ML18102A194

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Summary of 960528 Meeting W/Pse&G in Rockville,Md Re Issues Concerning Sgs,For Plant Units 1 & 2.Meeting Attendees Listed in Encl 1
ML18102A194
Person / Time
Site: Salem  PSEG icon.png
Issue date: 06/19/1996
From: Olshan L
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
TAC-M94797, TAC-M94798, NUDOCS 9606250060
Download: ML18102A194 (37)
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{{#Wiki_filter:( I I UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 19, *1995 LICENSEE: Public Service Electric & Gas Company FACILITY: S~lem Nuclear Generating Station, Units I and 2

SUBJECT:

SUMMARY

OF MAY 28, 1996, MEETING TO DISCUSS STEAM GENERATORS (TAC NOS. M94797 AND M94798) On May 28, 1996, members of the Public Service Electric & Gas Company (PSE&G, the licensee) met with the U.S. Nucle~r Regulatory Commission (NRC) in Rockville, Maryland, to discuss issues concerning the steam generators for Salem Nuclear Generating Station, Units 1 and 2. is a list of the meeting attendees. is a copy of the slides that were used in the licensee's presentation. _ During the presentation, the licensee discussed the inspections performed, the number of tubes repaired, and the results of the destructive examinations performed on six tubes removed from a steam generator. Based, in part, on the inspection results and the destructive analysis of the pulled tubes, the

  • licensee concluded that the Unit 2 steam generators could be operated safely for a full cycle.

The licensee verbally discussed *their basis for concluding that the steam generators could be operated safety for a full cycle of operation by addressing the more structurally significant indications detected during the inspection. The licensee intends to submit its tube integrity analysis (i.e., Regulatory Guide 1.121 analysis) by the end of June 1996. During the meeting, the licensee also reiterated its announcement that the Unit 1 steam generators would be replaced with steam generators originally purchased for the cancelled Seabrook Unit. The licensee is planning to have these steam generators on site by January 1997, and is planning to restart Unit 1 during the second quarter of 1997. A meeting was proposed for mid-June 1996, to further discuss the Unit 1 steam generator replacement. ~

  • ~v

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Enclosures:

1.

List of Attendees

2.

Licensee's Handouts cc w/encls: See next page 9606250060 960619 PDR ADOCK 05000272 p PDR Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Public Service Electr** & Gas Company cc: Mark J. Wetterhahn, Esquire Winston & Strawn 1400 L Street NW Washington, DC 20005-3502 Richard Fryling, Jr., Esquire Law Department - Tower SE 80 Park Place Newark, NJ 07101 Mr. Clay Warren General Manager - Salem Operations Salem Generating Station P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Louis Storz Sr. Vice President - Nuclear Operations Nuclear Department P.O. Box 236 Hancocks Bridge, New Jers~y 08038 Mr. Charles S. Marschall, Senior* Resident Inspector Salem Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Dr. Jill Lipoti, Asst. Director Radiation Protection Pro~*rams NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 Maryl and Office of People's Counsel 6 St. Paul Street, 21st Floor Suite 2102 Baltimore, Maryland 21202 Ms. R. A. Kankus Joint Owner Affairs PECO Energy Company 965 Chesterbrook Blvd., 63C-5 Wayne, PA 19087 Mr. Elbert Simpson Sr. Vice President - Nuclear Engineering Nuclear Department P.O. Box 236 Hantocks Bridge, New Jersey 08038 Salem Nuclea~enerating Station, Units I an9 Richard Hartung Electric Service Evaluation Board of Regulatory Commissioners 2 Gateway Center, Tenth Floor Newark, NJ 07102 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA. 19406 Lower Alloways Creek Township c/o Mary 0. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038

  • Mr. Frank X. Thomson, Jr., Manager Licensing and Regulation Nuclear Department P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, PA 17120 P. M. Goetz MGR. Joint Generation Atlantic Energy 6801 Black Horse Pike Egg Harbor Twp., NJ 08234-4130 Carl D. Schaefer External Operations ~ Nuclear Delmarva Power & Light Company P.O. Box 231 Wilmington, DE 19899 Pub 1 i c Service Cammi ss ion of Maryl and Engineering Division Chief Engineer 6 St. Paul Centre Baltimore, MD 21202-6806 Mr. Leon R. Eliason Chief Nuclear Officer & President-Nuclear Business Unit Public Service Electric and Gas Company Post Office Box 236
  • Hancocks Bridge, NJ 08038

SALEM NUCL.EAR GENERATING STATION, UNITS 1 AND 2 STEAM GENERATOR MEETING NAME P. Rush L 01 sh an T. Sullivan K. Karwoski S. Dembek J. Tsao E. Weiss* C. Liang* M. Modes P. Peterson R. Dulee E. Simpson J. Perrin C. J. Conner F. Thomson MAY 28, 1996 A. Kapsalopoulou L. Connor T. Sutter S. Vealle P. Gunter K. Redmond R. Coe A. Curtis D. Hansen

  • *Part-time attendance*

ORGANIZATION NRC/NRR NRC/NRR NRC/NRR NRC/NRR NRC/NRR NRC/NRR NRC/NRR NRC/NRR NRC/Region I NRC/Region I PSE&G PSE&G PSE&G PSE&G PSE&G NJ Department of

  • Environmental Protection Southern Technical Services Bechtel Bechtel Nuclear Information and Resource Service Babcock & Wilcox, Nuclear Environmental Services Framatome Technologies, Inc.

ARTECH Energy Services, Inc. Arizona Public Service ENCLOSURE 1

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,,,<;.~,~;>~~ Vp'!.,~~;:.'."<.%.~!'!°$.'{.,>\\lii):~JJ!~~ PSE&G/NRC Meeting Salem Steam Generators May 28, 1996 \\_,,.

Agenda

  • Introduction E. Simpson

~*-

  • Summary of Unit 2 Inspection Findings

- NOE Inspections C.J. Conner - Destructive Exams J. Perrin

  • Reg. Guide 1.121 Analysis for Unit 2 R. Dulee
  • Update Status on Unit 2 Repairs R. Dulee e
  • Remedial Actions/Future Plans for Unit 2 R. Dulee
  • Update Status on Unit 1 E. Simpson
  • Summary E. Simpson

.. Series 51 Tube Damage Locations AVBWear Row 1and2 U-Bend PWSCC PWSCC at Dented Tube Support Plate Denting and ODSCC at TSP Tube Thinning at Lower TSP's (cold leg only) ODSCCatTop of Tube Sheet PWSCC at Tube Expansion Zone 06H OSH 03H Anti-vibration bars 50.5" I 50.5" l r* osc 50.5 l 04( 50.5 03( Tube Support Number 02( 01( TSC TEC Hot Leg

Summary ofU/2 Inspection Findings NDE Inspection Scope

  • 1 OOo/o Bobbin Coil examination full length
  • 1 OOo/o +Point examination of hot leg tubesheet transitions and tube support plate intersections
  • 1 OOo/o +Point examination of SIG 22 cold leg tubesheet transitions and tube support plate intersections SIG 21 SIG 22 SIG 23 SIG 24 TOTAL Total Exams 29,564 55,370 29,653 29,577 144,164

Summary ofU/2 Inspection Findings NDE Inspection Enhancements

  • Separate Primary and S.econdary Data Analysis

>> T-1 Data Links to Lynchburg, VA; B~necia, CA; Issaquah, WA >> "Rigorous Resolution" Process

  • Separate Level Ill for oversight
  • "Site-specific Data Analysts Guidelines" training course and test e
  • QA monitoring of remote data analysis locations
  • 2 Separate Data Management Systems
  • Digital Tubesheet Photography

Summary ofU/2 Inspection Findings Tubes Plugged SAi SAi SAi SCI SCI SVI SVI MAI MAI MAI MCI MCI MVI MVI AVB C/L PU PRE-SIG @TSH- @TSH+ @TSP @TSH @TSP @TSH @TSP WEAR THIN PLP VENT TOTAL 21 26 2 2 1 2 2 3 2 1 41 22 31 5 1 9 1 1 4 52 23 4 4 2 2 5 1 2 2 22 24 79 3 4 8 1 1 9 105 SUM 140 7 6 9 21 6 4 7 6 2 12 220

Summary ofU/2 Inspection Findings* SOD & High Phase Angle Circ. Indications

  • Shallow Outside Diameter signals were tracked
  • NOE signals had flaw-like characteristics.

outside defect plane

  • Basis for Unit 2 Tube Pulls

Summary ofU/2 Inspection Findings S/G 24 Tube Pull NDE

  • Summary ofU/2 Inspection Findings Destructive Examinations oWF.Lt:*bN~l'\\,~Ji;'lf!fflml

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  • Laboratory Destructive Examinations

. Summary ofU/2 Inspection Findings Destructive Exam Objectives

  • Characterize any degradation which is present at TSP intersections
  • Compare SCI, MAI and SOD indications with destructive examination results
  • Investigate SODs to determine what they are and how they compare to classic SCls

)

  • Perform analyses on tube surface deposits

Summary ofU/2 Inspection Findings Test Matrix

  • Nondestructive Examination
  • Base Material Characterization
  • -Burst Testing -
  • Metallurgical Characterization
  • Tube Deposit Analysis

~------

Summary ofU/2 Inspection Findings Nondestructive Examination

  • NOE *soo indications became non-relevant
  • The other indications became non-relevant except for one MAI which became an SAi in lab exam.

~--------- r'

Summary ofU/2 Inspection Findings

  • Base Material Characteriza.tion
  • Chemical analysis typica.1 for I nconel 600.
  • Predominance of intragranular carbides with light and non-continuous grain boundary carbides
  • Tensile Tests

-~-- . Summary ofU/2 Inspection Findings Burst Testing Tube Segment 11/27 (FS) 11/27 (2H) 20/26 (3H) 20/26 (FS) 20/26 (4H) (FS = Frees.pan) Type. None SOD MAI, dent None SCl,dent Burst Pressure (psi) 12, 165 12,251 12,699 12,634 12,679 l

WMS-21 WMS-22 36.7X 73.SX SALEM SG 24 20/26*78, SAi AFTER BURST TESTING AND AXIAL STRAINING

LEC0-28 4/29/96 LEC0-31 4/29/96 206X UNETCHED 206X NITAL ETCH SALEM SG 24 20/26-9B-2A.2 SLIGHTLY DEEPER IGA (-7°/o TW) f 3.5 mils t

Summary ofU/2 Inspection Findings Summary of Observed IGA u e reas o nterest eepest Section n 1cat1ons IGA No. Location ype ent Observed ent 11/27 2H SOD 3.40°/o 21/71 SH SOD 2.20°/o. 19/4S 3H SCI Dent < 10.0°/o 20/26 4H SCI Dent 8.20°/o 11/31 SH SCI 4.90°/o 20/26 3H MAI Dent -30°/o 21/71 3H NOD 6.00°/o I e

Summary ofU/2 Inspection Findings Tube Deposit Analysis

  • SEM/EDS Tube Deposit Analysis

>> Freespan Regions >>TSP Crevice Regions*

Summary ofU/2 Inspection Findings Tube Deposit Analysis .. :r,.~i[*;*li"o/i~:&~~{~ff?~~:@.£;:~

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  • Tube Bulk Deposit Analysis

>> Freespan Regions >>TSP Crevice Regions e

Summary of U/2 Inspection Findings Top of Tubesheet Examinations

  • These examinations/analyses are in progress
  • Four TTS regions are being examined
  • IGA found in swelled and axial-strained specimens

Summary ofU/2 Inspection Findings Destructive Analysis Summary t;;c!J ~fil/.t'.litriYc'i\\'

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  • Six tubes were pulled; each of which had TSP indication (SODs, SC ls, MAI, SVls)
  • OD IGA at TSPs ranged from 2-30.0/o TW

Summary ofU/2 Inspection Findings Destructive Analysis Summary ¥ ;q ~,.f F< o

  • No destructive exam evidence to show SODs are related to tube degradation
  • SODs may be the result of surface deposits
  • The three burst specimens with indications (SOD, SCI, SCI) exhibited burst pressures characteristic of freespan burst specimens

Reg. Guide 1.121 Analysis. for Unit 2

  • Condition Assessment

>>As-found this outage (2R9)

  • Operational Assessment

>> Projections for Next Outage (2R10) ~ I e*

Reg. Guide 1.121 Analysis for U/2 Condition Assessment

  • As-found 2R9 (All 4 Steam Generators)
  • Performed Structural Integrity Analysis
  • In-Situ Pressure Testing (required for only three tubes)
  • Tube Pull t

0

J J Reg. Guide 1.121 Analysis for U/2 *

  • Condition Assessment
>~ lf

~ *

  • 1

~

== Conclusion:== Salem 2 steam generators met structural requirements of Reg. Guide 1.121 at end of last operating cycle

i J Reg. Guide 1.121 Analysis for U/2,

  • Operational Assessment
  • Projection of number of indications

, expected at next inspection

  • Size distribution of indications expected at next inspection
  • Ensure that indications found at next inspection will meet Reg. Guide 1.121
  • 1imits

I I Reg. Guide 1.121 Analysis forU/2 *

  • Operational Assessment
  • Conclusion

>> No observed damage mechanism is expected to challenge the limits of Reg. Guide 1.121 over the next operating cycle of 1.3 EFPY >> Therefore, a full cycle of operation is justified for Salem 2

Update Status of Unit 2 Repairs

  • Re-analysis results
  • All Plugging complete

>> 220 plugs installed.

  • All-Steam Generators closed J

I

--*-~ Remedial Actions/Future Plans for Unit 2

  • N-16 Monitors
  • Secondary System Opti*mization Areas

>>Oxidant Reduction >> Impurity Reduction >> Corrosion Product Transport Reduction I I >> Inhibitor Addition

  • e

>> Chemical Cleaning >>*T-hot Reduction

  • Develop Strategic Model of Degradation

~

I Update Status on Unit 1

Summary

. :;r,~

~7~kl"<*:mA'(:r

  • Extensive tube inspections performed in the Salem S/Gs

>> Comprehensive destructive exams on six tubes

  • All indications evaluated by several independent trained analysts
  • Conservative approach used to establish tube plugging scope
  • All Unit 2 tube plugging complete

) l A

Summary (continued)

  • Structural integrity verified -- past and upcoming cycle

>> In-situ pressure testing >> Reg. Guide 1.121 analysis

  • Continuing to pursue remedial actions to improve steam generator performance Salem Unit 2 Steam Generators are ready for safe, reliable operation.

jO ~* e.

June 19, 1996 ~~ LICENSEE: Public Service Electric & Gas Company FACILITY: Salem Nuclear Generating Station, Units 1 and 2

SUBJECT:

SUMMARY

OF MAY 28, 1996, MEETING TO DISCUSS STEAM GENERATORS (TAC NOS. M94797 AND M94798) On May 28, 1996, members of the Public Service Electric & Gas Company (PSE&G, the licensee) met with the U.S. Nuclear Regulatory Commissjon (NRC) in Rockville, Maryland, to discuss issues concerning the steam generators for Salem Nuclear Generating Station, Units 1 and 2. is a list of the meeting attendees. is a copy of the slides that were used in the licensee's presentation. During the presentation, the licensee discussed the inspections performed, the number of tubes repaired, and the results of the destructive examinations performed on six tubes removed from a steam generator. Based, in part, on the inspection results and the destructive analysis of the pulled tubes, the licensee concluded that the Unit 2 steam generators could be operated safely for a full cycle. The licensee verbally discussed their basis for concluding that the steam generators could be operated safety for a full cycle of operation by addressing the more structurally significant indications detected during the inspection. The licensee intends to submit its tube integrity analysis (i.e., Regulatory Guide 1.121 analysis) by the end of June 1996. During the meeting, the licensee also reiterated its announcement that the Unit 1 steam generators would be replaced with steam generators originally purchased for the cancelled Seabrook Unit. The licensee is planning to have these steam generators on site by January 1997, and is planning to restart Unit 1 during the second quarter of 1997. A meeting was proposed for mid-June 1996, to further discuss the Unit l steam generator replacement. Docket Nos. 50-272/311

Enclosures:

1. (ist of Attend~ss
2. -* Li~erisee's Handouts cc w/encls:

See next page DISTRIBUTION. See attached ljst OFFICE Dl-2/PM NAME .01 sh an: rb 96 Original signed by: Leonard N. Olshan, Senior Project Manager Project Directorate 1-2

  • Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation PDl-2/.

JStolz

DISTRIBUTION:

  • w/Enclosures 1 and.2 HARD COPY
  • Docket File
  • PUBLIC
  • PDI.:..2 Reading OGC ACRS E-MAIL WRussell/FMiraglia RZimmerman SVarga JZwol i nski JStolz
  • LOl sh an MO' Brien EJordan (E-Mail JKR)

PRush TSull i van KKarwoski SDembek JTsao EWeiss CLiang MModes PPeterson WDean

  • LNicholson, RGN-I cc:

Licensee and Service List

    • }}
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