ML20138H608

Summary of 961115 Meeting W/Util Re Results of Steam Generator Tube Insp & Repairs of Plant

ML20138H608
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	01/02/1997
From:	Shiraki C NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9701060139
Download: ML20138H608 (49)

Text

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l  % UNITED STATE 8 i) 4 NUCLEAR REGULATORY COMMISSION  !

E 4 WASHINGTON, D.C. 30006 4001

.m. January 2, 1997 l

LICENSEE

Commonwealth Edison Company ,

FACILITIES: Zion Nuclear Power Station, Units 1 and 2 L ,

j

SUBJECT:

SUMARY OF NOVEMBER 15, 1996, MEETING I

~

On November 15, 1996, a meeting was held between the NRC and Commonwealth  !

! Edison Company (Comed) to discuss the'results of the steam generator tube-

, inspections.and repairs of Zion Nuclear Power Station, Unit 2. Comed presented an overview of the inspections and repairs to date, its structural

!. assessment of tube integrity, and its leakage assessment. In addition, I different sleeving issues were discussed. Finally, the licensee presented its l conclusions and future plans. Enclosure 1 is a list of attendees. Enclosure ,

l .2 is the handout that was provided to the staff. l The objectives of the meeting were to inform the NRC of the results of the Zion, Unit 2, steam generator tube inspection, demonstrate that Zion, Unit 2,  !

steam generators meet the tube integrity requirements, and discuss root causes i i and corrective actions of ABB-Combustion Engineering (ABB/CE) issues. l l The licensee discussed the scope of the inspections performed on the Unit 2 j

. steam generators, the secondary side hydrostatic test and the steam generator  !

, tube repair breakdown. Concerning repairs, the licensee addressed the three

repair methods utilized (rerolls, plugs and sleeves) and the total number of j tubes repaired.

i In-situ pressure testing of 33 tubes was performed by pressurizing the primary l side of individual tubes. Two test pressures were used; one was the pressure expected in the event of a main steam line break'(MSLB) and the other was

! three times normal operating pressure. At the test pressure eqaal to main i steam line break pressure, no leakage was detected with the exception of three

'! Row I tubes with U-Bend axial indications in steam generator A that leaked.

! In addition, for one Row I tube, the licensee was unable to attain the test pressure of three times normal operation pressure because the leak rate exceeded the test pump capacity of 0.5 gallons per minute. The licensee discussed its structural assessment of this tube in which it concluded that structural integrity had been maintained. Based on the in-situ pressure testing results, the licensee decided to plug all tubes in Row 1, including those without indications.

The licensee also discussed its accident induced leakage assessment for the Row I U-Bends. Since it had decided to plug all Row 1 tubes, the concern for the next cycle has been eliminated. For the last cycle, the licensee determined the potential leakage during a MSLB. Its analysis showed that the MSLB potential leakage was less than 10 percent of the 10 CFR Part 100 limits.

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.y Comed discussed its criteria for selecting the five tubes that it pulled for  !

further analysis. The pulled tubes displayed ~a variety of types and sizes of f indications. Included were outside diameter axial indications above'and within the tubesheet, volumetric tubesheet indications and roll transition .

primary water stress corrosion cracking; indications. The laboratory analyses  !

will investigate indication morphology, deposits,. and . defect size.  :

Previous lower edge weld indications were ' discussed by Comed and ABB/CE.

Topics of discussion included the sleeve design'and nondestructive examination (NDE) requirements, equipment and personnel requirements, the Zion, Unit 2, ,

NDE results, root causes and corrective actions for the lower weld '

indications, applicability of 10 CFR Part 21, and an operability assessment of the Zion, Unit 1, sleeves lower weld.

The current status of the Unit 2 steam generator repairs is that, as of this '

date, all repairs are complete. The manways are scheduled to be on all four steam generators on November 16, 1996, transition to Mode 4 is scheduled for ,

December 4, 1996, and the unit is scheduled to be placed on-line on December 10, 1996.

The licensee concluded that Zion, Unit 2, met all steam generator tube integrity requirements. It also stated that the corrective actions for sleeve ,

issues have been implemented at Zion, Unit 2, and will be inlemented at Zion, Unit 1, during its spring 1997 refueling outage.

ORIGINAL SIGNED BY:

Clyde Y. Shiraki, Proje-t Manager Project Directorate III-2 f Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-295, 50-304

Enclosures:

1. Attendance List  ;

2. Meeting Handout 3 i

cc w/encls: see next page DISTRIBUTION:

HARD COPY w/encls 1 and 2-Docket File PUBLIC PDIII-2 r/f OGC, 015B18 ACRS, T2E26 M. Dapas, MLD1 C. Shiraki, CYS E-MAIL w/ enc 1 1: - -

i F. Miraglia, FJM A. Thadani, ACT R. Zimmerman, RPZ J. Roe, JWR ~E. Adensam, EGAl '

R. Capra, RAC1 S. Dembek, SXD C. Moore, ACM E. Jordan, JKR D.'Skay, DMS6 T. Sullivan, EJS S. Coffin, SMCI D. Lynch, MDL .B. McCabe, BCM DOCUMENT NAME: G:\CMNTJR\ ZION \ZI1115.MTS ,

To receive a copy of this document,indcat$the ,om: "C" = Copy witpft enclosures *E" = Copy with enclosures "N" = No copy  ;

0FFICE PM:PDIII-2 lt$ LA:EII-2 l Q. Q: M6,II-2 l c., . l l

.NAME CSHIRAKI fl OHG01E\ @PRA 6- i DATE 12 AQ96 12SD/96 1g/1./96 0FFICIAL' RECORD COPY

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Comed discussed its criteria for selecting the five tubes that it pulled for further analysis. The pulled tubes displayed a variety of types and sizes of indications. Included were outside diameter axial indications above and within the tubesheet, volumetric tubesheet indications and roll transition primary water stress corrosion cracking indications The laboratory analyses will investigate indication morphology, deposits, and defect size.

Previous lower edge weld indications were discussed by Comed and ABB/CE. l Topics of discussion included the sleeve design and nondestructive examination (NDE) requirements, equipment and personnel requirements, the Zion, Unit 2, NDE results, root causes and corrective actions for the lower weld indications, applicability of 10 CFR Part 21, and an operability assessment of the Zion, Unit 1, sleeves lower weld.

The current status of the Unit 2 steam generator repairs is that, as of this date, all repairs are complete. The manways are scheduled to be on all four steam generators on November 16, 1996, transition to Mode 4 is scheduled for December 4,1996, and the unit is scheduled to be placed on-line on December 10, 1996.

The licensee concluded that Zion, Unit 2, met all steam generator tube i integrity requirements. It also stated that the corrective actions for sleeve issues have been implemented at Zion, Unit 2, and will be implemented at Zion, Unit 1, during its spring 1997 refueling outage.

Clyd . Shiraki, Project Manager l Project Directorate III-2 i Division of Reactor Projects - III/IV '

Office of Nuclear Reactor Regulation Docket Nos. 50-295, 50-304 l

Enclosures:

1. Attendance List

2. Meeting Handout cc w/encis: see next page j

Zion Nuclear Power Station Unit Nos. I and 2 cc:

Ms. I. Johnson Document Control Desk-Licensing Acting Manager, Nuclear Regulatory Services Connonwealth Edison Company Commonwealth Edison Company 1400 Opus Place, Suite 400 Executive Towers West III Downers Grove, Illinois 60515 1400 Opus Place, Suite 500 Downers Grove, Illinois 60515 Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60603 Dr. Cecil Lue-Hing l Director of Research and Development Metropolitan Sanitary District '

of Greater Chicago '

100 East Erie Street Chicago, Illinois 60611 Phillip Steptoe, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60603 Mayor of Zion Zion, Illinois 60099 1

Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 U.S. Nuclear Regulatory Commission Zion Resident Inspectors Office 105 Shiloh Blvd. l Zion, Illinois 60099 l Regional Administrator U.S. NRC, Region III 801 Warrenville Road ,

Lisle, Illinois 60532-4351 Station Manager Zion Nuclear Power Station 101 Shiloh Blvd.

Zion, Illinois 60099-2797

1 ATTENDANCE LIST NOVEMBER 15,1996, MEETING l

Name Organization Denise Saccomando Commonwealth Edison Company Bryant Giffin Commonwealth Edison Company John Blomgren Commonwealth Edison Company Mike Sears Commonwealth Edison Company Keith Moser Commonwealth Edison Company Rich Skowzgird Commonwealth Edison Company Donna Skay USNRC Ted Sullivan USNRC I Stephanie Coffin USNRC Steve Dembek USNRC Dave Lynch USNRC Rore Gamble Sartrex David Stepnick ABB/ Combustion Engineering Richard Pearson Northern States Power - Prairie Island I

l Enclosure 1 l

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e 4 Comed /NRC Steam Generator Status Meeting Zion Unit 2 November 15,1996 Enclosure 2

Agenda

- Introduction J hnBlomgren

- Meeting Objectives

- Conclusions Rich Skowzgird Zion 2 Status

- Inspection and Repair Overview

- Structural Assessment

- Leakage Assessment ABB/CE Sleeving Issues .

Dave Stepnik

- Root Cause ABB/CE

- OperationalImpact

- Plan John Blomgren Conclusions

Meeting Objectives Inform NRC on the Results of Zion 2 Inspection Demonstrate Zion 2 Steam Generator Tube Integrity Requirements Discuss Root Cause and Corrective Action of ABB/CE ,

Sleeving Issues

Conclusions .

Zion 2 Met All Steam Generator Tube Integrity Requirements Corrective Actions for Sleeve Issues Have Been Implemented at Zion 2 Corrective Actions for Sleeves Will Be

! Implemented at Zion 1- Spring 1997

Zion Plan l

Run Zion 2 to Next Refuel Outage-Spring 1998 Zion 1 Refuel Outage-Spring 1997

-Inspection Scope Similar to Zion 2

- Inspect 1664 Sleeve Lower Edge Welds

- In-Situ Pressure Test, if necessary

- Pull Tubes, if necessary i

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Zion Unit 2 Steam Generator Inspection

- Inspection Scope '

100 % Full Tube Bobbin 100 % HL & CL Tubesheet MRPC 100 % Row I & 2 U-Bend + Point 100 % HL MRPC of Dents > 5.0 Volts 100 % ABB Sleeves + Point

- Secondary Side Hydro Test Steam Generator Tube Repair Breakdown

- 2312 PWSCC at the Roll Transition

- 235 Tubesheet IGA & SCC 13 Tube Support Plate

- 64 Row I U-Bends

- 80 Sleeves

- 4 Freespan 14 Other 158 Preventative Row 1 Plugs

Zion Unit 2 Steam Generator Repairs r

- Repair Method

- 2172 Rerolls '

- 442 Plugs

- 226 Sleeves Total 2838 Tubes Repaired

- 8.42 % Total Equivalent Plugged

- Technical Specification Limit 15 %

b Zion Unit 2 Steam Generator Repairs Status

- All Repairs Complete

- Manways on All 4 Steam Generators: Nov.16

- Mode 4 Scheduled: Dec. 4

- Unit On Line: Dec.10 1

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Zion Unit-2 In-Situ Pressure Testing Indications within Tubesheet Crevice Tested to MSLB -

2900 psi for Leakage Indications in Free Span Tested to MSLB and 3 dNOP -

5100 psi Local Test for Straight Length Tube Indic itions Full Length Tube Test for U-Bend Indications

.j Zion Unit-2 In-Situ Pressure Testing Total Number of Tubes Tested -- 33 (25 Crevice / 8 Free Span) i Tested 5 Different Modes of Degradation Criteria Used to Determine Candidates

-- Largest Voltage / Longest Length / Damp in Hydro

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- Seal Bladder Hydro Chamber

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---Seal Bladder ripper Hydro System Bladder Scal. System Special Tubesheet In-Situ Tool

Zion Unit 2 In Situ Pressure Test Results Rcil Transition PWSCC Steam Generator A inSitu Row Column Voltage Longest Location s-m No Leakage MAI 1 15 39 8 1.32 TEH + 2.93 No Leakage MAI 3 38 36.0 0.76 TEH + 2.64 DAup No Leakage MAI 16 43 26.5 0.76 TEH + 2.90 No Leakage SAI 16 91 17.9 0.47 TEH + 2.41 No Leakage mal 11 42 9.9 0.34 TEH + 2.82 No Leakage mal 8 92 7 0.27 TEH + 2.28 No Lee 6t aw sal 4 47 10.7 04 TEH + 2.86 No Leakage sal 9 92 5.1 0.25 TEH + 2.47 No Leakage sal 18 90 3.4 0.38 TEH + 2.42 Steam Generator C No Leekage SAI 13 44 15.1 0.58 TEH + 2.59 No Leakage sal 4 14 11.3 0.36 TEH + 2.90 No Leakage mal 28 60 21.9 0.6 TEH + 2.24 Steam Generator D No Leakage mal 25 39 25.9 0.57 TEH + 3.33 oAum No Leakage mal 16 28 25.3 0.54 TEH + 2.84 oAup No Leakage MAI 33 52 17.4 0.81 TEH + 2.65 No Leakage MAI 13 14 17.1 0.63 TEH + 2.90 onum No Leakage SAI 4 45 16.4 0.54 TEH + 2.66 No Leakage mal 22 21 12.1 0.66 TEH + 2.97 oAup U-Bend Length Stoani Generator C Leakage MAI 1 13 0.65 07H+14.1 No Leakage MAI 1 90 0.55 07H+ 3.5 Leakage SAI 1 72 .

0.59 07H+3.9 Steam Generator A Leekage MAI 1 90 0.52 07H+11.67 Arc Length Steam Generator D No Leakage SCI 1 56 0.3 07H+10.26 No Leakage SCI 1 70 0.3 07H+10.98 OD Axial Within Tubesheet Longa Steam Germtor C No Leakage mal 3 68 11.8 TEH + 3 to 14.8*

Steam Geneu A No Leakage SAI 13 63 11.0 TEM + 3.57 to 13.5"

. No Leekage MAI 21 57 1.27 TEH + 7.5 & 19.44" Steam Genwator D No Leekage MAI ~16 49 2.50 TEH + 17.86 to 20.4* -

OD Axial Top of Tubesheet Gnge Steam Generator C No Leekage sal 19 48 0.46 TSH + 0.97*

No Leekage sal 11 48 0.34 TSH + 1*

Volumetric vone sa. -

. Steam Generator D No Lukage VOL 46 50 11.6 ' O.38 x 0.53 TEH + 4.94 Steam Generator A No Leekage VOL 18 16 6.1 1.23 x 0.70 TEH + 17.47

. Steam Generator C

, No Leekage . VOL 38 58 1.3 1.09 x 0.42 TEH + 19.3 onup

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In-Situ Pressure Testing

- Roll Transition PWSCC

- Selection Criteria -

Largest Indications Determined by Voltage Tubes Identified as Damp / Wet During Secondary Pressure Test Range ofIndications

- 3.4 - 39.8 Volts i

- 0.27 - 1.32 Inches 18 Tubes Tested

- Results: No Leakage at MSLB OD Axial Within Tubesheet

- Selection Criteria ,

2 Largest Determined by Length 2 Smaller

- 4 Tubes Tested

- Results: No Leakage at MSLB

In-Situ Pressure Testing

= Volumetric Within Tubesheet

- Selection Criteria 2 Largest Indications Determined by Voltage 1 Small Indication With Possible Wetness

- 3 Tubes Tested

- Results: No Leakage at MSLB

- OD Axial Above Tubesheet

- Selection Criteria 2 Largest Indications Detemained by Length Only 2 Tubes

- 2 Tubes Tested

- Results: No Leakage at MSLB or 3 dNOP

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In-Situ Pressure Testing i

- Row 1 U-Bend Indications

- Cire Indications Selection Criteria

- Largest Circumferential Extent

- 2 Tubes 40 Deg Arc Length (Only 2 Cires)

- 2 Tubes Tested '

Results: No Leakage at MSLB or 3 dNOP

- AxialIndications Selection Criteria

- Largest Indications Based on Length

- 4 Tubes Tested Results: Leakage in 3 Tubes at MSLB

Conclusion:

Plug all Row 1 Tubing

In-Situ Pressure Testing U-Bend AxialIndications Corrected Leakage gpm Location Length dNOP MSLB 3 dNOP -

SG A R-1, C-90 0.52" <0.001 0.020 No Burst SG C R-1, C-90 0.55" 0 0 No Burst R-1, C-13 0.65" 0 0.004 No Burst R-1, C-72 0.59" 0.088 0.213 Performed Detailed Structural Analysis

Conclusion:

Plug All Row 1 Tubes

E Row 1 Col 72 Structural Assessment Axial Indication Sized @ 0.59" by CE / Comed Onsite

- Independently Sized By Westinghouse @ 0.594" Indication Located on Extrados at the U-Bend, Hot Leg Tangent Point

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In-Situ Achieved Max Pressure of 2900 psi Structural Analysis by Westinghouse / APTECH

- 3 dNOP Pressure is 4590 psi

- Normalized Burst Pressure Calculated for Row 1, Col 72 at 4892 psi i

Conclusion:

StructuralIntegrity Maintained

Accident Induced Leakage Assessment Leakage Concern is Due to Row I U-Bends -

Next Cycle Concern is Eliminated -- All Row I U-Bends were Plugged For Last Cycle Determine Potential Leakage During MSLB Criteria Max Leakrate for 10% of 10CFR100 Limits - 5.3 gpm MSLB affects one generator -- SG C Has Most Tubes With Indications - 24 of 64 Use Maximum In-Situ Leakrate to Bound All Indications Not In-Situ Tested

- All Have Shorter Length Indications Total U-Bend Leakrate @ MSLB for Steam Generator C 21 (Indications Not In-Situ Tested) x 0.213 gpm = 4.48 gpm

+ (Known Leakrate of 3 Tested Tubes) = 0.22 gpm

= 4.7 gpm Total i

Conclusion:

MSLB Potential Leakage Less Than 10% of .

10CFR100 Limits 6

Zion 2 SG Tubes Pulled Tube Length Comments OD Axial Within Tubesheet SG C 3/68 11.8" Longest Axial, Also Contains Roll Transition Ind SG A 21/5 1.2" Shorter Axial Tubesheet Volumetric SG A 28/16 1.23" x 0.7" Second Largest Voltage, Also Contains Roll Transition Indication Roll Transition PWSCC SG A 3/38 0.76" Largest Voltage Indication (36 Volts)

Identified as Wet / Damp OD Axial Above Tubesheet SG C 19/48 0.46" Longest Freespan Axial Laboratory Analysis: Morphology, Deposit Analyis, Defect Sizing

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WELDED TUBESHEET SLEEVES '

. AGEXDA.

O DESIGN & NDE REQUIREMEN'TS

1. EQUIPMENT & PERSONNEL REQUIREMENTS

1. ZION UNIT 2 - NDE RESULTS

1. ROOT CAUSE & CORRECTIVE ACTION  ;

1. 10CFR21 APPLICABILITY

1. OPERABILITY ASSESSMENT  ;

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1 STATDARD TUBESHEET SLEEVE NDE INSPECTION REQUIREMENTS

1. 100% VISUAL INSPECTION OF TUBE ID AFTER CLEANING 9 UPPER WELD ,

i 100% ULTRASONIC INSPECTION (' ENHANCED' TECHNIQUES) 100% VISUAL INSPECTION (VT-1)

1. LOWER JOINT  !

100%VISUALINSPECTION (VT-1)

1. 100% SLEEVE ECT APPENDIX H QUALIFIED PLUS POINT  !

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WELDED TUBESHEET SLEEVES '

AGENDA. .

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1. DESIGN & NDE REQUIREMENTS O EQUIPMENT & PERSONNEL REQUIREMENTS ,

1. ZION UNIT 2 - NDE RESULTS 8 ROOT CAUSE & CORRECTIVE ACTION

1. 10CFR21 APPLICABILITY

1. OPERABILITY ASSESSMENT '

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i LOWER WELD INSPECTION EXAMINATION EQUIPMENT i

e CAMERA REQUIREMENTS STANDARD WITH 0.020" DIAMETER HOLE 1/32" LINE ON 18% NEUTRAL GREY CARD e CAMERA MAGNIFICATION 12X  !

e RESOLUTION INVESSEL VISUAL INSPECTION RESOLUTION CARD 0.001" DIAMETER WlRE I.

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LOWER WELD INSPECTION EXAMINATION PERSONNEL .

i e CERTIFICATION PER ABB CENO QUALITY MANUAL ASNT SNT-TC-1 A IWA-2312 OF ASME SECTION XI e VT CATEGORY 1, LEVEL ll e WRITTEN & PRACTICAL EXAM e TRAINING ON SLEEVE WELD SAMPLES ADDITIONAL TRAINING IMPLEMENTED IN SPRING,1996

WELDED TUBESHEET SLEEVES AGENDA.. ,

9 DES!GN & NDE REQUIREMENTS

• EQUIPMENT & PERSONNEL REQUIREMENTS O ZION UNIT 2 -NDE RESULTS

• ROOT CAUSE & CORRECTIVE ACTION

1. 10CFR21 APPLICABILITY

• OPERABILITY ASSESSMENT

ZION UNIT 2 ABB CENO SLEEVES ECT RESULTS I

TOTAL FIELD ECT ECT R E-A N A LYSIS PIkkkIO USLY 408 72 WZI 13 WZI INST A LLED 27 GEO SLEEVES 32 WSI NEWLY .

237 6 WZI 5 WZI INSTALLED l 1 WSI SLEEVES I

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1. WELD ZONE INDICATION CAUSES (SEEN DURING APPENDIX H QUALIFICATION PROGRAM)  !

PERMEABILITY VARIATIONS  !

l l-WELD INCLUSIONS  ;

WELD SUCKBACK i SURFACE IRREGULARITIES WITH NOISE S 5 WZl'S ON NEWLY INSTALLED SLEVEES 2 ' CLASSIC' WELD SUCKBACK ,

3 - SURFACE IRREGULARITIES WITH NOISE (CONSERVATIVELY CALLED WZl)

ZION UNIT 2 ABB CENO SLEEVES NDE RESULTS

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(SLEEVES 3 WZI'S) lN EW LY 237

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PREVIOUSLY INSTALLED SLEEVES LOWER WELD INDICATIONS t

e LACK OF FUSION - 3 UP TO 200 e PIN HOLE -7

~0.010" DIAMETER MOISTURE

. IMPLEMENT AIR CONDITIONERS CLEANING

= ADDITIONAL BRUSH / MARK STEP e WELD HEAD MISALIGNMENT -1 '

WELDED TUBESHEET SLEEVES AGENDA. .

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.# DESIGN & NDE REQUIREMENTS

1. EQUIPMENT & PERSONNEL REQUIREMENTS ,

1. ZION UNIT 2 -NDE RESULTS r

G ROOT CAUSE & CORRECTIVE ACTIONS i

1. 10CFR21 APPLICABILITY i

9 OPERABILITY ASSESSMENT t

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ROOT CAUSE CONCLUSIONS

1. WZl'S ON NEWLY INSTALLED SLEEVES WELD INCLUSIONS ELIMINATED RESULTS (ECT SIGNALS) CONSISTENT WITH APPENDIX H QUALIFICATION PROGRAM G LOWER WELD FAILURES -

PERSONNEL ERROR IN IDENTIFICATION OF FLAWS I

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SLEEVE LOWER WELD .

CORRECTIVE ACTIONS .

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1. INPLACE CONTINUED ENHANCED TRAINING FOR INSPECTORS INDEPENDENT REVIEW BY WELD / PROCESS ENG e CONSIDERATION IMAGE QUALIT(INDICATOR ELIMINATE LOWER WELD

• ROLLED JOINT GENERIC LICENSING REPORT

WELDED TUBESHEET SLEEVES AGENDA .

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1. DESIGN & NDE REQUIREMENTS

1. EQUIPMENT & PERSONNEL REQUIREMENTS ,

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1. ZION UNIT 2 - NDE RESULTS O ROOT CAUSE & CORRECTIVE ACTIONS O 10CFR21 APPLICABILITY

1. OPERABILITY ASSESSMENT l

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SLEEVE LOWER WELD LEAKAGE RATES .

e LACK OF FUSION '

LEAKAGE TEST PROGRAM (20 LOF) 3.8 gpd @ MSLB PRESSURES CONSISTENT WITH Pl PULLED TUBE DATA l e PIN HOLE '

LEAKAGE TEST PROGRAM

.38 gpd.@ MSLB PRESSURES i

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SLEEVE LOWER WELD 10 C.FR PART 21 .

i e 10CFR21 REQUIREMENTS i

NOTIFY NRC, IF DEFECT CREATES SAFETY HAZARD e STRUCTURAL INTEGRITY MECHANICAL TEST PROGRAM UP TO 300 LACK OF FUSION e LEAKAGE RATE UP TO 3.8 gpd (LACK OF FUSION)

UP TO .38 gpd (PIN HOLE) e NOT 10CFR211SSUE

. o WELDED TUBESHEET SLEEVES AGEXDA. .

1. DESIGN & NDE REQUIREMENTS G EQUIPMENT & PERSONNEL REQUIREMENTS

1. ZION UNIT 2 - NDE RESULTS

1. ROOT CAUSE & CORRECTIVE ACTIONS

1. 10CFR21 APPLICABILITY O OPERABILITY ASSESSMENT i

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i ZION UNIT 2 VT - LOWER WELD t

POD ASSESSMENT  :

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. . . . , . . _ . . . _ . ~ . _ _ _ , . . _ , _ _ _ . ,

OUTAGE , INSTALLED i INITIAL l'  % MISSED i i i i SLEEVES VT l REJECTS REJECTS

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s Z2R12 i 171 i.!

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!. l Z2R13 162 i 15 9 8 ,

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4 TOTAL i 414 i 37 i 9 11 1  ;

i 4

t i I t~: ,u-.~. -_.__~.- .% .~,.,: _ -

I

ZION UNIT 1 VT - LOWER WELD POD ASSESSMENT OUTAGE i INSTALLED INITIAL  %  !

l SLEEVES i VT <

l  ! REJECTS '

ZR11 l 442 29 7 l

1 l l p..~_..-_ -.; _ _ _ _ _.,. , _ _ _ .

l Z1R12  !

125 6 5 i

i p._ ._ _ _p _. -__3_______ .

i Z1R13 l 62 .

8 13 .

i a .!_.- .---<.,..,.._.; ~,.....,_,,,m ,

Z1R14 l 983 119 12 l l  !

q__.----__

TOTAL  : 1612 162 10 i  !

t  !

s l

-. ~_m.m._.mh___._,__ _

ZION UNIT 1 VT - LOWER WELD POD ASSESSMENT i

e INITIAL VT REJECT RATE IS COMPARABLE 9% VS 10%

e ASSUMING COMPARABLE POD FOR VT 44 MISSED INDICATIONS AT ZION UNIT 1 1

i I

i

ZION UNIT 1 SLEEVE LOWER WELD OPERABILITY ASSISSMENT NORMAL I MSLB OPERATING t ,

15 LACK OF 3.8 gpd l .003 gym

, FUSION  ! l 35 PIN ,

.38 gpd l .0003 gpm HOLES  !

TbNALS 70 gpd .049 gpm

4 m **

Conclusions Zion 2 Met All Steam Generator Tube Integrity Requirements Corrective Actions for Sleeve Issues Have Been Implemented at Zion 2 Corrective Actions for Sleeves Will Be Implemented at Zion 1- Spring 1997

_ _ _ - _ _ . _ _ _ - - . _ _--a- + w