ML102980133

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E-Mail from Conte to Defrancisco, ISI Inspection Feeder
ML102980133
Person / Time
Site: Salem PSEG icon.png
Issue date: 07/20/2010
From: Conte R
Engineering Region 1 Branch 1
To: Anne Defrancisco
NRC Region 1
References
FOIA/PA-2010-0334
Download: ML102980133 (29)
v • d • e


Text

DeFrancisco, Anne From: Conte, Richard l-Sent: Tuesday, July 20, 2010 3:48 PM To: DeFrancisco, Anne

Subject:

FW: ISI inspection Feeder Attachments: Salem 1-(2010003)(OHara)(ISI-Rpt)(TI-1 72)(04-10)(7-12-201 0)B3review.docx From: Burritt, Arthur Sent: Tuesday, July 20, 2010 1:18 PM To: Conte, Richard Cc: OHara, Timothy; Cline, Leonard; Schroeder, Daniel

Subject:

FW: ISI inspection Feeder Attached is a copy of the inspection feeder for Tim's inspection with several comments and recommended revisions from Branch 3.

There are several comments regarding needed adjustments to the write-up to comply with MC 0612 and also some other minor change recommendations. The most siqnificantcomments relate to the NRC-identified finding. V(b)(5 I (b)(5)

Please review and consider the attached comments and that we discuss later today.

W'~oMw in this record was deleted in accordanc wt*h the F,*,dor 0! Irnflormatn Act.

. I UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 475 ALLENDALE ROAD KING OF PRUSSIA. PA 19406-1415 July 15, 2010 MEMORANDUM TO: Arthur L. Burritt, Chief Projects Branch 3 Division of Reactor Projects THRU: Richard J. Conte, Chief IRA by E. Burket fori Engineering Branch 1 Division of Reactor Safety FROM: Timothy L. OHara, Reactor Inspector IRAI Engineering Branch 1 Division of Reactor Safety

SUBJECT:

INSERVICE INSPECTION ACTIVITIES INSPECTION FEEDER FOR SALEM UNIT 1, INSPECTION REPORT 05000272/2010003 The enclosed feeder contains input for the subject report resulting from inspection of.inservice Inspection (ISI) activities during the period from April 5, 2010 to June 28, 2010, at Salem Unit 1.

The inspection was conducted using Inspection Procedure 71111.08, Inservice Inspection Activities and Temporary Instruction (TI) 2515/172, Reactor Coolant System Dissimilar Metal Butt Welds. The results of this inspection were presented to Mr. Ed Eilola, Salem Plant Manager, at an exit meeting on June 28, 2010.

Enclosure:

Feeder for Salem Unit 1, Inspection Report No. 05000272/2010003, 05000311/2010003

A. Burrilt 2 cc w/

Enclosure:

(VIA E-MAIL)

A. Burritt, DRP L. Cline, DRP D. Schroeder, DRP, SRI - Salem Unit 1 T. O'Hara, DRS R. Hardies, NRR DRS Files SUNSI Review Complete: TLO/RJC (Reviewer's Initials)

Non-Public Designation Category: MD 3.4 Non-Public A.7 DOCUMENT NAME: g:\DRS\EB1\ohara\saleml-(2010003)(ohara)(isi-rpt)(ti-172)(04-10)(7-12-2010).doc After declaring this document An Official Agency Record" it will not be released to the Public.

To receive a copy of this document, indicate In the box: "C" Copy without atlachmentienctosure 'E" Copy wmth attachment/enclosure "N = No opy OFFICE RI/DRS IR/DDRS I/"RS NAME TO'Hara/TLO WSchmidt/cgc for RConte/ECB for DATE 07/12/2010 07/15/2010 07/15/2010 NAME DATE OFFICIAL RECORD COPY

SUMMARY

OF FINDINGS Reactor Safety Cornerstone: Mitigating Systems j Formatted: Indent: Left: 0.25", No bullets or Sn u m ber ing ---

'(ormatted. No bullets or numbering re. The Inspector identified a non-cited violation (NCV) of very lowlsafety signifiancebr(Green) for the-PSEG's failure to perform Auxiaauxiia eedwatefeedwater 44041ffisvt(AF) ,diischarge piping pressure tests on bured piping components as required by IOCFR 50.55a(g)(4) anidthereferenced American Society. of MechanicalEngineers Code (ASM Section X1 l'ragraph WA-6244 for Salem Unit,1 and Salem Unit 2. T6he'reuired I ests intfendedt j,;Aa to provide evidence of the structurall~ntegrity of the buldkpiping portions of the~systeni., The afected piping is safetyrelated, A.SM- Class 3, Seimicri, Class 1 piping. This peformarice'deficiencyi is mrore than minor because tIhe conditl&n Iffected the EqulfPment Performneattribu~te (availabilit and reliability)of the miiaig ytrs cornerstone objective ensurethe availability, reliability and capability ofsystemsthat r6eSp*.id totnitiatinig events'Jtoprevent undesirableconsequences (ie.,core danage)ý..NotrossCutting Aspectl,; assIilgn to this vioiati6n because thiscondition Is not indicative of!d'urrnt Commae-t [L2]- Thi section was not written perfOrmancel - . ia MC 0612 requirement*;:

IB.- Li o .dont o... .. .. gOther Findings First paragraph e wth signittcance (color or SL), or T8o, Then describe enforcement action, requirement viola"td tidentification

-- A-One violation of very low safety significance wih-,w4iGA was identified by PSEG,-, credit, immediate CAs to restore compltance, and statement that violation entered into CAP.

was reviewed

-by the inspectors. Corrective actions taken or planned by PSEG were entered into the Secondparagraph - Summarize significance as corrective action program. The violation and corrective action (Notification) tracking number is- "discussed In Analy svhgreater than mino2,

'effect on cornerstone, wyhy notgreater than are listed .. s..4.ed-in Section 40A7 of this report, green, crvss-cuttttng area, component arid aspect, alpha numeric ideititLer tifno cross-cutting aspect state, Reterence section of report.

.See MC 0612 pg28 and 29-

, , liý -

Formatted: No underline Formatted: NObullets or numbering Formatted: No bullets or numbering Formatted; Indent: Left: 0" ii

REPORT DETAILS 1R08 Inservice Inspection (ISI) (7111108- 1 Sample)

a. Inspection Scope The inspector observed a selected sample of nondestructive examination (NDE) activities in process. Also, the inspector reviewed the records of selected additional samples of completed NDE and repair/replacement activities. The sample selection was based on the inspection procedure objectives and risk priority of those components and systems where degradation would result in.a significant increase in risk of core damage.

The observations and documentation reviews were performed to verify that the activities inspected were performed in accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code requirements.

The inspector reviewed the licensee's performance of a visual inspection (VT) of the Unit 1 Reacter-reactor Vesel-_vessel _Qs*-e-closure Head-head (RVCH) and the installed upper head penetrations. The inspector reviewed the visual procedure, the qualifications of the personnel and reviewed the inspection report documenting the inspection results. The inspector also reviewed the data sheets for the penetrant tests completed on 3-three of the penetration welds of the RVCH.

The inspector reviewed records e4-for ultrasonic testing (UT), visual testing (VT),

penetrant testing (PT) and magnetic particle testing (MT) NDE processes. PSEG did not perform any radiographic testing (RT) during this outage. The inspector reviewed inspection data sheets and documentation for these activities to verify the effectiveness of the examiner, process, and equipment in identifying degradation of risk significant systems, structures and components and to evaluate the activities for compliance with the requirements of ASME Code,Section XI.

Steam Generator Inspection Activities

,The inspectors reviewed a sample of the Salem Unit 1 steam generator E-d-dd- Field Code Changed

  1. u.Fent-current steg- (ECT) tube examinations, and applicable procedures for monitoring degradation of steam generator tubes to verify that the steam generator examination activities were performed in accordance with the rules and regulations of the steam generator examination program, Salem-Unit 1 steam generator examination guidelines, NRC Generic Letters, Code of Fedoral Rogubatine6 100CFR 50, Unit 1

-TehnaJ3-technical $pis ssecificationsfcr Salem Un~t 1, Nuclear Energy Institute 97-06, EPRI PWR steam generator examination guidelines- and the ASME Boiler and Pressure Vessel Code Sections V and XI. The review also included the Salem-Unit 1 steam generator degradation assessment and steam generator Cycle 21 and 22 operational assessment. The inspector also reykewed-aed-verified the PBrGOnne-certifications ef-t4efor personnel participating in the SG ECT inspections during the 1 R20 refueling outage.

2 The inspectors reviewed the-PSEG's efforts in identifying wear degradation to the tubing in the four Sds at Salem-Unit 1. The majority of these-wear indications waiere attributed to Aanti-44a4oavibration_*4S-bar (AVB) wear in the o-u-bend regions of the four SGs. The inspectors reviewed the analyses and evaluations whie~hthat determined that a total of 14 SG tubes would be removed from service by plugging.

Boris Acid Corrosion Control Pro-gram Activities The inspectors reviewed the PSEG boric acid corrosion control program. The -esideFA inspectors observed PSEG personnel performing boric acid walkdown inspections inside containment- and in other affected areas outside of containment- at the beginning of the Unit 1 refueling outage. The inspectors reviewed the 4notifications generated by the walkdowns and the evaluations conducted by Engineering to disposition the Netifiatierenotifications. Additionally, the inspector reviewed a sample of Netifi.atiGo-notifications and corrective actions oaF:Ned ýAcompleted to repair the reported conditions.

Section XI Repair/Replacement Samples:

AFW System Piping, Control Air & Station Air: The inspectors reviewed PSEG's discovery, reporting, evaluation and the repair/replacement of Unit 1 AFW piping whieW that had- bqeewas excavated for inspection during the April 2010 Unit I refueling outage (1R20). PSEG conducted this inspection in accordance with PSEG's Buried Piping Inspection Program.

The inspector reviewed the repair/replacement work orders and the 50.59 screening and evaluation for the AFW, CA and SA piping. The inspector reviewed the fabrication of the replacement piping, reviewed the documentation of the welding and NDE of the replacement piping and reviewed the'pressure tests used to certify'the replacement piping. Additionally, the inspector review*edthe specified replacement cobtir6g, the application of the replacement coating'andthe backfill of the excavated ar'eaafter the piping had been tested.

(b)(5)

Reiectable Indication Accepted For Service After Analysis:

The inspector reviewed the Notification and the UT data report of a rejectable wall thickness measurement on the #11 SG Ffeedwater elbow during 1R20, The inspector reviewed the additional wall thickness data taken to further define'the condition and reviewed the finite element analysis (FEA) whioh-that verified 04a4-sufficient wall thickness remained to operate the component until the next refueling outage when it will la) ! rs5n)r' 1(b)(5)

(b)(5)

(b)(5)

(b)(5)

The inspector identified the following violation related to ASME,Section XI testing of buried Unit 1 and Unit 2 buried AFW piping.

Introduction The inspector identified a GREEN non-cited violation (NCV) of 10 CFR 50.55a(g)(4) and the referenced American Society of Mechanical Engineers (ASME)

Code, Section Xl, paragraph IWA-5244 for PSEG's failure to perform required pressure tests of buried components. This piping is safety related, 4.0" ID, ASME Class' 3, Seismic Class 1 piping.

Description Portions of the Unit I:and Unit 2 Auxillar Feedyater (AFW) System pipiring is buried piping and has not been.visually inspected since the p*in began operation in 1977 for Unit.1 and sInce 1979 for.Salem Unit 2. In April 2010, approximately 680 ft.

(340 ft. of the #12 SG AFW'supply,and 340 ft. of the #14 SG AFW supply) of piping, Main Feedwater piping (b)(5) between the pump discharge manifoldrand the connection tothe to the'affected SGs was, discovered to be corroded to below minimum Wall thickness (0.278") for the' 1950 psi design pressure of - MAOZ^*+,*, Th*, , ,, thLns mAe urpd in the affected olbind was 0.077:()(

(b)(5) 10 CFR 50.55(a)(g)(4)(ii) requires licensees to follow the in-service requirements of the ASME Code,Section XI. Paragraph IWA-5244 requires licensees to perform pressure tests on buried components to demonstrate structural integrity of the tested piping. The pressure test requifncd hv IWA-5244 is considered to be an inservice inspection and is (b)(5)

PSEG sought relief, from the NRC, from the previous Code required pressure testing in 1988 for Unit 1 only. Relief was granted to PSEG, by the NRC, to perform an alternate flow test in 1991 for Unit 1. However, PSEG did not perform the proposed alternate tests during the 2 nd inservice interval and during the 1"* (5/19/01 to 6/3/04) an (6/24/04 to 5/20108) periods of the 3rd In Service Inspection Intervalfor Unit 1. (b)(5)

(b)(5)

5 missed an opportunity to identify and correct this performance deficiency which affects Unit 1 and Unit 2.

(b)(5)

(b)(5)

PSEG repl*c*d the affected buded'Unit I piping durng the refueling outage inApIrllMay 2010. The required presjs**_e tests were successfully completed aftetithe replaceieent of 1hurind pnIjlnaI(b)(5)

IM~n!,

(b)(5)

The Inspectori determined that a Cross Cutting Aspect did not exist because the issue was not indicative of current performance because the condition existed since 1991, Mrne than 3,years, ago. .Specifically.

Enforcement 10 CFR 50.55a(g)(4) states, in part: "Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components ... which are classified as ASME Code Class 1, Class 2 and Class 3 must meet the requirements,...

set forth in Section Xl of editions of the ASME Boiler and Pressure Vessel Code".

Paragraph IWA-5244, Buried Components, of Section XI says, in part,

"(b) For buried components where a VT-2 visual examination cannot be (1) The performed, the examination requirement is satisfied by the following:

6

'system pressure test for buried components that are isolable by means of valves shall consist of a test that determines the rate of pressure loss. Alternatively, the test may determine the change in flow between the ends of the buried components... "

Contrary to these requirements, PSEG did not perform the required pressure tests of the buried AFW piping to the #12 SG and #14 SG at Salem Unit 1 during the 2"d In Service Inspection Interval (2/27/88 to 5/19/01) and during the 1" (5/19/01 to 6/3/04) a ,

(6/24/04 to 5/20/08) periods of the 3 In Service Ins pection Interval ()5/19101 c,)(5)

(b)(5)

Because PSEG entered this condition into the corrective action process (Notification 20459686) and because it is s.-of very 1lw safety significance (Green), it is being treated as a non-cited violation consistent with Section VI.A.1 of the NRC Enforcement Policy.

NCV 50-272/2010-7? and NCV 50-311/2010-??

Outside of Scope

7 Outside of Scope 40A7 Licensee Identified Violations 4he4followng fiidingof verylow safety significance was identified byjPSEG., The findinaq was. aRýa Is a violationof0 C1&R.50, 'Appendix B, CrierinllI*DesignEGontrol'tht-reg ired. ,ipartithat measures shall be establi*shedto asisure t reoaire'merits'dideslon ,basis are corretlyW6t~~slated. nto se iaih~ rwnsn inStrubtio6ts anhd that.these:measures shall lincidde piVisions tobassuethedýiprpe selection an d'review for suitability of aippliti6hýof materials, pailts eguipmentC and

_rocess_ . ,an NRCo t idnot rovide'

' anberote i ........ "

f~th~uri~ARN~n'ntnnilitl bj (b)(5)

(b)(5) b)(5)61 Formatted: Indent: Left: 0,5",First le; 07 Because PSEG entered this condition into the corrective action process (Notification 20456999) and because the issue is of very low safety significance (Green), this issue is being treated as a non-cited violation consistent with Section VIA.1 of the NRC Enforcement Policy. NCV 50-27212010003-??

A-1 ATTACHMENT SUPPLEMENTAL INFORMATION KEY CONTACTS Licensee Personnel:

ýb)(5)

LIST OF DOCUMENTS REVIEWED Notifications:

20457869, Control Air Piping Leak*

20462034, Basis AFW Discharge Line Design Pressure*

20461785, Untimely retrieval of Design Documents*

20461255, U2 Containment Liner Blisters*

20459259, U2 Containment Liner Blisters*

20459689, failure to do IWA-5244 pressure tests*

20456999, Guided Wave (GW) pipe wall loss 20% to 44%*, in Equipment Apparent Cause Evaluation (EQ;ACE) Charter 20457854, see Equipment Apparent Cause Evaluation (EQ: ACE) Charter 20457869, Air Line Leak, in Equipment Apparent Cause Evaluation EQ: ACE Charter 20458147, see Equipment Apparent Cause Evaluation (EQ: ACE) Charter 20458148, see Equipment Apparent Cause Evaluation (EQ: ACE) Charter 20458568, see Equipment Apparent Cause Evaluation (EQ: ACE) Charter 20458554, 11 CA HDR Line In Fuel Xfer Area Degraded*

20458761, 1R20 CA Buried Pipe Coating Repair*

20458925, 1R20 SA Buried Pipe Coating Repair*

20457262, (88) 1R20 AF Buried Pipe Inspection Results*

20460624, Need Heat Trace on AF lines in FFT Area 20457877, Ul Containment Liner Corrosion at 78' El.*

A-2 20459259, Ul Corrosion on Containment Liner*

20459303, #14 AF pipe damaged penetration seal*

20459304, #12 AF pipe damaged penetration seal*

20459454, Request for Additional UT Data, 4/18/10 (due to 0.077" reading)*

20344017, Inspect steel liner in 11R19 20235636,.NRC noted water running down containment wall 204591.89, Question on location of RFO-14 location of a PZR shell weld 20290560, Replace section of 15B FWH shell-S1-R18 20457879, (184) 1R20 FAC(N18) 14# elbow below Tmin 20456828, (66) valve has visible boron buildup 1 R20

  • 20459232, Heavy Dry White Boron VIv Packing (1R20)
  • 20456834, Heavy Dry White Boron Vlv Packing (1 R20) 20456840, Medium Dry White Boron Vlv Packing (1R20) 20456839, Medium Dry White Boron VIv Packing (1 R20) 20389147, Recordable ISI Indications on CVC Tank 20344017, Inspect Steel Liner in 1R19 @ Containment Sump
  • 20235636, NRC Noted Water Running Down Containment Wall 20392631, ARMA From ISI Program Audit 2008 20460624, Need Heat Trace on AF lines in FTT Area 20333050, Response to NRC NOV EA-07-149 20322039, 20 Interval ISI NRC Violation 20397518, AlCVC-1CV180.Chk VIv Stuck Open - PI&R review 20444514, Boric Acid Leak from Drain Line - PI&R review 20445314, boron leak - PI&R review 20448241, Minor Packing Leak - BAC - PI&R review 20435861, 21SJ313 Has Boric Acid Leakage - PI&R review 20417331, Boric Acid Leak at 11 CV156- PI&R review 20411151, Tubing leak on 1SS653 - PI&R review 20414343, 12 Charging Pump seal inj. Line - PI&R review 20395346, 12 Bat PP Seal Leak - PI&R review 20450330, Containment Liner Corrosion - PI&R review 20385733, Severe Corrosion on FP Valve - PI&R review 20438320, (217) Op Eval. Of Containment Corrosion - PI&R review 20387897, Significant outlet pipe corrosion - PI&R review 20397225, MIC Corrosion Causing Through Wall Leak - PI&R review 20436836, Repair Cracks in Battery Cells - PI&R review.

20392145, Update U1 ISI Relief Request Book - PI&R review 20449447. Update Salem Unit 1 IS110 Yr Plan -PI&R review 20449744, Update Salem Unit 1 Containment ISI 10 Yr Plan - PI&R review 20449442, Update Salem Unit 2 Containment ISI 10 Yr Plan - PI&R review 20449554, Salem U2 RFO18 ISI Scope - PI&R review 20416605, INPO PSIRV Alloy 600 Program - PI&R review 20404057, Unit 2 ISI (MSIP) - PI&R review 20392631, ARMA FROM ISI PROGRAM AUDIT 2008 - PI&R review 20388065, Water leaking in decon room - PI&R review 20439023, 23 CFCU Head Leakage - PI&R review 20439022, SW Header Leakage 23 CFCU - PI&R review 20389148, 1R19 ISI Weld Exam Limitations - PI&R review 20416605, INPO PSIRV Alloy 600 Program - PI&R review 20449442, Update Salem 2 Containment IS110 yr. Plan ý PI&R review 20449554, Salem Unit 2 RFO18 ISI Scope - PI&R review

A-3 20449747, Update Salem 2 ISI 10 Yr. Plan - PI&R review 20401542, Perform ISl BMV Exam on RPV Upper Head - PI&R review 20449063, SA Ul Service Inspec -. ISI & Ul TI 2515 - PI&R review 20389147, Recordable ISI Indications on CVC Tank - PI&R review 20392145, Update U_! ISI Relief Request Book - PI&R review 20449744; Update Salem Ul Containment .ISI 10 Yr. Plan - PI&R review 20409943, NRC RIS 2009-04 SG Tube Insp Rqmts - PI&R review 20459851, Section XI Exams Limited to 90% or Less - PI&R review 20450520, Recoat Affected Areas of Liner 2R18 - PI&R review 20457388, Excavation Issues - PI&R review

  • Denotes this Notification was generated as a result of this inspection Section XI Repair/Replacement Samples:

W.O. 60079414, 14" Carbon Steel Elbow FAC indication below minimum wall W.O. 60084266,, Salem U1 AF Buried Piping Inspection W.O.'60089561, 80101381: Replace Aux FW U/G Piping W.O. 60064104, Repair 15B FWH Area W.O. 60084375, BACC Program repair to 1PS1 W.O. 60089612, BACC Program repair to SlCVC-14CV392 W.O. 60089615, BACcO Program repair to S1SJ-13SJ25 W.O. 60089848, 80101382 Advanced Work Authorization #2 FTTA Replace Aux. Feedwater Pipe W.O. 60089561, 80101381 Advanced Work Authorization - Replace Aux. FW U/G Piping, 4/9/10 Non-Code Repair WO. 60089848, Repair Non-nuclear, safety related CA Pipe, Unit 1 FTTA W 60089757, Test Non-nuclear, safety related CA Pipe Repair, Unit 1 FTTP, Miscellaneous Work Orders:

W.O. 60089917, Penetrations for CA & SA Lines, 4/23/10 W.O. 941017262, Activity 04, Excavate and ExamineAuxiliary Feedwater Piping, Unit 2, 12/94 W.O. 941017262, Activity 03, Excavate and Examine Auxiliary Feedwater Piping, Unit 2, 12/94 W.O. 941017262, Activity 02, Excavate and Examine Auxiliary Feedwater Piping, Unit 2, 12/94 W.O. 941017262, Activity 01, Excavate and Examine Auxiliary Feedwater Piping;, Unit 2, 12/94 W.O. 60089561, Flush New AFW piping 12 and 14 Drawings & Sketches:

205236A8761-54, Salem Nuclear Generating Station, Unit No. 1, Auxiliary Feedwater Salem Unit 1 Aux Feed Piping, Allan Johnson, 4/10/10 80101381RO, Buried Pipe, Replaced AFW Piping Arrangement 207483A8923-1 1, Salem Nuclear Generating Station, Unit No. 1 - Reactor Containment Auxiliary Feedwater, Plans & Sections - Elev. 78' 10" & 100' 0", Mechanical Arrangement, Revision 8, 9/31/86

A-4 207483A8923-28, Sheet 1 of 4, Salem Nuclear Generating Station, Unit No. 1 - Reactor Containment Auxiliary Feedwater, Plans & Sections - Elev. 84',Mechanical Arrangement, Revision 8, 9/31/86 207483A8923-31, Sheet 2 of 4, Salem Nuclear Generating Station, Unit No. 1 - Reactor Containment Auxiliary Feedwater, Plans & Sections - Elev. 84', Mechanical Arrangement, Revision 8, 9/31186 207483A8923-28, Sheet 3 of 4, Salem Nuclear Generating Station, Unit No. 1 - Reactor Containment Auxiliary Feedwater, Plans & Sections - Elev. 84',Mechanical Arrangement, Revision 8, 9/31/86 207483A8923-30, Salem Nuclear Generating Station, Unit No. 1 - Reactor Containment Auxiliary Feedwater, Plans & Sections - Elev. 84',Mechanical Arrangement, Revision 8, 9/31/86 207610A8896-12, Salem Nuclear Generating Station, Unit No. 1 - Auxiliary Building & Reactor Containmnet Compressed Air Piping, Aux. Building El. 84 East & React. Contain. El. 78, Mechanical Arrangement, Revision 8, 9/31/86 Design Change Packages/Equivalent Change Packages 80101382, Revision 2, Replace Salem Unit 1 AFW Piping from the Unit Mechanical Penetration Area El. 78'-0" to the Unit 1 Fuel Transfer Tube Area El. 100'-0" 80101381, Revision 1, Replace in-kind the Salem Unit 1 AF Piping that runs underground from the Unit 1 Fuel Transfer Tube Area to the Unit 1 Main Steam Outer Penetration Area 50.59 Applicability Reviews, Screenings & Evaluations 80101382; Salem Unit 1 12/14 AF Piping Reroute; 4/24/10 System & Program Health Reports & Self-Assessments:

Salem Boric Acid Corrosion Control Program Focused Area Self-Assessment, 112010 70106830, Salem S1R20 NRC 1SI Inspection Check-In Self Assessment 70095327, Salem Boric Acid Corrosion Control Program Focused Area Self-Assessment, 4/29/09 Program Documents PSEG Nuclear Salem Units 1 & 2, Alloy 600 Management Plan, Long Term Plan (LTP),

Revision 2, Integrated Strategic Plan For Long Term Protection from Primary Water Stress Corrosion Cracking (PWSCC), 10/15/09 ASME,Section XI,1998 Edition, 2000 Addenda, IWA-5244 Buried Components OAR-l, Owner's Activity Report, #S1RFO19, 1/15/09

A-5 Procedures DETAILED AND GENERAL, VT-1 AND VT-3 VISUAL EXAMINATION OF ASME CLASS MC AND CC CONTAINMENT SURFACES AND COMPONENTS SHRA - AP.ZZ - 8805(Q) - Revision 4, 8/31/06; Boric Acid Corrosion Management Program ER - AP - 331, Revision 4, Boric Acid Corrosion Control (BACC) Program ER - AP - 331 - 1001, Revision 2, Boric Acid Corrosion Control (BACC) Inspection Locations, Implementation And inspection Guidelines ER - AP - 331 - 1002, Revision 3, Boric Acid Corrosion Control (BACC) Program Identification, Screening, and Evaluation ER - AP - 331 - 1003, Revision 1. RCS Leakage Monitoring And Action Plan ER - AP - 331 - 1004, Revision 2, Boric Acid Corrosion Control (BACC) Program Training and Qualification ER - AA - 330 - 001, Revision 7, SECTION Xl PRESSURE TESTING LS - AA - 125, Revision 13; Corrective Action Program (CAP) Procedure LS - AA - 120, Revision 8; Issue identification And Screening Process SH.RA-IS.ZZ-0005(Q)-Revision 6; VT-2 Visual Examination Of Nuclear Class 1, 2 and 3 Systems SH.RA-IS.ZZ-0150(Q)- Revision 8, 10/19/04; Nuclear Class 1, 2, 3 and MC Component Support Visual Examination OU-AP-335-043, Revision 0; BARE METAL VISUAL EXAMINATION (VE) OF CLASS 1 PWR COMPONENTS CONTAINING ALLOY 600/82/182 AND CLASS 1 PWR REACTOR VESSEL UPPER HEADS OU-AA-335-015, Revision 0; VT 2 - VISUAL EXAMINATION Areva NP, Inc., Engineering Information Record 51-9118973-000; Qualified Eddy Current Examination Techniques for Salem Unit 1 Areva Steam Generators, 10/15/09 AREVA NP 03-9123233, Revision 000, 10/13/09; Salem Unit 2 RVCH Flange Repair SC.MD-GP.ZZ-0035(Q) - Revision 9, PRESSURE TESTING OF NUCLEAR CLASS 2 AND 3 COMPONENTS.AND SYSTEMS, 02/02/10 SH.MDGP.ZZ-0240(Q) - Revision 10, SYSTEM PRESSURE TEST AT NORMAL OPERATING I -PRESSURE AND TEMPERATURE, 7/29/09 S2.OP-AF-0007(Q)-Revision 20, 12/23/09; INSERVICE TESTING AUXILIARY FEEDWATER VALVES, MODE 3 ER-AA-5400-1002, Revision 1, BURIED PIPING EXAMINATION GUIDE Specification No. S-C-MPOO-MGS-0001; Piping Schedule SPS54, Auxiliary Feedwater, Revision 6 PSEG Test Procedure 10-H-8-R1, Unit 2 Auxiliary Feedwater 2100/2150 Hydro; 9/21/78 NDE Examination Reports & Data Sheets 003753, VT-10-113, PRV nozzle sliding support 003754, VT-10-114, RPV nozzle sliding support 006325, UT-10-041, PZR longitudinal shell weld J (100%)

007500 UT-1 0-132, PZR surge line nozzle (100%)

007901, UT-1 0-028, 13 SG lower head to tubesheet weld (67%)

006073, VE-10-026, CRDM TO VESSEL PENETRATION WELD, 4/12/10 008001, VE-10-027, 31-RCN-1130-IRS 008026, VE-10-028, 29-RCN-1130-IRS 009070, VE-10-030, 12-STG Channel Head Drain (100%)

033300, UT-10-027, 4-PS-1131-27 (100%)

033200, UT-10-029, 4-PS-1131-26 (100%)

A-6 033100, UT-10-032, 4-PS-1131-25 (100%)

032300, UT-t0-033, 4-PS-1 131-17 (100%)

031700, UT-10-040, 4-PS-1131-12 (100%)

032600, UT-10-034, 4-PS-I 131-20 (100%)

047600, UT-10-045, 29-RC-1 140-3 (100%)

051200, UT-10-048, 29-RC-1120-3 (100%)

203901, UT-10-047, 32-MSN-2111 -1 (100%)

204001, UT-10-046, 16-BFN-2111-1 (70.64%)

210586, UT-10-025, 14-BF-2141-19 (100%)

210588; UT-10-024, 14-BF-2141-20 (100%)

836300, IWE: VT-10-338, PNL-S1-343-1 836400, IWE: VT-i0-333, ALK-Sl-100-tubing 840000, IWE: Vert Leak Channels 1 - 14 006073, VE-10-026, RPV Upper Head Inspection 006051, PT-10-004, CRDM Housing Weld Exams, penetrations #66, 67, and 72 Salem Unit 1, VT-2, Visual Examination Record, 12/14 AF FTTA, W.O. 60089848, 4/26/10 (VT)

Salem Unit 1, VT-2, CA Repair Snoop Test. W.O. 60089575, 4/27/10 Salem Unit 1, UT, W.O. 60084266, Yard AF, 4/18/10 Salem Unit 2, UT, W.O,60089851, Exam of containment liner Salem Unit 1, UT 1-SGF-31-L2 FW elbow below min. wall Salem Unit 1, UT, W.O. 30176541, 1-SGF-31-L2 FW elbow below min, wall Salem Unit 1, UT, W.O. 60084266, AFW Order 50113214, ST 550D, Surveillance: ISI Perform PORV Check Order 50118090, ST 550D, Surveillance: OPS Perform PORV Check W.O. 60089848, VT-2 Visual Examination Record, 12/14 AFW in FTTA, 4/26/10 W.O. 941017262, Activity 02; Salem Unit 2, Excavate and Examine Auxiliary Feedwater Piping, 12/2/94 W.O. 60084266, UT Unit 1 AFW (thinnest area), 4/20/10 UT Analysis, Component 1-SGF-31-L2 (14" FW Elbow below Minimum wall), 4/10/10 W.O. 60089851, Unit 2 Containment Liner blister UT measurements, 4/21/10 W.O. 60086175, Unit 1 Containment corrosion 78' elevation W.O. 60084266, Unit 1 AFW piping UT measurements, 4/12/10 W.O. 30176541, Unit 1 AFW piping UT measurements, 4/12/10 WO. 60084266, Unit 1 AFW piping UT measurements, 4/7/10 W,O. 60084266, Unit I AFW piping UT measurements, 4/5/10 W.O. 60084266, Unit 1 AFW. pipe UT measurements at supports, 4/18/10 W.O. 30176541, Unit 1 CA piping UT measurements in FTTA 401600, VE-04-198; Hope Creek system pressure test CST to HPCI/RCIC and Core Spray, 11/5/04 VT-2, Salem Unit 1 AF 12 & 14 Pressure Test, 4/25/10 W.O. 60089661, UT measurements, Unit 2 AFW Piping #24 in FTTA, 4/25/10 W.O. 60089661, UT measurements, Unit 2 AFW Piping #22 in FTTA, 4/26/10

Outside of scope A-8 Engineernng Analyses & Calculations & Standards Calculation 6SO-1882, Revision 1, 8130/96; Qualification of Safety-Related Buried Commodities For Tornado Missle and Seismic Evaluation Calculation No. S-C-AF-MDC-1 789; Salem Auxiliary Feedwater Thermal Hydraulic Flow Model, 10/4/00 70087436, Steam Generator Degradation & Operational Assessment Validation, Salem Unit 1 Refueling Outage 18 (1R 18) & Cycles 19/20, 9/2008 51-9052270-000, Update - Salem Unit 1 SG Operational Assessment At 1Ri8 For Cycles 19 and 20, 10/1/08 51-9048311-002, Salem Unit 1 SG Condition Monitoring For 1R18 And Preliminary Operational Assessment For Cycles 19 and 20, 10/30/07 701086998-0050, Maximum Pressure in Underground Auxiliary Feedwater Piping 60089575-130, Past Operability Determination for the leak in the one inch air line to air operated valves in Unit 1 South Penetration Area 70109233/20459231; Boric Acid evaluation of leakage from S 1CVC-I"CV277 70109232/20459230; Boric Acid evaluation of leakage from S 1CVC-1CV2 70109230/20459228; Boric Acid evaluation of leakage from S2RC-1PS1 70109234120459232; Boric Acid evaluation of leakage from S 1SJ-1 3SJ25 70108698/30, Operating Experience Report for degraded Unit 1 AFW piping 51-9135923-000, AREVA; Salem unit 1 SG Condition Monitoring For 1R20 and Preliminary Operational Assessment For Cycles 21 And 22, 4/20/10 SA-SURV-201 0-001, Revision 1; Risk Assessment of Missed Surveillance - Auxiliary Feedwater discharge line underground piping pressure testing, 4/23/10 CQ9503151526; SCI-94-0877, EXCAVATED AUXILIARY PIPING WALKDOWN/DISPOSITION OF COATING REQUIREMENTS; 12/16/94 Specification No. S-C-M600-NDS-019, COATINGS INTERIOR/EXTERIOR SURFACES CARBON STEEL SERVICE WATER PIPING, NO. 12 COMPONENT COOLING HEAT EXCHANGER ROOM AUXILIARY BUILDING (ELEVATION 84)

Structural Integrity Associates, Inc. Calculation File No. 1000494.301, Evaluation of Degraded Underground Auxiliary Feedwater Piping (Between Unit 1 FTTA and OPA), 4/23/10 Technical Evaluation 60089575-0140, Acceptability of CA Piping in the Fuel Transfer Area, 4/29/10 Technical Evaluation 60089848-0960, Auxiliary Feedwater Piping Missle Barrier Exclusion, 4/29/10 Structural Integrity Associates, Inc. Calculation File No. 1000498,301, Evaluation of Thinned Feedwater Elbow, 4/22/10 Technical Evaluation 70108698-0050, Maximum Pressure in Underground Auxiliary Feedwater Piping, 4/29/10 SPECIFICATION NO. S-C-MPOO-MGS-0001, Piping Schedule SPS54 AUXILIARY FEEDWATER, Revision 6 OpEval. #10-005, Salem Unit 2 Operability Evaluation, Received 5/18/10 Technical Evaluation 60084266-105-20,'Alternative Exterior Coatings for'Buried Piping, AF, CA, SA and Pipe Supports Under W.O. 60084266, 4/2/10 Technical Evaluation H-1-EA-PEE-1871, Hope Creek Service Piping Coatings Alternatives, 80075587, Revision 0, 10/15/04 PSEG Nuclear, LLC, Technical Standard, Coating Systems and Color Schedules, Revision 5, 4/3/06

A-9 Weld Records - AFW Piping Repair (W.O. #'s 60084266, 60089561, 60089798, 60089848)

Multiple Weld History Record: 74626 Multiple Weld History Record: 74556 Multiple Weld History Record: 74557 Multiple Weld History Record: .74558 Multiple Weld History Record: 74559 Multiple Weld History Record: 74560 Multiple Weld History Record: 74561 Multiple Weld History Record: 74562 Multiple Weld History Record: 74563 Multiple W1ld History"Record: 74564 Multiple Weld'History Record: 74565 Multiple Weld History Record: 74566 Multiple Weld History Record: 74567

  • Multiple Weld History Record: 74627
  • Multiple Weld History Record: 74569 Multiple Weld History Record: 74599 Multiple Weld History Record: 74623 Multiple Weld History Record: 74600 Multiple Weld History Record: 74630 Multiple Weld History Record: 74622 Multiple Weld History Record: 74578 Multiple Weld History Record: 74596 Multiple Weld History Record: 74601 MultipleWeld History Record: 74602 Multiple Weld History Record: 74603 Multiple Weld History Record: 74604 Multiple Weld History Record: 74605 Multiple Weld History Record: 74598 Multiple Weld History Record: 74606 Multiple Weld History Record: 74607 Multiple Weld History Record: 74608 Multiple Weld History Record: 74609 Multiple Weld History Record: 74610 Multiple Weld History Record: 74611 Multiple Weld History Record: 74612 Multiple Weld History Record: 74613 Multiple Weld History Record: 74614 Multiple Weld History Record: 74615 Multiple Weld History Record: 74597 Multiple Weld History Record: 74616 Multiple Weld History Record: 74579 Multiple Weld History Record: 74580 Multiple Weld History Record: 74581 Multiple Weld History Record: 74582 Multiple Weld History Record: 74583 Multiple Weld History Record: 74595 Multiple Weld History Record: 74584 Multiple Weld History Record: 74585 Multiple Weld History Record: 74586

A-10 Multiple Weld History Record: 74587 Multiple Weld History Record: 74588 Multiple Weld, History Record: 74589 Multiple ,Weld History Record: 74590 Multiple Weld History Record: 74591 Multiple Weld History Record: 74592 Multiple Weld History Record: 74593 Multiple Weld History Record; 74577 Multiple Weld History Record: 74625 Multiple Weld History Record: 74574 Multiple Weld History Record: 74624 Multiple Weld History Record: 74573 Multiple Weld History Record: 74572 Multiple Weld History Record: 74570 Multiple Weld History Record: 74571 Multiple Weld History Record: 74623 Multiple Weld History Record: 74622 Multiple Weld History Record: 74621 Multiple Weld History Record: 74537 Multiple Weld History Record: 74538 Multiple Weld History Record: 74537 Welder Stamp Number: P-664 Welder Stamp Number: P-65 Welder Stamp Number: P-466 Welder Stamp Number: P-57 Welder Stamp Number: E-64 Welder Stamp Number: P-710 Welder Stamp Number: P-207 Welder Stamp Number: P-666 Welder Stamp Number: P-708 Welder Stamp Number: E-89 Welder'Stamp Number: P-84 Welder Stamp Number: P-228 Surface Exam Record: 60089561-0041 Surface Exam Record: 60089848-0001 Surface Exam Record: 60089848-0001 Surface Exam Record: 60089561-0041 Surface Exam Record: 60089561-0860 Miscellaneous Documents Salem Unit 1 & Salem Unit 2 Technical Specification, 3.4.11 STRUCTURAL INTEGRITY, ASME CODE CLASS 1, 2 AND 3 COMPONENTS Electric Power Research Institute (EPRI), Steam Generator Integrity Assessment Guidelines, Technical Report 1012987, Revision 2, July 2006 NRC Letter dated 3/11/91: FIRST TEN-YEARINSPECTION INTERVAL, INSERVICE INSPECTION PROGRAM RELIEF REQUEST, SALEM NUCLEAR GENERATING STATION, UNIT 1 (TAC NOS. 66013 AND 71101),

PSEG Nuclear, Salem Unit 1 & 2 Alloy 600 Management Plan, Long Term Plan (LTP), Revision 2,10/15/09 Salem Unit 1 - Buried Piping Risk Ranking

A-11 MPR Associates Report, Technical Input To Operability of Potential Containment Liner Corrosion, Revision 0, 10/30/09 Transmittal of Design Information #S-TODI-2010-0005, 4120/2010 Transmittal of Design Information #S-TODI-2010-0004, 4/1612010 0Q950315126, PSEG Itr., Dated 12/16/94; Excavated Auxiliary Feedwater Piping Walkdown/Disposition of Coating Requirements PSEG letter LR-N07-0224 dated 9/13/2007; REPLY TO NOTICE OF VIOLATION EA-07-149 UNTAGGING WORKLIST 4274446, 14 AF Underground Piping 1R20, 4/30/10 UNTAGGING WORKLIST 4274351, 12 AF Underground Piping 1R20, 4/30/10 LIST OF ACRONYMS ASME American Society of Mechanical Engineers BAST Boric Acid Storage Tank CEA Control Element Assembly CEDM Control Element Drive Mechanism CFR Code of Federal Regulations EDG Emergency Diesel Generator EPRI Electric Power Research institute EQ;ACE Equipment Apparent Cause Evaluation EQ Environmental Qualification ER Engineering Request FTTA Fuel .Transfer Tube Area IMC Inspection Manual Chapter IP Inspection Procedure IR NRC Inspection Report LER Licensee Event Report LOCA Loss of Coolant Accident MT Magnetic Particle Testing MSIP Mechanical Stress Improvement Process NCV Non-cited Violation Notification Corrective Action Notification NRC Nuclear Regulatory Commission NDE Nondestructive Examination OE Operating Experience PDI Performance Demonstration Initiative PI&R Problem Identification and Resolution PSEG Public Service Electric & Gas, LLC PWSCC Primary Water Stress Corrosion Cracking PQR Procedure Qualification Record (Welding Procedures)

RCS Reactor Coolant System RT Radiographic Test (Radiography)

PT Dye Penetrant Testing SDP Significance Determination Process SE Safety Evaluation

A-1 2 SG Steam Generator Sl Stress Improvement SSC Structure, System, and Component TS Technical Specifications UT Ultrasonic Test UFSAR Updated Final Safety Analysis Report VT' Visual Examination WPS Weld Procedure Specification

Outside of Scope Outside of Scope O~2.

Outside of Scope i 0 o*

4

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