ML20044D717

Summary of 930510 Meeting Re Status of Alternate SG Plugging Criteria to Uncover Defects within Tubesheet in Roll Expansion Region.Viewgraphs Encl

ML20044D717
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/17/1993
From:	Wang A Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9305200186
Download: ML20044D717 (40)

Text

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May 17,1993 Docket No. 50-213 LICENSEE:

Connecticut Yankee Atomic Power Company FACILITY:

Haddam Neck Plant

SUMMARY

OF MAY 10, 1993, MEETING REGARDING THE HADDAM NECK ALTERNATE STEAM GENERATOR TUBE PLUGGING CRITERIA On May 10, 1993, the staff meet with Connecticut Yankee Atomic Power Company (CYAPCO) to discuss the status of their alternate steam generator tube plugging criteria regarding defects within the tubesheet in the roll expansion region.

The staff informed CYAPCO that it would not be able to complete the alternate or interim plugging criteria (APC/IPC) review as requested for the upcoming outage because of limited staff resources.

The staff informed the licensee that we will focus our resources on the review of the generic submittal from EPRI, the basis for the Haddam Neck amendment, instead of continuing our review of the Haddam Neck amendment package.

The staff's review schedule could take 18 to 24 months, including 9-12 months for processing the review package through CRGR, public notice, and comment period.

CYAPCO stated it would like to implement the APC for Cycle 18 which would be abou', 16 months from now and will discuss with EPRI the possibility of being the lead plant for the primary water stress corrosion cracking topical being prepared by EPRI.

CYAPCO stated they have been working on a long term steam generator tube flaw management plan which includes re-rolling of the tubes.

The re-rolling would provide the TS required 1" of sound roll.

CYAPCO has concluded that re-rolling can be performed under 50.59, as they have concluded re-rolling would return the plant to its original design condition.

In addition, they believe they have the NDE capability to determine the re-roll joint acceptability.

CYAPCO stressed, however, that re-rolling is only a part of their flaw management plan which APC is still an important factor.

CYAPCO stated that steam generator replacement is not an option.

The staff noted that CYAPCO needs to work

)

with'EPRI and industry to provide a generic position with regards to primary water stress corrosion cracking and defect q specific criteria as the staff cannot support plant specific reviews.

g V *u: u% %m 7 m m M 19067L 9305200186 930517 PDR ADOCK 05000213 P

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May 17, 1993 l

Enclosed is CYAPCO's handouts for the meeting and the f

attendance list.

[

Original signed by i

Alan Wang, Project Manager Project Directorate I-4 l

l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation t

Enclosures-1.

CYAPCO Handouts t

j 2.

Attendance List cc w/ enclosures:

i See next page l

DISTRIBUTION:

Docket File NRC & Local PDRs PD I-4 R/F T. Murley F. Miraglia J.

Partlow S. Varga C. Miller A. Wang S. Norris i

OGC j

E. Jordan

+

P. Habighorst J. Richardson J.

Strosnider l

J.

Stolz

]

W.

Russell l

E. Murphy G.

Johnson H.

Conrad K. Desai K. Manoly J.

Ryan ACRS (10)

V.

McCree, EDO L. Doerflein, M W orrIcE LA:PDI-4 PM:PDI-4 hDI-4 NAME SN AWang:bp JS 2-DATE 05//,2/93 05/13-/93 05/lb/93

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/

/

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OFFICIAL RECORD COPY Document Name:

G:\\ WANG \\SGTB.MTG

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Enclosed is CYAPCO's handouts for the meeting and the attendance list.

va.^

by Alan Wang, Project Manager Project Directorate I-4 Division of Reactor Projects - I/II office of Nuclear Reactor Regulation

Enclosures:

1.

CYAPCO Handouts 2.

Attendance List i

cc w/ enclosures:

See next page 4

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Haddam Neck Plant cc:

Gerald Garfield, Esquire R. M. Kacich, Director Day, Berry and Howard Nuclear Licensing Counselors at Law Northeast Utilities Service Company City Place Post Office Box 270 Hartford, Connecticut 06103-3499 Hartford, Connecticut 06141-0270 W. D. Romberg, Vice President S. E. Scace, Vice President Nuclear Operations Services Millstone Nuclear Power Station Northeast Utilities Service Compu..y Northeast Nuclear Energy Company Post Office Box 270 Post Office Box 128 Hartford, Connecticut 06141-0270 Waterford, Connecticut 06385 Kevin McCarthy, Director Regional Administrator Radiation Control Unit Region I Department of Environmental Protection U.S. Nuclear Regulatory Commission State Office Building 475 Allendale Road Hartford, Connecticut 06106 King of Prussia, Pennsylvania 19406 Allan Johanson, Assistant Director Board of Selectmen Office of Policy and Management Town Office Building Policy Development and Planning Division Haddam, Connecticut 06438 80 Washington Street Hartford, Connecticut 06106 Resident Inspector Haddam Neck Plant J. P. Stetz, Vice President c/o U.S. Nuclear Regulatory Commission Haddam Neck Plant 361 Injun Hollow Road Connecticut Yankee Atomic Power Company East Hampton, Connecticut 06424-3099 362 Injun Hollow Road East Hampton, Connecticut 06424-3099 Nicholas S. Reynolds Winston & Strawn D. J. R y 1400 L Street, NW Haddam Neck Unit Director Washington, DC 20005-3502 Connecticut Yankee Atomic Power Company 362 Injun Hollow Road Mr. John F. Opeka East Hampton, Connecticut 06424-3099 Executive Vice President, Nuclear Connecticut Yankee Atomic Power Company G. H. Bouchard, Director Northeast Nuclear Energy Company Nuclear Quality Services Post Office Box 270 Northeast Utilities Service Company Hartford, Connecticut 06141-0270 Post Office Box 270 Hartford, Connecticut 06141-0270 l

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CONNECTICUT YANKEE ATOMIC POWER

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I MAY 10, 1993 4

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i MEETING WITH THE NRC STAFF i

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STEAM GENERATOR TUBE REPAIR-STRATEGIES i

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DOCKET NO. 50-213 4

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CYAPCO DOCKET NO. 50-213 i

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ATTENDEES l

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O R. T. HARRIS, DIRECTOR, ENGINEERING DEPT, NUSCO l

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O J. W. KLISIEWICZ, SUPERVISOR,' CHEMISTRY & MATERIALS, l

NUSCO O

M. R. GALLER, SENIOR ENGINEER, CHEMISTRY & MATERIALS, NUSCO I

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J.

M.

BENSON, SENIOR ENGINEER, WELDING & MATERIALS TEST ENG, NUSCO O

F.

C.

ANDERSON, SENIOR

ENGINEER, ENGINEERING MECHANICS, NUSCO j

O M. P. BAIN, ENGINEERING MANAGER, CYAPCO j

O R.

W.

PRITCHARD, SENIOR ENGINEER, ISI ENGINEERING, CYAPCO O

G. P. van NOORDENNEN, SUPERVISOR, NUCLEAR LICENSING, l

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NUSCO

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PERKINS, SENIOR ENGINEER, NUCLEAR LICENSING, 1

NUSCO a

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4, CYAPCO DOCKET NO. 50-213

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PURPOSE OF MEETING i

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4 DISCUSS WITH THE NRC STAFF THE STATUS OF SG.

TUBE REPAIR STRATEGIES FOR THE HADDAM NECK

PLANT, IN PARTICULAR ALTERNATE REPAIR CRITERIA AND TUBE ROLL EXPANSION.

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CYAPCO DOCKET NO. 50-213 4

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AGENDA l

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O INTRODUCTION - E.

P.

PERKINS 3

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O STATUS OF NRC STAFF REVIEW OF ALTERNATE i

REPAIR CRITERIA j

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O OVERALL SG STRATEGY.- R.

T.

HARRIS q

O SG TUBE REPP.IR BY ROLL EXPANSION M.

R.

GALLER

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NDE QUALIFICATION - J.

M.

BENSON l

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CONCLUSIONS - E.

P.

PERKINS 4

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CYAPCO DOCKET NO. 50-213 i

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1 OVERALL STEAM GENERATOR STRATEGY 4

R.

T.

HARRIS

DIRECTOR, ENGINEERING DEPARTMENT

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OBJECTIVE:

Maintain integrity of SGs for the Ucensed Plant Lifetime in a Safe, Reliable, and Economical Manner.

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l CYSG Stnnegy May 10.1993

e APPROACH:

Develop / Implement a Long-Term Strategic Plan Recognizes LT Structure Required

~

Documented Living Basis for Cycle-Specific Recommendations

• Focuses on Need to Avoid Plugging

• Reference Point for Interfacing Strategies / Actions t

I CYSG Strategy May 10,1993 N

Corrective Actions

1. Minimize Plugging through E.O.L.

2. Minimize Forced Outage Risk

3. Reduce Tube Fouling

4. Reduce Radiation Exposure CYSG Smnegy May 10,1993

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Cost Effective, Feasible Options for RFO 17

• Altemate Plugging Criteria (ARC)

• Rerolling (RX)

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• Plugging 4

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CYSG Strenegy l

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CYCLE SPECIFIC RECOMMENDATIONS Implement Actions which Maintain SG Integrity in a Safe, Reliable, and Cost-Effective Manner e

CYSG Strategy May 10,1993

17-CYAPCO DOCKET NO. 50-213 l

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M.

R.

GALLER i -

SENIOR ENGINEER, CHEMISTRY & MATERIALS l

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OBJECTIVE t

o BASES j

o CONNECTICUT YANKEE PROCESS DEMONSTRATION RESULTS i

o QUALIFICATION TEST RESULTS o

CORROSION POTENTIAL o

CONCLUSION Docs 28.20 ty 5/6/93 M F. G

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f OBJECTIVE

'I CREATE A NEW STRUCTURALLY SOUND, LEAK LIMITING MECHAN-i i

l ICAL JOINT A MINIMUM OF ONE INCH LONG BETWEEN THE TUBE AND TUBESHEET THAT WILL WITHSTAND ALL NORMAL OPERATING i

l AND DESIGN BASES ACCIDENT CONDITIONS.

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DOCS 28.20 tp 5/6/93 MRG

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EXPANDED ROLL AREA DIAGRAM

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BASES i

o ROLL EXPANSION (RX) IS A TECHNICALLY ESTABLISHED PROCESS PLUGGING SLEEVING P

o PROCESS APPLIED AT:

DOEL 2 MIHAMA 2 i

o PROCESS DEMONSTRATION AT CONNECTICUT YANKEE IN 1991 12 TUBE SAMPLE DETERMINATION OF TUBE EXPANSION CHARACTERISTICS l

ASSESS TOOLING PRE / POST ROLL NDE TUBE PLUGGING u

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Fig. 6.1.1.. Re-Roll Repair Joint s' ketch

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DESGN OVERLAP BOTTou ORI G1 NAL R0tt AREA i

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t CONNECTICUT YANKEE PROCESS DEMONSTRATION RESULTS l

o RX PRODUCED FAVORABLE TUBE EXPANSIONS ON TEN OF' TWELVE TUBES i

o NO NEW DEFECTS DETECTED l

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o PARTIAL EXPANSION ON 2 TUBES AS A RESULT OF TOOLING I

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QUALIFICATION OF TEST RESULTS f

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RX EXPANSIONS OF SLUDGE-FILLED CREVICES SIMULATING FIELD CONDITIONS i

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RX JOINT TESTED TO WITHSTAND ALL NORMAL OPERATING AND UPSET CONDITION LOADS i

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NO NEW DEFECTS PRODUCED r

o EXISTING DEFECTS DID NOT INCREASE IN SIZE 1

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RX PROCESS IMPARTS A SIMILAR OR LESS SEVERE TRANSI-TION GEOMETRY THAN EXISTS IN THE ORIGINAL HARD ROLL o

EXISTING FLAWS DID NOT INCREASE IN SIZE Docs 2s.2o tP 5/6/93 mas

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CORROSION POTENTIAL i

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o RX IS NOT EXPECTED TO RESULT IN THE INITIATION OF OD CREVICE CORROSION SLUDGE COMPOSITION CREVICE CHEMISTRY r

o PWSCC OF RX TUBES IS NOT EXPECTED TO BE A SIGNIFICANT i

LONG-TERM CONCERN DOCS 25.20 tp S/6/93 MRG

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CONCLUSION i

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RX IS AN ACCEPTABLE PROCESS FOR THE REPAIR OF PWSCC i

I DEFECTS IN THE HARD ROLL REGION OF CY STEAM GENERATOR f

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-i CYAPCO DOCKET NO.: 50-213 i

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h NDE QUALIFICATION l

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-i J. M.

BENSON SENIOR ENGINEER i

WELDING & MATERIALS' TEST ENGINEERING h

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OVERVIEW

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RE-ROLL JOINT ACCEPTANCE CRITERIA PURPOSE OF NDE QUALIFICATION PROGRAM i

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PRELIMINARY NDE RESULTS l

CONCLUSIONS i

RRNRC13 d3 l

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-RE ' ROLL JOINT ACCEPTA\\lCE CRITERIA F-STAR CRITERIA APPLIES TO NEW RE-ROLL JOINT ONE INCH OF SOUND ROLL IS REQUIRED ABOVE THE UPPERMOST CRACK TIP j

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ORIGINAL ROLL JOINT l

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i l. PURPOSE OF NDE QUALIFICATION PROGRAM TO QUALIFY AN NDE TECHNIQUE (S) FOR DETERMINING o

RE-ROLL JOINT ACCEPTABILITY l

TO DETERMINE THE ACCURACY OF NDE FOR CRACK o

DETECTION (BEFORE & AFTER RE-ROLLING)

TO DETERMINE THE ACCURACY OF NDE FOR MEASURING o

THE AXIAL LOCATION OF TUBE FLAWS i

TO DETERMINE THE ACCURACY OF NDE FOR MEASURING o

THE AXIAL LOCATION OF ROLL TRANSITIONS TO DEVELOP DATA ANALYSIS GUIDELINES FOR o

DETERMINING RE-ROLL JOINT ACCEPTABILITY l

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RRNRC16 d5 1

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SUMMARY

OF NDE MEASUREMENT PARAMETERS FOR DETERMINING RE-ROLL JOINT ACCEPTABILITY 4

CRACK DETECTION AXIAL LOCATION OF UPPERMOST CRACK TIP AXIAL LOCATION OF ROLL TRANSITIONS 1

RELATIVE TUBE EXPANSION DIAMETER 4

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NDE TECHNIQUES INCLUDED IN QUALIFICATION PROGRAM l

ULTRASONIC PROBE WITH ROTATING MIRRORS

1. CRACK DETECTION

2. MEASUREMENT OF AXIAL LOCATION OF UPPERMOST CRACK TIP

3. TUBE PROFILING 3-COIL ROTATING EDDY CURRENT PROBE i

1. CRACK DETECTION

2. MEASUREMENT OF AXIAL LOCATION OF i

UPPERMOST CRACK TIP BOBBIN COIL PROBE

1. TUBE PROFILING RRNRC25 47 J

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BOBBIN COIL PROFILES FOLLOWING RE-ROLLING l:

1991 CY REFUELING OUTAGE l

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RRNRC31 UNFAVORABLE ROLL JOINT l

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TIMNSDUCER UNIVERSALJOINT FLEXIBLE CENTERING GUIDE ROTATING MIRROR PROVIDES 360 COVERAGE SPLIT MIRROR ALLOWS DETECTION OF CRACKS AT VARIOUS ANGLES INCREASED SPEED

-1600 RPM (VS 300 RPM FOR RPC)

- 40 TUBE ENDS /HR (VS 30/HR FOR RPC)

HIGH PROBE LIFE EXPECTED

- 2000 TUBE ENDS / PROBE 2

ARCNRC20

1 CURVED G JIJE]CAllB'lATION TUBE FOR ULTFASONLC INSPECTION TUBE SHEET i

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UT PLOTS OF EDM NOTCHES BEFORE & AFTER RE-ROLLING I:

B SB 180 270 350 B0.1 Bl.3 HE CRRCK EvsLURT30N TRELE B2.3 CRCW RI.P05:

CRC POS: RI LNCTH CRC LGTH ANCLE:

157 is:

tin.3 rder.3 tin.2 tin.3 te r.3 a

B3.4 133 1

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St.B S2.5 B3.7 S4.8 BEFORE RE-ROLLING B

BB 1BB 270 3BB 77.5 78.5 2EE CRRCK EVALURTION TRBLE 3

CRCN RI.POS:

CRC POS: RI LNCTH CRC LGTH NNCLE:

79,7 157 -

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RRNRC35 AFTER RE-ROLLING

CONCLUSIONS A COMBINATION OF UT, RPC &/OR BOBBIN PROBE o

TESTING WILL BE USED FOR DETERMINING RE-ROLL JOINT ACCEPTABILITY o

NDE ERROR WILL BE CONSIDERED IN THE DETERMINATION OF RE-ROLL JOINT ACCEPTIBILITY o

DATA ANALYSTS WILL BE TRAINED ON THE REPORTING

~ REOUIREMENTS NECESSARY TO SUPPORT RE-ROLL NDE k

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i RRNRC23 3V

35 CYAPCO DOCKET NO. 50-213 i

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PERKINS SENIOR ENGINEER, NUCLEAR LICENSING i

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ATTENDANCE LIST NAME AFFILIATION i

Alan Wang NRC/NRR Jim Richardson NRC/NRR/DE Jack Strosnider NRC/NRR/DE John Stolz NRC/NRR/PDI-4 William Russell NRC/NRR/ADT En=ett Murphy NRC/NRR/EMCB i

George Johnson NRC/NRR/EMCB Herbert Conrad NRC/NRR/EMCB Kulin Desai NRC/NRR/SRXB l

Kamal Manoly NRC/NRR/EMEB Jai Rajan NRC/NRR/EMEB Peter Habighorst NRC/RI Everett Perkins NU Robert Harris NU Janes Benson NU Fred Anderson NU John Klisiewicz NU Gerry Van Noordennen NU l

Michael Bain Conn. Yankee l

Robert W. Pritchard CYAPCO l

Vince San Angelo Bechtel Power l

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