ML20238A184

Summary of 870812 Meeting W/Util in Phoenix,Az Re Concerns Generated During Assessment of Operating Performance of Units 1 & 2 in Consideration of Pending Licensing Decision for Unit 3.Attendee List & Viewgraphs Encl

ML20238A184
Person / Time
Site:	Palo Verde
Issue date:	08/24/1987
From:	Marlone Davis Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8709090175
Download: ML20238A184 (51)

Text

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Docket Nos.: 50-528, 50-529

[

and 50-530 LICENSEE: Arizona Public Service Company M

FACILITY: Palo Verde, Units 1, 2 and 3

SUMMARY

OF MEETING HELD IN PH0ENIX, ARIZONA, AUGUST 11 - 13, 1987 1.

Management Meeting

]

ALmanagement meeting was held on August 12, 1987, in the licensee's office in Phoenix, Arizor,a, with representatives of the licensee and NRC representatives from the Offices of NRR and Region V.

The purpose of the meeting was to discuss NRC concerns generated during assessment of the i

operating performance of Palo Verde Units 1 and 2 in consideration of the i

i pending licensing decision for Unit 3, and to identify needed licensee

)

actions for improvement prior to the licensing decision.

l l

The list of attendees and slides used in the licensee's presentation are enclosed as Enclosures 1 and 2 respectively.

I The licensee presented responses to the concerns identified by the NRC in l

the proposed agenda provided by letter dated July 22, 1987..

j 1

In the area of Compliance Trend Data, the licensee feels that downward

)

trends have been established in the number of Licensee Event Reports, personnel errors, unplanned reactor trips, and ESF actuations. The staff commented that improvement in these areas had been noted, but in recent months a slight trend upward in several areas is occurring. Additional management emphasis is needed to ensure that a significant upward trend does not occur with the startup of Unit 3.

i The licensee reviewed Fuel Performance figures for Units 1 and 2 and discussed actions taken over the past five years by the licensee and the fuel manufacturer to reduce fuel pin failures. The licensee has visited other utilities that have experienced fuel failures to discuss their problems and corrective actions. The licensee stated that with the actions taken Unit 3 will not be as susceptible to fuel failures, and fuel performance should improve.

The Unit 1 Circulatory Water (CW) system water hammer event was discussed. The root cause of the condenser waterbox damage was the failure of the quadrant gear bolts on the '2C' waterbox outlet valve. The bolts failed due to improper setting of the electrical limit switches and

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mechanical: stops caused by incorrect interpretation of the valve technical manual. The valve manufacturer provided training of licensee personnel and the electrical limit switches and mechanical stops were reset in Unit 1.

The licensee stated that the use of,locktite and hardened washers to distribute torque loading and an increase in preloading on the bolts should reduce the vibration induced fatigue loading on the bolts..

Similar. actions will be taken on Unit 2 CW valves at the next outage and" on Unit 3 CW valves prior to power ascension.

In the' area of Secondcry Water Chemistry Control the licensee discussed activities.in progress to reduce radweste generation and to enhance radwaste processing capability when primary to secondary leakage occurs.

r The Unit.1 LPSI. pump seal. failures:of early July 1987 were discussed.

bl When.the Unit remained at' approximately 325'F for steam generator cleanup

-following the condenser water'hanner event, the. continued operation at high temperature ~ caused degradation of the seals. The swelling of the-4

'O' rings was apparently due to the' application of a solvent to the 'O' ring surface. On the 'A' LPSI pump the. increased seal leakage up the.

i pump shaft displaced bearing lubricating oil and resulted _in bearing

' failure and motor damage. As corrective actions slingers are being installed on..all LPSI and CS pumps, no solvent or petroleum' lubricants are to be.used on.' rings, operating time above 210*F is being restricted

- on LPSI pumps, ano a seal life monitoring program by the system engineer 1

has been established.- The licensee is looking at different' seal designs

)*

and/or materials.-- The staff commented that a common theme in several recent events has been that technical manuals were not specific.

Increased interaction and information feedback between vendors and the licensee, and vendor involvement in maintenance activities might preclude similar >roblems in the future.. The staff also recommended that~infor--

mation a >out sea 1' degradation at high temperature should be shared with i

the rest of the industry.

Other. topics of discussion included Conduct of Radiation Protection Surve111ances, System Engineer, Involvement in Maintenance and Modification 6ctivities Status of Unit 3B Emergency Diesel Generator, Operator Confidence in Control Room Indications. Unit 3 Schedule Maintenance Backlog Annunicator Status, Simulator Time Goals for Operator Retraining, i

and the licensee's proposed Organizational Changes.

- The staff briefly discussed the. issuance of Commission' Paper 87-188 on New Plant Operating experience that addresses a number of initiatives to improve new plant performance. The staff will fomally transmit a copy of this document to the licensee to obtain their response.

The NRC' staff appreciated the presentation and will watch for evidence of success of corrective actions in improving performance trends.

1

t 6 l 2.

Unit 3 Plant Tour On August 11, 1987, the staff members toured Unit 3 and talked with plant personnel to assess Unit readiness for initial criticality. The licensee expects to be ready for startup in early October, and this appears to the staff to be reasonable.

M i

Michael J. Davis, Project Manager Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects

Enclosures:

i As stated cc: See next page l

l l

l DISTRIBUTION Docket File NRC PDR/LPDR I.

PDV Reading GKnighton MDavis/EAlicitra OGC - Bethesda EJordan JPartlow ACRS (glia FJMira 10)

HBClayton(RI)

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T0 Martin - ED0 DRSP/PDV4170 fpp V

MDavis:ca mi ton 8/21/87 8/21/87

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g Mr. E. E. Van Brunt, Jr.

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Arizona Nuclear Power Projp:t Palo Verde c

cc:

Arthur C. Gehr, Esq.

Kennesth Berlin, Esq.

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Snell & Wilmer Winsten & Strawn t

3100 Valley Center

.hite'500 6

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Phoenix, Arizona 85073

'2550 M Street, NW Washington, DC 20037;s Mr. James M. Flenner, Chief.0bunsel Arizona Corporation Comission.

Ms. Lynne Bernabei 1200 West Washington

/

Government Accountability Projecte Phoenix, Arizona 85007 of the Institute for Policy Studies 1901 Que Street, NW Charles R. Kocher, Esq. Assistant Washington, DC. 20009 j%

Council James A. Boeletto. Esq.

l l

):

. Southern California Edison Company Mr. Ron Rayner P.' O.. Box 800 P. O. Box 1509 Rosemead, California 91770 Goodyear, AZ 85338 u

i Mr. Mark Ginsberg Mr. Charles B. Brinkman, Manager i

Energy Director Washington Nuclear Operations Office of Economic Planning *J Combustion Engineering, Inc.

and Development.

7910 Woodmont Avenue Suite 1310 i

s 1700 West Washington - 5th Floor Bethesda, Maryland 20814 Phoenix, Arizona 85007 h

. Mr. Wayne Shirley i!

Assistant Attorney General Bataan Memorial Building

' Santa Fe, New Mexico. 87503

.i'I Mr. Roy Zimmennan

)

U.S. Nuclear Regulatory Comission P. O. Box 239

{

Arlington, Arizona 85322 j

Regional Administrator, Region V i

U. S. Nuclear Regulatory Commissinn 1450 Maria Lane Suite 210 4

Walnut Creek, California 94596 l

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f ENCLOSURE NAME AFFILIATION Mike Davis NRC/hRR/PDV' G. W. Knighton NRC/NRR/PDV e

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,i Bill Quinn MGR Licensing /ANPP Richard Bernier ANPP Lead Licensing Eng o

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Ike Zerinque ANPP Tech Support w'

Jec Gynum ANPP. Plant Mgr J. Martin Region V Administrator Robert J. Pate Chief, Reactor Safety Br., Reg. Y Jay R. Ball NRC Acting Senior Resident Inspector J. G. Haynes VP Nuclear Production E. E. Van Brunt Exec. V. P. - ANPP J. D. Driscoll Asst. V. P. Nuclear Prod.

F. J. Miraglia NRC/NRR/ADP Ross A. Scarano DRSS/RegV/NRC Ken Rotta Az. Corp. Com Duke Railsback Az. Corp. Com i

l Allan Mitchell Az. Corp. Com i

C KristinL.MCandlessClarkAPS/ PAD (Audit)

Larry Perea ANPP Lead Mech Engr Timothy Hall ANPP Lead Mech Eng - NSSS R. M. Butler ANPP Director Tech Serv.

W. E. Ide ANPP Director, Corp QA/QC l

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_____-____-U

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i NAME AFFILIATION

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7. R. Bradish ANPP Compliance Supervisor F

T. D. Shriver ANPP Compliance Mgr l-A. C. Gehr Snell & Wilmer e

Bill'Simko, ANPP Ops Engr E

k John Vorees ANPP Manager, Nuc Safety l

W. F. Fernow AP:?P Training Manager Dan.Canady ANPP Communications Mgr Brad Albert ANPP Licensing 1.

Kent Chavet Corporate Health Physics / Chemistry h-John Mann Corporate Health Physics / Chemistry -

Frank Turco Arizona Republic Victor Dricks Phoenix Gazette i

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4 ANPP - NRC MANAGEMENT MEETING r

PHOENIX, ARIZONA AUGUST 12, 1987

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III. (PDAT04 ECENT EVENTS II

- ONENSER WATER FW4ER W. M. Sl!KO

- E00ND4RY WATER GEMISTRY CONTROL J. R. f%NN t

- U4tT 1 LPSI R)PS W. M. SibKO i

IV. LPDATE ON PREVIOUS ISSUES.

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- 00t0UCT OF RP RJRVEILLANCES J. R. BrNLN

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- SYSTEM ENGitEER IbNOLVEKNT IN A

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PRINCIPLE PROBLEb6 ENCOLt#ERED DURlt6 LNIT 3 TESTitG

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GUIDELINES HAVE BEEN ISSUED TO PLANT OPERATIONS LIMITING THE RATE OF PLANT POWER INCREASE TO 10% PER HOUR COMPARED 3

TO THE CE CORE OPERATING GUIDELINES LIMIT OF 30% PER HOUR DAILY MONITORING OF REACTOR COOLANT SYSTEM ACTIVITY WITH REPORTS TO ANPP MANAGEMENT WEEKLY.

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UNIT 1 CIRCULATING WATER SYSTEM EVENT DESCRIPTION OF EVENT:

TRAIN

'A' 0F CW SYSTEM EXPERIENCES PIPE WELDS L

FAILURES PLANT IS SHUTDOWN.

EVENT IS CAUSED BY H01WELL '2C' OUTLET VALVE CLOSING.

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WELDS ON WATERBOX '2C' INLET AND OUTLET FAILED WATERBOX '28' OUTLET AND '2A' INLET CRACKED.

EXPANSION JOINT STUDS BENT. STRETCHED AND DAMAGED ON BOTH LOOPS.

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ROOT CAUSE.0F THE.WATERBOX DAMAGE WAS FAILURE'0F THE QUADRANT GEAR BOLTS u,

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. INADEQUATE / INCORRECT. INTERPRETATION:0FLTHE' TECHNICAL" MANUAL.

CORRECTIVE ACTIONS:

ELECTRICAL LIMIT SWITCHES AND MECHANICAL' STOPS

.;c ic WERE RESET IN UNIT 1.

'2C' 0UTLET VALVE REPAIRED.. BOLTING MATERl'AL-b REPLACED.- LOCKTlTE~AND HARDENED WASHERS AD'DED:

TO DISTRIBUTE-TORQUE LOADING'AND;ASSISTLIN-MAINTAINING TOROUE LOADING.

ALL OTHER SIMILAR VALVES IN UNIT 1 CHECKED FOR WEAR, TOROUE, AND WA.SHERS AND LOCKTITE USED AS DESCRIBED AB0VE.

y BOLTS.IN UNITS 2 AND 3 CHECKED TO VERIFY.TlGHTNESS~

WATERBOX REPAIRS COMPLETED ONE TUBE LEAK IDENTIFIED AND PLUGGED i

N0 INDICATIONS OF TUBE SHEET LEAKS OBSERVED I

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ACTIVITIES IN PROGRESS 4

a, CONTINUE INVESTIGATING MEANS TO INCREASE'RADWASTE PROCESSlNG CAPABILITY

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JUNE 29, 1987 --ENTERED MODE 4 TO REPAlR CIRCULATING WATER SYSTEM

, JUNE.30, 1987L-PLACED SHUTDOWN COOLING (SDC) IN SERVI'CE ON *BLPSI PUMP

.RX.: COOLANT:325*F-MAINTAIN TEMPERATURE / PRESSURE lFORSGlCHEMISTR CLEANUP JULY 1, 1987

- RCS LEAKAGE INCREASED.TO'2;5 GPM (ESTIMATED 1.6 GPM FROM.'B'1LPSI)..-PLACED 'A' TRAIN SDC IN SERVICE PER NORMAL OPERATING-b PROCEDURE. STOPPED 'B' LPSI

' JULY 3. 1987

- TOTAL RCS LEAKAGE AT 4.7 GPM - 4.0 GPM LEAKAGE FROM 'A' ANDB' LPSI PUMPS-CONTINUED OPERATION ON 'A' LPSI' PUMP BASED ON:

1) LEAKAGE-. TE CONSTANT i

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2) EXPECTED MODE 3 ENTRY WITHIN 24 HOURS

3) MOTORS QUALIFlED FOR 100% HUMIDITY JULY'4, 1987 LOSSOF'A'LPSIMOTORDUETOGROUNDFkULT

- RESTARTED 'B' LPSI - COMMENCED C00LDOWN OF RCS TO LESS THAN 210* TO ENTER MODE 5 l

AND PLACED CONTAINMENT SPRAY PUMP IN SERVICE JULY 5, 1987 CONCLUDED LOWER MOTOR' BEARING FAILURE CAUSED BY WATER SPRAY UP THE SHAFT FROM THE MECHANICAL SEAL, NEED TO PLACE SLINGER RING

.ON PUMP SHAFTS TO STOP WATER LEAK PATH 8/12/87 - WMS i

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SEAL FAILURE VENDOR INVOLVEMENT (PUMP VENDOR AND SEAL VENDOR)

SWOLLEN 'O' RINGS APPARENTLY DUE TO SOLVENT APPLICATION LOWER (ROTATING) SEAL SElZES AXIALLY ON SHAFT PREVENTING WEAR COMPENSATION r

HIGH TEMPERATURE' ACCELERATES WE4R RATE MOTOR FAILURE

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VENDOR INVOLVEMENT SEAL LEAKAGE UP PUMP SHAFT TO LOWER MOTOR GEARING BEARING OIL DISPLACED BY SEAL LEAKAGE WATER BEARING FAILURE MOTOR UPLIFT & DAMAGE l

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LPSI B - ROOT CAUSE ANALYSIS

- VENDOR INVOLVEMENT (PUMP VENDOR AND SEAL VENDOR)

DEBRIS IN ROTATING SEAL CAUSES MISALIGNMENT OF SEAL FACES h.

" BEVELED". WEAR PATTERN ON STATIONARY CARBON SEAL FACE -

SEALING SURFACE REDUCED HIGH TEMPERATURE ACCELERATES WEAR RATE CHIPPING ON CARBON SEALING' FACE g

SEAL LEAKAGE UP PUMP SHAFT TO LOWER MOTOR BEARING V

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CORRECTIVE ACTIONS r.

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SLINGERS ON ALL LPSI'AND CONTAINMENT SPRAY PUMPS

- I 2.

-NO SOLVENT OR PETROLEUM LUBRICANTS'ON'0-RING / RUBBER MATERIAL 3.

' LIMIT OPERATION TIME ON LPSI PUMPS WHEN ABOVE 210*F 4.

. SEAL LIFE MONITORING BY S STEM ENGINEER-L-

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. CONDUCT OF-RP SURVEILLANCE-1 n

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d APRIL 1982 - FALSIFICATION OF ELECTRICAL TERMINATION CARDS BY.

BECHTELCONSTRUCTIONPSRSONNEL-I 'n I

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TURLEY TAPE"IJ-ATTENTION TO DETAIL' INDIVIDUAL-RESPONSIBILlyY.FOR COMPLETE AND PROPER DOCUMENTATION 3

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COMPLIANCE 1WITH PROCEDURES ~

APRile1985'.- VAN BRUNT TAPE l - SAFETY AND QUALITY - ATTENT10N'-

TO DETAIL - KNOW AND FOLLOW ~ PROCEDURES

JANUARY.1986 - PUBLISHED ARTICLE IN ' REACTOR' DEAL 1NG WlTH.

SEABROOK EVENT

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FEBRUARY:1986-- QUALITY TALKS - FRAUD.AND FALSIFICATION -

INDIVIDUAL RESPONSIBILITIES 1

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- DISCUSSED SEABROOK EVENT o

DECEMBER 1.986 - RADIATION PROTECTION TECHNICIANS FALSIF1 CATION 1

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OF SURVEILLANCE DATA' D.

e SAMPLED RP. FIRE PROTECTION, OPERATOR LOGS AND COMPARED AGAINST ACAD TRANSACTIONS PUBLISHED ARTICLE ~-IN ' REACTOR' - THIS EVENT AND SEABROOK 9

EVENT QUALITY TALKS ISSUED ON SEABROOK EVENT EMPHASlZlNG INDIVIDUAL RESPONSIBILITY "

-h x

w PERSONNEL DEPARTMENT EVA!.UATION CONDUCTED TO DETERMINE l

IF HUMAN FACTORS SUCH AS MORALE, WORKING CONDITIONS COULD BE' CONTRIBUTORY CAUSE

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. CONDUCT OF RP SURVEILLANCE MAY 1987 - SECURITY GUARD FALSIF i / TION OF ROUNDS t

REVIEWED S1GNIFiCANT' SAMPLE OF. SECURITY LOGS AND ACAD' TRANSACTIONS' MAY 1987 - RADIATION PROTECTION TECHNICIAN FALSlFIED SAMPLE FLOW VERIFICATION s,

3 VAN BRUNT LETTER REITERATING FALSIFICATION SERIOUSNESS

!7 REVIEWED SAMPLE OF RP LOGS AND ACAD TRANSACTIONS EVALUATION BY COMPLIANCE OF OTHER ACTIONS TO MINIMlZE 6

FALSIFICATIONS CORRECT 1VE ACT1ONS TAKEN FOR SPECIFIC EVENTS'WERE APPROPRIATE ALL PERSONNEL RECOGNIZE SERIOUSNESS OF FALSIFICATION a

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SYSTEM ENGINEER INVOLVEMENT IN MAINTENANCE l

AND MODIFICATION ACTIVITIES-DESCRIPTION OF EVENT:

ASME SECTION XI TESTING WAS CONDUCTED ON THREE VALVES IN NOVEMBER, 1986.

5 THE VALVES MET THE ACCEPTANCE CRITERIA HOWEVER THE STROKE TIMES HAD lNCREASED BY MORE THAN 50% FROM THE PREVIOUS TESTS.

WHEN STROKE TIMES INCREASE BY 50% OR MORE RELATIVE TO PREVIOUS TESTS, SECTION XI REQUIRES TESTING FREQUENCY TO BE INCREASED r.

l TO A MONTHLY INTERVAL.

IN JANUARY, 1987, THE MODIFIED SURVEILLANCE INTERVAL WAS EXCEEDED.

y THE VALVES WERE SATISFACTORILY TESTED ON MARCH 6, 1987 AS PART OF THE REGULARLY SCHEDULED SURVEILLANCE TEST.

ON MARCH 31, 1987-THE ERROR WAS DISCOVERED'AND THE VALVES 4

WERE ADDED TO THE MONTHLY TESTING SCHEDULE AND SATISFACTORILY TESTED ON APRIL 2, 1987.

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AND MODIFICATION ACTIVITIES (CONT)

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- EVALUATION OF' EVENT:

THE CAUSE OF THE EVENT WAS A PERSONNEL ERROR ON THE PART L

0F THE ENGINEER RESPONSIBLE FOR THE SECTION XI TESTS..

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THE ENbINEER 01D NOT! EVALUATE THE STROKE. TIMES WITHIN k.

j SUFFICIENT TIME TO MODIFY THE TESTING !NTERVAL.

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- 7 A' REVIEW OE PREVIOUS TEST DATA WAS CONDUCTED WlilCH VERIFIED

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,i:f' THAT THESE THREE VALVES'WERE THE ONLY VALVES TESTED LATE.

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s ANPP IS CURRENTLY EVALUATING; PROPOSED CHANGES TO THE-ROLE OFTHESYSTEM[ENGINEERINTHEPREPARATIONANDCONDUCT h

0F SURVEILLANCE TESTING.

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s-REVIEW.:0F SURVEILLANCE TESToPROCEDURES, l

REVIEWOFSURVElLLANCETESI[RESULTSTOEVALUATESYSTEM e

c PERFORMANCE.

REVIEW 0F PREVENTATIVE MAINTENANCE PROCEDURES AND PERFORMANCE FREQUENCY.

- - REVIE)/OFPREVENTATIVENAINTENANCERESULTS.

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OPERATOR CONFIDENCE i

7 lN CONTROL ~ ROOM INDICAT10NS l

j DESCRIPTION OF EVENT:

I ON JUNE 10. 1987 A S/G COLD LEG BLOWDOWN SAMPLE ISOLATION. VALVE WAS STROKED CLOSED.TO PERFORM A STROKE TIME SURVEILLANCE TEST THE:"0 PEN" INDICATION LIGHT EXTINGUISHED BUT NO " CLOSED" b

INDICATION WAS RECEIVED ki '

THE TEST WAS DISCONTINUED AND A WORK REQUEST WAS GENERATED TO TROUBLESHOOT THE' INDICATION PROBLEM.

HOWEVER., BASED ON PREVIOUS PROBLEMS EXPERIENCED WITH THIS TYPE OF VALVE'S. POSITION INDICAll0N SWITCHES, THE VALVE WAS' NOT DECLARED INOPERABLE 1

~

ON JUNE 15, 1987. THE VALVE WAS STROKED TESTED AGAIN.

HOWEVER, DURING THIS TEST THE "0 PEN" INDICATION LIGHT DID NOT EXTINGUISH THE OPERATING CREW CHECKED THAT THE VALVE DID NOT MOVE, DECLARED THE VALVE INOPERABLE, AND CLOSED AND REMOVED POWER FROM A SECOND ISOLATION VALVE IN THE SAMPLE LINE IN ACCORDANCE WITH THE APPLICABLE ACTION STATEMENT SUBSEQUENT INVESTIGATION REVEALED THAT A SPRING, WHICH ACTS ON THE VALVE STEM TO CLOSE THE VALVE WHEN POWER IS REMOVED, WAS BROKEN k.c

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OPERATOR CONFIDENCE IN CONTROL ROOM INDICATIONS

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EVALUATION OF EVENT:

THE VALVE SHOULD HAVE BEEN DECLARED INOPERABLE ON JUNE p-10, SINCE=THE VALVE WAS NOT VERIFIED FULLY-CLOSED j,

SUBSEQUENT INVESTIGATION OF THE EVENT SHOWED COMPLIANCE-f WITH THE ACTION STATEMENT SINCE A MANUAL ISOLATION VALVE i

IN~THE' BLOWDOWN LINE WAS CLOSED AT ALL TIMES DURING THE'"lN0PERABILITY" 0F THE VALVE.

HOWEVER. THIS WAS NOT CONSIDERED AT THE TIME OF THE EVENT.

MAIN 1AINING THE VALVE OPERABLE, WITHOUT POSITIVE

(

VERIFICATION OF VALVE POSITION, AFTER CONTROL ROOM g(

INDICATION SHOWED THE VALVE DID NOT CLOSE IS CONTRARY TO ANPP OPERATING PHILOSOPHY CORRECTIVE ACTION LETTER WAS ISSUED TO UNIT 2 LICENSED PERSONNEL (COPIES TO UNIT 1 AND 3) BY THE UNIT 2 OPERATIONS SUPERINTENDENT TO REINFORCE THE RESPONSIBILITIES WITH REGARD TO DETERMINATION OF OPERABILITY OF TECHNICAL SPECIFICATION EQUlFMENT 4

THE RESPONSIBLE OPERATOR AND THE UNIT SUPERINTENDENTS WERE COUNSELED t

8/12/87 - OJZ s

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DIESEL GENERATOR "B" - CURRENT STATUS i

NRC APPROVED SPEClAL TEST PROGRAM COMPLETED JULY 5

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INSPECTION OF #2 MAIN BEARING AND #9 R0D BEARING BY NRC, COOPER, CLEVITE (BEARING MANUFACTURER)

AND ANPP COMPLETED y

JULY 10.

BEARINGS WERE DETERMINED TO BE ACCEPTABLE DURING INSPECTION OF THE GENERATOR ON JULY 15, A LOOSE POLE WINDING WAS DISCOVERED r

h PREVIOUS FAILURE:

IN NOVEMBER, 1986, PRIOR TO INITIAL ENERGlZATION, SEPARATED WINDING WAS DISCOVERED ON THE #12 POLE PIECE. POLE PIECE WAS SHIPPED TO THE GENERATOR j

MANUFACTURER (PARSON-PEEBLES) TO DETERMINE THE ROOT CAUSE

,0F THE FAILURE. ROOT CAUSE WAS EVALUATED TO BE LOCAL CONTAMINATION OF THE RESIN FROM CLEANING SOLVENT ON THE BRUSH

(..

USED TO APPLY THE RESIN.

?

DEDUCTIVE EVALUAT10N:

AMOUNT OF RESIN

- OK QUALITY OF RESIN - OK l

RESIN CORE

- OK lNSPECTION OF UNIT 1. UNIT 2 AND UNIT 3 'A' DIESEL GENERATOR POLES WAS CONDUCTED - NO FAILURES FOLLOWING THE JULY 15TH FAILURE:

l DAMAGED POLE REMOVED NATIONAL ELECTRIC C0ll WAS CONTACTED TO PERFORM ROOT CAUSE ANALYSIS (IN PROGRESS) INCLUDING DESIGN EVALUATI'ON OF FORCES

(.

ON POLE PIECE 8/1 /87 -

JZ

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'D!ESEL' GENERATOR

'B'

--CURRENT STATUS (CONT) s.

'B' GENERATOR ROTOR SHIPPED TO WESTINGHOUSE FOR REQUALIFICATION TESTING 4

X AUG 1 - 125% OVERSPEED TEST (COLD)

X AUG 2--

112% OVERSPEED TEST AT 130*C TESTING SUCCESSFULLY COMPLETED FINAL ROOT CAUSE NOT COMPLETE:

PRELIMINARY RESULTS'lNDICATE THAT NOT EN0 UGH RESIN, WHICH PROVIDES THE. BONDING THAT HOLDS WINDING TO POLE, WAS APPLIED.

QUALITY OF RESIN APPEARED GOOD.

RESIN SUITABLE FOR THIS APPLICATION CONSULTANT IS BEING SOUGHT TO EVALUATE THE CORRELATION, IF

. (-

ANY,1DF THE ENGINE FAILURE OF 12/23 TO THE POLE WINDING FAILURE 5

' 0F JULY 15 WORKING WITH THE VENDOR TO DETERMINE AN APPROPRIATE INSPECTION FREQUENCY OF THE POLES 4

4 8/12/87 - OJZ

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(c jj STATUS OF UNIT 3 LOW 6

POWER TESTING PROGRAM 1

MAJOR TEST PHASES' I

-1.

POST-CORE HOT' FUNCTIONAL TESTING (HFT)

F

• PERFORM R.G. 1,68 TESTING AT SPECIFIED TEMPERATURE /

PRESSURE CONDIT10NS BETWEEN. MODE 5 (COLD SHUTDOWN-210*F).

~

-AND HOT ZERO POWER (565*F/2250 PSIA) f

2. INITIAL CRITICALITY / LOW POWER PHYSICS TESTING (IC/LPPT) i

• PERFORM R.G. 1.66 TESTING BY TAKING THE REACTOR CRITICAL AND VERIFYING LOW POWER REACTOR PHYSICS PREDICTIONS.

STATUS s

1. SCHEDULE

2. PERSONNEL i

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8/12/87 - JRB 9

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ANNUNCIATOR STATUS DESCRIPTION OF PROBLEM:

CONCERNS IDENTIFlED REGARD lNG NUMEROUS INVALID (BOGUS)

CONTROL ROOM ANNUNCIATORS l

l CORRECTIVE ACTIONS:

COMP'UTERIZED LISTING TO TRACK ACTIONS TO RESOLVE ANNUNC!ATOR PROBLEMS DEDICATED OPERATIONS ENGINEER TO CENTRAL!ZE ENGINEERING RESOLUT1ONS TO ANNUNCIATOR PROBLEMS DEDICATED WORK CONTROL FOR EACH UldT 9

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