ML20215D329

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Forwards Summary of 861125 Meeting W/Util in Region IV Ofc Re Corrosion of High Pressure Injection Nozzle A.Meeting Provided Better Understanding of Corrosion & Corrective Actions.Viewgraphs & List of Attendees Encl
ML20215D329
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 12/05/1986
From: Gagliardo J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Campbell G
ARKANSAS POWER & LIGHT CO.
References
NUDOCS 8612160322
Download: ML20215D329 (32)
v • d • e


Text

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DEC 51986 In Reply Refer To:

Dockets: 50-313 Arkansas Power & Light Company ATTil: Mr. Gene Campbell Vice President, Nuclear Operations P. O. Box 551 Little Rock, Arkansas 72203 Gentlemen:

This refers to the meeting conducted in the flRC Region IV office on November 25, 1986, with Mr. D. Howard and other members of your staff.

The meeting was held to discuss the recent corrosion of the "A" high pressure injection nozzle.

The subjects discussed at this meeting are described in the enclosed Meeting Summary.

It is our opinion that this meeting was beneficial and has provided for a better understanding of the corrosion mechanism and corrective actions, including repair of the nozzle.

In acenrdance with Section 2.790 of the llRC's " Rules of Practice," Part 2 Title 10, Code of Federal Regulations, a copy of this letter will be placed in the NRC's Public Document Room.

Should you have any questions concerning this matter, we will be pleased to discuss them with you.

Sincerely, c,_,

J. :.. L

/

J. E. Gagliardo, Chief Reactor Projects Branch

Enclosure:

Meeting Summary cc/w enclosure:

J. II. Levine, Director Site Nuclear Operations Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Arkansas Radiation Control Program Director

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,o Arkansas Power & Light Company bec to DMB (IE01) bec w/ enclosure distrib. by RIV:

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r-Arkansas Power & Light Company Attachment A MEETING

SUMMARY

Licensee:

Arkansas Power & Light Company Facility:

AN0-1 License No.:

DPR-51 Docket No.:

50-313

Subject:

MeetingConcerningthe"A"HighPressureInjection(HPI) Nozzle Corrosion and Repair On November 25, 1986, representatives of Arkansas Power & Light Company, met in Arlington, Texas, with NRC Region IV personnel to discuss the "A" HPI nozzle corrosion and repair. The attendance list is attached as Appendix A to this summary. The meeting was held at the request of NRC, Region IV.

The licensee presented information (Appendix 3) regarding the "A" HPI nozzle corrosion mechanism and corrective actions, including the repair of the nozzle. Specific and generic corrective actions taken and planned by the licensee were discussed.

Attachments:

1.

Appendix A - Attendance List 2.

AppendixB-AP&LCo. Handout (toDMBandRIVFileOnly) l I

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APPENDIX A 1

MEETING ATTENDANCE LIST NRC REGION IV ARKANSAS POWER & LIGHT COMPANY NRC Attendees:

1. Barnes, Chief, Comanche Peak Task Group J. Gagliardo, Chief, Reactor Projects Branch R. Hall, Deputy Director, Division of Reactor Safety and Projects

.D. Hunnicutt, Chief Operations Section, Reactor Safety Branch D. Hunter, Chief, Project Section B, Reactor Projects Branch T. Westerman, Chief, Reactor Safety Branch Licensee Attendees:

. B. Baker, Operations Manager D. Howard, Manager, Special Projects R. Lane, Manager, Engineering A. Smith, Engineer F. Snow, Engineer, Babcox and Wilcox M. Snow, Licensing Engineer

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HPI N0ZZLE 'A ' CORROSION INFORMA TION BRIEFING

,I TO NUCLEAR REGULATORY COMMISSION NOVEMBER 25, 1986 I

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HIGH PRESSURE INJECTION N0ZZLE 'A ' CORROSION INFORMATION BRIEFING AGENDA I

NOVEMBER 25, 1986 I

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INTRODUCTION Dan Howerd I

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BACKGROUND Don Lomax I

o DAMAGE DESCRIPTION. -

Don Lomax I

o REPAIRS Rick Lane I

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CAUSE Basil Baker Alan Smith I

o ADDITIONAL ACTIONS Rick Lane l

Basil Baker I

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BACKGROUND I

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AND-1 TYPICAL HPI/MU N0ZZLE CONFIGURATION I

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Carbon Steel RCS Cold Leg Piping m-((

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Stainless Steel Carbon Steel Safe End Nozzle Body I

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ANO-1 THERMAL SLEEVE DESIGNS I

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NEW OESIGN OLD DESIGN

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Safe End Inconel Weld I

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Inconel Stainless Steel I

Weld Butter-2

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Thermal Sleeve S/8" Nom. %

Carbon Steel Nozzle Body i

2-1/16 " Nom. -e-Carbon Steel Reactor Coolant Pipe 2-1/4" Nom.

I 1/8" Min.W Stainless Steel Cladding I

I MID-CYCLE 4 HPI N0ZZLE THERMAL SLEEVE INSPECTION I

I HPI AS FOUND REPAIR SUBSEQUENT N0ZZLE CONDITION REQUIRED INSPECTIONSM I

A SLEEVE LOOSE /

NEW SLEEVE UT& RT l

BUTTONS MISSING 1R5,1R7,1R9 I

B SLEEVE TIGHT /

REROLLED RT I

PARTIAL GAP 1R5 THRU 1R9 I

C OK NONE RT l

1R5 THRU 1R9 I

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SLEEVE TIGHT /

NEW SLEEVE UT& RT CIRCUMFERENTIAL 1R5 1R7 1R9 I

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HPI N0ZZLE 'A ' CORROSION DAMAGE DESCRIPTION I

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MOST SEVERE CORROSION BEGINS ADJACENT TO INCONEL NELD BUTTER (AT THE SAFE END TO N0ZZLE WELD) IN THE CARBON I

STEEL OF THE N0ZZLE o

CORROSION EXTENDS APPROXIMA TEL Y 1/4 0F CIRCUMFERENCE l

OF WELD ALONG BOTTOM OF N0ZZLE l

0 MAXIMUM WASTAGE IS APPROXIMA TEL Y 1/2 INCH DEEP IN THIS REGION I

o TWO CORROSION CAVITIES WITH AN INTERVENING ISLAND OF MINIMAL CORROSION DAMAGE EXTEND LONGITUDINALL Y FROM THE WELD l

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THE TWO CAVITIES NARROW AND BRANCH INTO FOUR PARALLEL GROOVES BEGINNING AT THE N0ZZLE THICKNESS TRANSITION I

o THE FOUR GROOVES CONTINUE ALONG THE N0ZZLE TRANSITION I

AND MERGE TO FORM TWO GROOVES AT THE END OF THE N0ZZLE THICKNESS TRANSITION 0

THE TWO GROOVES CONTINUE ALONG THE N0ZZLE BOTTOM AND

,l THEN VERTICALL Y DOWN THE RCS COLD LEG PIPING BECOMING l

MORE SHALLOW

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I REPAIR INVESTIGA TION I

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PT G RT SHOWED NO THROUGH WALL PENETRATION OR Cuvo1NG EXPOSURE g

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THERMAL SLEEVES NOT AFFECTED I

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DAMAGED AREAS GROUND OUT I

o MAXIMUM DEPTH OF GRINDING APPROXIMA TEL Y 1/2 INCH I

o REPAIR METHODS SELECTED :

I DAMAGED AREAS LESS THAN MINIMUM WALL THICKNESS I

TO BE WELD REPAIRED I

OTHER AREAS TO BE BLEND GROUND TO A MINIMUM 3 TO 1 TAPER l

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WELD REPAIR I

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WELD REPAIR PERFORMED PER ASME SECTION XI I

0 REPAIR PLAN SPECIFIED WELD BUILDUP USING INCONEL TO l

REQUIRED WALL THICKNESS I

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MOCKUP TESTING WAS PERFORMED PRIOR TO WELDING I

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o PREHEA T OF A T LEAST 200F WAS MAINTAINED THROUGHOUT g

WELDING PROCESS WITH INTERPASS TEMPERATURE NOT l

EXCEEDING 350F I

o PT WAS PERFORMED AFTER THE FIRST PASS o

NO POST WELD HEAT TREATMENT REQUIRED I

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o RT UT

& PT EXAMINATIONS WERE PERFORMED ON THE I

WELD REPAIRED AREAS I

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UT & PT EXAMINA TIONS WERE PERFORMED ON THE GROUND AREAS WHICH WERE NOT WELD REPAIRED I

o FINAL RESULTS VERIFIED CODE ACCEPTABILITY AND THERMAL SLEEVE INTEGRITY AND TIGHTNESS I

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STRESS ANALYSIS I

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GUALIFIED THE REPAIRED N0ZZLE FOR AT LEAST ONE CYCLE OF OPERATION I

o TRANSIENT CYCLES ADRESSED :

I HEATUP AND C00LDOWN FROM 8% POWER - 20 CYCLES I

HPI INITIATION AND RECOVERY - 10 CYCLES g

HPI TEST - 10 CYCLES

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N0ZZLE BODY AND RCS PIPE /N0ZZLE JUNCTION ADDRESSED

'I l I STRUCTURAL REQUIREMENTS OF AS4E SECTION III MET o

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FURTHER DETAILED ANAL YSIS WILL BE PERFORMED

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I CYCLE 6 MU-45A LEAKAGE HISTORY I

I 8/25/85 MU-45A LEAKAGE DETECTED (0.078 GPM)

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9/18/85 MU-45A SEAL RING REPLACED I

9/26/85 MU-45A LEAKAGE DETECTED (0.094 GPM)

I 2/02/86 MU-45A SEAL RING REPLACED - NO SUBSEQUENT l

LEAKAGE DETECTED

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I BORIC ACID CORROSION I

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INDUSTRY EXPERIENCE I

o PROPERTIES OF BORIC ACID :

I pH VS. CONCENTRATION CORROSIVITY VS TEMPERATURE PHYSICAL STATES OF CONCENTRATED AND MOLTEN l

BORIC ACID I

o POSTULA TED DAMAGE SCENARIO I

o CONCLUSIONS I

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I RELATED INDUSTRY EXPERIENCE I

Io LOW-ALLOY FASTENER CORROSION

-Numerous Incidents of Degradation and/or Failure

-RV Closure Studs, RCP Studs, Primary S/G and Pzr g

Manway Studs, Valve Bonnet Bolts / Studs I

o (1970) BEZNAU (SWITZERLAND) l

-Reactor Vessel Closure Head

-CRD Tube Leaked for 6-8 Months I

-2" Long x 1" Wide x 1" Deep Gauge I

ga (1971)

CALVERT CLIFFS-2

-RCS Cold Leg Near RCP Suction l

-1/8" to 1/4" x 18" Long at Dissimilar Weld Joint

-Leakage From Weld Failures in RCP Seal Lines I

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B, P P M pil of Boric Acid Solutions at 77 F and 200 F

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TIME ( HOURS )

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HB0 METABORIC ACID B 0 *N 0 2

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B0HO (HYDRATED) BORIC 0XIDE B 0.H O g

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I HPI N0ZZLE 'A' INSULATION ARRANGEMENT I

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CONCLUSIONS I

o CBSERVED CORROSION INCIDENT WAS DUE TO COMPLEX INTERACTIONS OF :

I LEAK RA TE I

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MATERIAL PROPERTIES I

o COMBINA TIONS CAPABLE OF PRODUCING WASTAGE OF I

THIS TYPE ARE RARE I

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ADDITIONAL ACTIONS I

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I ANO-1 CONTAINMENT INSPECTIONS I

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IDENTIFICATION OF POTENTIAL PROBLEM AREAS :

I ENGINEERING DESIGN REVIEW TO IDENTIFY CARBON STEEL COMPONENTS PREVIOUS KNOWN BORATED WATER LEAKAGE l

SYSTEM WALKDOWN TO LOOK FOR BORIC ACID / RUST DEPOSITS I

o SIXTY-NINE LOCA TIONS IDENTIFIED

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SCREENING CRITERIA FOR LOCATIONS TO BE INSPECTED :

PHYSICAL POSITION OR LOCATION MATERIAL COMPOSITION l

INSPECTED DURING RECENT REFUELING OUTAGE RELATED AREAS I

o TNENTY-FOUR LOCATIONS INSPECTED I

o INSPECTIONS FOUND NO EXCESSIVE GENERAL CORROSIVE

ATTACK, PITTING, OR GROOVING OF CARBON STEEL g

SURFACES I

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I ANO-2 CONTAINMENT INSPECTIONS I

o IDENTIFICATION OF POTENTIAL PROBLEM AREAS:

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-PREVIOUS KNOWN BORATED WATER LEAKAGE NINETEEN LOCATIONS I

'-SYSTEM WALKDOWN TO LOOK FOR BORIC ACID / RUST DEPOSITS THIRTEEN LOCATIONS o

SCREENING CRITERIA FOR LOCATIONS:

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-PHYSICAL LOCATION l

-MATERIAL

-PREVIOUS INSPECTIONS a

LOCATIONS OF POTENTIAL CONCERN WERE DOCUMENTED AS BEING ACCEPTABLE I

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I RCS LEAKAGE EVALUA TION I

I EVENT DESCRIPTION AND SIGNIFICANCE PROVIDED TO o

OPERA TORS 0

INTERIM INSTRUCTIONS TO OPERA TORS :

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REPAIR OF LEAKAGE DURING OUTAGES INCREASED EMPHASIS ON RCS LEAKAGE MEASUREMENTS I

EVALUATIONS REQUIRED FOR DETECTABLE LEAKAGE o

PROPOSED PROCEDURE CHANGES :

I INCORPORA TE INTERIM ACTIONS l

SPECIFY FUTURE INSPECTIONS I

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