ML20058G479

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Forwards Summary of 901022 Meeting W/Util in Arlington,Tx Re Secondary Plant Reliability Problems at Unit 1
ML20058G479
Person / Time
Site: Comanche Peak  
Issue date: 10/31/1990
From: Collins S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: William Cahill
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
References
NUDOCS 9011130200
Download: ML20058G479 (27)
v • d • e


Text

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OCT3I W i

i Docket Nos. 50-445 i

50-446

+

License Nos. NPF-87 CPPR-127 l

TV Electric j

ATTN:

W. J. Cahill, Jr., Executive Vice President Nuclear Skyway Tower 400 North Olive Street, L.B. 81 Dallas, Texas 75201 Gentlenen:

I r

This refers to the neeting conducted at Region IV's request in the Region IV l

office on October 22, 1990.

This neeting rela ced to activities authorized by NRC License No. NPF-87 for Comanche Peak Steam Electric Station, Unit 1 and war, attended by those on the attached Attendance List.

3 The subjects discussed at this meeting are described in the enclosed Meeting i

Summa ry.

I It is our opinion that this neeting was beneficial and has provided a better understanding of your efforts to identify and evaluate secondary plant reliability improvement areas.

In accordance with Section 2.790 of the NRC's

" Rules of Practice," Part 2. Title 10 Code of Federal Regulations, e copy of this letter will be placed in the NRC's Public Document Room.

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

Sincerely.

OriginalSloned By:

Thomas P.Gwynn l

9011130200 901131 Samuel J. Collins, Director l

DR ADOCK0500g45 Division of Reactor Projects l

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Enclosure:

Meeting Summary w/ Attachments i

cc w/ enclosure:

l TU Electric l

ATTN:

Roger D. Walker, Manager, Nuclear Licensing Skyway Tower

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400 North Olive Street, L.B. 81 Dallas, Texas 75201 RIV:DRP/B C:DRP/B D:DRP

/k' VSJCo}/90 I

lins ATHowell;df DDChanterla g10/0 10/p/90 10/30/90 1

,l TV Electric 2-Juanita Ellis President - CASE 1426 South Polk Street Dallas, Texas 75224 GDS Associates, loc.

Suite 720 1850 Parkway Place Marietta, Georgia 30067-8237 Billie Pirner Garde, Esq.

Robinson, Robinson, et. al.

103 East College Avenue Appleton, Wisconsin 54911 TV Electric Bethesda Licensing 3 Metro Center Suite 610 Bethesda, Maryland 20814 Heron, Burchette, Kuckert, & Rothwell ATTN William A. Burchette, Esq.

Counsel for Tex-La Electric Cooperative of Texas 1

1025 Thomas Jefferson St., N.W.

Washington, D.C.

20007 E. F. Ottney P.O. Box 1777 Glen Rose. Texas 76043 Newman & Holtzinger, P.C.

ATTN: Jack R. Newman, Esq.

1615 L. Street, N.W.

Suite 1000 Washington, D.C.

20036 Texas Department of Labor & Standards ATTN:

G. R. Bynog, Program Manager /

Chief Inspector Boiler Division P.O. Box 12157. Capitol Station Austin, Texas' 78711 Honorable George Crump County Judge Glen Rose, Texas 76043 t

Texas Radiation Control Program Director 1100 West 49th Street Austin, Texas 78756

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l TU Electric l bectoDMB(IE45) bcc distrib, by RIV:

  • R. D. Martin
  • ResidentInspector(2)
  • DRP
  • DRS
  • SectionChief(DRP/B)
  • Project Engineer (DRP/B)
  • DRSS-FRPS Lisa Shea, RM/ALF
  • MIS System
  • RSTS Operator
  • RIV Files i
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i MEETING

SUMMARY

l j

Licensee:

TV Electric Facility:

Comanche Peak Steam Electric Station (CPSES), Unit 1 i

License No.:

NPF-87 Docket No.:

50-445

Subject:

TECHNICAL MEETING TO DISCUSS SECONDARY PLANT RELIABILITY PROBLEMS AT CPSES, UNIT 1 On October 22, 1990, representatives of TV Electric presented the preliminary conclusions and reconsntndations resulting from a licensee task team that was formed to investir te secondary plant reliability problems at CPSES, Unit 1.

The licensee form a multidiscipline task team in September 1990 following an increase in the

  • squency of plant events during August and September 1990.

The task team assessed Unit I reliability since initial criticality. This was accomplished by the following activities:

docunentation review and analysis secondary plant walkdown l

feedwater regulating valve events analysis l

design / design modification review corrective action tineliness operator / maintenance activities l

data acquisition analysis personnel interviews other initiatives Of 21 secondary plant events that have occurred since initici criticality, the licensee determined that 67 percent of the events were related to various problems with the main feedwater and heater drain systems; however, the licensee concluded that the events have been caused by individual failures I

or problems with no corranon root causes. For each event, the licensee determined root causes and corrective actions; however, the task team recommended several short-and long-term corrective actions to further enhance secondary plant reliability.

l Although licensee management is still evaluating the task team's recontrendatlons, the licensee plans to conduct an 8-10 day ~ outage contrencing on November 2,1990, to implenent several design modifications to enhance the reliability of the main feedwater and heater drain systems.

l Attachnents:

l 1.

Attendance List 2.

Licensee Presentation (NRC distribution only) l r

i ATTENDANCE LIST Attendance at the meeting between TV Electric and NRC on October 22, 1990, at the Region IV office was as follows:

TU Electric W. J. Cahill, Executive Vice President, Nuclear A. B. Scott, Vice President, Nuclear Operations J. J. Kelley, Plant Menager C. L. Terry, Director Quality Assurance R. D. Walker, Manager, Nuclear Licensing C. B. Hogg, Chief Engineer P. B. Stevens, Manager, Technical Support and Operations Support Engineering S. S. Palmer, Stipulation Manager A. H. Saunders, Quality Technical Support Manager i

J. C. Hicks, Licensing Manager, Unit 2 G. Krishnan, Supervisor, Unit 2 Systems D. R. Woodlan, Manager, Docket Licensing

1. C. Whitt, Supervisor, Balance of Plant Mechanical Systems l

Newman & Holtringer S. Franz, Attorney i

i Citizens Association for Sound Energy E. F. Ottney, Project Manager t

0. L. Thero, Consultant J. Doyle, Consultant NRC T. P. Gwynn, Deputy Director, Division of Reactor Projects (DRP)

L. J. Callan, Director, Division of Reactor Safety (DRS)

J. P. Jaudon, Deputy Director, DRS J. C. Linville, Actin Director, Project Directorate IV-2, Office of Nuclear Reactor Regulation NRR)

D. D. Chamberlain, Ch ef, Project Section B, DRP A. T. Howell, Project Engineer, DRP W. D. Johnson, Senior Resident Inspector, Comanche Peak Steam Electric Station. Unit 1. DRP D. N. Graves, P,esident Inspector, Comanche Peak Steam Electric Station, Unit 1 DRP J. W. Clifford, Senior Project Manager, Project Directorate IV-2, NRR l

M. B. Fields, Project Manager, Project Directorate IV-2, I;RR

SECONDARY PLANT EVENTS GENERATOR MAIN HEATER MAIN MAIN PRIMARY EVENT FEEDWATER DRAIN STEAM GENERATOR CONDENSER WATER TOTAL REACTOR TRIP 5

2 7

SAFETY INJECTION 2

2 i

TURBINE TRIP-2 2

FORCED TURBINE SHUTDOWN 1

1 2

REDUCTION IN POWER 2

4 1

1 8

TOTAL 8

6 3

2 1

1 21 o

APPROXIMATELY 38% OF THE E*.'ENTS ARE RELATED TO THE FEEDWATER SYSTEM 0F THE TOTAL, 5 WERE FRV, 1 VALVE, 2 MFP R:e o

APPROXIMATELY 29% OF THE EVENTS ARE RELATED TO THE HEATER DRAIN SYSTEM 2

0F THE 6 TOTAL, 3 WERE HDP, 2 TRANSIENT, 1 VALVE f

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t SECONDARY PLANT EVENTS PRIOR TO COM4ERCIAL OPERATION t

DATE TRANSIENT CAUSE APRIL 23, 1990 TURBINE TRIP MAIN GENERATOR GROUND FAULT APRIL 28, 1990 TURBINE SHUTDOWN UNIS0LABLE STEAM LEAK MAY 9, 1990 REACTOR TRIP MAIN FEEDWATER PUMP SPEED CONTROLLER MAY 12, 1990 TURBINE SHUTDOWN FEEDWATER REG VALVE FAILURE MAY 27, 1990 REACTOR TRIP FEEDWATER REG VALVE FAILED CLOSED JUNE 18, 1990 POWER REDUCTION GENERATOR PRIMARY WATER REPAIRS JUNE 27, 1990 POWER REDUCTION HEATER DRAIN PUMP FAILURE JULY 02, 1990 POWER REDUCTION MAIN FEEDWATER PUMP FAILURE JULY 16, 1990 POWER REDUCTION MAIN CONDENSER LEAKS JULY 26, 1990 SI (MODE 3)

INADVERTENT OPENING OF MSIV'S JULY 30, 1990 SI (MODE 3)

STEAM GENERATOR ATMOSHPERIC RELIEF VALVE FAILED OPEN j

AUGUST 8,:1990 REACTOR TRIP FWPBV FAILED CLOSED

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L SECONDARY PLANT EVENTS DURING C0ftqERCIAL OPERATION l

DATE TRANSIENT CAUSE i

AUGUST 16, 1990 POWER REDUCTION HEATER DRAIN PUMP FAILURE I

AUGUST 28, 1990 POWER REDUCTION FEEDWATER HEATER TRAIN PROBLEMS AUGUST 25, 1990 REACTOR TRIP FEEDWATER REG VALVE FAILED OPEN SEPTEMBER 7, 1990 REACTOR TRIP FEEDWATER REG VALVE FAILED OPEN SEPTEMBER 10, 1990 REACTOR TRIP MOISTURE SEPARATOR REHEATER HI LEVEL SEPTEMBER 15, 1990 REACTOR TRIP HEATER DRAIN PUMP TRIP 1

SEPTEMBER 22, 1990 POWER REDUCTION HEATER DRAIN PUMP DISCHARGE VALVE FAILURE SEPTEMBER 23, 1990 TURBINE TRIP SWITCHYARD DISCGNNECT SWITCH 8002 WRONG POSITION SEPTEMBER 26, 1990 POWER RcDUCTION FEEDWATER REG VALVE VIBRATION l

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IMPROVEMENTS RESULTING FROM INDIVIDUAL EVENTS I

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o PUMP ALIGNMENT /M*,1NTENANCE PROCEDURE AND METHODS ENHANCED o

CLEARANCE PROCESS AND TRAINING WERE UPGRADED o

PROGRAMS ENHANCED I

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PLANT IMPACT REVIEW FORMALIZED i

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i SINGLE POINT ITEMS LIST MADE USER FRIENDLY l

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OUTDOOR EQUIPMENT WORK PRACTICES ENHANCED i

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OPERATING MODE PHILOSOPHY ENHANCED l

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MODIFICATIONS IMPLEMENTED j

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e-i SUM 4ARY I

l ROOT CAUSES/ CORRECTIVE ACTION DETERMINED FOR INDIVIDUAL EVENTS i

o i

NO GENERIC CAUSES IDENTIFIED AS PART OF THE INDIVIDUAL EVENT REVIEWS o

o UNIT RESPONDED IN ACCORDANCE WITH DESIGN o

OPERATIONS PERFORMED CONSISTENT WITH PROCEDURES INCREASED FREQUENCY OF EVENTS DURING SEPTEMBER PROMPTED FORMATION o

0F A RESPONSE TEAM i

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CONSTRUCTION ERA SECONDARY DESIGN CHANGES FOR IMPROVED RELIABILITY AUXILIARY STEAM - SYSTEM 2000 (SA)

REPLACED THE C0ATES ELECTRODE BOILER (CAPACITY 20,000 lbm/HR) WITH A CLEANER BR0DIC DIESEL FIRED BOILER (CAPACITY 75,000 lbm/HR)

EXTRACTION STEAM - PPF-145 CHANGED OUT ALL THE EXTRACTION STEAM CARBON STEEL PIPING WITH PIPING WITH A HIGHER CHROMIUM NICKEL CONTENT TO IMPROVE EROSION / CORROSION RESISTANCE, CONDENSATE SYSTEM DM 84-108 MAIN CONDENSER TUBE BUNDLE CHANGE 0VT FROM COPPER-NICKEL TAKEN TO TITANIUM TUBES FOR IMPROVED STEAM GENERATOR RELIABILITY.

DM 84-210 AUXILIARY CONDENSER TUBE BUNDLE CHANGE 0VT FROM l

COPPER-NICKEL TVBES TO TITANIVM TUBES, t

DM 86-149 REWORK CONDENSER SPARGERS TO PREVENT TUBE BUNDLE.

IMPINGEMENT.

DMRC 87-1-054 CONDENSATE /FEEDWATER FULL FLOW RECIRCULATION SYSTEM FOR IMPROVED SECONDARY SIDE CLEANUP.

MAIN STEAM SYSTEM - MOISTURE SEPARATOR / REHEATER TVBE BUNDLE CHANGE 0VT FROM COPPER-NICKEL TO TITANIUM t

S SELF ASSESSMENT OF SECONDARY PLANT RELIABILITY CHARTER o

MULTI DISCIPLINE TASK TEAM j

1 o

ASSESSMENT OF RELIABILITY SINCE INITIAL CRITICALITY SCOPE o

EVALUATED DESIGN, HARDWARE, PRACTICES, AND DOCUMENTATION i

o EVALUATED OTHER INITIATIVES t

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SELF ASSESSMENT OF SECONDARY PLANT RELIABILITY

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SUMMARY

CONCLUSIONS o

EVENTe HAVE BEEN CAUSED BY INDIVIDUAL FAILURES WITH NO COMMON THREAD TO ROOT CAUSES o

DESIGN OF THE SECONDARY PLANT IS GENERALLY ADEQUATE TO SUPPORT OPERATIONS o

SECONDARY PLANT IS GENERALLY BEING MAINTAINED AND OPERATED IN ACCORDANCE WITH PROCEDURES l

o OPERATING EXPERIENCE TO DATE IS COMPARABLE TO OTHER NEW OPERATING PLANTS o

PREVIOUS MANAGEMENT INITIATIVES HAVE BEEN EFFECTIVE t

IN IMPROVING RELIABILITY o

SPECIFIC CONCLUSIONS WITH RECOMMENDATIONS WILL FURTHER IMPROVE SECONDARY PLANT RELIABILITY l

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l Comparison of CPSES Secondary Plant induced LERs to Sirnitar Westinghouse Plants

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(Vogtle 1, Wolf Creek, Byroa 1, South Texas 1, Callaway) 25 - -

20 --

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Average cdm

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CPSES m

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Lowest

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1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 Months Snice Irwtial Criticabty 4

- Highest

-- Lowest

- Average of Five Plants - CPSES-1 I

l l

d SELF ASSESSMENT OF SECONDARY PLANT RELIABILITY 4

SECONDARY PLANT ANALYSIS o

ONE FORM REVIEW (96) 69% COMPONENTS 19% PROGRAMS 12% HUMAN FACTORS o

EXPANDED DOCUMENT REVIEW j

o MOST FREQUENT ISSUES FEEDWATER REGULATING VALVES VALVE LEAKS INSTRUMENTATION o

MOST IMPACTED SYSTEMS MAIN FEEDWATER l

MAIN STEAM' HEATER DRAINS 1

r l

1 SELF ASSESSMENT OF SECONDARY l

PLANT RELIABILITY I

ACTIVITIES l

o DOCUMENTATION REVIEW AND ANALYSIS i

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o SECONDARY PLANT WALKDOWN o

FEEDWATER REGULATING VALVE EVENTS ANALYSIS l

o DESIGN / DESIGN MODIFICATION REVIEW o

CORRECTIVE ACTION TIMELINESS o

OPERATOR / MAINTENANCE ACTIVITIES i

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DATA ACQUISITION ANALYSIS o

PERSONNEL INTERVIEWS o

OTHER INITIATIVES 1

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j SELF ASSESSMENT 0F SECONDARY H

PLANT RELIABILITY l

CONCLUSIONS i

CONCLUSION 1 (MAIN FEEDWATER REGULATING VALVES):

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MAIN FEEDWATER REGULATING VALVES HAVE BEEN MARGINALLY RELIABLE DUE 1

TO FLOW-INDUCED OSCILLATIONS l

CONCLUSION 2 (HEATER DRAIN AND CONDENSATE SYSTEMS):

I HEATER DRAIN AND CONDENSATE SYSTEM COMPONENTS HAVE EXPERIENCED FAILURES j

CONCLUSION 3 (INSTRUMENTATION):

INSTRUMENTATION FAILURES AND MALFUNCTIONS HAVE OCCURRED DVE TO ENVIRONMENTAL FACTORS AND FLOW-INDUCED OSCILLATIONS CONCLUSION 4 (CONTROL ROOM INDICATION):

SOME SECONDARY PLANT MAIN CONTROL BOARD MULTIPLE INPUT ANNUNCIATORS DO N01 HAVE REFLASH AND SOME INSTRUMENTATION IS NOT AVAILABLE IN THE CON 190L ROOM CONCLUSION 6 (VALVE ACTUATOR N LEAKAGE):

3 l

MAIN FEEDWATER AND MAIN STEAM ISOLATION VALVE ACTUATORS REQUIRE j

FREQUENT RECHARGING t

CONCLUSION 6 (EQUIPMENT ACCESSIBILITY):

EQUIPMENT ACCESSIBILITY POTENTIALLY AFFECTS PERSONNEL SAFETY DURING l

PLANT OPERATIONS l

1 SELF ASSESSMENT OF SECONDARY PLANT RELIABILITY 1

CONCLUSIONS (CONT'D)

CONCLUSION 7 (VALVE LEAKS):

A NUMBER OF VALVE LEAKS HAVE BEEN IDENTIFIED IN THE SECONDARY PLANT r

CONCLUSION 8 (SPARE PARTS):

l SPARE PARTS ARE NOT ALWAYS AVAILABLE CONCLUSION 9 (PERSONNEL SURVEY):

WORKING LEVEL PERSONNEL INTERVIEWED FELT THAT EMPHASIS HAS NOT BEEN PLACED ON THE SECONDARY PLANT CONCLUSION 10 (FOREIGN MATERIAL):

FOREIGN MATERIAL WAS A FACTOR IN SOME SECONDARY PLANT INCIDENTS CONCLUSION 11 (PROGRAMS):

SOME CPSES PROGRAMS REVIEWED ARE PROACTIVE, MOST-ARE'WELL DEVELOPED AND ENHANCE SECONDARY PLANT RELIABILITY CONCLUSION 12 (VENDOR MANUALS):

MOST OF THE SECONDARY PLANT VENDOR MANUALS HAVE NOT BEEN REVIEWED BY ENGINEERING CONCLUSION 13 (SENSITIVE EQUIPMENT):

SOME EQUIPMENT IN THE PLANT IS SENSITIVE TO VIBRATION OR RAD'O INTERFERENCE

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. SE'LF ASSESSMENT.0F SECONDARY PLANT RELIABILITY CONCLUSIONS (CONT'D)

CONCLUSION 14 (PROACTIVE PROGRAMS):

A PROGRAM THAT ANTICIPATES POTENTIAL SECONDARY PLANT TRANSIENTS AND EVOLUTIONS IN THE VARIOUS MODES OF OPERATION WOULD BE BENEFICIAL TO PLANT OPERATION CONCLUSION 15 (SUPPORT SERVICES):

l INPUT FROM SUPPORT SERVICES SHOULD BE ENC 0URAGED CONCLUSION 16 (WORK ORDER REVIEW):

WORK ORDER ANALYSIS INDICATED MINIMAL DIFFERFNCES IN PRIORITIZATION AND WORK COMPLETED BETWEEN PRIMARY AND SECONDARY PLANT SYSTEMS CONCLUSION 17 (DOCUMENT TIMELINESS REVIEW):

SOME PLANT INCIDENT REPORT AND TECHNICAL EVALUATION RESOLUTIONS WERE NOT TIMELY 1

CONCLUSION 18 (DESIGN MODIFICATIONS):

POSITIVE ACTIONS HAVE BEEN TAKEN T0' IDENTIFY AND IMPLEMENT DM'S TO ENHANCE SECONDARY PLANT RELIABILITY CONCLUSION 19(PERSONNELOBSERVATIONSl:

AUXILIARY OPERATORS AND MAINTENANCE PERSONNEL GENERALLY PERFORM THEIR ACTIVITIES IN ACCORDANCE WITH ESTABLISHED GUIDELINES CONCLUSION 20 (LESSONS' LEARNED):

UNIT 2 PROJECT SHOULD TAKE APPROPRIATE ACTION TO PREVENT IDENTIFIED i

HARDWARE ISSUES-FROM RECURRING ON UNIT 2 l

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SELF ASSESSMENT OF SECONDARY PLANT RELIABILITY i

RECOMENDATIONS 1

SHORT TERM IA:

IMPLEMENT FEEDWATER REGULATING VALVE MODIFICATIONS AS S0ON AS PARTS ARE AVAILABLE TO ENHANCE RELIABLE FULL POWER OPERATION 18:

IMPLEMENT MODIFICATION TO PROTECT THE FEEDWATER REGULATING VALVES FROM THE ENVIRONMENT 2A:

IMPLEMENT PROPOSED MODIFICATIONS TO IMPROVE HEATER DRAIN i

SYSTEM RELIABILITY 3A:

EVALUATE FREQUENCY OF SECONDARY PLANT INSTRUMENTATION CALIBRATION 3B:

IMPLEMENT PENDING MODIFICATION TO INSTALL CONDENSER VACUUM INSTRUMENTATION M0ISTURE TRAPS l

3E:

IMPLEMENT PENDING MODIFICATION TO INSTALL D/P LEVEL TRANSMITTERS ON THE MSR DRAIN TANKS 3G:

PROTECT TEMPORARY MODIFICATIONS FROM FREEZING WEATHER 6A:

EVALUATE MODIFICATIONS FOR IDENTIFIED DIFFICULT TO ACCESS COMPONENTS 7A:

ASSESS IDENTIFIED VALVE WORK FOR RELIABILITY IMPACT PRIOR TO OUTAGES 8A,:

IDENTIFY AND EXPEDITE REQUIRED MATERIAL FOR'THE SPRING 1991 B

OUTAGE

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SELF ASSESSMENT OF SECONDARY PLANT RELIABILITY l

RECOMENDATIONS l

l SHORT TERM (CONT'D) 8D:

DEVELOP REPLACEMENT PLAN FOR PLANT EQUIPMENT THAT IS NO LONGER MANUFACTURED 8E:

VPGRADE THE MATERIAL IDENTIFICATION SYSTEM TO IMPROVE MATERIAL RESERVATION AND STAGING 9A:

INCREASE EMPHASIS ON PLANNING, ACCOMPLISHING AND SUPERVISORY i

OVERVIEW 0F SECONDARY PLANT WORK 9C:

EXPAND THE PLANT MANAGEMENT MONITORING PROGRAM TO INCLUDE MANAGER OBSERVATION OF ROUTINE SECONDARY PLANT WORK ACTIVITIES 10A: IMPLEMENT FOREIGN MATERIAL LESSONS LEARNED INCLUDING FILTER f

MEDIA CHANGE OUT PROGRAM l

110: COMPLETE IMPLEMENTATION OF THE EQUIPMENT HISTORY PROGRAM 11E: COMPLETE THE COMPUTER TRENDING FIELDS ON MMCP WORK ORDERS l

11F: DETERMINE WHETHER FURTHER REDUCTION IN THE STEAM GENERATOR LO-LO LEVEL SETPOINTS IS STILL DESIRED AND IMPLEMENT DM'S AS i

APPROPRIATE 13A: ENCLOSE THE MAIN FEEDWATER PUMP LUBE OIL PRESSURE SWITCHES IN A PROTECTIVE B0X 15A: EVALUATE CABLE SHIELDING AND PLANT GROUNDING PRACTICES AGAINST l

THOSE USED IN TV FOSSIL PLANTS t

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SELF ASSESSMENT OF SECONDARY PLANT RELIABILITY RECOMENDATIONS SHORT TERM (CONT'D)

ISB: EVALUATE SUPPORT SERVICES COMMENTS ON EQUIPMENT PROTECTION AND TRIPPING 17A: COMPLETE THE PIR EVALVATIONS ON FX-90-1473 AND FX-90-2109 17B: EVALUATE TIMELINESS OF EVALUATIONS OF PLANT INCIDENT REPORTS AND TECHNICAL EVALUATIONS i

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1 SELF ASSESSMENT OF SECONDARY PLANT RELIABILITY RECOMENDATIONS 1

LONG TERM 2B:

EVALUATE THE RECOMMENDATIONS OF ER-ME-37 TO FURTHER REDUCE THE FLOW-INDUCED OSCILLATIONS IN THE CONDENSATE PUMP RECIRCULATION LINE 2C:

EVALUATE THE EFFECTS ON STRUCTURAL INTEGRITY OF THE HEATER DRAIN AND CONDENSATE SYSTEMS DUE TO FLOW-INDUCED OSCILLATIONS AND TRANSIENTS q

2D:

EVALUATE THE HIGH VOLUME CONDENSATE AND MAIN FEEDWATER FLUSH SYSTEM OPERATIONAL REQUIREMENTS AND PRACTICES 1

3C:

EVALUATE THE NEED FOR A DM TO RELOCATE VALVE CURRENT TO PRESSURE TRANSDUCERS (I/Ps) 30:

INITIATE A DM TO REPLACE THE MAIN FEEDWATER AND MAIN STEAM

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FLOW TRANSMITTERS 3F:

INITIATE A DM TO REPLACE THE MSR HEATING STEAM CONTROL SYSTEM 3H:

EVALUATE THE NEED FOR A DM TO REPLACE THE FEEDWATER PUMP LUBE OIL PRESSURE REGULATORS 4A:

INITIATE A DM TO PROVIDE "REFLASH" CAPABILITY FOR MCB ANNUNCIATORS WITH MULTIPLE EQUIPMENT INPUTS l

4B:

INITIATE A DM TO INSTALL ADDITIONAL SECONDARY PLANT MONITORING.

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INSTRUMENTATION IN THE CONTROL ROOM i

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SELF ASSESSMENT OF SECONDARY PLANT RELIABILITY RECOMENDATID.lli l

LONG TERM (CONT'D) l 5A:

REPAIR MAIN FEEDWATER AND MAIN STEAM ISOLATION VALVE ACTUATOR LEAKAGE 78:

COMPLETE IMPLEMENTATION OF THE CPSES VALVE PROGRAM t

8C:

DETERMINE MATERIAL LESSONS LEARNED FROM THE SPRING 1991 OUTAGE 9B:

PROVIDE FEEDBACK TO PERSONNEL SUBMITTING WORK REQUESTS 10B: UNIT 2, REVIEW THE LESSONS LEARNED FROM UNIT 1 100: UNIT 2, ENSURF, PLANS INCLUDE FLUSHING THE SECONDARY PLANT, CONTROLLING C!..EANLINESS OF COMPONENT INTERNALS, ADEQUATE LAYUP OF COMPONENTS AND A FILTER MEDIA CHANGE OUT PROGRAM 11A: INCLUDE THE RESULTS OF THE SINGLE POINT FAILURE ANALYSIS, THE CRITICAL COMPONENTS LIST AND'THE EQUIPMENT IDENTIFIED BY THIS SELF ASSESSMENT IN THE PREDICTIVE MAINTENANCE PROGRAM.

EVALUATE BROADER COVERAGE OF THE SECONDARY PLANT, 118: INCLUDE MAIN STEAM, HEATER DRAIN, AND MAIN FEEDWATER SYSTEMS IN THE RELIABILITY CENTERED MAINTENANCE (RCM) CONTRACT.

110: INCORPORATE SINGLt FAILURE COMP 0NENTS FROM THE RCM ANALYSIS INTO WORK.0RDERS AND PROCEDURES 11G: COMPLETE THE EVALUATION OF THE CONDENSER-STEAM DUMPS AND ASSOCIATED PIPING FOR 100 PERCENT LOAD REJECTION CAPABILITY f

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SELF ASSESSMENT OF SECONDARY PLANT RELIABILITY REC 0044ENDATIONS i

i LONG TERM (CONT'D) 12A: COMPLETE ENGINEERING REVIEW OF SECONDARY PLANT EQVIPMENT MANUALS i

13B: PAINT THE FLOOR AROUND SENSITIVE EQUIPMENT AREAS WITH TELLOW l

HASH MARKS l

14A: IMPLEMENT A PROGRAM THAT ANTICIPATES OPERATING CONDITIONS AND SITUATIONS THAT CAN IMPACT POWER OPERATIONS 15C: EXCHANGE INFORMATION BETWEEN CPSES AND THE CORPORATE TV ELECTRIC SYSTEM 18A: IMPLE"ENT THE APPROVED TRIP REDUCTION DM'S 18B: EVALUATE THE NEED FOR A DM TO RESOLVE MAIN STEAM SYSTEM ATMOSPHERIC RELIEF VALVE NOISE-INDUCED VIBRATION 18C: EVALVATE THE NEED FOR ADDITIONAL DM'S TO UPGRADE TURBINE GENERATOR AND AUXILIARY SYSTEMS 19A: ENSURE AUXILIARY OPERATORS UTILIZE THEIR SENSES TO ASSESS EQUIPMENT CONDITION l

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m APPROVED DM'S FOR NOVEMBER OUTAGE

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DM 90-305 DESCRIPTION OF MOD:

ELIMINATE ACCELERATED OSCILLATIONS OF THE FEEDWATER FLOW CONTROL VALVES DM 89-13 DESCRIPTION OF MOD:

EMERGENCY LOW PRESSURE HEATER BYPASS CONTROL LOGIC MODIFICATION DM 89-034 DESCRIPTION OF MOD:

LOWER & STAGGER THE MAIN FEED PUMP LOW SUCTION PRESSURE TRIP

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DM 90-245 DESCRIPTION OF MOD:

PROVIDE A HAND LOADER i

STATION TO PERMIT MANUAL CONTROL OF PUMP DISCHARGE VALVE.

l RDM-351 DESCRIPTION OF MOD:

CHANGE #6 FEEDWATER.

HEATER ALTERNATE DRAIN CONTROL FROM MODULATING CONTROL TO " DUMP OPEN" CONTROL, L

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RDM-352 DESCRIPTION OF MOD:

RAISE THE SETPOINT j

FOR THE HEATER DRAIN TANK OPERATING LEVEL.

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ADDITIONAL MAINTENANCE ACTIVITIES I

f!)R.. NOVEMBER DUTAGE l

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CORRECTION OF MAIN CONTROL BOARD INDICATION PROBLEMS P

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REPAIR LEAKING VALVES.IN CONDENSATE FEEDWATER, MAIN STEAM-HEATER DRAINS AND EXTRACTION STEAM SYSTEMS l

ALIGNMENT CHECKS ON MAIN FEEDWATER PUMP FUNCTIONAL CHECKS OF HEATER DRAIN PUMP LEVEL TRIP i

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t CONTINUED FEEDWATER' HEATER TUNING AFTER PLANT.'STARTUP i

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