG R

PSEG S

PSEG T

Team U

PSEG V

WESDYNE VOLUME 3 VOLUME 4 VOLUME 5 Visual Examination Field Data Records Visual Data Records Numerically Assembled By Summary Number.

Visual IWE Examination Field Data Records VT-G Visual Data Records Numerically Assembled By Summary Number.

System Pressure Test Field Data Records System Pressure test Data records Numerically Assembled By Summary Number Field NDE Examinations Field Data Records performed by Team Industrial Numerically Assembled By Summary Number.

Field Snubber Visual Examinations Field Data Records performed by PSEG Numerically Assembled By Exam Number

21 RCP Shaft Ultrasonic Examination Final Report for #21 RCP Shaft Examination performed by Wesdyne Flywheel ExaminationsSection XI In-service Inspection Ten Year Examination Performed By Areva Manual Examinations 2006 Section XI In-service Inspection Final Report Revision 00. For PSE&G Salem Unit 2 Nuclear Generating Station, RFO# 15 (Areva)

Flow Accelerated Corrosion (FAC)

Field Data Records performed by Team Industrial Numerically Assembled By FAC Component Number.

Page: v

40

ý SALEM UNIT 2 (RFO#1 5) ISI FINAL

SUMMARY

REPORT I.

SUMMARY

REPORT During RFO#15, PSEG, Team Industrial, Areva, and Wesdyne personnel performed ISI/NDE examinations of selected Salem Generating Station Unit 2 Class 1, Class 2, Class 3, Class MC, components. These examinations constituted the fifteenth (15th) outage overall and the second outage of the first period of the third interval (3rd Interval 1st Period, 1st Outage 3-1-2) at Salem Unit 2. This final report covers the time period between breaker closure after RFO#1 4 (May 11, 2005) until breaker closure after RFO#1 5 (November 1, 2006).

Containment ISI examinations were conducted in accordance with ASME Section XI IWE/IWL 1998 Edition up through and including 1998 Addenda as amended by the NRC's Safety Evaluation Report (SER). These examinations constituted the first (1st) outage of the third (3rd) period of the first interval (1-3-1) at Salem Unit 2 marking the beginning of the third period of scheduled exams of the First 10- year Inspection Interval.

This final report covers the time period between breaker closure after RFO#14 (May 11, 2005 until breaker closure after RFO#1 5 (November 1, 2006).

This report also contains augmented examinations required by Salem Unit 2 TS and commitments made in response to NRC Regulatory Guides, Circulars and Bulletins and selective preventive maintenance examinations.

Allocation tables are contained in Appendix "G" of this report.

This report is presented, in 4 volumes as follows:

Volume 1 - ISI Salem 2 RFO# 15 Summary Report with Appendices A through P Volume 2 - ISI Salem 2 RFO# 15 Appendixes Q thru V Field Data Reports Volume 3 - ISI Salem 2 RFO# 15 RCP Flywheel Ten Year Exam Report.

Volume 4 - ISI Salem 2 RFO# 15 Manual ISI Exams Final Report (Areva).

Volume 5 - ISI Salem 2 RFO# 15 Flow Accelerated Corrosion (FAC) Field Data Reports.

A.

Applicable Documents ISI/NDE exams were conducted in accordance with the following documents:

Section XI of the ASME Boiler and Pressure Vessel (B&PV) Code, "Rules for Inservice Inspection of Nuclear Power Plant Components", 1998 Edition 2000 Addenda.

Ultrasonic testing requirements were completed in accordance with ASME XI 1998 Edition 2000 Addenda Appendix VIII as amended by the 10CFR50.55a Final Rulemaking.

Page: 1

SALEM UNIT 2 (RFO#15) ISI FINAL

SUMMARY

REPORT Containment Inservice Inspection examinations were conducted in accordance with ASME Section XI IWE/IWL 1998 Edition up through and including 1998 Addenda as amended by the NRC's SER.

Salem Generating Station Unit 2 ISI Program Long Term Plan, Third Interval, Revision 0.

PSEG's Salem Nuclear Generating Station Unit 2, ISI RFO EXAM PLAN (S2RFO#15, REV. 1), Third Interval, First Period, Second Outage.

B.

ISI Section Xl Volumetric & Surface Examinations Performed.

Framatome-ANP, Team Industrial and Wesdyne under the direction of the PSEG ISI Group, conducted twenty-nine (29) manual ultrasonic (UT), seven (7) liquid penetrant (PT), two (2) Magnetic Particle (MT) Examinations, and one (1)

RCP Shaft ultrasonic exam.

PSEG Nuclear applies Risk Informed Inservice Inspection (RI-ISI) of Nuclear Class 1 and 2 Piping Welds, formerly known as ASME Section Xl Exam Category B-F, B-J, C-F-1 and C-F-2. The bases of the Salem Unit 2 RI-ISI Program are documented in the Salem Nuclear Generating Station - Final Report - Risk Informed Inservice Inspection Application (VTD-326046).

During 2R15 ISI NDE examinations were conducted of the following Class 1 and 2 systems and components:

Class 1 Vessels Rx Vessel Shell to Flange and ligaments Pressurizer Steam Generators Piping Reactor Coolant Safety Injection Residual Heat Removal Chemical and Volume Control Class 2 Vessels Steam Generator Piping Feed Water Main Steam Residual Heat Removal Chemical and Volume Control Safety Injection Containment Spray Page: 2

SALEM UNIT 2 (RFO#15) ISI FINAL

SUMMARY

REPORT C.

ISl Section Xl Reactor Vessel Visual (IVVI) Examinations Performed.

Sum#

Component I.D.

Description 931000 IVVI-100 UPPER INTERNALS TO LOWER INTERNALS KEYS 932000 IWI-200 RPV STUD AREA 932100 IVVI-202 CORE BARREL-TO-FLG MATING SURFACES 932150 IVVI-203 VESSEL HEAD ALIGNING KEYS (PINS) 932250 IVVI-205 IRRADIATION SPECIMEN PLUGS (FLG AREA) 933000 IVVI-300 BAFFLE PANEL BOLTS 933050 IVVI-301 DEBRIS SCAN ON CORE BARREL DISTR.

PLATE 933100 IVVI-302 CIRC WELD ABOVE CORE BARREL SHROUD 933250 IVVI-305 TOP OF FORMERS (0 TO 360 DEG.) PLAN VIEW 933300 IVVI-306 INSIDE CORE BARREL TOP FLG-TO-SHELL WELD 933400 IVVI-308 LOWER CORE PLATE (DISTR. PLATE)

FORGING There were no unacceptable exam results identified.

D.,

ISl Section Xl Visual Examinations of Valves and Bolting PSEG's ISI Group conducted ten (10) Class 1 bolting exams. There was no Class 1 valve internal exam.

The following components were examined:

UUz+ýUU 005100 2-RPVCH-WASHERS 1- {

VT-1 Exam of Bolting

~54 022800 24-STG-OMB VT-1 Exam of Bolting 022900 23-STG-OMB T VT-1 Exam of Bolting 023100 21 -STG-OMB T VT-i Exam of Bolting S.............

V T - E x aB 023200 24-STG-IMB VT-1 Exam of Bolting 023500 23-STG-IMB VT-1 Exam of Bolting 023500 ~

................l Ea.0..

.o !ti~ g...........

258250 23SJ56 BOLTING VT-1 Exam of Bolting 258800 24SJ43 BOLTING VT-i Exam of Bolting Page: 3

SALEM UNIT 2 (RFO#1 5) ISl FINAL

SUMMARY

REPORT ISI Section XI examinations were conducted on the following systems:

Safety Injection Reactor Coolant Chemical and Volume Control There were no unacceptable exam results identified.

E.

ISI Section XI Visual Examination of Components Supports PSEG Nuclear's ISI Group conducted five (5) VT-3 visual examinations.

There were no unacceptable indications identified F.

ISI section Xl Visual Examination of Containment Integrity.

PSEG's ISI Group conducted one hundred fifty four (154)

VT-G IWE Visual Examinations There were no unacceptable exam results identified.

G.

ISI Section XI System Leakage Examinations PSEG's ISI Group conducted seventy four (74) System Pressure Tests of System functional or Inservice Test, on Nuclear Class 1, 2, and 3, in accordance with ASME Section XI.

A system leakage exam was performed in accordance with ASME Section XI on all Class 1 Systems. The system leakage test was performed with the Reactor Coolant System in Mode 3 (normal operating pressure) with the insulation installed. No pressure boundary leakage was detected.

Work requests were initiated to correct minor mechanical leakage that was not corrected during the system walk downs.

Page: 4

SALEM UNIT 2 (RFO#1 5) ISI FINAL

SUMMARY

REPORT Class 2 and 3 System Pressure Tests were conducted of the following systems:

Auxiliary Feed Water Component Cooling Containment Spray Control Air Fire Protection Residual Heat Removal Reactor Coolant Station Air Spent Fuel Pool Cooling Safety Injection Sampling Service Water Ventilation Control Waste Liquid There were no unacceptable results Identified.

H.

RCP Flywheel Examination - USNRC Regulatory Guide 1.14 Areva completed required ultrasonic and surface examinations on 21 reactor coolant pump flywheel Serial # 1 S-D003 in accordance with station TS requirements.

There were no unacceptable exam results identified.

1.

Augmented High Energy Piping Welds Risk Informed Break Exclusion Region (RI-BER) (Branch Technical Position MEB 3-1)

PSEG applied Risk Informed Break Exclusion Region (RI-BER) of Nuclear Class 1 and 2 Piping Welds, formerly known as MEB-3-1 Program. The bases of the Salem Unit 2 RI-BER Program are documented in the Salem Nuclear Generating Station - Final Report - Risk Informed Inservice Inspection Application (VTD-326046).

There were no welds examined, during RFO#1 5 to comply with the Risk Informed Break Exclusion Region (RI-BER).

J.

Augmented Bolted Connection Exams-Code Case N 533-1 PSEG's ISI Group conducted eighty-three (83) Class 1 bolted connection VT-2's in accordance with the ISI Long Term Plan Program and Code Case N 533-1.

There were no other unacceptable exam results identified.

K.

Augmented System Leakage Tests per NUREG 0578 "TMI Lessons Learned" PSEG's ISI Group conducted twenty-seven (27) System Leakage Tests in accordance with NUREG 0578 on the following systems:

Safety Injection Chemical and Volume Control Sampling Waste Gas Residual Heat Removal Containment Spray Boron Recovery Waste Liquid Page: 5

SALEM UNIT 2 (RFO#1 5) ISI FINAL

SUMMARY

REPORT There were no unacceptable exam results identified.

L.

Additional Augmented Examinations Performed.

SSum#

T ompnewltD_

Ds~kio'Xt~

ND.E Flux Thimble Tubing Dissimilar 007116 Metal weld FLUX THIMBLE WELDS ON LOWER HEAD VT-2 012520 PZR Inst. Penetrations Instrument Nozzles (4) Top - (4) Bottom VT-2 080010 24 HOT LEG Thermal Welds

24 HOT LEG Thermal Welds VT-2 081210 23 HOT LEG Thermal Welds

23 HOT LEG Thermal Welds VT-2 082210 22 HOT LEG Thermal Welds

22 HOT LEG Thermal Welds VT-2 083310 21 HOT LEG Thermal Welds

21 HOT LEG Thermal Welds VT-2 083410 24 COLD LEG Thermal Welds #24 COLD LEG Thermal Welds VT-2 084410 23 COLD LEG Thermal Welds #23 COLD LEG Thermal Welds VT-2 085610 22 COLD LEG Thermal Welds #22 COLD LEG Thermal Welds VT-2 086510 21 COLD LEG Thermal Welds #21 COLD LEG Thermal Welds VT-2 251555

21 RCP SHAFT

21 Reactor Coolant Pump Shaft UT NO.21 Accumulator Instrumentation Nozzles 734262 2SJE6 Penetrations VT-2 NO.22 Accumulator Instrumentation Nozzles 734263 2SJE7 Penetrations VT-2 NO.23 Accumulator Instrumentation Nozzles 734264 2SJE8 Penetrations VT-2 NO.24 Accumulator Instrumentation Nozzles 734265.

2SJE9 Penetrations VT-2 004672 27.5-RC-1210-5-BMV NO. 21 Cold leg Nozzle to Safe End VT-2 004662 27.5-RC-1220-5-BMV NO. 22 Cold leg Nozzle to Safe End VT-2 004642 27.5-RC-1230-5-BMV NO. 23 Cold leg Nozzle to Safe End VT-2 004652 27.5-RC-1240-5-BMV NO. 24 Cold leg Nozzle to Safe End VT-2 004632 29-RC-1210-1-BMV NO. 21 Cold leg Nozzle to Safe End VT-2 004622 29-RC-1220-1-BMV NO. 22 Cold leg Nozzle to Safe End VT-2 004602 29-RC-1230-1-BMV NO. 23 Cold leg Nozzle to Safe End VT-2 004612 29-RC-1240-1-BMV NO. 24 Cold leg Nozzle to Safe End VT-2 012510 HTR. PENETRATIONS (SPT) Pressurizer Heater Penetrations VT-2 There were no unacceptable exam results identified.

Page: 6

SALEM UNIT 2 (RFO#1 5) ISI FINAL

SUMMARY

REPORT M.

Preservice Examinations of Various Bolting Material Replacements There Were No Pre-Service Visual Bolting Examinations Performed This Outage.

N.

Preservice Examinations of Various Piping Welds Due To Repair/

Replacement / Modifications There Were No Pre-Service Pipe Weld Examinations Performed This Outage.

0.

Preservice Examinations on Various Component Supports and their Associated Integral Attachments Due to Repair/ Replacement /

Modifications One (1) component support or their associated integral attachment were repaired / replaced or modified as identified below:

Preservice Examinations Of Various Component Supports And Their Associated Integral Attachments Due To Repair/ Replacement / Modifications Item #

Sum #

Component I.D.

PSEG DCP PSEJ CJP Order #

1.

203770 2C-23-SIH-875 N/A N/A 50086564 The applicable (PSI) examination was performed with no unacceptable indications identified.

P.

Preservice Examinations on IWE/IWL Component Due to Repair/

Replacement / Modifications One (1) IWE component was repaired / replaced or modified as identified below:

Preservice Examinations Of Various Component Supports And Their Associated Integral Attachments Due To Repair/ Replacement / Modifications Item #

Sum #

Component I.D.

PSEG DCP PSEJ CJP Order #

1.

835700 ALK-S2-100-AIRLOCK N/A N/A 50086564 The applicable (PSI) examination was performed with no unacceptable indications identified.

Page: 7

SALEM UNIT 2 (RFO#1 5) ISI FINAL

SUMMARY

REPORT Q.

Erosion / Corrosion UT Thickness Program In response to NRC Bulletin 87-01 and Generic Letter 89-08, one hundred and thirty nine (139) components were scheduled for UT thickness examinations. The data reports and results can be obtained by contacting the FAC program engineer.

The following components were replaced, due to the results of the erosion/corrosion UT examinations performed.

Erosion / Corrosion UT Thickness Program ITEM SYSTEM COMPONENT ID COMPONENT NO.

DESCRIPTION

1.

MSR Drain 2S-MSR-336-L1 4" Elbow MSR Drain 2S-MSR-399-L1 2" Elbow MSR Drain 2S-MSR-316-Li 4" Elbow The following is a break down of these examinations.

Three (3) components were replaced.

One hundred thirty six (136) were acceptable for continued service, based'on minimum wall design requirements.

" No components required a weld build-up.

The following components were replaced as a result of low readings obtained during Salem 2 RFO#14 outage.

FC Component ID Description SysteZm tfw A24 2S-HD-437A-V2 12"X10" Reducer

21 HD Pump Discharge C88 2S-MSR-323-T1 4" Tee MSR Drain F33 RD-2S-SGB-31 0-T1 6" Tee Steam Generator Blow Down K01 2S-HW-616-Ri 6"x4" Reducer Heating Water M52 2S-C03-T1 24"x1 8" Tee Condensate M 1i5 2S-C-480-B1 18" Bend Condensate N51 20SGF-1 -T1 18"xl 4" Reducer Steam Generator Feedwater N86 2-SGF-28-Bl 14" Bend Steam Generator Feedwater J37 2S-RS-1 093-Li 1 Y2" Elbow Turbine Drain There were no other unacceptable exam results identified.

R.

Functional Testing Of Selected Snubbers-Technical Specification 4.7.9 (C)

LARGE BORE REXNORD HYDRAULIC SNUBBERS Hydraulic snubbers were removed or modified during the Steam Generator Page: 8

SALEM UNIT 2 (RFO#15) ISI FINAL

SUMMARY

REPORT Snubber elimination project design change:

" Eight (8) S/G 1,000 Kip -Rexnord Removed From Service Eight (8) S/G 1,000 Kip -Rexnord Removed Modified to Limit Stops There were no degraded and or failed snubbers identified during Visual Examinations.

LISEGA HYDRAULIC SNUBBERS Lisega snubbers were tested using the Technical Specification 4.7.9(c), 10%

sample plan using the Wyle Laboratories Model 150 snubber test machine as follows:

Twelve (12) Lisega small snubber There were no degraded and or failed snubbers identified during testing.

All inaccessible Unit 2 Snubbers were visually examined per Salem Unit 2 TS Section. 4.7.9.

Examination results were found satisfactory.

Page: 9

SALEM UNIT 2 (RFO#15) ISI FINAL

SUMMARY

REPORT Date:

Section S Salem Unit 2 Nuclear Generating Station ISI Proaram Lona Term Plan Third Interval Class I Comnonents Page:

Revision:

~'$~nna

~Corlpnpoet ID 2

Description GruMisc.

Info Planit ISO#

IS2 I~SO #<

MEAS Cat ASME It~em ýASME Clas Systernm Examination Method~

(6)

(7)

(8)

(9)

(10

11)

(12)

12)

T 12)

Com~ments (13)

(14) 1st Interval 2nd Interval 3rd Interval 4th Interval SCOPE I

2nd Period }3,Peibdod 1st Period 2nd Pei*d' 3rd Period 1PSt*eriod 2nd Period 3rd Period 1 st Period.nid Pr!iqd 3rd Period SIl AUG OWN PRE 1) 2)

3) 4)

5) 6)

7)

Unique Reference Number.

ISI Program Component Identification Number Component Description/ Configuration Component Group Designation Miscellaneous Information-Hanger Detail No., Calibration Block No.

Construction Isometric No.

IS[ Sketch No.

8) ASME Section XI Examination Category Designation

9) ASME Section XI Examination Item Number

10) ASME Classification

11) System Designation

12) NDE Exam Method

13) Comments-Exam Limitation/Coverage, Additional Instructions

14) Examination History (Interval/Period/Outage)

Page: 10

SALEM UNIT 2 (RFO#1 5) ISI FINAL

SUMMARY

REPORT IDDEAL Concepts ISI Program Scheduling Identifiers Scheduled Completed Re-scheduled Expanded Additional Expanded Scope "s"

To schedule a component, place the identifier "s" in the required period/outage.

"c" Upon exam completion for a scheduled component and by uploading the outage scope from IDDEAL back to Schedule Works, an 's" will be updated to completed "c".

"r" Once a component has been scheduled, and you wish to reschedule to another outage, replace the scheduled "s" with a rescheduled "r" and enter an "s" in the new outage schedule.

"e" To increase a work scope without taking code credit in the percentage calculations, enter an expanded "e".

"E" Upon exam completion of an expanded scope and by either uploading the outage scope from IDDEAL or manually changing the letter to an upper case "E" the exam scope is completed.

"a" After an initial expanded work scope has been identified and you wish to add an increased expanded work scope, enter an additional expanded scope "a".

"A" Upon exam completion of an additional expanded scope and by either uploading the outage scope fro IDDEAL or manually changing the letter to an upper case "A" the exam scope is completed.

p To track partially completed component examination requirements enter a partial "p".

"d" Once a component has been scheduled, and you wish to defer the inspection to another Outage, or Period, replace the scheduled 's" with a deferred "d" and enter an "s" in the new Outage.

IT.

To track limited component examinations or limited completions of requirements enter "I".

"b" For multiple scheduling of the same component in successive Outages or Periods within an Interval enter "b".

"B" Upon exam completion of a multiple scope in the same Interval and by either uploading the outage scope from IDDEAL or manually changing the letter to an upper case "B" the exam scope is completed. This multiple scheduling scope will not count as complete "t"

To track exam scopes or use as reminder or identifier to confirm scheduling enter "t'.

Partial Deferred Limited Multiple Tickler Successive "h"

Successive examinations.

( Code Required Re-Exams )

"H" Upon exam completion of a successive scope and by either uploading the outage scope from IDDEAL or manually changing the letter to an upper case "H" the exam scope is completed.

Page: 11

SALEM UNIT 2 (RFO#1 5) ISI FINAL

SUMMARY

REPORT T.

List of Acronym's ABBREVIATION A-E AF ASME BF BIT BR CA CC CCW CHR CRC CRD CS CW CV DG DR ECCS EXAM FO DESCRIPTION AUGMENTED EXAM AUXILIARY FEEDWATER SYSTEM AMERICAN SOCIETY OR MECHANICAL ENGINEERS STEAM GENERATOR MAIN FEEDWATER SYSTEM BORIC ACID INJECTION TANK BORIC ACID RECOVERY SYSTEM CONTROL AIR SYSTEM COMPONENT COOLING SYSTEM COUNTER CLOCK WISE CONTAINMENT HEAT REMOVAL SYSTEM CORROSION RESISTANT CLAD CONTROL ROD DRIVE CONTAINMENT SPRAY SYSTEM CLOCK WISE CHEMICAL VOLUME AND CONTROL SYSTEM DIESEL GENERATORS AND AUXILIARIES DEMINERALIZED WATER - RESTRICTED EMERGENCY CORE COOLING SYSTEM EXAMINATION DIESEL GENERATOR FUEL OIL SYSTEM Page: 12

SALEM UN C.

List of Acronym's (Cont'd ABBREVIATION FB FLG FP FW GB HT IA INSIG ISI LD LDI IT 2 (RFO#1 5) ISI FINAL

SUMMARY

REPORT DESCRIPTION FLANGE BOLTING FLANGE FIRE PROTECTION SYSTEM MAIN FEED WATER PUMP & PIPING STEAM GENERATOR BLOWDOWN SYSTEM HEAD TANK INTEGRAL ATTACHMENT INSIGNIFICANT INSERVICE INSPECTION LONGITUDINAL SEAM WELD EXTENDING DOWNSTREAM LONGITUDINAL SEAM WELD EXTENDING DOWNSTREAM ON THE INSIDE RADIUS OF AN ELBO LONGITUDINAL SEAM WELD EXTENDING DOWNSTREAM ON THE OUTSIDE RADIUS OF AN ELBOW LUGS ZERO REFERENCE LOCATION LONG TERM PLAN LONGITUDINAL SEAM WELD EXTENDING UPSTREAM LONGITUDINAL SEAM WELD EXTENDING UPSTREAM ON THE INSIDE RADIUS OF AN ELBOW LONGITUDINAL SEAM WELD EXTENDING UPSTREAM ON THE OUTSIDE RADIUS OF AN ELBOW LDO LGS LO LTP LU LUI LUO Page: 13

SALEM UNIT 2 (RFO#1 5) ISI FINAL

SUMMARY

REPORT

f.

List of Acronym's (Cont'd)

ABBREVIATION DESCRIPTION MS MAIN STEAM SYSTEM M-UT MECHANIZED ULTRASONIC EXAMINATION MT MAGNETIC PARTICLE EXAMINATION NDE NONDESTRUCTIVE EXAMINATION NDT NONDESTRUCTIVE TESTING NPS NOMINAL PIPE SIZE NRC NUCLEAR REGULATORY COMMISSION PR PRESSURIZER RELIEF SYSTEM PS PRESSURIZER SPRAY SYSTEM PSAR PRELIMINARY SAFETY ANALYSIS REPORT PSEG PSEG NUCLEAR LLC PSI PRESERVICE INSPECTION PT LIQUID PENETRANT EXAMINATON PZR PRESSURIZER RC REACTOR COOLANT SYSTEM RCP REACTOR COOLANT PUMP REV REVISION RHR RESIDUAL HEAT REMOVAL SYSTEM RPV REACTOR PRESSURE VESSEL RPVCH REACTOR PRESSURE VESSEL CLOSURE HEAD Page: 14

SALEM UNIT 2 (RFO#1 5) ISI FINAL

SUMMARY

REPORT List of Acronym's (Cont'd)

ABBREVIATION DESCRIPTION RX SCAN PLAN SA SF SJ SW UFSAR UT VT WL REACTOR MECHANIZED EXAMINATION PLAN STATION AIR SYSTEM SPENT FUEL POOL COOLING & FILTERING REFUELING CANAL

& FUEL TRANSFER TUBE SPENT FUEL POOL SAFETY INJECTION SYSTEM SERVICE WATER SYSTEM UPDATED FINAL SAFETY ANALYSIS REPORT MANUAL ULTRASONIC EXAMINATION VISUAL EXAMINATION WASTE LIQUID SYSTEM Page: 15

LR-N07-0016 Salem Unit 2 2R15 Examination Results

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO-15 ISI Examination Results Page 1 of 17 Revision 1 I

Q~nntI

[

Lioppn JNDE[ Sjt4us 4 41 1ei1t¶1 oments 2-RPV-7442 VESSEL TO FLANGE UT-7 Accept Examination performed by AREVA qualified personnel 4

4-4 002701 2-RPV-7442 IVESSEL TO FLANGE UT-12 Accept Examination performed by AREVA qualified personnel 4-4-

4-2-RPV-7442 VESSEL TO FLANGE UT-2 Accept Examination performed by AREVA qualified personnel

+

~

29-RC-1230-1 NOZZLE TO SAFE-END jUT-0 Accept Examination performed by AREVA qualified personnel 004600

+

004602 29-RC-1230-1-BMV NOZZLE TO SAFE-END VT-2 Accept Examination performed by AREVA qualified personnel SDH's 1/4T, 112T, 3/4T unavailable from clad side of block 109-SAM. Used SDH's at the following depths for calibration from cladding, 21.25", 26.75" and 32.25" SDH's 1/4T, 1/2T, 3/4T unavailable from clad side of block 109 SAM. Used SDH's at the following depths for calibration from cladding, 21.25", 26.75" and 32.25" SDH's 1/4T, 1/2T, 3/4T unavailable from clad side of block 109-SAM. Used SDH's at the following depths for calibration from cladding, 21.25", 26.75" and 32.25" Thickness & Contorour's readings taken on nozzle to safe-end weld.

BMV Inspection performed as PerW.MRP-139 looking for evidence of leakage.

Thickness & Contorour's readings taken on nozzle to safe-end weld.

BMV Inspection performed as Per. MRP-139 looking for evidence of leakage.

Thickness & Contorour's readings taken on nozzle to safe-end weld.

BMV Inspection performed as Per. MRP-139 looking for evidence of leakage.

Thickness & Contorour's readings taken on nozzle to safe-end weld.

BMV Inspection performed as Per. MRP-139 looking for 004610 29-RC-1240-1 NOZZLE TO SAFE-END UT-0 Accept Examination performed by AREVA qualified personnel 004612 29-RC-1240-1-BMV NOZZLE TO SAFE-END VT-2 Accept Examination performed by AREVA qualified personnel 004620 29-RC-1220-1 NOZZLE TO SAFE-END UT-0 Accept Examination performed by AREVA qualified personnel 004622 29-RC-1220-1-BMV NOZZLE TO SAFE-END VT-2 JAccept Examination performed by AREVA qualified personnel 004630 004632 29-RC-1210-1 29-RC-1210-1-BMV NOZZLE TO SAFE-END NOZZLE TO SAFE-END UT-0 VT-2 Accept Accept Examination performed by AREVA qualified personnel Examination performed by AREVA qualified personnel 4

004640 j27.5-RC-1230-5 NOZZLE TO SAFE-END UT-0 004642 27.5-RC-1230-5-BMV NOZZLE TO SAFE-END VT-2 004650 1 004652 004660 27.5-RC-1 240-5 27.5-RC-1 240-5 NOZZLE TO SAFE-END NOZZLE TO SAFE-END VT-2 UT-0 VT-2 UT-0 VT-2 Accept Accept Accept Accept Accept Accept Accept Examination performed by AREVA qualified personnel w{

Br Examination performed by AREVA qualified personnel ev Exam Performed by certified PSEG personnel.

V Th Examination performed by AREVA qualified personnel w

idence of leakage.

hickness & Contorour's readings taken on nozzle to safe-end eld.

MV Inspection performed as Per. MRP-139 looking for idence of leakage.

T-2 Exam performed during class 1 walkdown hickness & Contorour's readings taken on nozzle to safe-end eld.

MV Inspection performed as Per. MRP-139 looking for 27.5-RC-1240-5-BMV 27.5-RC-1220-5 27.5-RC-1220-5 NOZZLE TO SAFE-END NOZZLE TO SAFE-END NOZZLE TO SAFE-END 004662 27.5-RC-1220-5-BMV INOZZLE TO SAFE-END 004670 27.5-RC-1210-5 NOZZLE TO SAFE-END 27.5-RC-1 210-5 JNOZZLE TO SAFE-END VT-2 Accept UT-0 Accept VT-2 Accept Examination performed by ARE VA qualified personnel evidence of leakage.

Exam. Performed by certified Team Industrial Thickness & Contorour's readings taken on nozzle to safe-end Personnel.

weld.

Exam Performed by certified PSEG personnel.

VT-2 Exam performed during class 1 walkdown Exam. Performed by certified Team Industrial BMV Inspection performed as Per. MRP-139 looking for Personnel.

evidence of leakage.

Exam. Performed by certified Team Industrial Thickness & Contorour's readings taken on nozzie to saie-endI Personnel.

1weld.

Exam Performed by certified PSEG personnel.

VT-2 Exam performed dIuring class 1 walkdown

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO-I5 ISI Examination Results Page 2 of 17 Revision 1 S I7 I#K Corn onentI ib Des crinpti o 7N6E Statst~I

~

Remarks 047 27RC11--M JZETSFENj jcp ~

Exam. Performed by certified Team Industrial 004672 J27.5-RC-1 210-5-BMV NOZZLE TO SAFE-ENDL \\7F-.2 Accep.t Personnel.

VT-1 2-RPVCH-NUTS 1-54 CLOSURE NUTS Accept 004900

+

4 4

4 2-RPVCH-NUTS 1-54 CLOSURE NUTS THREADS-] N-FLANGE (LIGAMENTS)

VT-1 UT-0 005000 005100 2-RPV-LIG 1-54 2-RPVCH-WASHERS 1-54 Accept Accept Accept Examination performed by AREVA qualified personnel Exam Performed by certified Team Industrial Personnel Examination performed by AREVA qualified personnel Exam Performed by certified Team Industrial Personnel CLOSURE WASHERS VT-1 4

4

.1.

-4.

2-RPVCH-WASHERS 1-54 CLOSURE WASHERS VT-1 Accept

4.

4 4

4 4-PRN-1200-IRS RELIEF NOZZLE 4

UT-70' UT-70' 4-PRN-1200-IRS RELIEF NOZZLE 011200

+

-1'

+

Accept Accept Accept Accept 4-PRN-1200-IRS RELIEF NOZZLE UT-60 UT-70' 4-PRN-1200-IRS RELIEF NOZZLE 4

4 4

4 6-PRN-1205-IRS RELIEF NOZZLE UT-60 jAccept Examination performed by AREVA qualified personnel Examination performed by AREVA qualified personnel Examination performed by AREVA qualified personnel Examination performed by AREVA qualified personnel Examination performed by AREVA qualified personnel Examination performed by AREVA qualified personnel Examination performed by AREVA qualified personnel Examination performed by AREVA qualified personnel Examination performed by AREVA qualified personnel Exam Performed by certified PSEG personnel.

Exam Performed by certified PSEG personnel.

4 Inspection performed as Per. MRP-139 looking for nce of leakage.

Exam performed onnuts #7, 8, 9,10,11, 12,13, 14,15" 7 and18 Exam performed on nuts # 101, 102, 103, 304, 105 and n performed in ligaments #1 thru 20. Scanned diameter of ents plus 1" Exam performed on Washers #1, 2, 3, 4, 5, and 6 Exam performed on Washers # 7, 8, 9, 10, 11, 12, 13, 14, 6, 17 and 18 ned in accordance with EPRI model. Maintained 10% to ID clad roll. Combined coverage 93.5%.

ned in accordance with EPRI model. Maintained i0% to ID clad roll. Combined coverage 93.5%.

ination limited due to insulation bracket. Scanned in rdance with EPRI model. Combined coverage 93.5%.

nination limited due to insulation bracket. Scanneed in rdance with EPRI model. Combined coverage 93.5%.

nination limited due to insulation brackets. Scanned in rdance with EPRI model. Combintion coverage 92.5%.

nination limited due to insultion bracket. Scanned in rdance with EPRI model. Combination coverage 92.5%.

ned in accordance with EPRI model. Maintained 10% to ID clad roll throughout examination. Combined coverage

%/.

med in accordance with EPRI model. Maintained 10/% to ID clad roll throughout examination. Combined coverage n performed during class 1 walkdown.

rn performed during class 1 walkdown.

n performed during class 1 walkdown.

rn performed during class 1 walkdown.

Exam Performed to Code Case N-533-1 Examination Performed to detect leakage from i

surizer heater sleeves as Per. Westinghouse Advisory 6-PRN-1205-IRS RELIEF NOZZLE UT-70 jAccept 011500 6-PRN-1205-IRS RELIEF NOZZLE UT-45 Accept 6-PRN-1205-IRS RELIEF NOZZLE UT-45 jAccept VT-2 Accept 011810 76-PR-1204-1 NOZZLE TO SAFE-END 011820 6-PR-1203-1 NOZZLE TO SAFE-END VT-2 Accept 011830 4-PR-1200-1 NOZZLE TO SAFE-END VT-2 Accept 011851 4-PS-1231-33 NOZZLE TO SAFE-END VT-2 Accept 012500 2-PZR-MB 1-16 MANWAY BOLTS VT-2 Accept HTR. PENETRATIONS (SPT) 012510 PARTIAL PENETRATION WELDS IN HEATER PEN.

Instrument Nozzles (4)

Top - (4) Bottom VT-2

[Accept 012520 Exam Performed by certified PSEG personnel.

Letter NSAL 8 Rev. 1 VT-2 Exam Performed to detect leakage in dissimilar metal Exam Performed by certified PSEG personnel.

welds.

PZR Inst. Penetrations VT-2 Accept 012520 PZR Inst. Penetrations VT-2

[Accept

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO-15 ISI Examination Results Page 3 of 17 Revision 1

[ Sumn#Y Componentld7J 9Desciption9 ND Si W ILOWER HEADTO TUBE I Remarks~

22-STG-LHTS SHEET UT-60 Accept Examination performed by AREVA qualified personnel 020300 22-STG-LHTS LOWER HEAD TO TUBE SHEET UT-45 Accept I Examination performed by AREVA qualified personnel LOWER HEAD TO TUBE SHEET ID notch at 80% at 7.0 screen divisions at 55.7 db. Same coverage obtained as to previous data.

Obtained same coverage as previous exmination. 49.7 db required to resolve ID Notch @ 80% ID Notch at 7.9 screen divsions.

Scanned WRV only. Lamination scan performed previously.

Obtained same coverage as previous examinaiton.

V--2 Exam.Performed to Code Case N-533-1 j VT-1 exam performed on bolting in-place and under tension VT-1 exam performed on bolting in-place and under tension 22-STG-LHTS UT-0 Accept I

I OUTLET MANWAY BOLTING 24-STG-OMB VT-2 022800 OUTLET MANWAY BOLTING 24-STG-OMB 022900 023000 23-STG-OMB 23-STG-OMB 22-STG-OMB OUTLET MANWAY BOLTING OUTLET MANWAY BOLTING OUTLET MANWAY BOLTING VT-i VT-i VT-2 Accept Accept Accept Accept Examination performed by AREVA qualified personnel Exam Performed by certified PSEG personnel.

Exam Performed by certified PSEG personnel.

VT-2 jAccept 21-STG-OMB 023100 i

OUTLET BOLTIN(

OUTLET BOLTINI 21-STG-OMB MANWAY G

MANWAY G

IANWi6AY G

IANWAY VT-2 VT-i VT-2 Accept Accept Accept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 Exam Performed by certified PSEG personnel.

VT-1 exam performed on bolting in-place and under tension Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-I 023200 023300 023400 023500 INLET M 24-STG-IMB BOLTIN(

INLET M 24-STG-IMB JBOLTING INLET MANWAY 23-STG-IMB BOLTING INLET MANWAY 23-STG-IMB BOLTING INLET MANBWAY 22-STG-IMB BOLTING INLET MANWAY 21-STG-IMB BOLTING IINLET MANWAY 21-STG-IMB iBOLTING INTEGRAL 6-PR-1205-5PS-1&2

'ATTACHMENT 6-PR-1205-6 ELBOW TO PIPE 6-PR-1205-6 1

ELBOW TO PIPE VT-1 VT-1 VT-2 VT-2 VT-2 VT-1 PT UT-45 LUT-60 Accept Exam Performed by certified PSEG personnel.

VT-i1 exam performed on bolting in-place and under tension Accept Exam Performed by certified PSEG personnel.

VT-1 exam performed on bolting in-place and under tension Accept Exam Performed by certified PSEG personnel.

eVT-2 Exam Performed to Code Case N-533-1 Accept Exam Performed by certified PSEG personnel.

VT-2 Exam Performed to Code Case N-533-1 Accept Exam Performed by certified PSEG personnel.

1VT-2 Exam Performed to Code Case N-533-1 Accept Exam Performed by certified PSEG personnel.

VT-1 exam performed on bolting in-place and under tension Accept Examination performed by AREVA qualified personnel Variable support lug elbow weld.

Accept Examination performed by AREVA qualified personnel None Accept Examination performed by AREVA qualified personnel None 050455 050600

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO-15 ISI Examination Results Page 4 of 17 Revision 1 Su# CrnoetIDDsrpto 1E I St~

Remrk Comments FLANGE BOLTING 051100 6-PR-1205-10FB (2PR5)

VT-2 'Accept Exam Performed by certified PSEG personnel.

VT-2 Exam Performed to Code Case N-533-1 FLANGE BOLTING 052300 6-PR-1204-10FB (2PR4)

VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 Exam Performed to Code Case N-533-1 FLANGE BOLTING c

053700 6-PR-1203-10FB (2PR3)

VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 Exam Performed to Code Case N533-1 24 HOT LEG Thermal

24 HOT LEG Thermal VT-2 Exam Performed to detect leakage in dissimilar metal 080010 Welds Welds VT-2 Accept Exam Performed by certified PSEG personnel.

welds.

23 HOT LEG Thermal

23 HOT LEG Thermal

\\-T-2 Exam Performed to detect leakage in dissimilar metal 081210 Welds Welds VT-2 Accept Exam. performed by certified PSEGPersonnel welds.

4 22 HOT LEG Thermal

22 HOT LEG Thermal

.VT-2 Exam Performed to detect leakage in dissimilar metal 082210 Welds Welds VT-2 Accept Exam Performed by certified PSEG personnel.

welds.

i 21 HOT LEG Thermal

21 HO-T LEG Thermal VT-2 Exam Performed to detect leakage in dissimilar metalI 083310 Welds Welds VT-2 Accept Exam Performed by certified PSEG personnel.

welds.

24 COLD LEG Thermal

24 COLD LEG Thermal VT-2 Exam Performed to detect leakage in dissimilar metal 083410 Welds Welds VT-2 Accept Exam Performed by certified PSEG personnel.

welds.

-23 COLD LEG Thermal

23 COLD LEG Thermal mdVT-2 Exam Performed to detect leakage in dissimilar metal 084410 Welds Welds VT-2 Accept Exam Performed fiedPSEG personnel welds.

22 COLD LEG Thermal

22 COLD LEG Thermal VT-2 Exam Performed to detect leakage in dissimilar metal 085610 Welds Welds VT-2 Accept "

Exam Performed by certified PSEG personnel.

welds.

21 COLD LEG Thermal

21 COLD LEG Thermal j VT-2 Exam Performed to detect leakage in dissimilar metal 086510 Welds IWelds VT-2 Accept Exam Performed by certified PSEG personnel.

welds.

jNCD examinaion performed from downstream side only, due toI 10-SJ-1241-14 TEE TO PIPE UT-45 Accept Examination performed by AREVA qualified personnel cast tee confiuration.

NCD Examination performed from downstream side only, due 161200 10-SJ-1241-14 TEE TO PIPE UT-60 Accept Examination performed by AREVA qualified personnel to cast configuation.

NCD Examination performed from downstream side only, due 10-SJ-1241-14 TEE TO PIPE UT-60

_Accept I Examination performed by AREVA qualified personnel to cast tee configuration.

NDExaminatiion performed from downstream side only, due 10-SJ-1211-15 TEE TO PIPE UT-45 Accept Examination performed by AREVA qualified personnel to cast tee configuration.

NCD Examination performed from downstream side only, due 1164900 10-SJ-1211-15 TEE TO PIPE UT-60 Accept Examination performed by AREVA qualified personnel cast tee configuration.

NCD Examination performed from downstream side only, due 10-SJ-1211-15 ITEE TO PIPE UT-60 Accept Examination performed by AREVA qualified personnel to cast tee configuration.

10-SJ-1211-18 ELBOW TO PIPE UT-60 Accept Examination performed by AREVA qualified personnel None 161010-SJ-1211-18 fELBOW TO PIPE UT-45 Accept Examination performed by AREVA qualified personnel None 10-SJ-1211-18 ELBOWTO PIPE UT-60,Accept Examination performed by AREVA qualified personnel None 10-SJ-1211-19

-PIPE TO ELBOW UT-620Accept

!Examination performed by AREVA qualified personnel None

11/17/2006 Salem Nuclear.Generating Station, Unit 2 ISI Program Long Term Plan RFO-15 ISI Examination Results Page 5 of 17 Revision 1 Ls S1 =1# I Compo~nt ID Descrptio NDE~

1620 f1 -SJ-1 211-19 1PIPE TO ELBOW IUT-45 *1 Sýýtus Comments I

Remarks 10-SJ-1211-19 ULT-60 iAccept SAccept Examination performed by AREVA qualified personnel None PIPE TO ELBOW Examination performed by AREVA qualified personnel JNone

-4 10-SJ-1211-20

!ELBOW TO PIPE UT-60 UT-60 Accept Accept Examination performed by ARE VA qualified personnel lNone Examination performed by AREVA qualified personnel None 165250 10-SJ-1211-20 ELBOW TO PIPE ation performed by AREVA qualified personnel-I 4

10-SJ-1211-20 ELBOW TO PIPE UT-45 183550 3-SJ-1292-15 PIPE TO PIPE PT 183700 3-SJ-1292-16 PIPE TO VALVE 2SJ150 1 PT Accept Accept Examination performed by AREVA qualified personnel Exam. Performed by certified Team Industrial Personnel.

Exam. Performed by certified Team Industrial Personnel.

Exam Performed by certified PSEG Personnel

-None None This component subject to external chloride stress corrosion cracking (ECSCC) Exam performed on weld #15 and 2 1/2 Dia.

Which starts at containment penetration #42 andcontinues downstream 7 1/2" This component subject to external chloride stress corrosion cracking (ECSCC) Exam performed on weld #16 and 2 1/2 Dia.

Which starts at valev 2SJ 150 and proceeds upstream 7 1/2".

VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 lAccept 184200 2-SJ-1249-2FB 186700 2-SJ-1247-4FB

-I.

FLANGE BOLTING FLANGE BOLTING (NEAR, 24SJ138)

FLANGE BOLTING (NEAR, 23SJ143)

FLANGE BOLTING FLANGE BOLTING VT-2 Accept IExam Performed by certified PSEG personnel.

I VT-2 188000 189800 191000 2-SJ-1239-2FB 2-SJ-1237-7FB 2-SJ-1229-2FB 193350 12-SJ-1228-2FB IFLANGE BOLTING 196400 196450 196500 198350 200300 200350 200400 2-SJ-1219-1 2-SJ-1219-2 2-SJ-1219-2FB 2-SJ-1218-5FB 1.5-SJ-1 242-6 1.5-SJ-1242-7 1.5-SJ-1242-8 TEE TO PIPE PIPE TO FLANGE FLANGE BOLTING FLANGE BOLTING PIPE TO ELBOW ELBOW TO PIPE PIPE TO FLANGE VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VTI-2 Accept Accept Accept Accept Accept Accept Accept Accept Accept Accept Accept Accept Accept Accept Accept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 Exam Performed by certified PSEG personnel.

Exam performed during class 1 walkdown.

Exam Performed by certified PSEG personnel.

Exam performed during class 1 walkdown.

Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 Exam Performed by certified PSEG personnel.

-VT-2 Exam.Performed to Code Case :N-533-1 Exam Performed by certified PSEG personnel.

Exam performed during class 1 walkdown.

Exam Performed by certified PSEG personnel.

None Exam Performed by certified PSEG personnel.

None Exam Performed by certified PSEG personnel. __

VT-2 Exam.Performed to Code Case N-533-1 Exam Performed by certified PSEG personnel.

None Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 xVT-3 Exam performed. Hanger Satisfactory for Continued Exam Performed by certified PSEG personnel.

Operation

'E-xamPe-rfo~r-med by -certified P-SEG pe-rsonne'l.

[VT-2 Exam.Performed to Code Case N-533-1 200450 11.5-SJ-1242-8FB 200500 11.5-SJ-1242-9 200550 202700 1.5-SJ-1242-10 1.5-SJ-1232-10FB FLANGE BOLTING FLANGE TO PIPE PIPE TO VALVE 24SJ388 FLANGE BOLTING VAR.SUPPORTTYP.AS Z1,CL-107,HL-102 FLANGE BOLTING 2)3770 2C-23-SIH-875 204700 1.5-SJ-1222-13FB VT-3 JAccept VT-2 j-Accept

11/17/2006 Salem Nuclear Generating Station, Unit 2 Page 6 of 17 ISI Program Long Term Plan Revision 1 RFO-15 ISI Examination Results Sjn1#

Copnn ID

~Descript nion NE I SR Coumments 206950 1.5-SJ-1212-8FB FLANGE BOLTING VT-2 yAccept Exam Perormed by certifed PSEG personnel.

VT-2 ExamPerformed to Code Case N-533-1 250100 24-PMP-BOLTS 1-24 BOLTING VT-2 Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 250200 23-PMP-BOLTS 1-24 BOLTING

-,VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 250300 22-PMP-BOLTS 1-24 BOLTING VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 *ECxamPe0rmed to Code Case N-533-1 250400 21-PMP-BOLTS 1-24 BOLTING VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1

21 Reactor Coolant 251805

21 RCP SHAFT Pump Shaft UT-0 Accept..

Exam Performed by certified Wesdyne personnel.

UT Exam performed on #21 RCP Shaft ID # 979-933D303 255050 2CV2 BOLTING NON LINE 3-CV-1243 VT-2 Accept Exam Performed by certified PSEG persone.

VT-2Exam.Performed to Code Case N-533-1 ONLINE 3-CV-1243 255100 2CV277 BOLTING (FIG. A-10)

VT-2 jAccept Exam Perfomed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 ON LINE 3-CV-1241

[Exam.e.r..e...N 1

255150 2CV79 BOLTING (FIG. A-12)

VT-2 Accept Exam. Performed by certified PSEG Personnel VT-2 Exam.Performed to Code Case N-533-1 ON LINE 3-CV-1 241 255200 2CV275 BOLTING (FIG. A-12)

VT-2 Accept a

Performed by certified PSEG personnel.

VT-2 ExarnPerformed to Code Case N-533-1 ON LINE 3-CV-1241 255250 2CV80 BOLTING (FIG. A-12)

VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 ON LINE 3-CV-1231 255300 2CV77 BOLTING (FIG. A-13)

VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 ON LINE 3-CV-1231 255350 2CV274 BOLTING (FIG. A-13)

VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 ExamPerformed to Code Case N-533-1 ON LINE 3-CV-1231 I

255400 2CV78 BOLTING (FIG. A-13)

VT-2 Accept lExam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 ON LINE 2-CV-1275 255450 2CV75 BOLTING (FIG. A-15 SHT 1)

VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 ExamPerformed to Code Case N-533-1 ON LINE 6-PR-1205 255550 2PR5 BOLTING (FIG. A-17)

VT-2 IAccept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 BOLTING ONULNE 6-PR-1204-,________

255600 2PR4 BOLTING (FIG. A-18)

VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 ExamPerformed to Code Case N-533-1 ON LINE 6-PR-1203 255650 2PR3 BOLTING (FIG. A-19)

VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2Exam.Performed to Code Case N-533-1 ON LINE 3-PR-1207 255675 2PR7 BOLTING (FIG. A-20)

VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 ON LINE 3-PR-1207 255700 2PR2 BOLTING (FIG. A-20)

VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 2557252PR6 ~~~~~~~~

~

G 4

VT-

.V-2Eae..mdt.Cd aeN ON LINE 3-PR-1206 25575 2PR BOLTING FGA-24)

VT-2 Accept Exam.Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 ON75 LPIBLTN FIN GA-4-P-231 2

Accept lExam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case~

N-3

-1 ON LINE 4-PS-1231 V

P 255800 2PS28 BOLTING (FIG. A-26 SliT 2)

VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 ON LINE 4-PS-1231 ce'[

L255850 2PS3 BOLTING (FIG. A-26 SHT 2T2 (cet L

mPefre ycriie SGpronl VT-2 Exam.Performed to Code Case N-533-1

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO-15 ISI Examination Results Page 7 of 17 Revision 1 Corn poiie Do

escid*o

Status<,4 ON LINE 4-PS-I 231-255900 2PS29 BOLTING (FIG. A-26 SHT 3)

VT-2 Accept ON LINE 4-PS-1211 255950 2PS24 BOLTING (FIG. A-28)

VT-2 Accept ION LINE 4-PS-121 1 255975 2PS1 BOLTING (FIG. A-28)

VT-2 Accept 2ON LINE 4-PS-1)2 c

256000 2PS25 BOLTING

{(FIG. A-28)

VT-2 Accept O0N LINE 14-RH-i1211 257850 2RH1 BOLTING (FIG. A-61)

VT-2 Accept ON LINE 14-RH-1211 257900 2RH2 BOLTING j(FIG. A-61)

VT-2 Accept ON LINE 12-RH-i1251 Ii xam,y iieda k s

o Exam Performed by certified PSEG personnel.

Exam Performed by certified PSEG personnel.

257950 258000 2RH26 BOLTING 24SJ54 BOLTING (FIG. A-62)

ON LINE 10-SJ-1241 (FIG._A-63)

ON ~LINE 10-SJ-1 241 VT-2 jAccept 258050 24SJ55 BOLTING (FIG. A-63)

ION L

-INE 10-SJ-1241 258100 24SJ56 BOLTING (FIG. A-63)

ON LINE 10-SJ-1231 258200 23SJ55 BOLTING

!(FIG. A-64)

ON LINE 10-SJ-1231 258200 3SJ56 BOLTING (FIG. A-64) 1ON LINE 10-SJ-1 231 23SJ56 BOLTING (FIG. A-64)

ON LINE 10-SJ1-11221 258300 22SJ54 BOLTING (FIG. A-65)

ON LINE 10-SJ-1221 258350 22SJ55 BOLTING (FIG. A-65)

ON LINE 10-SJ-1221 2 5 8 4 0 0 22SJ56 BOLTING (FIG. A-65)

ON LINE 10-SJ-1211 258450 21SJ54BOLTING (FIG. A-66)

ON LINE 10-SJ-1211 258500 21SJ55 BOLTING (FIG. A-66)

ON LINE 10-SJ-1211 258550 21SJ56 BOLTING (FIG. A-66)

ON LINE 8-SJ-1262 (FIG.

L258600 22SJ49 BOLTING A-67 SHT 1)

VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-i VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 Accept Accept Exam Performed by certified PSEG personnel.

Accept Exam Performed by certified PSEG personnel.

Accept lExam Performed by certified PSEG personnel.

Accept.

Exam Performed by certified PSEG personnel.

Accept Exam Performed by certified PSEG personnel.

.Exam Performed by certified PSEG personnel.

Exam Performed by certified PSEG personnel.

V CodeCse VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 ExamPerformed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1

~VT-2 Exam.Performed to Code Case N-533-1 jVT-i exam performed on bolting in-place and under tension VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1

_,* E~~~~x2 mP2*2 r n]~....

oC....

Ca.N 3 -.......................

VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT2Ea.Performed to Code Case N-533-1 Exam.Pe...rmed Cod.Cse.-53.

Accept Accept Accept Accept Exam Performed by certified PSEG personnel.

Exam Performed by certified PSEG personnel.

i I VT-2 Accept

!Exam Performed by certified PSEG personnel.

11/17/2006 Salem Nuclear Generating Station, Unit 2 Page 8 of 17 ISI Program Long Term Plan Revision 1 RFO-15 ISl Examination Results

<Surn#

Co;r;pmponhent ID Decito DEI ~Stats 1

%Remarks Commerneits Y~

ON LINE 8-SJ-1252 (FIG.1 258650 21SJ49 BOLTING A-69 SHT 1)

VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 ON LINE 8-SJ-1245 (FIG.

258700 24RH27 BOLTING A-71)

VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 ON LINE 8-RH-i235 1

258750 23RH27 BOLTING (FIG. A-62)

VT-2 Accept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO-15 ISI Examination Results Page 9 of 17 Revision 1 I'

11 C ornpongtIDj Decito D

1~O LINE 6-SJ-1 242 (FI G.

24SJ43 BOLTING

A-73)

VT-1 ON LINE 6-SJ-1242 (FIG.

24SJ43 BOLTING A-73)

VT-2 ON LINE 6-SJ-1241 (FIG.

258850 24SJ156 BOLTING A-74)

VT-2 ON LINE 6-SJ-1232 (FIG.

258900 23SJ43 BOLTING A-76)

VT-2 ON LINE 6-RH-1231 258950 23SJ156 BOLTING (FIG. A-77)

VT-2 ON LINE 6-SJ-1222 (FIG.

259000 22SJ43 BOLTING IA-79)

VT-2 ON LINE 6-SJ-1221 (FIG.

259050 22SJ156 BOLTING A-80)

VT-2 ON LINE 6-SJ-1212 (FIG.

259100 21SJ43 BOLTING A-81)

VT-2 ON LINE 6-SJ-1211 (FIG.

259150 21SJ156 BOLTING A-99)

VT-2 ON LINE 4-SJ-1295 (FIG.

259200 2SJ13 BOLTING A-84)

VT-2 ON LINE 4-SJ-1294 (FIG.

259250 2SJ135 BOLTING A-85)

VT-2 I ON LINE 4-SJ-1293 (FIG.

1259300 2SJ12 BOLTING 1A-84)

VT-2

,ON LINE 4-SJ-1282 (FIG.

259350 22SJ40 BOLTING A-86)

VT-2 SON LINE 4-SJ-1272 (FIG.

259400 21SJ40 BOLTING JA-87)

VT-2 ION LINE 3-SJ-1292 (FIG.

259450 2SJ150 BOLTING A-84)

VT-2 ON LINE 1.5-SJ-1212 259500 21SJ388 BOLTING (FIG. A-1 07).VT-2 ON LINE 1.5-SJ-1222 259550 22SJ388 BOLTING FIG. A-105)

VT-2 ON LINE 1.5-SJ-1232 259600 23SJ388 BOLTING (FIG. A-103)

VT-2 ION LINE 1.5-SJ-1242 259650 24SJ388 BOLTING

{(FIG. A-101)

VT-2 330220 14-BF-2241-12R1 PIPE TO ELBOW UT-45 330230

[14-BF-2241-13R1 1ELBOWTO REDUCER UT-45 Accept Accept Accept Accept Accept Accept

~Remarks Exam Performed by certified PSEG personnel.

Exam Performed by certified PSEG personnel.

I VT-1 exam performed on bolting in-place and under tension VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exar.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 VT-2 Exam.Performed to Code Case N-533-1 Accept Accept Accept Accept Exam Performed by certified PSEG personnel.

Exam Performed by certified PSEG personnel.

Accept Accept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 Accept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 Accept ttExam Performed by certified PSEG personnel.

.,-2 Elxam.Peformed toCodeCase N-533-1 Accept

'Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 Accept Exam Performed by certified PSEG personnel.

VT-2 Exam.Performed to Code Case N-533-1 Accept Examination performed by AREVA qualified personnel NCD Thickness and contour taken from previous data.

Accept Examination performed by AREVA qualified personnel NCD Thickness and contour taken from previous data.

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO-15 ISI Examination Results Page 10 of 17 Revision 1 Sumheonyprt IDi D"

~

ciption ~ ]

DiE Status Remark~s Cmet 330260 16-BF-2241-1R2 REDUCER TO NOZZLE UT-45 Accept Examination performed by AREVA qualified personnel INCD Thickness and contour taken from previous data.

14-BF-2231-15PL-11 1

r330515 THRU 18 2____

FWH-23-24 MT Accept Examination performed by AREVA qualified personnel 1None Exam. Performed by certified Team Industrial 381070 34-MS-2241-242PL PIPE LUG 242 MT Accept Personnel.

None 385680 2-MSAA-130 "AVCHOR3 Accept lExam Performed by certified PSEG personnel.

None Due to clamp configurtaiion 0.5" of base material and end of near side and far side welds were not examined on clamp end.

Lugs were welded on three sides. Drawing# 222846-04207-1, sheet 24 of 43.

None 502895 502897 503695 572035 8-RH-2226-9PL-1 &2 2-RH RH-22-9 8-RH-2216-39PS 1-4 12-RH-2269-3PL-1&2 PIPE LUG HANGý6ER 11 PIPE SUPPORT INTEGRAL ATTACHMENT PIPE LUG VAR.SUPPORT,TYP.A,S Z13,CL-3191,HL-2875 lPT Accep!.t

[Examination performed by AREVA qualified personnel VT-3 Accept xam erformed by certified PSEG personnel.

PT

.Accept Examination performed by AREVA qualified personnel None Due to clamp configuration, 0.5" of base material and end of each weld were not examined on clamp end. Lugs were welded I Examination performed by AREVA qualified personnel only on near side and far side. See Drawing #222846-0-4207 PT VT-3 Accept 572037 2-RHRH-21-4 709720 715260 2-CV-2214-10 IPIPE TO TEE 1 0-SW-2273-2 1PIPE TO ELBOW 10-SW-2273-2 IPIPE TO ELBOW PT UT-0 UT-45 Accept Accept Accept Accept 10-SW-2273-2 PIPE TO ELBOW 10-SW-2275-2 ELBOW TO PIPE 10-SW-2275-2 ELBOW TO PIPE Exam Performed by certified PSEG personnel.

IThis component subject to external chloride stress corrosion UT-70 UT-45 UT-0 UT-70 715320 1 0-SW-2275-2 ELBOW TO PIPE Accept Accept Accept Accept Accept Accept Accept Exam. Performed by certified Team Industrial cracking (ECSCC) Exam performed on weld #10 and 2 1/2 Dia.

Personnel.

(5") Upstream.

Performed lamination scan on base material only. NCD Examination performed by AREVA qualified personnel Summary #715260 and 715325 were scanned in parallel.

Examination perormed by AREVA qualified personnel NCD Summary #715260 and #715325 were scanned in parallel.

Examination performed by AREVA qualified personnel {NCD Summary# 715260 and 715325 were scanned in parallel.

Examination performed by AREVA qualified personnel None Examination performed by AREVA qualified personnel Performed lamination scan on base material only. NCD Examination performed by AREVA qualified personnel 1None Examination performed by AREVA qualified personnel S5and 715260 were scanned in parallel.

Examination performed by AREVA qualified personnel INCD Summary# 715325 and 715260 were scanned in parallel.

iPerformed lamination scan on base material only. NCD Examination performed by AREVA qualified personnel ISummary# 715325 and 715260 were scanned in parallel.

715325 10-SW-2275-3 PIPE TO ELBOW 10-SW-2275-3 PIPE TO ELBOW 10-SW-2275-3 1PIPE TO ELBOW UT-70 UT-45 UT-0

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO-15 ISI Examination Results Page 11 of 17 Revision 1 SU#

C.omponent ID b...ription jND Sta Remarks

Comments, Performed a lamination scan on base material only. NCD 10-SW-2276-5 ELBOW TO PIPE UT-0 Accept Examination performed by AREVA qualified personnel Summary# 715370 and 715395 were scanned in parallel.

715370 ND ma,,750nd 39wrs ne,,pr 10-SW-2276-5 ELBOW TO PIPE UT-45 Accept Examination performed by AREVA qualified personnel NCD Summary# 715370 and 715395 were scanned in paralel.

10-SW-2276-5P ELBOWTOPIPE UT-70 Accept Examination performed by AREVA qualified personnel NCD Summary# 715370 and 715395 were scanned in parallel.

713510-S W-2276-6

~

PIPE TO ELBOW I UT-Acet

______________________759 715375me a________

T laminatio scan on baemtra ny NOD 10-S W-2276-6 PIPE TO ELBOW UT-45 Accept Examination performed by AREVA qualified personnel NCD Summary# 715375 and 715390 were scanned in parallel.

10-SW-2276-6 PIPE TO ELBOW UT-70 Accept Examination performed by AREVA qualified personnel NCD Summary# 715375 and 715390 were scanned in parallel.

Performed lamination scan on base material only. NCD 10-SW-2277-2 ELBOW TO PIPE UT-0 Accept Examination performed by AREVA qualified personnel Summary# 715390 and 715375 were scanned in parrallel.

715390 10-SW-2277-2 10-SW-2277-2 ELBOW TO PIPE ELBOW TO PIPE PIPE TO ELBOW UT-45 UT-70 UT-45 Accept Accept Accept Examination performed by AREVA qualified personnel Examination performed by AREVA qualified personnel Examination performed by AREVA qualified personnel 10-SW-2277-3 715395 1 0-SW-2277-3 10-SW-2277-3 721250 12A-CCA-462 734262 2SJE6 2SJE7 734263 PIPE TO ELBOW-PIPE TO ELBOW ANCHOR NO.21 Accumulator Instrumentation Nozzels Penetrations NO.22 Accumulator Instrumentation Nozzels Penetrations NO.23 Accumulator Instrumentation Nozzels Penetrations NO.24 Accumulator Instrumentation Nozzels Penetrations UPPER INTERNALS TO LOWER INTERNALS KEYS UT-70 UT-0 VT-3 Accept Examination performed by AREVA qualified personnel Accept IExamination performed by AREVA qualified personnel Accept Exam Performed by certified PSEG personnel.

Accept I Exam Performed by certified PSEG personnel.

VT-2 734264 ]2SJE8 734265 2SJE9 9361000 IWVVI-100 NCD Summary# 715390 and 715375 were scanned in parallel.

NCD Summary# 715390 and 715375 were scanned in parallel.

NCD Summary# 715395 and 715370 were scanned in parallel.

Performed lamnation scan on base material only. NCD Summary# 715395 and 715370 were scanned in parallel.

Hanger is located in waste evap room accessed from outside.

Need security and key.

VT-2 Exam Performed to detect leakage in dissimilar metal welds.

VT-2 Exam Performed to detect leakaqe in dissimilar metal VT-2 Accept Exam Performed by certified PSEG personnel.

welds.

VT-2 Exam Performed to detect leakage in dissimilar metal VT-2 Accept Exam Performed by certified PSEG personnel.

welds.

I VT-2 Exam Performed to detect leakage in dissimilar metal VT-2 Accept Exam Performed by certified PSEG personnel.

welds.

VT-3 Exam performed with remote camera inside Reactor VT-3 Accept IExam Performed by certified PSEG personnel.

lVessel.

p d

m e

11/17/2006 Salem Nuclear Generating Station, Unit 2 Page 12 of 17 ISI Program Long Term Plan Revision 1 RFO-15 ISI Examination Results ND tau emarkcs~

co~mnents

~

VT-3 Exam performed with remote camera inside Reactor 932000 IVVI-200 iRPV STUD AREA VT-3 Accept Exam Performed by certified PSEG personnel.

Vessel.

CORE BARREL-TO-FLG VT-3 Exam performed with remote camera inside Reactor 932100 IVVI-202 MATING SURFACES VT-3 Accept Exam Performed by certified PSEG personnel.

Vessel.

TVESSEL HEAD VT-3 Exam performed with remote camera inside Reactor 932150 IVl-203 ALIGNING KEYS (PINS) VT-3 Accept Exam Performed by certified PSEG personnel.

Vessel.

IRRADIATION SPECIMEN PLUGS (FLG VT-3 Exam performed with remote camera inside Reactor 932250 IVVI-205 AREA)

VT-3 Accept Exam Performed by certified PSEG personnel.

Vessel.

IVT-3 Exam performed with remote camera inside Reactor 933000 IVVI-300 BAFFLE PANEL BOLTS VT-3 Accept Exam Performed by certified PSEG personnel.

Vessel.

DEBRIS SCAN ON CORE BARREL DISTR.

_3VT-3 Exam performed with remote camera inside Reactor 933050 IVVI-301 PLATE VT-3 Accept Exam Performed by certified PSEG personnel.

Vessel.

CIRC WELD ABOVE CORE BARREL VT-3 Exam performed with remote camera inside Reactor t9333100 IVVI-302 SHROUD

_VT'-3 IAccept Exam Performed by certified PSEG personnel.

Vessel.

TOP 0O

""O-R--M-.-E

-R-S (0_

TO 360 DEG.) PLAN IVT-3 Exam performed with remote camera inside Reactor 933250 IWI-305 jVIEW VT-3 jAccept Exam Performed by certified PSEG personnel.

Vessel.

INSIDE CORE BARREL TOP FLG-TO-SHELL VT-3 Exam performed with remote camera inside Reactor 933300 IVVI-306 WELD VT-3 Accept Exam Performed by certified PSEG personnel.

IVessel.

LOWER CORE PLATE L(DISTR. PLATE)

VT-3 Exam performed with remote camera inside Reactor 933400 IVVI-308 FORGING VT-3 Accept Exam Performed by certified PSEG personnel.

Vessel.

Class 1 walkdown performed by VT certified inspectors David Mora, Michael Hicks, Pete Durant, Tony Oliveri, Heather 950000 SPT-2-RC-001 ALL CLASS 1 SYSTEMS VT-2 Accept Exam Performed by certified PSEG personnel.

Malikowski, Walt Wikoff, and William Kiddel.

(AF) AUXILIARY FEED 950150 SPT-2-AF-003 WATER SYSTEM VT-2 Accept Exam Performed by certified PSEG personnel.

None (BF) BOILER FEED 950225 SPT-2-BF-001 SYSTEM VT-2 Accept Exam Performed by certified PSEG personnel.

None 950250 SPT-2-CA-001 (CA) CONTROL AIR VT-2

Accept Exam Performed by certified PSEG personnel.

None J(CC) COMPONENT 950350 SPT-2-CC-002 ICOOLING SYSTEM VT-2 Accept Exam Performed by certified PSEG personnel.

None 950450 SPT-2-CC-004 COOLING SYSTEM VT-2 Accept Exam Performed by certified PSEG personnel.

None 1(CH) CHILLED WATER 950550 SPT-2-CH-001 JSYSTEM VT-2 Accept Exam Performed by certified PSEG personnel.

iNone 9560 SPT-2-CH-002 ISYSTEM VT-2 Accept ~Exam Performned. by certified PSEG personnel.

jNone

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO-15 ISI Examination Results Page 13 of 17 Revision 1 Sum#~

Compone' ID

~

Description.

Ij ME I Stats U

~

Rema4rs C

~

ommenits (CS) CONTAINMENT 2CS16 has a drip bag installed under it, but no active leakage 950650 SPT-2-CS-001 SPRAY SYSTEM VT-2 Accept Exam Performed by certified PSEG personnel, has been detected.

(CVC) CHEMICAL VOLUME CONTROL Notification 20276363 for Fig. on N. side of 2CVEI. 20269831 950850 SPT-2-CV-001 SYSTEM VT-2 Accept Exam Performed by certified PSEG personnel.

written for 2CVE4 seal leak when pump I/S Notf# 20276365 950900

[950950 951000 951050 SPT-2-CV-002 SPT-2-CV-003 (CVC) CHEMICAL VOLUME CONTROL SYSTEM (CVC) CHEMICAL VOLUME CONTROL SYSTEM (CVC) CEMIC IAL VOLUME CONTROL SYSTEM (CVC) CHEMICAL VOLUME CONTROL SYSTEM (CVC) CHEMICAL VOLUME CONTROL VT-2 lAccept VT-2 jAccept IExam Performed by certified PSEG personnel.

jNone Exam Performed by certified PSEG personnel.

INone SPT-2-CV-004 VT-2 VT-2 Accept Accept Exam Performed by certified PSEG personnel.

Exam Performed by certified PSEG personnel.

.Performed by certified PSEG personnel.

SPT-2-CV-005 None 951100 951250 951300 951.350 951400

951500, 951550 952200 952250 952300 952450 952500 SPT-2-CV-006 SYSTEM (GB) GENERATOR SPT-2-GB-001 IBLOWDOWN SYSTEM T(MS) MAIN STEAM SPT-2-MS-001 SYSTEM (MS) MAIN STEAM SPT-2-MS-002 SYSTEM (RC) REACTOR SPT-2-RC-003 COOLANT SYSTEM (RC) REACTOR SPT-2-RC-005

[COOLANT SYSTEM l(RH) RESIDUAL HEAT SPT-2-RH-001 REMOVAL SYSTEM (SJ) SAFETY SPT-2-SJ-009 INJECTION SYSTEM T(SS) SAMPLING SPT-2-SS-001 SYSTEM

§(SS) SAMPLING SPT-2-SS-002 SSTEM (SS) SAMPLING SPT-2-SS-005 SYSTEM (SS) SAMPLING SPT-2-SS-006 SYSTEM VT-2 Accept VT-2 Accept f-Exam Performed by certified PSEG personnel.

VT-2 VT-2 VT-2 VT-2 VT-2

,VT-2 Accept Accept Accept Accept Accept

,Accept Exam Performed by certified PSEG personnel.

Exam Performed by certified PSEG personnel.

76340 for 2C299, dry boric acid from packing. Notif#

for 2CV54, wet active boric acid from packing.

itoring enclosure pation completed proir to 2R15.

d in-conjuction with 23AFP run.

as wet boric acid from packing, not a system VT-2 VT-2 VT-2 VT-2 Accept Accept Accept Accept pressure test failure, condition oocumentea unoer Exam Performed by certified PSEG personnel.

Notf.#20263549.

Exam. Performed by certified Team Industrial Personnel.

None Exam Performed by certified PSEG personnel.

None

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO-15 ISl Examination Results Page 14 of 17 Revision 1 S; unip Compnen ID ecito D

I Status Remarks Comments 4

952550 ISPT-2-SS-007 SYSTEM 952600JSPT-2-SS-008 (SS) SAMPLING SYSTEM (SW) SERVICE WATER SYSTEM (SW) SERVICE WATER SYSTEM VT-2 VT-2 VT-2 VT Accept Accept Accept Reject Exam Performed by certified PSEG personnel.

Exam Performed by certified PSEG personnel.

None 953300 SPT-2-SW-006 SPT-2-SW-006 (SW).

SYST 953400 SPT-2-SW-008 i(sw) 953450 SPT-2-SW-009 JSYST (SW) 953500 SPT-2-SW-010 SYST 953550 SPT-2-SW-011 SYST (SW) 953600 SPT-2-SW-012 SYST (Sw))

953650 SPT-2-SW-013 SYST (SW) 953700 SPT-2-SW-014 SYST (S,W) 953750 SPT-2-SW-015 SYST

~(SW) 953800 SPT-2-SW-016 SYST (SW) 953850 SPT-2-SW-017 SYST (SW) 953900 SPT-2-SW-018 SYST (SW) 953950 SPT-2-SW-019 SYST 9 0 T"(SW) 954000 SPT-2-SW-020

[SYST SERVICE WATER EM SERVICE WATER EM SERVICE WATER EM SERVICE WATER EM SERVICE WATER EM SRICE WATER EM SERVICE WATER EM SERVICE WATER EM SERVICE WATER EM SERVICE WATER EM SERVICE WATER EM SERVICE WATER EM SERVICE WATER EM SERVICE`WATER EM VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 Accept Accept Accept Accept Accept Accept Accept Accept Exam Performed by certified PSEG personnel.

Exam Performed by certified PSEG personnel.

None This is a as-left after repair of a pin-hole leak. Results satisfactory for continues operration.

VT-2 Exam noted a pinhole leak thru bottom of discharge nozzle.

None None None None Exam Performed by certified PSEG personnel.

None Exam Performed by certified PSEG personnel.

JNone Exam Performed by certified PSEG personnel.

None VT-2

[Accept I

VT-2

[Accept (Sw)

ISYST 954050 954100 954150 SPT-2-SW-021 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 Accept Accept Accept Accept Accept Accept Exam Performed by certified PSEGpersonnel.

'None Exam Performed by certified PSEG personnel. _

None Valve opner during 405p surveillance test on 24CFCU. Held vlv.

Exam Performed by certified PSEG personnel.

open for 11 min. prior to exam. Exam area 8' of pipe.

Exam Performed by certified PSEG personnel.

None Performed by certified PSEG personnel.

None Exam Performed by certified PSEG personnel.

None l(SW) SERVICE WATER SPT-2-SW-022 SSTEM j(SW) SERVICE WATER SPT-2-SW-023 SYSTEM (SW) SERVICE WATER SPT-2-SW-024 SYSTEM

.1 954200 Accept Exam Performed by certified PSEG personnel.

lNone

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO-15 ISI Examination Results Page 15 of 17 Revision 1

~Sum#

C np on nt I, Description

~

NDE 4Status' :I Remarks

{

(SW) SERVICE WATER 954250 SPT-2-SW-025 SYSTEM VT-2 Accept Exam Performed by certified PSEG personnel.

(SW) SERVICE WATER 954300 SPT-2-SW-026 SYSTEM VT-2 Accept Exam Performed by certified PSEG personnel.

(SW) SERVICE WATER 954350 SPT-2-SW-027 SYSTEM VT-2 Accept Exam Performed by certified PSEG personnel.

(SW) SERVICE WATER 954400 SPT-2-SW-028 SYSTEM VT-2 Accept Exam Performed by certified PSEG personnel.

(SW) SERVICE WATER 954450 SPT-2-SW-029 SYSTEM VT-2 Accept Exam Performed by certified PSEG personnel.

(SW) SERVICE WATER 954500 SPT-2-SW-030 SYSTEM

___.VT-2 Accept Exm Performed by certified PSEG personnel.

(SW) SERVICE WATER I

None None None None None None__________________________________

954550 SPT-2-SW-031 SYSTEM VT-2 954600 954650 (SW) SERVICE WATER SPT-2-SW-032 SYSTEM (SW) SERVICE WATER SPT-2-SW-033 SYSTEM (SW) SERVICE WATER 954655 SPT-2-SW-034 SYSTEM (SW) SERýVICE WAMTE R 954660 SPT-2-SW-035 SYSTEM (SW) SERVICE WATER 954665 SPT-2-SW-036 SYSTEM (SW) SERVICE WATER 954670 SPT-2-SW-037 SYSTEM (SW) SERVICE WATER 954675 SPT-2-SW-038 SYSTEM (VC) CONTAINMENT 954700 SPT-2-VC-001 VENTILATION SYSTEM (VC) CONTAINMENT 954750 SPT-2-VC-002 VENTILATION SYSTEM (VC) CONTAINMENT 954800 SPT-2-VC-003 VENTILATION SYSTEM i(VC) CONTAINMENT 954850 SPT-2-VC-004 VENTILATION SYSTEM (VC) CONTAINMENT 954950 SPT-2-VC-006 IVENTILATION SYSTEM I

f(VC) CONTAINMENT 955000 SPT-2-VC-007 VENTILATION SYSTEM 11 (WG) WASTE GAS 955050 SPT-2-WG-001 SYSTEM VT-2 VT 2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 Accept Exam Performed by certified PSEG personnel.

None Accept Exam_ Performed by certified PSEG personnel.

None Accept Exam Performed by certified PSEG personnel.

None

" cce]

t Exam Pef

-ormed-by c

P.EG.

e.

Accept Exam Performed by certified PSEG personnel.

None

.This is an open-ended system and exempt from system lpressure testing. A satisfactory LLRT was performed and Accept Exam Performed by certified PSEG personnel.

Jstructural interrity.

Ope n-ended system and eyempt from sys. press. test.A Accept Exam Performed by certified PSEG personnel.

walkdown was performed to ensure component interity, Open-ended system and exempt from system pressure test.

Accept Exam Performed by certified PSEG personnel.

iComponent structural interrity is satisfactory.

l~pen-ended and exemnted from SPT. Structural integrity Accept Exam Performed by certified PSEG personnel.

jsatisfactory.

Accept Exam Performed by certified PSEG personnel.

1None

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO-15 ISI Examination Results Page 16 of 17 Revision 1 Sum##

C~>:ori~

ous ripin ND Status~

Remark Comments~

(WG) WASTE GAS Various pressures used. Each tank and compressor has a 955055 SPT-2-WG-002 SYSTEM VT-2 Accept Exam Performed by certified PSEG personnel.

different pressure. All exams SAT.

(WL) WASTE LIQUID 955100 SPT-2-WL-001 SYSTEM VT-2 Accept Exam Performed by certified PSEG personnel.

None (WL) WASTE LIQUID 955150 SPT-2-WL-002 SYSTEM VT-2 Accept Exam Performed by certified PSEG personnel.

None (WL) WASTE LIQUID'ine fill"ed from pressure from Reactor collant drain tank.

955200 SPT-2-WL-003 SYSTEM VT-2 lAccept Exam Performed by certified PSEG personnel.

Snooped with no leakage detected.

955250 SPT-2-WL-004 (WL) WASTE LIQUID SYSTEM (WL) WASTE LIQUID SYSTEM VT-2 VT-2 Accept Exam Performed by certified PSEG personnel.

Exam Performed by certified PSEG personnel.

955300 ISPT-2-WL-005 Accept 958010 (BR) BORON RECOVERY NR-SPT-2-BR-001 VT-2 VT-2 958020 (CS) CONTAINMENT SPRAY NR-SPT-2-CS-001 958030 958040 INR-SPT-2-CS-002 NR-SPT-2-CV-001 958050 NR-SPT-2-CV-002 958060 NR-SPT-2-CV-003 (CS) CONTAINMENT SPRAY (CV) CHEMICAL &

VOLUME CONTROL (CV) CHEMICAL &

VOLUME CONTROL VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 Accept Accept Accept Accept Accept Accept Accept Accept 958070 NR-SPT-2-CV-004 958080 NR-SPT-2-CV-005 Exam Performed by certified PSEG personnel.

Exam. Performed by certified Team Industrial Personnel.

Exam Performed by certified PSEG personnel.

Exam. Performed by certified Team Industrial Personnel.

None None None None Line is under static pressure and never runs for more than a couple minutes. Verified structual integrity to be Sat.

This is a static line that only sees miminal flow when dumping into the sump line is LRT. tested Sat.

None None None None None ----------

I(CV) CHEMICAL &

958090 NR-SPT-2-CV-006 IVOLUME CONTROL (CV) CHEMICAL &

958100 NR-SPT-2-CV-007 VOLUME CONTROL (RH)REHEAT 958110 NR-SPT-2-RH-001 REMOVAL (RH) REHEAT 958120 NR-SPT-2-RH-002 REMOVAL L 958130 NR-SPT-2-SI-001 INJECTION

~~(S J)SAFETY 958140 NR-SPT-2-Sl-002 INJECTION I(SJ) SAFETY S958150 rNR-SPT-2-SI-003 iINJECTION VT-2 Accept VT-2 IAccept VT-2 lAccept VT-2 lAccept VT-2 tAccept VT-2

,Accept VT-2 jAccept None 21RH19 has wet Boric Acid from packing. Nota NUREG-0578 None None Dry Boric Acid on 2SJ195 None

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO-15 IS1 Examination Results Page 17 of 17 Revision 1 I Sum#¶ Component ID' Description (SS) SAMPLING 958160 NR-SPT-2-SS-001 SYSTEM 958170 NR-SPT-2-SS-002 SYSTEM I

~(SS) SAMPliNG 958180 NR-SPT-2-SS-003 SYSTEM (SS) SAMPLING 958190 NR-SPT-2-SS-004 SYSTEM

21 WASTE GAS 958200 NR-SPT-2-WG-001 DECAY TANK I~ NDE]

Sat,]LS~ I "4

R~emarks~'

VT-2 VT-2 VT-2 VT-2 Accept Accept Accept Accept Exam Performed by certified PSEG personnel.

Exam Performed by certified PSEG personnel.

-~

VT-2 958210 958220 958230 NR-SPT-2-WG-002 NR-SPT-2-WG-003 NR-SPT-2-WG-004

22 WASTE GAS, DECAY TANK

23 WASTE GAS DECAY TANK

24 WASTE GAS.

DECAY TANK WASTE GAS DISCHARGE HEADER WASTE GAS ICOMPRESSORS VT-2 VT-2 VT-2 Accept Accept Accept Accept Exam Performed by certified PSEG personnel.

Exam Performed by certified PSEG personnel.

Comuments

.None 23SS94 has active packing leak.

None Boric acid on packing of 21SS181. Not aninspectiion failure.

None None None.

None Operatiions ran 21 compressor from 64'el panel snooped for leakage, no leakage detected from pressure retaining

[components.

None None Boric Acid collections in many locations on 21 waste hold-up tank.

958240 INR-SPT-2-WG-005 VT-2 lAccept IExam Performed by certified PSEG personnel.

958250 NR-SPT-2-WG-006 958260 NR-SPT-2-WG-007 SUCTION HE

21 & #22W COMPRESSC (WL) WASTE SYSTEM ADER VT-2 Accept Exam Performed by certified PSEG personnel.

ASTE GAS cp 1

)RS VT-2 Accept Exam Performed by certified PSEG personnel.

LIQUID I

VT-2 Accept Exam Performed by certified PSEG personnel.

958270 INR-SPT-2-WL-001

LR-N07-0016 Salem Unit 2 RCP Flywheel Inspection Plan and Results

Salem Nuclear Generation Station, Unit 2 ISI Program Long Term Plan RFO #15 FlvwhAAIl Examination RnAHltq Page 1 of 1 Revision 00 11/29/2006 1 S-D003 Magnetic Particle examination was done on Salem RCP#

i 21 Flywheel. Coating Thickness measurement of 0.0040" jAccept was the average noted.

9000

+/-

I #21 RCP Motor Flywheel

21 RCP Motor Flywheel Surface MT I--I Magnetic Particle examination was performed under contract# 1250149 by Areva personnel at their Lynchburg locataion Ultrasonic examination was performed under contract# 1250147 by Areva personnel at their Lynchburg locataion.

Flywheel is 2 pieces bolted together. both plates were 9000 1 S-D003 Volumetric UJTi

+

Accept tscanned from accessible surfaces.

LR-N07-0016 Salem Unit 2 IWE Examination Plan and Results

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO #15 IWE Examination Results Page 1 of 10 Revision 1 QUADRANT A FROM 78 TO 100 820000 LNR-S2-QUAD-000A-078 MC Visual VT-G Accept QUADRANT B FROM 78 TO 100 820100 LNR-S2-QUAD-OOOB-078 SQUADRANT C FROM 78 820200 LNR-S2-QUAD-000C-078 ]TO 100 MC MC MC Visual Visual Visual VT-G Accept VT-G jAccept INSIDE: Containment Liner insulated 78' to 100', Not 20162294 for stainless steel permanent insulation rusting, No recordable findings on visible part of liner INSIDE: Containment Liner insulated 78' to 100' No recordable findings on visible part of liner INSIDE: Containment Liner insulated 78' to 100' No recordable findings on visible part of liner INSIDE: Containment Liner partial insulated 78' to 100',

No recordable findings on visible part of liner INSIDE: Containment Liner insulated 100' up to 110',

channel scaling Flux Thimble area EI.113', Not 20162379 INSIDE: Containment Liner insulated 100' up to 110',

No recordable findings on visible liner OUTSIDE: N/A OUTSIDE: N/A OUTSIDE: N/A OUTSIDE: Partial coated/noncoated no recordable findings noted QUADRANT D FROM 78 TO 100 820300 1 LNR-S2-QUAD-OOOD-078 VT-G

'1~

.4, 4

820400 LNR-S2-QUAD-000A-100 4,

QUADRANT A FROM 100 TO 130 QUADRANT B FROM 100 TO 130 MC MC Visual Visual VT-G VT-G Accept Accept Accept 820500 1 LNR-S2-QUAD-OOOB-1 00 t

QUADRANT C FROM 100 TO 130 820600 LNR-S2-QUAD-000C-100 MC Visual VT-G

+

4.

QUADRANT D FROM 100 TO 130 820700 ILNR-S2-QUAD-000D-100 MC Visual VT-G

+

4

4.

~....L................4 INSIDE: Containment Liner insulated 100' up to 110',

Not 20162378 for stainless steel permanent insulation Accept rusting

!INSIDE: Containment Liner insulated 100' up to 110',

Accept INo recordable findings on visible liner INSIDE: EI.130' to EI.160' Behind Fan Coil Units Coating is chipped, light to medium rust(<Grade 7-2),

Accept and liner coated surfaces are stained. Not. 20162675 INSIDE: EI.130' to EI.160' Behind Fan Coil Units Coating is chipped, light to medium rust(<Grade 7-2),

Accept and liner coated surfaces are stained. Not. 20162675 OUTSIDE: N/A OUTSIDE: N/A OUTSIDE: N/A OUTSIDE: N/A OUTSIDE: N/A OUTSIDE: N/A QUADRANT A FROM 130 TO 218 820800 LNR-S2-QUAD-OOOA-1 30 MC Visual VT-G

4.

4.....................4 4

QUADRANT B FROM 130.TO 218 820900 1 LNR-S2-QUAD-OOOB-1 30 MC Visual VT-G PC 1

Yisual QUADRANT 130 TO 218 C FROM 821000 LNR-S2-QUAD-000C-130 821200 821300 LNR-S2-QUAO-OOOD-130 LNR-S2-QUAD-OOOA-218 LNR-S2-QUAD-OOOB-218 130 TO 218 QUADRANT A FROM 218 TO 288 QUADRANT B FROM 218 TO 288 MC MCd' MC MC Visual vr-G V isual V-G Visual j \\f-G Visual VT-G Acet iAccept INSIDE: EI.130' to EI.160' Behind Fan Coil Units Coating is chipped, light to medium rust(<Grade 7-2),

and liner coated surfaces are stained. Not. 20162675 OUTSIDE: N/A Coating is chipped, fight to medium rust(<Grade 7-2),

OUTSIDE: N[A INSIDE: No recordable findings on visible liner OUTSIDE: N/A INSIDE: No recordable findings on visible liner OUTSIDE: N/A INSIDE: No recordable findings on visible liner IOUTSIDE: N/A Accept Accept 821400~~~~~~~

LN-2QA-OC21-CVsa G

Acp 1821400 QUADRANT C FROM 218 TO 288 Visual VT-G I

jLNR-S2-QUAD-000C-218 MC Accept

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO #15 IWE Examination Results Page 2 of 10 Revision 1 821500 j LNR-S2-QUAD-000D-218 QUADRANT D 218 TO 288 MC i1821600 MBR-S2-QUAD-OOOA-078 821700 MBR-S2-QUAD-000B-078 821800 MBR-S2-QUAD-000C-078 QUAD A MOIST BAR 78 EL. 0/90 DEG QUAD B MOIST BAR 78 EL. 270/0 DEG QUAD C MOIST BAR 78 EL. 180/270 DE QUAD D MOIST BAR 78 EL. 90/180 DEG QUADRANT A MECH

!PEN AT 108 EL.

MC MC MC MC MC Visual VT-G Visual IVT-G Visual VT-G Visual VT-G Visual VT-G Visual.

IVT-G Accept Accept INSIDE: Above 24 F liner, Not 20162676 OUTSIDE: N/A OUTSIDE: N/A INSIDE: Accessible areas intact I

~1 Accept Accept_

Accept Accept 821900 iMBR-S2-QUAD-000D-078 822000 IPEN-S2-M-01 INSIDE: Accessible areas intact INSIDE: Accessible areas intact INSIDE: Accessible areas intact INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings 822100 IPEN-S2-M-02

+

QUADRANT B MECH PEN AT 108 EL.

QUADRANT D MECH PEN AT 108 EL.

822200 IPEN-S2-M-03 MC MC Visual VT-G Visual JVT-G Accept Accept Accept 822300 IPEN-S2-M-04 QUADRANT C MECH PEN AT 108 EL.

IVT-G MC Visual

+

I.

Accep.qlNSlDE: Coating no recordable findings 822400 IPEN-S2-M-05 822500 1PEN-S2-M-06 822600 IPEN-S2-M-07 QUADRANT A MECH PEN AT 107 EL.

QUADRANT B MECH PEN AT 96 EL.

QUADRANT D MECH PEN AT 96 EL.

QUADRANT C MECH PEN AT 96 EL.

QUADRANT D MECH PEN AT 90 EL.

MC 822700 !PEN-S2-M-08 822800 1PEN-S2-M-09 MC MC MC MC Visual IVT-G Visual

-VT-G Visual VT-G Visual.

V. -.

Visual lVT-G Accept Accept Accept Accept INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings Accept iINSIDE: Coating no recordable findings OUTSIDE: N/A OUTSIDE: N/A OUTSIDE: N/A OUTSIDE: N/A OUTSIDE: Partial coated/noncoated no recordable findings noted OUTSIDE: Partial coated/noncoated no recordable findings noted OUTSIDE: Partial coated/noncoated no recordable findings noted OUTSIDE: Partial coated/noncoated no recordable findings noted OUTSIDE: Partial coated/noncoated no recordable findings noted OUTSIDE: Partial coated/no ncoated no recordable findings noted OUTSIDE: Partial coated/noncoated no recordable findings noted OUTSIDE: Coated, no recordable findings noted OUTSIDE: 5-7 O'clock penetration wall area has efflorescence and degradation of coating not.20161683 OUTSIDE: 5-7 O'clock penetration wall area has efflorescence and degradation of coating not.20161683 OUTSIDE: Coated, no recordable findings noted OUTSIDE: Coated, no recordable findings noted 822900 PEN-S2-M-10 823000

,PEN-S2-M-1 1 QUADRANT D MECH PEN AT 85 EL.

QUADRANT D MECH PEN AT 85 EL.

MC MC Visual IVT-G Visual iVT-G Accept INSIDE: Coating no recordable findings QU 823100 PEN-S2-M-12 PE 823200 PEN-S2-M-13 PE JADRANT D MECH NAT 85 EL.

JADRANT D MECH NAT 88 EL.

MC MC Visual VT-G

_Visual

-VT-G Accept INSIDE: Coating no recordable findings Accept INSIDE: Coating no recordable findings Accept INSIDE: Coating no recordable findings

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO #15 IWE Examination Results Page 3 of 10 Revision 1 Visual QUADRANT D MECH PEN AT 85 EL.

823300 IPEN-S2-M-14 MC VT-G Accept INSIDE: Coating no recordable findings I

OUTSIDE:

noted OUTSIDE:

noted QUADRANT D MECH PEN AT 88 EL.

Visual Accept 823400 IPEN-S2-M-15 MC V-T-G INSIDE: Coating no recordable findings 8QUADRANT D MECH OUTSIDE:

823500 PEN-S2-M-16 PEN AT 85 EL.

MC Visual

'VT-G Accept INSIDE: Coating no recordable findings measurabl E

QUADRANT D MECH OUTSIDE:

823600 PEN-S2-M-17 PEN AT 90 EL.

MC Visual VT-G Accept INSIDE: Coating no recordable findings noted QUADRANT D MECH OUTSIDE:

823700 IPEN-S2-M-18 PEN AT 88 EL.

MC IVisual VT-G Accept INSIDE: Coating no recordable findings noted QUADRANT QUADRANT D MECH I-OUTSIDE:

823800 PEN-S2-M-19 PEN AT 124 EL.

MC Visual VT-G Accept INSIDE: Coating is Peeling Not. 20162583 Not.20163 QUADRANT D MECH OUTSIDE:

F823900 jPEN-S2-M-20 PEN AT 124 EL.

MC Visual_

VT-G Accept INSIDE: Coating is Peeling Not. 20162583 noted 82400 QADRANTTOMECH OUTSIDE:

824000 IPEN-S2-M-21 PEN AT 85 EL.

MC Visual VT-G Accept INSIDE: Coating no recordable findings noted QUADRANT D MECH OUTSIDE:

824100 IPEN-s2-M-22 PEN AT 85 EL.

MC Visual Accept INSIDE: Coating no recordable findings noted Coated, no recordable findings Coated, no recordable findings Minor rust discoloration, no e loss of metal.

Coated, no recordable findings Coated, no recordable findings Coating < Grade 7-2 (ASTM D 610) 181 Coated, no recordable findings Coated, no recordable findings Coated, no recordable findings Coated, no recordable findings I

Coated, no recordable findings Coated, no recordable findings 824200 IPEN-S2-M-23 i

QUADRANT D MECH PEN AT 88 EL.

QUADRANT D MECH PEN AT 85 EL.

MC Visual VT-G 824300 PEN-S2-M-24 MC Visual VT-G Accept Accept Accept Accept 824400 PEN-S2-M-25 824500 IPEN-S2-M-26 QUADRANT D MECH PEN AT 85 EL.

MC QUADRANT D MECH 1

PEN AT 90 EL.

IMC Visual VT-G Vfisul T

INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings

'noted OUTSIDE: Coated, no recordable findings notedI OUTSIDE:

noted OUTSIDE:

Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO #15 IWE Examination Results 11/17/2006 Page 4 of 10 Revision 1 824600 IPEN-S2-M-27 824700 jPEN-S2-M-28 824800 1PEN-S2-M'29 824900 IPEN-S2-M-30 825000 IPEN-S2-M-31 PEN AT 88 EL.

QUADRANT A MECH PEN AT 70 EL.

QUADRANT D MECH PEN AT 70 EL.

QUADRANT A MECH PEN AT 50 EL.

QUADRANT D MECH PEN AT 50 EL.

QUADRANT D MECH PEN AT 88 EL.

MC MC Visual Visual VT-G VT-G Accept_

N/A.

MC MC MC MC Visual VT-G Visual L2I-cL Visual

_VT-G Visual

-VT-G N/A N/A N/A Accept

+

825100 IPEN-S2-M-32 I

825200 IPEN-S2-M-33 825300 jPEN-S2-M-34 825400 1PEN-S2-M-35 825500 iPEN-S2-M-36 QUADRANT D MECH PEN AT 85 EL.

QUADRANT D MECH PEN AT 90 -EL.

QUADRANT D MECH PEN AT 90 EL.

QUADRANT D MECH PEN AT 85 EL.

QUADRANT D MECH PEN AT 90 EL.

QUADRANT D FUEL TRANS TUBE AT 91 EL.

MC MC MC MC Visual Visual Visual Visual VT-G VT-G VT-G VT-G Accept Accept Accept Accept OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted INSIDE: Inaccessible, Containment Sump OUTSIDE: Inaccessible, Containment Sump INSIDE: Inaccessible, Containment Sump OUTSIDE: Inaccessible, Containment Sump OUTSIDE: Inaccessible, SJ44 hatch requires INSIDE: Inaccessible, covered by PEN-S-M-28 opening OUTSIDE: Inaccessible, SJ44 hatch requires INSIDE: Inaccessible, covered by PEN-S-M-29 opening INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted OUTSIDE:.Coated, no recordab g..........s OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted IOUTStDE: Coated, no recordable findings INSIDE: Coating no recordable findings

!noted I OUTSIDE: Coated, no recordable findings INýSIDE: Coating no recordable findings noted INSIDE: Inaccessible, requires removal of Concrete IOUTSIDE: Inaccessible, requires removal of Plug Concrete Plug 825600 iPEN-2-M-37 825700 !PEN-S2-M-38 MC isual

-G V

JVT Accept...l I

I-

!PEN-S2-M-38-BLIND 825750 FLANGE 1825800l PEN-S2-M-39 QUADRANT D FUEL TRANS TUBE AT 91 EL.

QUADRANT D MECH PEN AT 88 EL.

no recordable findings OUTSIDE: Coated, no recordable findings noted OUTSIDE: Coated, no recordable findings noted SIDE: Coating no recordable findings

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO #15 IWE Examination Results Page 5 of 10 Revision 1 825900 IPEN-S2-M-40 QUADRANT D MECH PEN AT 124 EL.

Visual IVT-G OUTSIDE: Coated, no recordable findings noted MC Accept INSIDE: Coating is Peeling Not. 20162583

+

826000 [PEN-S2-M-41 QUADRANT D MECH PEN AT 88. EL.

MC visual VT-G

.VT-G Accept

[INSIDE: Coating no recordable findings n edOUTSIDE:

Coated, no recordable findings no ed OUTSIDE: Coated, no recordable findings Inoted PEN-S2-M-42 QUADRANT D MECH PEN AT 88 EL.

826100 MC Visual Accept INSIDE: Coating no recordable findings

+

4 QUADRANT D MECH PEN AT 90 EL.

IVT-G IVT-G 826200 PEN-S2-M-43 QUADRANT D MECH PEN AT 90 EL.

MC MC Visual Visual Accept Accept INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings OUTSIDE: Coated, no recordable findings noted OUTSIDE: Coated, no recordable findings noted 826300 PEN-S2-M-44 826400 PEN-S2-M-45 826500 PEN-S2-M-46 826600 IPEN-S2-M-47 QUADRANT D MECH PEN AT 90 EL.

QUADRANT D MECH PEN AT 90 EL.

QUADRANT D MECH PEN AT 88 EL.

QUADRANT D MECH PEN AT 85 EL.

QUADRANT D MECH PEN AT 88 EL.

QUADRANT D MECH PEN AT 85 EL.

MC MC MC Visual Visual Visual VT-G VT-G VT-G Accept Accept Accept

+

826700 IPEN-S2-M-48 826800 PEN-S2-M-49 826900 IPEN-S2-M-50 1827000 !PEN-S2-M-51 827100 IPEN-S2-M-52 QUADRANT D MECH PEN AT 90 EL.

QUADRANT D MECH PEN AT 88 EL.

QUADRANT D MECH PEN AT 85 EL.

M~C

~Visual jVT-G -Accept MC Visual VT-G Accept MC IVisual- ~VT-G Accept MC V-is-u a Accept MC Visual IVT-G Accept MC.

ual VT-G Accept OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted

'OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings Inoted OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted

.OUTSIDE:

Coated, no recordable findings INSIDE: Coating no recordable findings noted

.INSIDE: Coating no recordable findings 2168

!OUTSIDE: Coated, medium rust, notification INSIDE: Coating no recordable findings 120161684 OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings

_no.ted OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted J

L872Oý20 PEN-S2-M-53

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO #15 IWE Examination Results 827300 !PEN-S2-M-54 827400 PEN-S2-M-55 827500 PEN-S2-M-56 827600 N

827700 IPEN-S2-M-58 827800.PEN-S2-M-59 PEN AT 88 EL.

QUADRANT D MECH PEN AT 85 EL.

QUADRANT D MECH PEN AT 90 EL.

QUADRANT D MECH PEN AT 88 EL.

QUADRANT D MECH PEN AT 90 EL.

QUADRANT D MECH PEN AT 88 EL.

QUADRANT D MECH PEN AT 85 EL.

QUADRANT D MECH PEN AT 90 EL.

-Q-UADRAN4T D ME9CH IPEN AT 90 EL.

MC MC MC MC MC Visual 1VT G Visual IVT-G Visual IVT-G Visual j VT-G Visual iVT-G Accept Accept Accept Accept Accept Accept Accept INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings Accept.

INSIDE: Coating no recordable findings 827900 IPEN-S2-M-60 828000 jPEN-S2-M-61 MC MC MC MC MC Visual IVT-G Visual

'VT-G Visual VT-G UU I SIDE: Uoated, no recordable tindings noted OUTSIDE: Coated, no recordable findings noted OUTSIDE: Coated, no recordable findings jnoted I

O UTSID:* C oated, no re ord aibln e fi n di.n.g.s noted OUTSIDE: Coated, no recordable findings noted OUTSIDE: Coated, no recordable findings noted OUTSIDE: Inaccessible, Covered by shielding OUTSIDE: Coated, no recordable findings noted OUTSIDE: Coated, light rust, no recordable findings OUTSIDE: Coated, no recordable findings noted 828100 IPEN-S2-M-62 Visual VT-G Visual jVT-G 828200 1PEN-S2-M-63 828300 jPEN-S2-M-64 828400 iPEN-S2-M-65 i

828500 !PEN-S2-M-66 QUADRANT D FUEL TRANS TUBE AT 91 EL.

QUADRANT D MECH PEN AT 91 EL.

QUADRANT D MECH PEN AT 90 EL.

QUADRANT D MECH PEN AT 88 EL.

QUADRANT D MECH PEN AT 85 EL.

QUADRANT D MECH PEN AT 90 EL.

828600 tPEN-S2-M-67 828700 !PEN-S2-M-68 828800 IPEN-S2-M-69 MC MC MC MC MC MC Visual IVT-G Visual jVT-G Visual IVT-G Visual' IVT-G Visual VT-G Visual

!VT-G Accept Accept N/A N/A Accept Accept Accept Accept NWS(not in IWE program)

NWS(not in IWE program)

INSIDE: Coating no recordable findings NWS(Not within scope of IWE)

!NWS(not in IWE program)

OUTSIDE: Coated, light rust, no recordable findings OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings rnoted OUTSIDE: Coated, no recordable findings noted OUTSIDE: Coated, no recordable findings noted OUTSIDE: Coated, no recordable findings noted 8290 QUADRANT D MECH PEN AT 88 EL.

MC Visual I

,VT-G 8Accept,_ LINSIDE: Coating no recordable findings ____

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO 915 IWE Fxaminatinn RP__iltq Page 7 of 10 Revision 1 829000 jPEN-S2-M-71 i

829200 IPEN-S2-E-01

~4 829300 PEN-S2-E-02 829400 PEN-S2-E-03 829500 PEN-S2-E-04 1

829600 PEN-S2-E-05 829700 IPEN-S2-E-06 4.

829800 IPEN-S2-E-07 829900 ýPEN-S2-E-08 QUADRANT D MECH PEN AT 85 EL.

QUADRANT A ELECT PEN AT 90 EL.

QUADRANT A ELECT PEN AT 88 EL.

QUADRANT A ELECT PEN AT 90 EL.

QUADRANT A ELECT PEN AT 88 EL.

QUADRANT A ELECT PEN AT 90 EL.

QUADRANT A ELECT PEN AT 85 EL.

QUADRANT A ELECT PEN AT 90 EL.

QUADRANT A ELECT PEN AT 85 EL.

QUADRANT A ELECT PEN AT 9O EL.

MC Visual VT-G Accept MC Visual IVT-G -Accept MC Visual VT-G Accept MC Visual VT-G Accept MC.

Visual _VT-G Accept McC

Visual, VT-G Accept MC Visual VT-G Accept MC Visual VT-G] Accept MC Visual

!VT-G Accept MC Visual VT-G Accept MC Visual VT-G Accept MC Visual VT-G Accept MC 1Visual IVT-G A ccept M c IYJV al,I,,,vT-G Accept MC JVisual VT-G Accept MC.

Visual VT-G Accept MC lVisual jVT-G Accept MC Visual VT-G Accept OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted OUTSIDE: Inaccessible, Covered by fire INSIDE: Coating no recordable findings shielding OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted OUTSIDE: Inaccessible; Covered by fire INSIDE: Peeling with rust Not. 20162114 shielding OUTSIDE: Inaccessiblef Covered by fire INSIDE: Coating no recordable findings shielding OUTSIDE: Coated, no recordable findings tiINSIDE: Coating no recordable findings

___noted ib OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted OUTSIDE: Inaccessible, Covered by fire INSIDE: Coating no recordable findings shielding OUTSIDE: Inaccessible; Covered by fire INSIDE: Coating no recordable findings shielding OUTSIDE: Coated, no recordable findings I..NSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings INSIDE: Coating no recordable findings noted 4.

830000 IPEN-S2-E-09 1

830100 !PEN-S2-E-10 830200 !PEN-S2-E-11 830300 IPEN-S2-E-12 830404 IPEN-S2-E-13 830500 IPEN-S2-E-14 830600 IPEN-S2-E-15 830700 'tPEN-S2-E-16 8308&M0 IPEN-S2-E-17

Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO #15 IWE Examination Results 11/17/2006 Page 8 of 10 Revision 1 830900 IPEN-S2-E-18 4

UUAUIKANI A

LL-PEN AT 90 EL.

QUADRANT A ELE PEN AT 90 EL.

831000 IPEN-S2-E-19 831100 1PEN-S2-E-20 831200 PEN-S2-E-21 831300 IPEN-S2-E-22 i

831400 IPEN-S2-E-23 831500 PEN-S2-E-24 831600 j PEN-S2-E-25 831700 IPEN-S2-E-26 831800,PEN-S2-E-27 831900.iEN-S2-E-28 832000 !PEN-S2-E-29 832100

,PEN-S2-E-30 832200 1.PEN-S2-E-31 832300 jPEN-S2-E-32 832400,PEN-S2-E-33 832500 JPEN-S2-E-34 832600 1PEN-S2-E-35 QUADRANT A ELE PEN AT 90 EL.

QUADRANT A ELE(

PEN AT 90 EL.

QUADRANT A ELE PEN AT 88 EL.

QUADRANT A ELE PEN AT 85 EL.

QUADRANT A ELE PEN AT 88 EL.

QUADRANT A ELE PEN AT 85 EL.

QUADRANT A ELE PEN AT 88 EL.

QUADRANT A ELE PEN AT 85 EL.

QUADRANT A ELE PEN AT 88 EL.

Ul I

OUTSIDE: Coated, no recordable findings MC 1Visuai VT-G Accept INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings MC Visual VT-G Accept INSIDE: Coating no recordable findings noted CT

[

OUTSIDE: Coated, no recordable findings MC Visual lVT-G IAccept INSIDE: Coating no recordable findings noted CT OUTSIDE: Coated, no recordable findings MC Visual VT-G Accept INSIDE: Coating no recordable findings noted CT OUTSIDE: Coated, no recordable findings MC Visual VT-G Accept INSIDE: Coating no recordable findings noted CT OUTSIDE: Inaccessible, Covered by fire MC Visual VT-G Accept INSIDE: Rust on coupling Not. 20162113 shielding CT

.OUTSIDE:

Coated, no recordable findings MC Visual iVT-G Accept INSIDE: Coating no recordable findings

]noted CT~~~~~~~~~~~~~~~~..

.53'

.5 e;n-recra~ei

.is CT jOUTSIDE: Coated, no recordable findings MC Visual IVT-G Accept INSIDE: Coating no recordable findings

noted CT I

OUTSIDE: Coated, no recordable findings MC jVisual VT-G Accept INSIDE: Coating no recordable findings noted T

OUTSIDE: Coated, no recordable findings MC Visual VT-G Accept INSIDE: Coating no recordable findings noted CT OUTSIDE: Coated, no recordable findings MC Visual IVT-G Accept, INSIDE: Coating no recordable findings noted CT OUTSIDE:i...ac-ce~s's'i ble-, -C~o-v e-red byý fire MC Visual IVT-G Accept INSIDE: Coating no recordable findings shielding COUTSIDE: Coated/non-coated, non-coated has MC Visual A

pVT-G INSIDE: Coating no recordable findings medium rust not. 20164011 CT OUTSIDE: Coated, no recordable findings MC lVisual VT-G Accept INSIDE: Coating no recordable findings noted CT I

OUTSIDE: Coated, no recordable findings MC lVisual IVT-G Accept INSIDE: Rust on coupling Not. 20162113 noted OUTSIDE: Coated, no recordable findings T

MC Visual lVT-G Accept INSIDE: Coating no recordable findings

_noted CT4 OUTSIDE: Coated, no recordable findings MC Visual

!VT-G iAccepit INSIDE: Coating no recordable findings noted CT OUTSIDE: Coated, no recordable findings MC

'Visual i VT-G Accept INSIDE: Coating no recordable findings noted_______

CT OUTSIDE: Coated/non-coated, non-coated has MC Visual v-G Accept INSIDE: Coating no recordable findings medium rust not. 20164011 Aa OUTSIDE: Inaccessible; Covered by fire e,

Visual VT-G INSIDE: Coating no recordable findings shielding 832700 IPEN-S2-E-36 832890 PEN-S2-E-37 QUADRANT A ELE PEN AT 85 EL.

QUADRANT A ELE PEN AT 85 EL.

11/17/2006 Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO 915 IWE Ixaminntinn RA*_*ultq Page 9 of 10 Revision 1 832900 IPEN-S2-E-38 8

833000 IPEN-S2-E-39 833100 PEN-S2-E-40 833200 !PEN-S2-E-41 833300 iPEN-S2-E-42 1833400 !PEN-S2-E-43 i833500 PEN-S2-E-44 833600 jPEN-S2-E-45 833700 PEN-S2-E-46 i

QUADRANT A ELECT PEN AT 88 EL.

QUADRANT A ELECT PEN AT 85 EL.

QUADRANT A ELECT PEN AT 88 EL.

QUADRANT A ELECT PEN AT 85 EL.

QUADRANT A ELECT PEN AT 90 EL.

QUADRANT A ELECT PEN AT 85 EL.

QUADRANT A ELECT PEN AT 88 EL.

QUADRANT A ELECT PEN AT 85 EL.

QUADRANT A ELECT PEN AT 88 EL.

QUADRANT A ELECT PEN AT 85 EL.

MC Visual IVT-G MC Visual fVT-G MC Visual VT-G MC Visual VT-G MC Visual 1VT-G MC IVisual IVT-G I

MC Visual VT-G MC Visual 1VT-G Accept Accept

Accept, Accept Accept Accept Accept Accept I

INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Rust on coupling Not. 20162113 INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings

-.U

-I1U-.

'.UdaLU, IIU I oLA UIUauIlt I[lmUlllyb noted OUTSIDE: Coated, no recordable findings noted OUTSIDE: Coated, no recordable findings noted OUTSIDE: Inaccessible, Covered by fire shielding OUTSIDE: Coated, no recordable findings noted OUTSIDE: Inaccessible, Covered by fire shielding OUTSIDE: Coated, no recordable findings noted OUTSIDE: Coated, no recordable findings noted OUTSIDE: Coated, no recordable findings noted Visual IVT-G I

MC Accept INSIDE: Coating no recordable findings 4

+-------.--

4 833800 PEN-S2-E-47 833900 PEN-S2-E-48 834000 IPEN-S2-E-49 834100 IPEN-S2-E-50 i

834200 !PEN-S2-E-51 834300 PEN-S2-E-52 834400 iPEN-S2-E-53 I

MC Visual IVT-G I

MC Visual VT-G MC Visual VT-G MC Visual VT-G MC Visual

-VT-G MC Visual VT-G MC Visual VT-G II C

VisualJ VT-G MC

~Visual Rr-F-G MC IVisual IVT-G MMC Visual VT-G Accept INSIDE: Rust on coupling Not. 20162113 noted OUTSIDE: Coated, no recordable findings Accept INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings Accept INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings Accept INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings Accept INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings-Accept INSIDE: Coating no recordable findings noted OUTSIDE: ISD:Cai no recordable findings Accept INSIDE: Coating no recordable findings noted OUTSIDE: mirror Insulation removed, coated Accept INSIDE: Coating no recordable findings sat,non-coat med. rust not. 20163807 OUTSIDE: mirror Insulation removed, coated I

Accept INSIDE: Rust on coupling Not. 20162113 satnon-coat med. rust not. 20163807 OUTSIDE: Coated, no recordable findings Accept INSIDE: Coating no recordable findings noted OT"S"I'D"E:" Coated, no recordable findings Accept INSIDE: Coating no recordable findings noted OUTSIDE: Coated, no recordable findings -1 834500 ;PEN-S2-E-54 8

0 I

834600 PEN-S2-E-55 834800 PEN-S2-E-57 QUADRANT A ELECT PEN AT 85 EL.

QUADRANT A ELECT PEN AT 85 EL.

Salem Nuclear Generating Station, Unit 2 ISI Program Long Term Plan RFO #15 IWE Examination Results 11/17/2006 Page 10 of 10 Revision 1 834900 fPEN-S2-E-58 835000 !PEN-S2-E-59 835100 !PEN-S2-E-60 j83 5200 IEN-S2-E-61 835300p PEN-S2-E-62 835400 IPEN-S2-E-63 835500 IPEN-S2-E-64 835600 IPEN-S2-E-65 UU*U'MN-kI'JI

/A r-LI",

PEN AT 85 EL.

QUADRANT A ELECT PEN AT 90 EL.

QUADRANT A ELECT PEN AT 88 EL.

QUADRANT A ELECT PEN AT 85 EL.

QUADRANT A ELECT PEN AT 88 EL.

QUADRANT A ELECT PEN AT 90 EL.

QUADRANT A ELECT PEN AT 88 EL.

QUADRANT D AIRLOCK AT 100 EL.

MC MC-MC MC Visual Visual Visual Visual VT-G IVT-G jVT-G Accept Accept Accept Accept MC MC MC MC MC MC Visual 1VT-G Visual IVT-G Visual

!VT-G Visual IVT-G Visual

,-3 Visual RVT-G Accept Accept Accept Accept Accept Accept INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Rust on coupling Not. 20162113 INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Coating no recordable findings INSIDE: Airlock 100' Pre-service VT-3 performed on repaired hinge No recordable issues INSIDE: Airlock 100' No recordable issues uu I 1.-iuL:

coated/non-coated, izstuds and Z4 nuts, no recordable findings OUTSIDE: Inaccessible, Covered by fire shielding OUTSIDE: Coated, no recordable findings noted OUTSIDE: Coated, no recordable findings noted OUTSIDE: Inaccessible, Covered by fire shielding OUTSIDE: Coated, no recordable findings noted OUTSIDE: Coated, no recordable findings noted OUTSIDE: Inaccessible, Covered by fire shielding N/A OUTSIDE: Coated, no recordable findings noted OUTSIDE: Minor paint chipping, medium rust, no measurable loss of metal, notification 20164181 OUTSIDE: N/A 835700 !ALK-S2-100-AIRLOCK 835700 IALK-S2-100-AIRLOCK

~1-

-~1

+

QUADRANT D AIRLOCK AT 130 EL.

MC Visual jI VT-G 835800 1ALK-S2-130-AIRLOCK Accept MC Visual iVT-G INSIDE: Airlock 130' No recordable issues INSIDE: Equipment Hatch Cover (16) bolting/nuts/washers - coating is chipped off of bolts; Only traces of coating appear on nuts. No rejectable items noted on the inspection of bolting/nuts/washers.

Acceptable for continued use. Not.20163296 Equipment I

835900 1 HCH-S2-130-EQ. HATCH IQUADRANT C EQUIPMENT HATCH AT 130 EL.

Accept

LR-N07-0016 Salem Unit 2 Owners Activity Report

SALEM GENERATING STATION UNIT 2-S2RFO15 OAR REPORT FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number S2RFO15 Owner PSEG Nuclear LLC, PO Box 236, Hancocks Bridge, NJ 08038 Plant Salem Generating Station Unit No. 2 Commercial Service Date October 31, 1981 Refueling Outage No. 15 Current Inspection Interval Third (3 d); IWE/IWL - First (1st)

Current Inspection Period First (1st); IWE/IWL-Third (3rd)

Edition and Addenda of Section XI Applicable to the inspection plan 1998 Edition 2000 Addenda; IWE and IWL - 1998 Edition, 1998 Addenda; Appendix VIII examinations - 1995 Edition 1996 Addenda as amended by Final Rule Date and revision of inspection plan 11/2003, Revision 0 Edition & Addenda of Section XI Applicable to repairs and replacements, if different than the inspection plan ASME Class 1, 2 and 3 - 1998 Edition, 2000 Addenda; Class MC-1992 Edition, 1992 Addenda (Unless specifically identified in the individual repair plan)

CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations, and corrective measures represented by this report conform to the requirements of Section XI.

'C4 II r

-fioi L f A k if h*-_

rlin.

I Ella c-vLI 1f1 ri L-.÷I

'll Signed "I.

s ria Date

.AP IiC dLU" QLcL I'J1P Owner or Owner's"Designe&, Tifre V,

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Hartford Steam Boiler Inspection and Insurance Company of Connecticut have inspected the items described in this Owner's Activity Report, during the period May 12, 2005 to November 1, 2006, and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, repairs, replacements, evaluations and corrective measures described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or con cted with this inspection.

___Commissions

/T 71C lnspqtar's Signature National Board, State, Province, and Endorsements Date QII/Pi?(/'(Qi-(

Pori= 1 nf '4

SALEM GENERATING STATION UNIT 2- $2RFO15 OAR REPORT TABLE 1 -ABSTRACT OF EXAMINATIONS AND TESTS Exam Total Total Total Total Remarks Category Examinations Examinations Examinations Examinations Required for Credited for Credited (%)

Credited (%)

the Interval the Period for the Period To Date for the Interval B-A 21 0

0%

3 rd Interval, 1st Period; See Note 1 B-B 8

1 13%

13%

3 rd Interval, 1s' Period; See Note 5 B-D 30 4

13%

3 rd Interval, 1 st Period; See Note 2 B-G-1 12 4

0%

3 rd Interval, 1St Period; See Note 1 B-G-2 84 35 42%

42%

3rd Interval, 1s' Period B-K 7

2 29%

29%

3 rd Interval, 1 t Period B-L-1 4

0 0%

0%

3 rd Interval, 1st Period; See Note 1 B-L-2 4

0 0%

0%

3Td Interval, 1t Period; See Note 3 B-M-1 2

2 100%

100%

3 rd Interval, Is Period; See Note 1 B-M-2 30 1

3%

3rd Interval, 1St Period; See Note 3 B-N-1 9

5 56%

56%

3 rd Interval, ls Period B-N-2 1

0 0%

0%

3 rd Interval, 1St Period; See Note 1 B-N-3 16 0

0%

3 rd Interval, 1 st Period; See Note 1 B-O 1

0 0%

0%

3 rd Interval, 1St Period; See Note 1 B-P 6

2 33%

33%

3rd Interval, 1st Period C-A 21 5

24%

3 rd Interval, 1 st Period C-B 6

0 0%

0%

3 rd Interval, 1Vt Period; See Note 6 C-C 38 8

21%

3rd Interval, 1 st Period C-D 2

0 0%

0%

3 rd Interval, 1st Period; See Note 7 C-G 2

1 50%

50%

3 rd Interval, 1 st Period; See Note 8 C-H 153 45 29%

29%

3 rd Interval, 1st Period D-A 37 11 30%

30%

3 rd Interval, 1 st Period D-B 174 58 33%

33%

3rd Interval, 1't Period F-A 269 82 30%

30%

3 rd Interval, 1 st Period R-A 147 56 38%

38%

3 rd Interval, lt Period; See Note 4 E-A 480 154 32%

98%

1 st Interval, 3 rd Period; See Note 9 L-A 372 0

0%

100%

1ot Interval, 3r Period; Notes:

1) Deferral permissible for: B-A, B-E, B-G-l, B-L-l, B-M-l, B-N-2, B-N-3, B-O

2) Reference Table IWB-2500-1, Exam Category B-D, Program (B) Notes 2 and 5

3) To be examined only if disassembled for maintenance, repair or volumetric exam. Reference Table IWB-2500-1, Exam Category B-l_-2, B-M-2, Note 2

4) Risk Informed was implemented in the second interval, third period, replacing ASME categories B-F, B-J, C-F-i, and C-F-2.

5) Reference Table IWB-2500-1, Exam Category B-B, Note 1

6) Reference Table IWC-2500-1, Exam Category C-B, Note 4

7) Reference Table IWC-2500-1, Exam Category C-D, Note 2

8) Reference Table IWC-2500-1, Exam Category C-G, Note 1

9) Inaccessible components will be examined when they become accessible.

!P ln 9 nf 'A

0 SALEM GENERATING STATION UNIT 2-S2RFO15 OAR REPORT TABLE 2 - ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Exam Item Item Description Flaw Characterization Flaw or Relevant Condition Found Category Number (IWA-3300)

During Scheduled Section XI Examination or Test (Yes or No)

D-B D2.10 Valve S2SW-22SW468 Non-Planar No TABLE 3 - ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Code

Repair, Item Description Description of Work Flaw or Relevant Date Repair/

Class Replacement, Condition Found Completed Replacement or Corrective During Scheduled Plan Number Measure Section Xl Examination or Test (Yes or No) 3 Replacement Valve S2SW -24SW63 Replacement of No 10/30/06 60066003 valve 2

Replacement Upper hinge stub of airlock Replacement upper No 10/29/06 60054240 of S2CAN-2RCE35 hinge stub 3

Replacement Flange connection to flow Replacement of No 08/22/06 60064581 orifice S2SW-2F16056 flange bolting 3

Repair 25 service water auto Repair of discharge No 05/05/06 60062566 strainer S2SW -2SWE1 1 nozzle 3

Replacement Instrument tubing to valve Replacement of No 12/23/05 60060182 S2SW - 22SW237 tubing 3

Replacement Instrument tubing to valve Replacement of No 12/08/05 60059645 S2SW -22SW4 tubing 2

Replacement Standpipe upstream of Replacement of pipe No 08/23/05 60057022 valve S2SW -24SW5 2

Replacement Flow transmitter tubing Replacement of No 10/30/06 60065541 S2RC -2FT415 tubing and block

!valve 2

Replacement Flow transmitter tubing Replacement of No 10/14/06 60065595 S2RC -2FT425 tubing 3

Replacement Valve S2SW-22SW468 Replacement of No 10/21/06 60035383 valve J

P~no -q nf.q

LR-N07-0016, Inservice Inspection Activities - 90-Day Report

Contents

Text

SUBJECT:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

LR-N07-0016, Inservice Inspection Activities - 90-Day Report

Text

SUBJECT:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search