ML20043E311

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Summary of 900523 Meeting W/Util Re Results of Util Steam Generator Tube Insp & Program for Operation of Steam Generators During Forthcoming Cycle.Licensee Briefing Matls & List of Attendees Encl
ML20043E311
Person / Time
Site: Maine Yankee
Issue date: 06/07/1990
From: Leeds E
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 9006120284
Download: ML20043E311 (51)
v • d • e


Text

'

',,e June 7,1990 l

Doctet No. 50 309 1

LICENSEE:

Maine Yankee Atomic Power Company FACILITY:

Maine Yankee Atomic Power Station

SUBJECT:

MEETING WITH MAINE YANKEE ATOMIC POWER COMPANY REGARDING THE STEAM GENERATOR EXAMINATION DURING THE 1990 OUTAGE On May 23, 1990, representatives of Maine Yankee met with NRR to discuss the results of their steam generator examination and program for operation of the steam generators during the forthcoming cycle. Er. closure 1 is a copy of the licensee's briefing material and enclosure 2 is a list of meeting attendees.

Maine Yankee conducted a complete inspection of all tubes (in the tube sheet area) in all three steam generators, as well as the inspections required by i

Technical Specifications. The extended inspection effort was initiated because of leakage during the previous operating cycle and the identification of a small number of circumferential crack indications.

A total of 42 tubes were plugged.

Maine Yankee has proposed conservative operating limits to be effective upon startup for the next cycle and will document these limits in a letter to the NRC prior to restart. Maine Yankee will also provide a revised steam generator leakage Technical Specification within approximately 30 days. The j

licensee's proposed course of action is acceptable to the staff. No mid-cycle inspection is planned at this time.

The licensee will provide additional inspection results regarding the No. 2 steam generator (results were not yet complete at the time of the meeting).

The licensee will also provide the staff with the results of chemical analyses currently in progress, the analysis of the single tube that was removed, and the results of the Regulatory Guide 1.121 analysis.

o0 Eric J. Leeds. Project Manager E82 Project Directorate 1-3 j

s'8 Division of Reactor Projects 1/11 ClO

Enclosures:

As stated ah cc:

See next page em

, DISTRIBUTION:_ DocketeFile,50 309, NRC & Local PDRs, FMira lia, PDI-3 R/F, 5

ort RWessman, Eleeds, MRushbrook, OGC (info), EJordan, ACRS (1 ), JDyer, S$4.

RBoorchardt, JJohnson, EMcCabe, RWinters, JRichardson, CYCheng RFreudenberger, EMurphy, FWitt, HFConrad, JCaldwell i

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0FFICIAL RECORD COPY D Fol

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Docuraent Name: MY MEETING

SUMMARY

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3 Mr. C. D. Frizzle Cc' Mr. Charles B. Brinkman Mr. G. D. Whittier, Panager Manager - Washington Nuclear Nuclear Engineering and Licensing Operations Peine Yankee Atomic Power Company Combustion Engineering, Inc.

83 Edison Drive 12300 Twinbrook Parkway, Suite 330 Augusta, Maine 04336 Rockville, Marylard 20852 Mr. Robert W. Blackmore, John A. Ritsher, Esquire Plant Manager Ropes & Gray Maine Yankee Atomic Power Company 225 Franklin Street P.O. Box 408 Boston, Massachusetts 02110 Wiseasset, Maine 04578 State Planning Officer Executive Department 189 State Street Augusta, Maine 04330 Dr. E. T. Boulette, Vice President Operations Maine Yankee Atomic Power Company P. O. Box 408 Wiscasset, Maine 04578 4

Mr. J. H. Garrity, Vice President Licensing and Engineering Maine Yankee Atomic Power Company 83 Edison Drive Augusta, Maine 04336 Regional Administrator, Region i U.S. Nuclear Regulatory Comnission 475 Allendale Road King of Prussia, Pennsylvania 19406 First Selectman of Wiscasset Municipal Building U.S. Route 1 Wiseasset, Maine 04578 Mr. Cornelius F. Holden i

Resident inspector Maine Yankee Atomic Power Station U.S. Nuclear Regulatory Commission P. O. Box E Wiscasset, Maine 04578 Mr. P. L. Anderson, Project Manager Yankee Atomic Electric Company 580 Main Street Bolton, Massachusetts 01740-1398

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J ualNE YANKEE /NRC MEETING AGENDA STEAM GENERATOR EXAMINATION - 1990 REFUELING i

i C. D. FRIZZLE INTRODUCTION P.J.PLANTE INSPECTION PROGRAM & RESULTS l

STEAM GENERATOR CHEMISTRY CONSIDERATIONS P.B.RADSKY P.J.PLANTE STEAM GENERATOR REPAIRS PROGRAM FOR IDENTIFYING DEFECT MECHANISM P.J.PLANTE S. E. NICHOLS f

LEAKAGE MONITORING 1

R. W. BLACKMORE OPERATOR TRAINING PROGRAMS t

C. D. FRIZZLE CLOSURE

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INSPECTION PROGRAM & RESULTS P.J.PLANTE l

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SUMMARY

- MAINE YANKEE EDDY CURRENT HISTORY 13 EDDY CURRENT TEST PROGRAMS HAVE BEEN CONDUCTED PRIOR TO 1990.

SINCE 1985 (WHEN DIGITAL TECHNOLOGY WAS INTRODUCED) 1985 S/G #1 S/G #2 S/G #3 VOLUNTARY MANDATORY VOLUNTARY 1,740 TUBES 4,764 TUBES 1100 TUBES 3 PLUGGABLES 22 PLUGGABLES 11 PLUGGABLES FLAWS ASSOCIATED WITH COPPER DEPOSITS SPURRED DECISION TO CHEMICAL CLEAN 1987 S/G #2 MANDATORY 1,017 TUBES 2 PLUGGABLES PLUGGABLES 1 DENT,1 DEFECT MASKED BY COPPER FLAWS ASSOCIATED WITH COPPER DEPOSITS 1988 S/G #1 S/G #3 MANDATORY PLANNED BUT 3069 TUBES SWITCHED TO 13 PLUGGABLES S/G #1 PLUGGABLES - 6 PITTING,5 DENTS,2 POSSIBLE DEBRIS EMPHASIS ON FLAWS ASSOCIATED WITH COPPER DEPOSITS CONDUCTED PERIPHERAL TUBE EXAM SINCE CHEMISTRY DATA INDICATED POSSIBLE TUBE LEAK IN S/G #1 MAINE YANKEE 1990 S/G PROGRAM 5/23MD

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SUMMARY

- MAINE YANKEE PLUGGING NISTORY i

STEAM GENERATOR #1 5 RIM CUT PLUGS 1978 3 PLUGS 1985 13 PLUGS 1988 21 TOTAL r

l STEAM GENERATOR #2 6 SHOP PLUGS ORIGINAL 5 RIM CUT PLUGS 1978 13 PLUGS 1982 22 PLUGS 1985 1

2 PLUGS 1987 48 TOTAL

}

STEAM GENERATOR #3 5 RIM CUT PLUGS - 1978 11 PLUGS - 1985 16 TOTAL l

MAINE YANKEE 1990 S/G PROGRAM 5/234 0 l

I-

a DESCRIPTION OF INSPECTION METHODS 1990 LEAK TEST ALL 3 S/G'S.

160 PSIG ON SECONDARY SIDE BOWL SCAN ON PRIMARY SIDE STANDARD 0.580 IN BOBBIN PROBE (TECH. SPEC. EXAM)

SPEED: 24 IN/SEC 25,100,400,600 KHZ MOTORIZED ROTATING PANCAKE COIL (PRIMARY TECHNIQUE)

SPEED: 0.2 IN/SEC,300 RPM l

50, 200, 300, 400 KHZ 3 COIL MOTORIZED ROTATING PANCAKE COIL (DIAGNOSTIC TECHNIQUE)

SPEED: 0.1 IN/SEC,200 RPM 50, 200, 300, 400 KHZ ULTRASONIC (D! AGNOSTIC TECHNIQUE)

ROTATING MIRROR 45' SHEAR WAVE AXIAL AND CIRCUMFERENTIAL SCANS SAME EXAM PARAMETERS AS WAS USED AT MILLSTONE 2 j

WITH THE ADDITION OF THE AX1AL TECHNIQUE.

MAINE YANKEE 1990 S/G PROGRAM 5/23AO

i DEGREE OF INSPECTIONS 1990 LEAK TESTING ALL 3 STEAM GENERATORS FOR 6 HOURS MINIMUM BOBBIN COIL FULL LENGTH OF TUBE TEST.1543 TUBES EXAM TESTED (1S + 2S PROGRAM PER TECH.

SPEC.)

MOTORIZED ROTATING 2 INCHES ABOVE TO 2 INCHES BELOW THE PANCAKE COIL EXAM TUBE SHEET IN ALL ACCESSIBLE TUBES (34000+ TUBES) IN ALL 6 PLENUMS ULTRASONIC EXAM ALL CIRCUMFERENTIAL INDICATIONS INDICATED BY ECT PLUS SOME DISTORTED SIGNALS i

MAINE YANKEE 1990 S/G PROGRAM 5/23/.0

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DESCRIPTION OF SPECIAL EDDY CURRENT TESTS 1990

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AW 1 (8 AXIALLY WOUND EDDY CURRENT COILS):

COMBINES BOBBIN TECH. AND CIRC. CRACK DETECTION (PROBED 23 CIRC. INDICATIONS) l i

SPEED: 12IN/SEC 100, 200, 400, 900 KHZ I--

MOTORIZED ROTATING PANCAKE COLL USING MILLSTONE 2 PROBE SPEED l

(PROBED 23 CIRC. INDICATIONS) l SPEED: 0.1 IN/SEC,200 RPM I

100, 200, 400, 600 KHZ BOBBIN TEST (23 TUBES WITH CIRC. INDICATIONS TO COMPARE WITH 1

1988 BOBBIN DATA,20 PREVIOUSLY TESTED).

PROFILOMETRY (CONDUCTED ON 23 TUBES WITH CIRC. INDICATIONS, 23 ADJACENT TUBES,25 TUBES IN DESCENDING ROW NOS.).

REVIEWED BOBBIN COIL DATA FOR S/G#3 WITH DENT SUPPRESSION MIX TO CHECK FOR HIDDEN AXIAL INDICATIONS.

1 MAINE YANKEE 1990 S/G PROGRAM 5/235D L

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VENDORS CONDUCTING TESTING AND QUALIFICATIONS EDDY CURRENT TESTING CONDUCTED BY BABCOCK AND WILCOX/CONAM 4

INDEPENDENT PRIMARY AND SECONDARY ANALYSIS CONDUCTED.

ALL DISCREPANCIES REVIEWED BY LEVEL lil ANALYSIS.

- ALL ANALYSTS HAVE BEEN BL.;40 TESTED ON A MAINE YANKEE DATA TAPE WHICH HAD 4 CIRCUMFERENTIAL CRACKS t

ALL ANALYSTS HAD PRIOR MRPC EXPERIENCE SOME ANALYSTS HAD MILLSTONE 2 MRPC EXPERIENCE MAINE YANKEE'S PROJECT CONSULTANT FROM COMBUSTION ENGINEERING HAS BEEN THE LEAD ANALYST AT MILLSTONE 2 SINCE 1985.

  • ULTRASONIC TESTS CONDUCTED BY COMBUSTION ENGINEERING /NUCON. THEY ALSO PERFORMED ULTRASONIC TESTING AT MILLSTONE 2.

MAINE YANKEE 1990 S/G PROGRAM 5/23T f

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lNSPECTION RESULTS LEAK TEST S/G 1 - TWO LEAKING TUBES IDENTIFIED f

1 DRIPPED EVERY 4 MINUTES (ROW 82, LINE 113).

1 WET THE TUBE SHEET BUT DID NOT DRIP (ROW 82, LINE 33).

CONFIRMED CIRCUMFERENTIAL CRACKS WITH ECT-MRPC, t

S/G 2 NO LEAKING TUBES IDENTIFIED.

S/G 3 ONE LEAKING TUBE IDENTIFIED.

t ONE DRIPPED EVERY 3 MINUTES.

CONFIRMED WITH ECT BOBBIN AND MRPC AXIAL CRACK AT NO. 2 EGGRATE SUPPORT i

MAINE YANKEE 1990 S/G PROGRAM 5/23/50

I INSPECTION RESULTS j

BOBBIN COIL EXAM 1543 TUBES

- 4 TUBES WITH GREATER THAN 40% WALL LOSS PLUGGABLE PIT LIKE INDICATIONS 6 INCHES ABOVE THE COLD LEG TUBE SHEET 12 BETWEEN 30 AND 39% WALL LOSS 6 BETWEEN 20 AND 29% WALL LOSS 20 BETWEEN O AND 19% WALL LOSS 1

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MAINE YANKEE 1990 S/G PROGRAM 5/235

INSPECTION RESULTS

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MRPC EXAM (PLUGGABLES ONLY)

S/G # 1 HOT LEG (5682 EXAMS) 23 CIRCUMFERENTIAL INDICATIONS 1

1 PIT LIKE INDICATION i

S/G # 1 COLD LEG (5682 EXAMS) 0 INDICATIONS l

S/G # 2 HOT LEG (5655 EXAMS) 3 CIRCUMFERENTIAL INDICATIONS l

1 PIT LIKE INDICATION I

S/G # 2 COLD LEG (5655 EXAMS) 0 INDICATIONS S/G # 3 HOT LEG (5687 EXAMS) 1 AXIAL INDICATION l

1 DISTORTED SIGNAL WITH POSSIBLE INDICATION 4 CIRCUMFERENTIAL INDICATIONS 2 PIT LlKE INDICATIONS S/G # 3 COLD LEG (5686 EXAMS) 1 CIRCUMFERENTIAL INDICATION 1

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3 COIL MOTORIZED ROTATING PANCAKE COIL 4

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AXIAL WOUND COIL CIRCUMFERENTIAL WOUND COIL PANCAKE COIL

  • RESULTS ALLOW ANALYSTS TO DISTINGUISH BETWEEN CIRCUMFERENTIAL INDICATIONS (NO AXIAL COMPONENT) AND OTHER TYPES OF INDICATIONS.

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INSPECTION RESULTS SPECIAL TESTS-

  • AW 1 - SAW LARGE CIRCUMFERENTIAL INDICATIONS, BUT NOT ALL CIRCUMFERENTIAL INDICATIONS, NOT A CANDIDATE FOR FUTURE APPLICATIONS.

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  • MY MRPC TECH. VS. MILLSTONE MRPC TECH. NO APPRECIABLE DIFFERENCE BETWEEN THE ABILITY OF THESE TECHNIQUES TO DETECT CIRCUMFERENTIAL FLAWS.
  • BOBBIN TEST RESULTS COMPARED FROM 1990 WITH 1988. TWENTY COMMON TESTS. NO APPRECIABLE CHANGE IN BOBBIN SIGNAL FROM ONE YEAR TO THE OTHER IN 19 SIGNALS COMPARED.1 St JAL SHOWED CHANGE (THIS IS THE TUBE PULL CANDIDATE).
  • PROFILOMETRY SHOWN NO APPARENT CORRELATION BETWEEN j

DENTING AND CIRC. INDICATIONS.

  • DENT SUPPRESSION REVIEW SHOWED LEAKING TUBE WITH AXIAL INDICATION TO BE ISOLATED CASE.

I MAINE YANKEE 1990 S/G PROGRAM.

5/23$

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ULTRASONIC TESTING (PREUMINARY RESULTS)*

S/G #1 HOT LEG (26 EXAMS) 5 AXIAL INDICATION 15 CIRCUMFERENTIALINDICATlONS t

1 PIT INDICATION I

S/G #2 HOT LEG (3 EXAMS) 1 TO BE CONDUCTED S/G #3 HOT LEG (5 EXAMS) 2 CIRCUMFERENTIALINDICATION 1

4 PIT CLUSTERS S/G #3 COLD LEG (1 EXAM) 1 CIRCUMFERENTIALINDICATION

  • lN,SOME CASES TUBE HAD MORE THAN ONE TYPE OF DEFECT i

MAINE YANKEE 1990 S/G PROGRAM 5/350

NUCON - Inspection and Plant Services 20 MAY 1990 i

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INSPECTION RESULTS -

SUMMARY

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,BO,BBIN, EXAM:

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1543 TUBES EXAMINED 4 TUBES REQUIRE PLUGGING 0.3% DEFECTIVE TUBES MRPC AND UT EXAM:

34047 TUBES EXAMINED 38 TUBES REQUIRE PLUGGING 0.1% DEFECTIVE TUBES l

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MAINE YANKEE 1990 S/G PROGRAM 5/2350

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1 ATEAM GENERATOR CHEMISTRY CONSIDERATIONS 1

P.B.RADSKY e

HISTORY OF STEAM GENERATOR CHEhBSTRY CONTROL l

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STARTUP WTTH ALL VOLATILE CHEMISTRY.

E o

ADOPTED POLICY TO REPAIR ALL CONFIRMED CONDENSER LEAKS.

1974-1976 o INCRE/. ding FREQUENCY OF CONDENSER LEAKS.

o METHODS DEVELOPED TO DETECT, LOCATE AND PLUG CONDENSER LEAKS LESS THAN 0.01 GPM.

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o DENTING FIRST DETECTED.

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o INITIATED CONDENSER RETUBING WTTH AL6X.

o INITIATED COPPER REMOVAL PROBLEM.

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SECONDARY SYSTEM BORIC ACID-ADDITION INITIATED.

o OXYGEN INGRESS PREVENTION PROGRAM.

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.o TITANIUM CONDENSER.

o COPPER PLATING AND TUBE PTITING DETECTED.

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STEAM GENERATOR CHEMICAL CLEANING.

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FEEDTRAIN COPPER CHANGE OUT SCHEDULE-TURE

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$URFACE TOTAL ~

OPERA-- PLACE-FT4 SURFACE TING MENT TEMP.

DATE MOISTURE SEPARATOR REHEATERS-68,400 10.5%

550*F 1984 FIRST POINT HEATERS 38,970 6.2%

450*F 1980 l

SECOND POINT FEEDWATER HEATERS 19,590-3.1%

380*F 1987 THIRD POINT FEEDWATER HEATERS 20,180 3.2%

320*F 1990 FOURTH POINT FEEDWATER HEATERS 24,380 3.8%

270*F 1990 FIFTHPOINTFEEDWATERHEATERS 23,590 3.7%

220*F 1990 SIXTH POINT FEEDWATER HEATERS 29,290 4.6%-

180*F 1987 FIFTH POINT EXTERNAL DRAIN 7,450 1.0%

190*F 1988 COOLERS l

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GLAND STEAM CONDENSERS 790

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210*F 1988 CONDENSER

  • 200,000 31.7%

180'F 1978 200.000 31.7%

180*F 1980 TOTAL 630,640 NOTE 7"E CONDENSER TUBES WERE CHANGED AGAIN IN 1985 rROM STAINLESS STEEL To-TITANIUM

2 DENT PROGRESSION-RATES MMME yANMrf fV6'$

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PARTIAL ORILLEO SUPPORT PLATL I

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STEAM GENERATOR ACTIVITY (following Plant Shutdowns)

PLANT 8/G #1 S/G #2 S/G #3 SHUTDOWN hcl /ml uC1/al uCi/al 10/21/88 I-131 = 8.55E-8 Co-60: 6.11E-7 Co-60:9.13E-7 Co 5.25E-7

- Cs-137:1.27E-7 Cs-137 = 8.40E-8 10/21/89 I-131: 3.76E-8 No detectable No detectable I-133: 4.52E-8 Activity Activity.

l 11/8/89 I-131: 5.26E-8 No dea;ectable No detectable I-133: 7.95E-8 Activity Activity Na-24: 3.13E-8 t

Xe-135: 2.26E-8 j

Cs-137: 2.71E-8 l

l 4/7/90*

I-131 1.18E No do,tectable I-131: 2.64E-7 T-132: 2.76E-7 Activity I-133: 4.85E-7 I-133: 2.60E-6 I-135: 2.33E-7 I-135: 8.79E-7 Na-24: 1.06E-7 Ma-24: 2.38E-7 Xe-135: 1.995-8 Xe-135e: 4.29E-7 l

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  • Samples on 4/7/90 were obtained significantly earlier in the shutdown prior to effects of. dilution or decay.

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SECONDARY SYSTEM CHEMISTRY Stamm Generator Impuritics*

CONDENSATE CHLORIDE SODIUM SULFATE OXYOEN DDh Dpb puh sah 1988 2.4 2.3 2.3 2.2 i

1989 2.0 1.3 2.4 3.7 i

1/1/90 to 3/18/90**

2.4 2.1 l

1st Qtr 1990 18.6**

14.7**

2.3 1.8

  • Avotage concentrations at power operations >30%.

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    • Condeesec leek on 3/19/90. First inicakage since 3/18/87.

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STEAM GENERATOR TUBE REPAIR PROGRAM-l

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REPAIRS BASED ON PRIMARILY ECT DATA j

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STEAM GENERATOR TUBES WITH PLUGGABLE DEFECTS OTHER THAN CIRCUMFERENTIAL MECHANICAL TUBE PLUGS j

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STEAM GENERATOR TUBES WITH CIRCUMFERENTIAL DEFECTS

- HOT LEG DEFECT (MECHANICAL PLUG COLD LEG SIDE)

INSTALL FLEXIBLE STAKE INSTALL MECHANICAL TUBE PLUG WITH WEAR COLLAR

- COLD LEG DEFECT (MECHANICAL PLUG HOT LEG SIDE)

INSTALL FLEXIBLE STAKE INSTALL WELDED TUBE PLUG

- SAMPLED STEAM GENERATOR TUBE

- HOT LEG CUT NEAR SUPPORT PLATE OR STAKE INSTALL WELDED TUBE SHEET PLUG

- COLD LEG INSTALL WELDED TUBE PLUG l

COMBUSTION ENGINEERING TO PERFORM ALL REPAIR OPERATIONS l

MAINE YANKEE - 1990 S/G PROGRAM 5/23 90

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PROGRAM FOR IDENTIFYING DEFECT MECHANISM P.J.PLANTE s

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MRPC AND UT CHARACTERIZATIONS A COMPARISON OF ECT AND UT CHARACTERIZATIONS SHOWS ECT TO BE THE MORE CONSERVATIVE METHOD FOR INSPECTING TUBES FOR CIRCUMFERENTIAL INDICATIONS.

CORRELATION BETWEEN ECT AND UT IS GOOD FOR LARGER FLAW SIZES.

MAINE YANKEE BASED STAKING AND PLUGGING REQUIREMENTS PRIMARILY ON ECT RESULTS.

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,.I HISTORICAL MATERIALS AND FABRICATION REVIEW

  • A REVIEW OF MAINE YANKEE STEAM GENERATOR MATERIAL AND FABRICATION RECORDS BY COMBUSTION ENGINEERING INCLUDING:

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- CERTIFIED MATERIAL TEST REPORTS

- SHOP TRAVELLERS

- TUBING FABRICATION HISTORY

- NONCONFORMANCE REPORTS 7

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TUBE' PULL AND ANALYSIS CANDIDATE TUBE IS ROW 75, UNE 34 IN S/G #1 HOT LEG

- ECT CHARACTER: 109' 126' CIRCUMFERENTIAL EXTENT

- UT CHARACTER:

3 CRACKS 1 CRACK IS 79% THRU '- WALL, 53' l

CIRCUMFERENTIAL EXTENT AVERAGE THRU WALL 16%

1 LABORATORY ANALYSIS PROGRAM:

- DETERMINE FAILURE MODE.

- DETERMINE WHAT CAUSED OBSERVED FAILURE, IF FAILURE IS

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- CORROSION RELATED

- CHARACTERIZE TUBE PROPERTIES TO DETERMINE IF TUBE

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PROPERTIES RELATED TO FAILURE.

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- CHARACTERIZE TUBE DEPOSITS

- PERFORM ADJACENT SLUDGE ANALYSIS i

' MAINE YANKEE - 1990 S/G PROGRAM 5/Z3T

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CREVICE CHEMISTRY ANALYSIS USE EPRI MULTEQ CODE WITH MAINE YANKEE DATA TO PREDICT CREVICE CHEMISTRY CONDITIONS IN THE STEAM GENERATOR SLUDGE PILE.

DETERMINE IF ANY TRENDS IN CREVICE CHEMISTRY ARE APPARENT OVER THE LAST SEVERAL CYCLES FOR WHICH DATA IS AVAILABLE.-

NWT CORPORATION TO CONDUCT ASSESSMENT.

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L MAINE YANKEE CIRCUMFERENTIAL FLAW CHARACTERISTICS

.t MAINE YANKEE FLAWS CLEARLY EXHIBIT LEAK BEFORE BREAK CHARACTERISTICS:

BASED ON LEAKAGE EXPERIENCE PASED ON FLAW SHAPES DEFINED BY ULTRASONIC TESTING (THE ACCURACY OF WHICH WILL BE VERIFIED BY LABORATORY TESTING.

OF THE TUBE PULL SAMPLE).

BASED ON THE ANTICIPATED RESULT FROM STRUCTURAL

- ANALYSIS OF WOPST CASE DEFECT, USING MAINE YANKEE ~

SPECIFIC FLAW SHAPES FROM THE 1990 S/G INSPECTION.

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MAINE YANKEE FLAWS PROBABLY HAVE EXISTED FOR SEVERAL -

CYCLES. THEY HAVE LEAKED FOR A MINIMUM OF 1 CYCLE.

DEFECT GROWTH IN MAINE YANKEE STEAM GENERATORS WAS NOT RAPID. THIS IS BASED ON OBSERVED LEAKAGE RATES (1 GPD IN 1988 TO 3 GPD IN 1990) AT EOC 10 AND EOC 11 AND AS FOUND FLAW SHAPES.

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- REG. GUIDE 1.121 ANALYSIS i

I CATALOGUE ALL PLUGGABLE FLAW SIZES AND SHAPES (AS FOUND)

BASED ON EDDY CURRENT TEST AND ULTRASONIC TEST RESULTS.

PERFORM A REG. GUIDE 1.121 ANALYSIS OF THE WORST CASE, AS FOUND DEFECT (S) TO ASSURE COMPLIANCE TO.THE REG. GUIDE 1.121 CRITERIA.

i PERFORM AN ANALYSIS TO DETERMINE THE THRESHOLD FLAW SIZE FOR FAILURE OF REG. GUIDE 1.121 CRITERIA.

j COMBUSTION ENGINEERING TO CONDUCT ANALYSIS,

.1 MAINE YANKEE - 1990 S/G PROGRAM 5/2350

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' MAINE YANKEE CIRCUMFERENTIAL' FLAW CHARACTERISTICS MAINE YANKEE FLAWS CLEARLY EXHIBIT LEAK BEFORE BREAK CHARACTERISTICS:

BASED ON LEAKAGE EXPERIENCE BASED ON FLAW SHAPES DEFINED BY ULTRASONIC TESTING (THE ACCURACY OF WHICH WILL BE VERIFIED BY LABORATORY TESTING OF THE TUBE PULL SAMPLE).

BASED ON THE ANTICIPATED RESULT FROM STRUCTUPAL ANALYSIS OF WORST CASE DEFECT, USING MAINE YANKEE SPECIFIC FLAW SHAPES FROM THE 1990 S/G INSPECTION.

MAINE YANKEE FLAWS PROBABLY HAVE EXISTED FOR SEVERAL CYCLES. THEY HAVE LEAKED FOR A ' MINIMUM OF 1 CYCLE.

DEFECT GROWTH IN MAINE YANKEE STEAM GENERATORS WAS NOT RAPID. THIS IS BASED ON OBSERVED LEAKAGE RATES (1 GPD IN 1988 TO 3 GPD IN 1990) AT EOC 10 AND EOC 11-AND AS FOUND FLAW SHAPES.

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LEAKAGE MONITORING L

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LEAKAGE MONITORING MAINE YANKEE IS SENSITIVE TO THE OPERATIONAL AND l

MAINTENANCE CONCERNS OF OPERATING WITH STEAM GENERATOR LEAKAGE.

MAINE YANKEE EMPLOYS SEVERAL METHODS UTILIZING DIFFERENT OPERATING PRINCIPLES TO MONITOR PRIMARY TO SECONDARY LEAKAGE.

CONDENSER AIR EJECTOR RADIATION MONITORING SYSTEM STEAM GENERATOR BLOWDOWN RADIATION MONITORING SYSTEM l

MAIN STEAM LINE RADIATION MONITORS W

ROUTINE GRAB SAMPLES p

L REACTOR COOLANT SYSTEM CALCUl.ATED LEAK RATE (DAILY) i AIR EJECTOR, BLOWDOWN AND MAIN STEAM RADIATION MONITORS ARE-ON-LINE AND ALARM IN THE CONTROL ROOM.

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' ANALYSIS TECHNIQUES UTILIZING THE AIR EJECTOR RMS AND GRAB SAMPLES WERE EFFECTIVE IN IDENTIFYING STEAM GENERATOR.

LEAKS OF LESS THAN 5 GALLONS PER DAY (0.0035 GPM) PRIOR TO l

THE 1990 REFEULING SHUTDOWN.

AIR EJECTOR RADIATION MONITORING SYSTEM TRENDS ARE PLOTTED MONTHLY.

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g MAINE YANKEE TECHNICAL SPECIFICATION r

CURRENT SPECIFICATION 3.14:

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TOTAL LEAKAGE THROUGH ALL STEAM GENERATOR TUBES SHALL NOT EXCEED 1.0 GPM g

METHODS:

PRIMARY SYSTEM WATER BALANCE STEAM GENERATOR BLOWDOWN MONITOR AIR EJECTOR EFFLUENT MONITOR COMBUSTION ENGINEERING STANDARD TECH SPEC.

TOTAL LEAKAGE THROUGH ALL STEAM GENERATOR TUBES L

SHALL NOT EXCEED 1.0 GPM

. LEAKAGE FROM TUBES OF ANY ONE STEAM GENERATOR SHALL NOT EXCEED 0.34 GPM PROPOSED CHANGE TO SPECIFICATION 3.14:

I LEAKAGE FROM TUBES OF ANY ONE STEAM GENERATOR SHALL NOT EXCEED 0.15 GPM METHODS: SAME AS ABOVE

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p CYCLE 12 ADMINISTRATIVE CONTROLS lg IN THE EVENT OF CONFIRMED INCREASED ACTIVITY IN SECONDARY -

SYSTEMS, THE FOLLOWING ACTIONS WILL BE TAKEN:

AT 15 GPD:

INCREASED MONITORING AND TRENDING

-GRAB SAMPLES ONCE PER DAY DAILY AIR EJECTOR RMS TRENDS INITIATE LEAK INVESTIGATION CONDUCT SPECIAL PORC MEETING AT 50 GPD:

CONTROLLED PLANT SHUTDOWN (WITHIN 6 HOURS) TO IDENTIFY AND REPAIR LEAK SOURCE AT 100 GPD:

RAPID PLANT SHUTDOWN (WITHIN 2 HOUFi3) TO IDE'NTIFY AND REPAIR LEAK SOURCE i

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OPERATOR TRAINING PROGRAMS -

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Since 1988, significantly more emphasis has been placed on operator response to potential Steam Generator Tube Ruptures.

This emphasis was based on:

Industry operating experience involving SGTRs at other operating PWRs.

l Experience gained through training / evaluating operating crews in the use of upgraded EOPs.

The highest task importance rating' analyzed during licensed operator job analysis (only task rated at 5.0 on a 1.0 to 5.0 scale).

Subjective analysis by Operations Department and Operations Training that a SGTR is the most credible event specifically addressed by the EOP set.

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a7 increased emphasis has resulted in the following training-related activities concerning operator response to SGTRs.-

Classroom:

Addition of a specific SGTR lesson plan in License Operator training. This lesson plan includes:

Discussion of events and actions taken during SGTR experiences at other PWRs.

Strategies in place at Maine Yankee to minimize the potential for and to mitigate the consequences of a SGTR.

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Simulator Training:.

Added requirements to evaluate license operator response to a SGTR annually, including operator action during recovery from a SGTR.

Over 25% of simulator exam scenarios to support LORC require action in response to a SGTR.

Added more simulator sessions on response to SGTR events.

l From June 1989 to April 1990, each Operations crew performed simulated SGTR recovery actions an average of four times.

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Approximately 1/3 of crew simulator annual exams over the l

past two years have included crew response to a STGR.

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PROPOSED TRAINING In light of recent findings from Steam Generator inspections, the following training will be conducted:

The Shutdown Modification Summary document, which is reviewed by all operstors in detail during the first requal block, will include a synopsis of the results of the Steam Generator testing and corrective actions taken.

All administrative leakage limits and appropriate procedural guidance will be reviewed by all licensed operators prior to start-up and followed up with formal training in both the classroom and Simulator during the first requal block, L

scheduled to start September 10,1990.

Additional training for licensed operators in early detection of Steam Generator Tube leaks will be provided during first requal block.

H Information will be provided to all licensed operators on the i-analyzed tube failure mechanism (s) and corrective actions taken or proposed. This will be done during the first requal block' assuming the analysis is complete.

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CONCLUSION MAINE YANKEE HAS CHOSEN A CONSERVATIVE APPROACH TO STEAM GENERATOR INSPECTION AND REPAIR ALL TRANSITION AREA DEFECTS WERE IDENTIFIED DURING OUR 1990 REFUELING SHUTDOWN DEFECTS HAVE BEEN PLUGGED AND STAKED TO MAINTAIN STEAM l

GENERATOR PRESSURE BOUNDARY INTEGRITY DEFECTS HAVE MOST LIKELY EXISTED FOR SOME TIME L

L ALL REGULATORY REQUIREMENTS ARE MET TUBE DEFECTS EXHIBITED A LEAK BEFORE BREAK BEHAVIOR CYCLE 12 OPERATION IS JUSTIFIED 1

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SUMMARY

I CONDUCTED 100% INSPECTION OF THE TRANSITION AREA OF ALL 3 STEAM GENERATORS, AS WELL AS THE REQUIRED TECH SPEC INSPECTION 31 TRANSITION AREA CIRCUMFERENTIAL CRACKS WERE IDENTIFIED OUT OP APPROXIMATELY 34,000 TUBE ENDS INSPECTED i

ALL DEFECTS WERE REPAIRED USlHG BEST AVAILABLE MEANS CURRENT EQUIPMENT AND ANALYSIS TECHNIQUES RELIABLY IDENTIFIED TUBE LEAKAGE OF LESS THAN 5 GALLONS PER DAY l.

TUBE EXAMINATIONS AND ANALYSES WILL CONTINUE i

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