ML15222A026

Summary of 891116 Interface Meeting W/Util Re Planned Improvements to Radiation Monitoring & Control Programs, Steam Generator Tube Program & Recent Problems W/Catawba Auxiliary Feedwater Pump Control Valves.Viewgraphs Encl

ML15222A026
Person / Time
Site:	Oconee, Mcguire, Catawba, McGuire, 05000000
Issue date:	12/07/1989
From:	Wiens L Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8912210078
Download: ML15222A026 (74)

Text

December 7, 1989 Dockets Nos. 50-269, 50-270, 50-297 50-369, 50-370, 50-413 and 50-414 FACILITY: Oconee Nuclear Station, Units 1, 2 and 3; McGuire Nuclear Station, Units 1 and 2; Catawba Nuclear Station, Units 1 and 2 LICENSEE: Duke Power Company

SUMMARY

OF NOVEMBER 16, 1989, INTERFACE MEETING WITH DUKE POWER COMPANY On November 16, 1989, the NRC staff met at the Catawba Nuclear Station with representatives of the Duke Power Company (Duke) to discuss licensing and regulatory issues. This meeting was part of a continuing series of meetings held on a bimonthly basis. Representatives from the Duke corporate office, the three Duke nuclear stations, NRC Region II, NRC Resident Inspection staff and NRR participated in the meeting.

Duke made presentations on planned improvements to radiation monitoring and control programs, steam generator tube program, recent problems with Catawba's auxiliary feedwater pump control valves and the system expert program at Catawba.

The NRC discussed current generic issues and technical issues applicable to the Duke stations. In addition, the NRC proposed to make a presentation at the next interface meeting, scheduled for January 16, 1990, at Oconee, on the licensing

.process dealing with nonconformance issues. After the presentations, the participants broke into three groups to discuss plant-specific issues relating to Oconee, McGuire and Catawba.

Meeting participants are listed in Enclosure 1. Handouts used by Duke during the presentation are provided in Enclosure 2.

Original signed by:

Leonard A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects -

I/Il Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/encls:

See next page Distribution:

Docket File S. Kirslis P. Skinner, RII NRC & Local PDRs R. Ingram M. Shymlock, RH o

J. Sniezek 12/G/18 W. Scott 1O/A/19 OGC (info. only) 15/B/18 PDII-3 R/F T. Cooper, RI E. Jordan MNBB 3302 S. Varga 14/E/4 P. Van Doorn, RII ACRS (10)

P 135 o

D. Matthews 14/H/25 W. Orders, RII R. Borchardt 17/G/21 L. Wiens 14/H/25 Document Name:

DUKE MTG SUMMA 16 LA:PDH13 PM:PDII3A D

RIngram

'LWiens:A DM thews

Duke Power Company cc:

A.V. Carr, Esq.

North Carolina Electric Membership Duke Power Company Corp.

422 South Church Street 3400 Sumner Boulevard Charlotte, North Carolina 28242 P.O. Box 27306 J. Mchal M~arr, II, sq.Raleigh, North Carolina 27611 J. Michael McGarry, III, Esq.

Bishop, Cook, Purcell and Reynolds Saluda River Electric Cooperative, 1400 L Street, N.W.

Inc.

Washington, D. C. 20005 P.O. Box 929 Laurens, South Carolina 29360 North Carolina MPA-1 Senior Resident Inspector Suite 600 Route 2, Box 179N 3100 Snoketree Ct.

York, South Carolina 29745 P.O. Box 29513 Raleigh, North Carolina 27626-0513 Regional Administrator, Region II U.S. Nuclear Regulatory Commission Ms. S. S. Kilborn 101 Marietta Street, NW, Suite 2900 Area Manager, Mid-South Area Atlanta, Georgia 30323 ESSD Projects Westinghouse Electric Corp.

Mr. Heyward G. Shealy, Chief MNC West Tower - Bay 239 Bureau of Radiological Health P.O. Box 355 South Carolina Department of Health Pittsburgh, Pennsylvania 15230 and Environmental Control 2600 Bull Street County Manager of York County Colunbia, South Carolina 29201 York County Courthouse York, South Carolina 29745 Ms. Karen E. Long Assistant Attorney General Richard P. Wilson, Esq.

N.C. Department of Justice Assistant Attorney General P.O. Box 629 S.C. Attorney General's Office Raleigh, North Carolina 27602 P.C. Box 11549 Columbia, South Carolina 29211 Mr. Robert G. Morgan Nuclear Production Department Piedmont Municipal Power Agency Duke Power Company 100 Memorial Drive P.O. Box 33189 Greer, South Carolina 29651 Charlotte, North Carolina 28241 Mr. Alan R. Herdt, Chief Mr. H. B. Tucker, Vice President Project Branch #3 Nuclear Production Department U.S. Nuclear Regulatory Commission Duke Power Coinan 101 Marietta Street, NW, Suite 2900 422 South Church Street Atlanta, Georgia 30323 Charlotte, North Carolina 28242

-2 cc:

Dr. John M. Barry Manager, LIS Department of Environmental Health NUS Corporation Mecklenburg County 2536 Countryside Boulevard 1200 Blythe Boulevard Charlotte, North Carolina 28203 Office of Intergovernmental Relations County Manager of Mecklenburg County 116 West Jones Street 720 East Fourth Street Raleigh, North Carolina 27603 Charlotte, North Carolina 28202 Honorable James M. Phinney Mr. J. S. Warren County Supervisor of Oconee County Duke Power Company Nuclear Production Department P. 0. Box 33189 Mr. Paul Guill Charlotte, North Carolina 28242 Duke Power Company P.O. Box 33189 Senior Resident Inspector 422 South Church Street c/o U.S. Nuclear Regulatory Commission Charlotte, North Carolina 28242 Route 4, Box 529 Hunterville, North Carolina 28078 Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Mr. Dayne H. Brown, Chief Radiation Protection Branch Division of Facility Services Department of Human Resources 701 Barbour Drive Raleigh, North Carolina 27603-2008 Mr.

Robert B. Borsum Babcock & Wilcox Nuclear Power Division Suite 525 1700 Rockville Pike Rockville, Maryland 20852 ATTENDANCE LIST Duke/NRC Interface Meeting November 16, 1989 NAME ORGANIZATION Dave Matthews NRR/Director, PDII-3 Len Wiens NRR/Project Manager, Oconee Stan Kirslis NRR/Project Engineer Wayne Scott NRR/PQEB Todd Cooper NRC/RI, McGuire P.

Kim Van Dcorn NRC/SRI, McGuire W. T. Orders NRC/SRI, Catawba Tom Curtis Duke/Oconee P. H. Skinner NRC/SRI, Oconee M. B. Shymlock NRC/Atlanta DRP-3A Robert G. Morgan Duke/G.O.

J. S. Warren Duke/G.O./Reg. Comp.

Robert 0. Sharpe Duke/McGuire Robert Gill Duke/NPD/G.O./Reg. Comp.

Bob Futrell Duke/NPD/G.O./Nuc. Safety J. E..Snyder Duke/MNS/Perf. Manager C. L. Hartzell Duke/CWS/Comp. Group M. S. Sills Duke/Design Engineer, Oconee D. L. Rehn Duke/Design Engineer, Catawba A. S. Daughtridge Duke/Design Engineer, McGuire NR/RScur Revised Agenda DUKE/NRC INTERFACE MEETING November 16, 1989 Catawba Nuclear Station Training Center AGENDA 9:00 AM Coffee 9:30 AM Opening Remarks 9:40 AM Radiation Monitoring and Control Mike Terrell 10:00 AM NRC Presentation 11:00 AM Duke Steam Generator Programs Bill Haller 12:00 PM Lunch 12:30 PM Catawba Nuclear Station Tony Owen (Including Discussion of System Experts) 1:30 PM Breakout Sessions 3:30 PM Adjourn

• II

• I RA DIA ION MONI TORING

& CONTROL S'

DUKE POWER

II I

Radiation Protection Functional Area Evaluation

1. Reduce Personnel Exposure

2. Minimize 0 & M Cost

3. Meet Changing Requlations

4. Make Radiological Data A Corporate Resource S DUKE POWER

• II

• I Reduce Personnel Exposure

1. Obtain Accurate Exposure Information

2. Minimize Record Keeping Errors

3. Better Work Planning

4. Better Utilization of Related Data DUKE POWER

• II I.7 Minimize 0 & M Cost

1. Automate Work Activities

2. Integrate Computer Programs

3. Maximize Worker Productivity

4. Standardize Procedures & Practices DUKE POWER

• II

• I Meet Regulatory Changes

1. Proposed 10CFR20 Changes

2. Clean Air Act

3. N.C. Disposal Site Requirements

4. Adoption of IAEA Regs. by DOT DUKE POWER

II I

Corporate Data Resource

1. Distributed, Relational Database Strategy

2. Integration With Other DPC Databases

3. Eliminate Data Redundancy

4. Seamless Platform Technology DUKE POWER

II I

Implementation Strategy

1. Eight Major Projects Identifed

2. Phased Implementation

3. Project Technical Teams

4. Separate Project Funding S DUKE POWER

• II*

I Executive Sponsor H. B. Tucker Steering Committee I/A Director Project Sponsor Rad. Protection FAM NPD Computer Gp.

M. E. Peterson W. A. Haller M. L. Birch J. T. Middleton Project Manager M. S. Terrell I/S Resource Mgr.

R. E. St.Clair Tech. Team Leader P/S Project Leader EDC Project der R. C. Baker Cotatr Prtable Ins. issue Contoom A

r 1/S Team Member ALARA Access Cntl.

r A M. Morgan r

Environ.

si L. F. Shan L~lr Ir Rad. Matt. Inven.

er r

TLD System?

DUKE POWER

• II*

I..

Portable Equipment lectronic Issue TLD System Dose Replacement Capture ountroomRadiation Monitoring Misc.

Countrooml ata as Investigation DAS ConrolDataaseReports ALARA' Radioactive Planning Materials Effluent Control Environment Analysis DUKE POWER

II

• I.7 Project Descriptions Electronic Dose Capture This project involves the elimination of routine dose cards by providing a computer interface for radiation workers entering/exiting radiation control areas. The system will be capable of receiving manual inputs from the workers and/or automatic input of information. The system will initially interface with the REC/JEC programs and eventually replace them.

Portable Equipment Issue & Control This project will allow RP Technicians to document the performance of portable instrument calibrations, document the assignment, maintenance, cleaning, and performance testing of portable instruments such as, respirators, and survey instruments. The project will enable the collection and correlation of portable instrument data.

Countroom Data Acquisition Systems This project covers the upgrade of existing countroom equipment to allow the automation of date transfer and reporting. Initially this project will focus on the GENIE Systems, and then be expanded to include other countroom equipment.

DUKE POWER

II

• I Project Descriptions ALARA Access Control and Planning This project includes implementing the PRS System at all three stations as manual input systems and then upgrading the systems to allow the automation of data inputs from the Countrooms, and portable instruments. Additionally, this project covers the development and implementation of an automated RWP Generation System which will utilize past and existing plant conditions to plan and track jobs.

Environmental Analysis and Reporting This project will allow us to replace existing in-house programs such as the Radwaste Effluents Program, and develop other programs to report the release of radioactive materials while integrated with sample and survey results.

Radioactive Materials & Inventory Control This project will allow us to integrate with the WASTRAK Program, maintain an inventory of radioactive materials that are stored on site, and provide a mechanism for evaluating the results of processing options.

DUKE POWER

• II*

I Project Descriptions Miscellaneous Investigations & Reports This project will enable us to allow the generation of incident investigations and other other reports for management, and regulatory bodies.

Dosimetry System Replacement This project involves the replacement of the TLD System with a system that automates the data reduction effort and integrates the ASC's activities with NPD's tfforts to implement an integrated relational database structure. This project with the EDC project will position as to replace the REC/JEC System.

S DUKE POWER

I IAUG-89a I m (DEC-8 JA-9

~~JU-9 3

h fl c

-90 NO09

• II

• I.*,

Project Benefits

1. Minimize Dose Recording Errors

2. Provide On-line Work Planning and Assessment

3. Improve Accessibility of Data

4. Minimize Hardcopy Records

5. Eliminate Manual Transfer of Data DUKE POWER

DUKE POWER COMPANY'S STEAM GENERATORS

DPC STEAM GENERATORS ONCE THROUGH STEAM GENERATORS o

CURRENT STATUS o

REMEDIAL ACTIONS o

THE FUTURE RECIRCULATING STEAM GENERATORS o

CURRENT STATUS o

REMEDIAL ACTIONS o

THE FUTURE

\\WAH\\TRNSPNCY.003

PRIMARY INLET NOZZLE AUXILIARY FEEDWATER INL.ET Tm STE&14 AMILLUS STEAM OUTLET NOZZLE low______

FEDWATER SPRAY NOZZLES73 MAIN FEEOWATER HEADER 1a STEAM RECIRCUArION PORT p

FEEMWATER HEATING CHAMBER ADJUSTABLE ORIFICE LOWER TUBESHEET PRIMARY OUTLET NOZZLE (2)

Tiqure 1-1.

-B&W 1 7 7-rA OhCS..ThZouqh Steam Generator

OTSG CONCERNS o

PRESSURE DROP o

LOWER TUBE SHEET INDICATIONS o

10TH TSP DINGS o

HIGH CYCLE FATIGUE (LANE & WEDGE) o EROSION/CORROSION o

RESTABILIZATION MLA.002

OTSG STEAM GENERATOR TUBE PLUGGING BY CAUSE, BY STEAM GENERATOR lA 1B 2A 2B 3A 3B HIGH CYCLE FATIGUE 26 17 8

11 26 20 (LANE AND WEDGE)

EROSION/CORROSION 51 336 17 32 61 56 OTHER 53 134 10 24 118 28 TOTALS 130 487 35 67 205 104 PERCENT 0.84 3.14 0.23 0.43 1.32 0.67 MLA.02A

NUMBER OF LEAKER OUTAGES PER YEAR (3 UNITS) o LATE 70'S 3/STATION/YEAR o

80 TO 85 2/STATION/YEAR o

85 TO 90 1/STATION/YEAR o

90'S

< 1/STATION/YEAR

\\WAH\\TRNSPNCY.006

OTSG CHEMISTRY o

ALL VOLATILE CHEMISTRY NH 3, HYDRAZINE PRESENT MORPHOLINE, HYDRAZINE IMMEDIATE FUTURE o

pH 9.3 - 9.6 o

ESSENTIALLY Cu FREE o

CONDENSATE POLISHERS (POWDER RESIN) 0 CLEAN UP RECIRC PATH o

COORDINATED B-Li PROGRAM pH 3 0 0 = 7.15, 2.2 PPM Li MAX.

\\WAH\\TRNSPNCY.008

PRESSURE DROP o

CHEMICAL CLEANING SUCCESSFUL IN RETURNING UNIT 1 &

UNIT 2 TO NEAR ORIGINAL OPERATING LEVEL.

o MORPHOLINE CHEMISTRY WILL REDUCE IRON TRANSPORT BY 69%.

o REFOULING RATE LOWER THAN INITIAL FOULING RATE.

o POTENTIAL FOR ANOTHER CHEMICAL CLEANING AFTER TURN OF CENTURY.

o CAREFUL CONTROL OF CHEMISTRY PARAMETERS SHOULD ENSURE PRESSURE DROP PROBLEM DOES NOT REOCCUR.

MLA.003

OCONEE UNIT 1 OTSG OPERATE LEVELS OTSGs A & B 110 CYCLE 10 CYCLE 11 CYCLE 12 100-r 90 U

80 70 L

OTSGu CHEMICALLY CLEANED 60 50 5/86 11/87 y/g9 DATE POWWR OTSG A OTSG B

OCONEE UNIT 2 OTSG OPERATE LEVELS OTSGe A & B 105 CYCLE 10 100 CYC 9

t 95 90 0

OTSG CHEMICALLY CLEANED 75 70 65 60 10/864/

5/89 DATE POWER OTSG A OTSG B

OCONEE MORPHOLINE TEST RESULTS o

REDUCED THE FEEDWATER IRON CONCENTRATION BY 69.1%.

o REDUCED THE MOISTURE SEPARATOR DRAIN IRON CONCENTRATION BY 68.8%.

o REDUCED SLUDGE INPUT TO THE STEAM GENERATORS BY 250 LBS.

PER EFPY.

o INCREASED MOISTURE SEPARATOR DRAIN pH FROM 8.8 TO 9.3.

o NO ADVERSE EFFECT ON CONDENSATE POLISHER OPERATION.

o INCREASED FEEDWATER CATION CONDUCTIVITY FROM 0.09 TO 0.16 EMHOS DUE TO ORGANIC ACIDS FROM DECOMPOSITION OF MORPHOLINE.

IMLA.03E

EXPECTED BENEFITS OF USING MORPHOLINE AT OCONEE o

LOWER EROSION/CORROSION RATES IN STEAM EXTRACTION PIPING.

o GENERALLY LOWER SECONDARY SYSTEM CORROSION.

o LESS SLUDGE INPUT TO THE STEAM GENERATORS.

o REDUCED RATE OF INCREASE IN PRESSURE DROP ACROSS THE STEAM GENERATORS.

o REDUCED PROBABILITY OF HAVING TO CHEMICALLY CLEAN THE STEAM GENERATORS.

MLA.03G

LOWER TUBE SHEET INDICATIONS o

LARGE NUMBER OF INDICATIONS o

VERY LITTLE IF ANY GROWTH THROUGH MANY CYCLES o

FURTHER CHARACTERIZATION IN THE FUTURE DESIRABLE o

DEVELOP CAPABILITY TO SLEEVE LOWER TUBE SHEET

\\WAH\\TRNSPNCY.004

TENTH TUBE SUPPORT PLATE DINGS o

AREA AFFECTED HAS INCREASED SLOWLY o

AREA HAS NOT PROGRESSED RAPIDLY LIKE CLASSICAL DENTING o

AREA WARRANTS CONTINUED ATTENTION MLA.005

HIGH CYCLE FATIGUE (LANE AND WEDGE) o HAS CAUSED z80% OF TUBE LEAK OUTAGES o

CORRECTIVE ACTION UNIT I SLEEVING 1987 UNIT II SLEEVING 1990 UNIT III SLEEVING 1988 o

WHEN SLEEVING COMPLETED SHOULD REDUCE HIGH CYCLE FATIGUE LEAKER OUTAGES TO :0

\\WAH\\TRNSPNCY.005

Tubes REMOVEDFROMSEVE O W E N 3w u GB T R A TOTAL T M i m l W MA E

08/80AOM Ra 7.........

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TOTAL TUBM1~

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ILUE MeB TOTAL 11M AMM3 0 V.*T**

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....................................... ~...................................

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EROSION / CORROSION o

CURRENTLY CAUSES MOST TUBE PLUGGING IN OTSG'S o

AREA OF STEAM GENERATOR AFFECTED HAS INCREASED o

COULD CAUSE LOCALIZED COLD SPOTS o

OTSG-1B AT RISK FROM TOTAL # TUBES PLUGGED o

CORRECTIVE ACTION SLEEVE TO PREVENT COLD SPOTS SLEEVE TO PREVENT EXCEEDING 10% PLUGGING MARGIN CONTINUE AGGRESSIVE ECT PROGRAM TO ELIMINATE TUBE LEAK OUTAGES.

MLA.008

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RESTABILIZATION o

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NEWER STABILIZATION CRITERIA IDENTIFIED PROBLEM AREAS o

SEVERED TUBE COULD RESULT IN TUBE RUPTURE o

CORRECTIVE ACTION PLUG REMOVAL AND RESTABILIZATION RESTABILIZATION PROGRAM IS A PHASED EFFORT TO BE COMPLETED BY 1992.

MLA. 009

ONS UNIT #1: STM GEN "A" PLUGGING RATES PER STM GEN PER YEAR 2.4 2.2 2.0 o

1.8 I

.61=

UMIT hi 1.4 a

1.2 0@

1.0 0.8 0.6 0.4 0.2 0.0 1

I I

1.970 1.990 2.010 2.030 (Thousands)

TIME. YEARS ACTUAL VALUES 6-12 24

ONS UNIT #1: STM GEN "B" PLUOGING RATES PER STM WEN PER YEAR 3.0 2.8 2.6 a

iii 2.4 a

e 2.2 2.0 0 bi M 1.8 0.6 1.4 1.2 5

1.0 2

0.8 2

o 0.6 0.4 0.2 0.0 1.970 1.990 2.010 2.030 (Thuundu)

TIME, YEARS ACTUAL VALUES 16 33 66

NPD GOAL FOR ONS OTSG'S TO MAXIMIZE UNIT AVAILABILITY BY ACHIEVING

RELIABLE, COST-EFFECTIVE OPERATION OF CURRENTLY INSTALLED OTSG'S FOR LIFE OF PLANT INCLUDING MODERATE LIFE EXTENSION.

o PREVENT NEW DEGRADATION MECHANISMS o

MINIMIZE IMPACT OF EXISTING MECHANISMS o

PREVENT TUBE RUPTURES o

ELIMINATE TUBE LEAK OUTAGES o

KEEP PLUGGING BELOW 10% LIMIT o

MINIMIZE CORROSION PRODUCT TRANSPORT o

EFFECTIVELY MANAGE PRESSURE DROP PROBLEM o

MAXIMIZE EFFICIENCY AND COST EFFECTIVENESS OF OTSG RELATED ACTIVITIES.

o SUPPORT DEVELOPMENT OF TECHNOLOGIES WHICH WILL RESOLVE EMERGING PROBLEMS MLA.011

ACTIONS INCLUDED IN PLANS TO MEET NPD GOAL o

MAINTAIN EXCELLENT SECONDARY SIDE CHEMISTRY o

PROACTIVE AND COMPREHENSIVE INSPECTION PROGRAM o

APPLICATION OF NECESSARY REMEDIAL MEASURES o

DEVELOP LONG RANGE ECONOMIC STRATEGIC PLAN o

DEVELOP TECHNOLOGIES WHICH WILL RESOLVE EMERGING PROBLEMS

\\WAH\\TRNSPNCY.002

PROGNOSIS FOR OTSG'S o

OTSG'S HAVE POTENTIAL TO LAST LIFE OF PLANT INCLUDING MODERATE LIFE EXTENSION.

MLA.010

MODEL D3 STEAM GENERATOR 48=00 FT.2 STEAM OUTLET TO TUMSINE SECONDARY MOISTURE SEPARATOR MANWAY PRIMARY MOISTURE SEPARATOR (12/20" DIA.)

AUXILIARY FEEDWATER NOZZLE ANTI-VIBRATION BARS TUBE BUNDLE TUBE SUPPORT PLATES (4674.750/.664 TUBES)

(DRILLED CS)

PREHEATER (9053 FT.2 )

FEEDWATER INLET FLOW DISTRIBUTION BAFFLE (8" ABOVE TUBE SHEET)

TUBE SHEET COOLANT IN LET MANWAY

U-TUBE TYPE STEAM GENERATORS (WESTINGHOUSE D SERIES)

MCGUIRE I D-2 MCGUIRE II D-3 CATAWBA I D-3 CATAWBA II D-5

\\WAH\\TRNSPNCY.007

DIFFERENCES D2-D3 VS. D5 o

CARBON STEEL SUPPORT PLATES VS. FERRETIC STAINLESS o

DRILLED HOLES VS. QUATRAFOIL BROACH o

MILL ANNEALED VS. THERMALLY TREATED INCONEL 600 0

.~

\\wAH\\TRNSPNCY. 010

RECIRC CHEMISTRY o

ALL VOLATILE CHEMISTRY o

NH 3 ' HYDRAZINE PRESENT o

MORPHOLINE, HYDRAZINE IMMEDIATE FUTURE o

pH 8.8 -

9.4 o

McGUIRE: ESSENTIALLY Cu FREE o

CATAWBA: Cu IN REHEATER TUBES (90-10) o CONDENSATE POLISHERS (POWDER RESIN) o DEEP BED BLOWDOWN DEMINERALIZERS o

CLEAN UP RECIRC PATH o

COORDINATED B-Li PROGRAM:

pH 3 0 0 = 6.9

\\WAH\\TRNSPNCY.009 0II

RSG CONCERNS SECONDARY PROBLEMS o

PITTING o

WASTAGE o

DENTING o

OD SCC/IGA o

TUBE WEAR PRIMARY WATER STRESS CORROSION CRACKING o

STRESS CORROSION CRACKING (I. D.)

o TIGHT U-BEND CRACKING (I. D.)

TUBE RUPTURE MLA.014

STEAM GENERATOR REPLACEMENTS Unit Year Reason Surry 2 1980 Denting Surry 1 1981 Denting Turkey Point 3 1982 Denting Turkey Point 4 1983 Denting Point Beach 1 1984 IGA/SCC Robinson 2 1984 Wastage D. C. Cook 1 1989 IGA Indian Point 2 Planned Denting Indian Point 3 Planned Pitting Ringhals Planned Pitting Millstone 2 Planned Pitting Dampierre Planned IGA Palisades Planned General Chemistry Attack

\\wah\\trnspncy.013

1A.

0 II I'

I II ' I

RSG STEAM GENERATOR TUBE PLUGGING BY CAUSE, BY UNIT MNS-1 MNS-2 CNS-1 CNS-2 PWSCC (HLTS) 328 279 53 0

PWSCC (CLTS) 13 19 0

0 PWSCC (U-BEND) 385 456 3

0 OD MECHANISMS, 0

0 0

0 (CHEMISTRY)

OD - SCC 1

0 0

0 WEAR (PREHEATER) 20 0

0 0

OTHER 100 1

20 29 TOTALS 847 755 76 29 PERCENT 4.53 4.04 0.41 0.16

PITTING/WASTAGE/DENTING o

RELATED PRIMARILY TO SECONDARY CHEMISTRY.

o HAS RESULTED IN 9 RSG REPLACEMENTS, PLANNED OR ACTUAL.

o CURRENTLY NOT A PERVASIVE PROBLEM IN DUKE'S RSG'S.

o POTENTIALLY LIFE THREATENING TO ALL DUKE RSG'S.

o MITIGATION MAINTAIN EXCELLENT SECONDARY CHEMISTRY.

CONTINUE SLUDGE LANCING PROGRAM.

DEVELOP CAPABILITY TO CHEMICALLY CLEAN RSG'S.

o MAY NOT BE ABLE TO PREVENT FOR LIFE OF PLANT.

MLA.015

WASTAGE Steam Outlet Steam Separators H

Downcomer Feedwater (Ingress of Impurities) r Local Concentration of Impurities To Blowdown (Removal of Impurities)

ISGOG Primary Inlet Primary Outlet

CONSEQUIENCES OF DENTING Stam Outlet StaaM0000000 Separators of Imparne.w Tuba Suppor Plate iTop Viw Hwa"of TIW~eube o Fl $ m43 n

Local Suppot: MMConcestruea Impumpitiese Primary Inlet Primary Oulet SGOGI

OD SCC/IGA o

RELATED TO MATERIAL CONDITION, OPERATING TEMPERATURE AND SECONDARY CHEMISTRY.

o HAS RESULTED IN 2 RSG REPLACEMENTS.

o MNS-1, MNS-2, CNS-1 TUBING MATERIAL VERY SUSCEPTIBLE.

o CURRENTLY NOT A PERVASIVE PROBLEM IN DUKE'S RSG'S.

o POTENTIALLY LIFE THREATENING TO ALL DUKE RSG'S.

0 MITIGATION MAINTAIN EXCELLENT SECONDARY CHEMISTRY.

T-HOT REDUCTION.

DEVELOP CAPABILITY TO CHEMICALLY CLEAN RSG'S.

o MAY NOT BE ABLE TO PREVENT FOR LIFE OF PLANT.

MLA.016

INTERGRANULAR ATTACK/STRESS CORROSION CRACKING (OUTSIDE DIAMETER)

Steam Outlet Steam Separators Downcomer Feedwater (Ingress 8

4 of Impurities)

Local Concentration of Impurities

-C To Blowdown (Removal of Impurities)

ISGOG Primary Inlet Primary Outlet

TUBE WEAR o

OCCURS BOTH IN PREHEATERS AND AT ANTI-VIBRATION BARS (AVB ' )

o PREHEATER MODS SLOWED GROWTH RATE IN PREHEATERS BUT DID NOT ELIMINATE PROBLEM o

PROBLEMS WITH AVB'S POINTED OUT BY NRC BULLETIN 88-02 o

TUBE PLUGGING DUE TO WEAR HAS INCREASED o

COULD PRESENT PROBLEMS IN LONG TERM 0

MITIGATION DEVELOP CAPABILITY TO SLEEVE PREHEATER PERFORM AVB MODIFICATIONS MLA.019

PWSCC o

ASSOCIATED WITH MILL ANNEALED INCONEL 600 o

HIGH That CONDITION HASTENS THE ONSET OF CRACKING o

CURRENTLY PRIMARY CAUSE OF TUBE PLUGGING AT MNS-1, MNS-2, CNS-1 o

AFFECTS HOT LEG AND COLD LEG TUBE SHEETS AND U-BENDS o

EFFECTIVENESS OF HOT LEG PEENING SOMEWHAT DIMENISHED BECAUSE OF WHEN THEY WERE PERFORMED o

PWSCC COULD CAUSE REPLACEMENT OF MNS-1, MNS-2, CNS-1 o

PWSCC + SIGNIFICANT SECONDARY SIDE ATTACK WILL CAUSE REPLACEMENT OF THESE GENERATORS

\\WAH\\TRNSPNCY.011

CORRECTIVE ACTIONS FOR PWSCC MNS-1 o

HOT LEG SHOT PEENING 1986 o

U-BEND STRESS RELIEF 1988 o

COLD LEG SHOT PEENING 1990 MNS-2 0

HOT LEG SHOT PEENING 1987 o

U-BEND STRESS RELIEF 1988 o

COLD LEG SHOT PEENING 1989 CNS-1 o

HOT LEG SHOT PEENING 1987 o

U-BEND STRESS RELIEF 1988 o

COLD LEG SHOT PEENING 1992 o

HYDROGEN REDUCTION FOR ALL STEAM GENERATORS MLA.021

TUBE RUPTURE o

MNS-1 RUPTURE APPEARED TO BE ISOLATED OCCURRENCE o

SENSITIVITY OF MNS-1, MNS-2, CNS-1 TUBING MATERIAL o

NEED FOR GOOD ECT BASELINE DATA o

NEED FOR COMPREHENSIVE INSPECTION PROGRAM o

MITIGATION ADHERENCE TO EPRI SG EXAMINATION GUIDELINES COMPREHENSIVE FOSAR PROGRAM PROACTIVE RESPONSE TO INDUSTRY EXPERIENCE (NRC BULLETIN 88-02, TUBE PLUG ISSUES)

MLA.018

EPRI STEAM GENERATOR NDE GUIDELINES PURPOSE o

PROVIDE SPECIFIC GUIDELINES AND RECOMMENDATIONS BASED ON RESEARCH AND PLANT EXPERIENCES.

o ACHIEVE MAXIMUM BENEFIT FROM PERIODIC STEAM GENERATOR EXAMINATION.

CONCERNS o

ASSURE STEAM GENERATOR EXAMINATION IDENTIFIES TUBES TO BE REMOVED FROM SERVICE.

o PREVENT FORCED OUTAGES DUE TO TUBE LEAKAGE.

o ASSURE THAT A TUBE RUPTURE IS NOT LIKELY TO OCCUR.

\\WAH\\TRNSPNCY.014

MNS UNIT #1: STM GEN TUBE PLUGGING PLUGGING RATES PER STM GEN PER YEAR 3.0 2.8 2.4 O

2.2 L

2.0-1an UMIT se; 1.8 1.6

a.

1.4 1.2 1.0 -

an LIMIT 2

0.8 4

0.6 0.4

0.2 0.0 1.980 1.990 2.000 2.010 2.020 TI-At. YEARS Actual Values"'

1 30

CNS UNIT #1: STEAM GEN TUBE PLUGGING PLUGGING RATES PO STM GEN PER YEAR 5.0 2.5 145 UMIT 2.6 a

2.4 2.2 2.0 -

I LadT 1.6 41.6 1.4 1.2 1.0 -

55 UMIT S

0.8 0.6 0.4 0.2 0.0 '-

IIIII (Thousnlbf 2

ACTUAL VALUES T

A-15 30

NPD GOAL FOR MNS AND CNS RSG'S TO MAXIMIZE UNIT AVAILABILITY BY ACHIEVING

RELIABLE, COST-EFFECTIVE OPERATION FOR THE OPTIMUM LIFETIME OF THE CURRENTLY INSTALLED RSG' S AND TO ENSURE THAT ONLY ONE RSG REPLACEMENT WILL BE REQUIRED FOR LIFE OF PLANT INCLUDING MODERATE LIFE EXTENSION.

o PREVENT NEW DEGRADATION MECHANISMS o

MINIMIZE IMPACT OF EXISTING MECHANISMS o

PREVENT TUBE RUPTURES o

ELIMINATE TUBE LEAK OUTAGES o

PERFORM SLEEVING AND PLUGGING AS REQUIRED TO SUPPORT OPTIMUM RSG LIFE o

MINIMIZE CORROSION PRODUCT TRANSPORT o

MAXIMIZE EFFICIENCY AND COST-EFFECTIVENESS OF RSG RELATED ACTIVITIES o

SUPPORT DEVELOPMENT OF TECHNOLOGIES WHICH WILL RESOLVE EMERGING PROBLEMS o

OPTIMIZE RSG MAINTENANCE AND REPLACEMENT IF NECESSARY TO BEST SUPPORT COMPANY'S OVERALL GOALS

\\wah\\trnspncy.001

ACTIONS INCLUDED IN PLANS TO MEET NPD GOAL o

MAINTAIN EXCELLENT SECONDARY SIDE CHEMISTRY o

PROACTIVE AND COMPREHENSIVE INSPECTION PROGRAM o

APPLICATION OF NECESSARY REMEDIAL MEASURES o

DEVELOP LONG RANGE ECONOMIC STRATEGIC PLAN o

DEVELOP TECHNOLOGIES WHICH WILL RESOLVE EMERGING PROBLEMS o

DEVELOP CHEMICAL CLEANING FOR RSG'S

\\WAH\\TRNSPNCY.002

PROGNOSIS FOR RSG'S o

CNS RSG'S HAVE POTENTIAL TO LAST LIFE OF PLANT INCLUDING MODERATE LIFE EXTENSION, ALTHOUGH CNS-1 IS AT HIGH RISK OF REQUIRING REPLACEMENT RSG'S.

o APPEARS VERY UNLIKELY THAT MNS RSG' S WILL LAST LIFE OF PLANT.

MLA. 022

PERFORMANCE

November, PERFORMANCE MANAGER W. F. Beaver PERF SECTION CLERK INSTRUCTOR E. J. Meares R. H. Miller (1)

L.H. Earley IETTS ECO TEST j

TEST ENG ER ENG ER ENINE SUPERVISOR SUPERVISOR Z. L. Taylor J. A. Kammer G.P. Horne J. L. Lowery C. M. Sahms S.B. Brown (2)

ENGINEER ENGINEER ENGINEER SPECIALIST SPECIALIST M. Carwile M. D. Ceraldi R. G. Blesing G. K. Cook M. A. Belizone M. A. Geckle T. L. Forrest J. R. Fox S. D. Galloway R. N. Choate R. L. Herring W. B. Hallman G. A. Harbin DJ.LcyG.

F. Dixon M. S. Kirksey R. L. Scarborough M. W. Hawes D1.LcyR.

D. Finley R. W. Weathers J. L. Lang D. A. Wellbaum A. H. O'Dell M.E. Greer TECHNICIAN TECHNICIAN K. R. Butterfield W. B. Queen H. S. Holland R. J. Stevens T. W. Whitesides ASSISTANT TECHNICIAN M.B. Mackey Note:

1 - Production Support Employee - Not included in number for total Station Employees or total approved.

2 - Rx Engineer in Training

CATAWBA NUCLEAR STATION SYSTEM EXPERT DEFINITION A System Expert is "an individual with an engineering degree or a strong demonstrable technical backround who is assigned the responsibility of maintaining expertise in a designated plant system(s) and/or area(s).

CATAWBA NUCLEAR STATION SYSTEM EXPERT PURPOSE The purpose of the System Expert Program is to maximize the performance, availability, and reliability of station systems and the station as a whole.

Catawba Nuclear Station System Expert Qualifications Four year engineering or physical science degree or a strong demonstrable technical background At least one year nuclear power plant experience Exemplary knowledge of systems assigned Training

• Systems

• Components

• Technical Specifications

• Design Basis

• Operational Understanding

• Codes

• Case Studies

Catawba Nuclear Station System Expert Program Systems Steam Generator Blowdown Recycle System Ice Condenser Refrigeration System Auxiliary Feedwater System Safety Injection System Main Condenser Containment Spray System Feedwater System Chemical & Volume Control System Condensate System Containment Penetration Valve lnj Water System Trace Heating System Condenser Circulating Water System Loose Parts Monitoring (Unit)

Fir Protection System Radiation Monitoring (Unit)

Conventional Low Press Service Water System Incore Instrumentation Nuclear Service Water System Out-of-Core Instrumentation Extrior Fire Protection System Diesel Load Sequiencing System Main Steam Supply to Auxiiary Equpment Diesel Control System Main Steam Bypass to Condenser Refueling Water System Main Stem Heater Drain System Main Steam Vent to Atmosphere Containment Personnel Air Lock System Auxiliary Ventilation System Containment Leak Testing System Control Room Area HVAC System Operator Aid Computer System Annulus Ventilation System Engineered Safety Features Actuation System Fuel Pool Ventilation System Transient Monitoring System Instrument Air System IWP/IWV Containment Purge Component Cooling System Containment Air Return & Hydrogen Skimmer System Diesel Generator Engine Cooling Water System Reactor Generator Stator Cooling Water System Fuel Recirculated Cooling Water System Special Nuclear Materials Reactor Coolant System Appendix J iResidual Heat Removal System

Catawba Nuclear Station System Expert Responsibilities

• Detail System Understanding

• Scheduling

• System Walkdown

• System Monitoring

• Reliability Review

• Operating Experience Program

• ALARA

• Problem Resolver

• Information Review

• Modification Review

Catawba Nuclear Station NSM Program System Expert Involvement SPR SE counsels superintendent NSM approval Scope meeting PMT Plan 30 days after scope document Planning meeting Commitment meeting PMT summary letter TN approval Retest Activities

July 12, 1989 INTRASTATION LETTER CATAWBA NUCLEAR STATION TO: T. B. Owen

SUBJECT:

Catawba Nuclear Station NSM CN-11045, Rev. 0 & NSM CN-20432, Rev. 0 Keywords: NSM Retest The above referenced NSM's will modify the VP System controls such that all isolation val ves can be electrically sealed closed during Modes 1 through 4 without the use of a TSM to remove power. The modification also provides for a time delay bypass of the high relative humidity isolation and trip function during startup of the VP System.

The functional that will be conducted as part of implementation procedures TN1A10450001A & 02A, and TN2AO4320001A & 02A fully demonstrate the adequacy of the NSM to meet its intended purpose. The ability of the time delay relay to allow start of VP with a simulated high humidity for the required time interval is tested along with the ability to start without a high humidity. In addition the new "BLOCK/CLOSE" function is verified to isolate all VP valves when placed in the required position. As an added as surance that the required safety function of the affected circuits is not adversely altered, al though the functional does test all such circuits, Performance will conduct PT1(2)A420041C upon completion of the modification prior to return to service. This is re quired by the applicable TNs.

Therefore, the proposed NSM implementation plan including functional and retests as out lined above fully challenge the modification to function in both normal and design basis conditions.

Z. Laylor Test Engineer For Approval:

W. F. BeanM a

Perfromance Manager

Catawba Nuclear Station System Expert Program Development August Work Plan September Modifications October Design Basis, Technical Documentation December Information Review

0.

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I Catawba Nuclear Station 0

System Expert Program Development I

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