ML20196B982

Summary of Operating Reactors Events Meeting 88-47 on 881129.List of Attendees,Events Discussed & Significant Elements of Events,Two Events Suggested for long-term Followup & Summary of Reactor Scrams Encl

ML20196B982
Person / Time
Site:	Dresden, Nine Mile Point, 05000000
Issue date:	12/01/1988
From:	Lanning W Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
GL-88-15, OREM-88-047, OREM-88-47, NUDOCS 8812070119
Download: ML20196B982 (14)

Text

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DEC 91 M MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment .

FROM: Wayne D. Lanning, Chief Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

THE OPERATIND REACTORS EVENTS MEETING November 29, 1988 - MEETING 88-47 C '.ovember 29, 1988, an Operating Reactors Events meeting (88-47) was held to brief senior managers from NRR, AE00, OSP, Commission Staff, and Regional Officos on events which occurred since our last meeting on November 22, 1986.

The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 presents two events suggested for long-term followup and a sumary of reactor scrams. One significant event was identified for input to NRC's performance indicator program.

Wayne D. Lanning, Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As ste.ted cc w/ Encl.:

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DATE :11/ 74/88 :1D

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1 cc: L T. Murley, 12G-18 B. Siegel, 130-1 F. Miraglia, 12G-18 D. Muller, 13D-1 J. Sniezek, 12G-18 M. Haughey, 148-2 E. Jordan, AE00 R. Capra, 148-2 I J. Taylor, 17G-13 E. Beckjord, NL-007 W. Russell, RI  :

M. Ernst, RII B. Davis, RI!! ,

R. D, Martin, RIV l J. 3. Martin, RV W. Kane, RI  :

L. Reyes, RI! . ,

E. Greenman, RI!!

L. Callan, RIV D. Kirsch, RV f S. Varga, 14E-4 t D. Crutchfield, 13A-2 i B. Boger, 14A-2  !

G. Lainas, 14H-3 G. H91ahan, 138-4 L. Shao, 8E-2 <

J. Partlow, 70-24 [

B. Grimes, 9A-2 F. Congel, 10E-4  !

E. Weiss, AE00  !

T. Martin, EDO J. Guttmann, SECY A. Thadani, 7E-4 S. Rubin, AE00 i J. Forsyth, INP0 '

R. Barrett, 10E-2  ;

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DEC 011El MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Wayne D. Lanning, Chief Events Assessment Branch ,

Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING November 29, 1988 - MEETING 88-47 On November 29, 1988, an Operating Reactors Events meeting (88-47) was held to brief senior managers from NRR, AE00, OSP, Commission Staff, and Regional Offices on events which occurred since our last meeting on November 22, 1988.

The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 presents two events suggested for long-term followup and c summiry of reactor scrams. One significant event was identified for input to NRC's performance indicator program.

& MYY Wayne D. Lanning, h ef Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated  ;

cc w/ Encl.:

See Next Page I

1

. l ENCLOSURE 1 l

LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (88-47)

November 29, 1988 NAME ORGANIZATION NAME ORGANIZATION t T. Murley D:NRR U. Potapovs NRR/RVIB i L. Zerr NRR/DOEA F. Rosa NRR/SELB >

J. Lazevnick NRR/SELB S. Juergens SECY  !

4-M. Fields OSP R. Kendall NRR/DOEA ,

, J. Kudrick NRR/SPLB J. Carter NRR/D0EA .

] R. Karsch NRR/DOEA R. Borchardt OEDO

• L. Norrholm OCM/KC H. Faulkner IP/GPA i

V. Benaroya AEOD/OSP M. Haughey NRR/DRPI-2

, G. West, Jr. NRR/HFAB C. Haughney NRR/DRIS  ;

M. Reardon NRR/DOEA B. Boger NRR/ADR-1 E. Rossi NRR/DOEA J. Roe NRR/DLPQ ,

B. Grimes NRR/DRIS T. Gwynn OCM/LZ B. Siegel NRR/PD3-2 J. Dyer NRR/DRIS d

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9 ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 88-47 EVENTS ASSESSMENT BRANCH LOCATION: 12-B-11 WHITE FLINT TUESDAY, NOVEMBER 29, 1988, 11:00 A.M.

NINE MILE POINT 1 DEGRADED VOLTAGE IN 125 VOLTAGE DC SYSTEM DRESDEN UNIT 2 DAMAGE TO SAFETY-RELATED EQU:? MENT DUE TO ELEVATED DRYWELL TEMPERATURES

.- 88 47 NINE MILE POINT 1 DEGRADED VOLTAGE IN 125 VOLTAGE DC SYSTEM NOVEMBER 18, 1988 PROBLEb THE 125 V0LTAGE DC (VDC) SYSTEMS DO NOT MEET THEIR DESIGN BASIS, E.G..

INSUFFICIENT VOLTAGE SUPPLIED TO POWER BOARDS TO ALLOW BREAKER OPERATION.

ChiLSE DESIGk DEFICIEliCY: EXCESSIVE VOLTAGE DROP If1 CABLES SAFETY SIGlilFICANCE l A LOSS OF NORMAL AC POWER COULD LEAD TO A COMPLETE LOSS OF DC POWER Afl0 THE SUBSECUENT LOSS OF EMERGEllCY AC POWER.  !

I DISCUSSION l

l 0 REACTOR SHUTDOWN SitiCE 12/57 AND CURRENTLY DEFUELED.

0 PROBLEM DISCOVERED DURING REDESIGN EFFORT.

o BATTERIES CONSIDEREL OPERABLE (PER TECHNICAL SPECIFICATIONS) WITH BATTERY TERMINAL VOLTAGE GREATER THAN 106 VDC.

o 114 VDC AT BATTERY TERhlNALS, REQUIRED TO MEET MANUFACTURER's MINIMUM OF 90 VDC AT BATTERY BOARD FOR BREAKER GPERATION.

o WITH 114 VDC, BATTERY CHARGERS MAY NOT SWITCH 10 EMERGENCY AC POWER, CAUSING BATTERY TO RUN DCWN AND TRIP EDG PROTECTIVE RELAYS, o LICEllSEE DGES NOT PERFORM AN 18 MONTH SERVICE TEST.

0 LICENSEE L0ES liOT KNOW/HAVE DESIGN BASIS OR ORIGINAL TESTING DATA.

l l o NIAGARA M0 HAWK WAS SYSTEM DESIGNER.

i o LICENSEE PLANNED TO DOCUMENT REVISED DESIGli BASIS FOR Ti1ElR RECORDS.

o LICENSEE WILL SUBMIT BASIS FOR NRR REVIEW, o GENERIC LETTER (GL) 68-15 "ELECTRIC POWEk SYSTEMS - INADE00 ATE C0hTROL OVER DESIGN PROCESS" ENVELOPES THIS EVENT, LICENSEE HAS GL.

FOLLOWUE o REGION T0 lilSPECT MODIFICATIONS, o NRR TO REVIEW REVISED DESIGN AND BASIS, CONTACT: J. CARTER

REFERENCE:

50.72 # 14039 AtlD MORllikG REPORT 11/22/88

88-47 i

DRESDEN UNIT 2 DAMAGE TO SAFETY-RELATED EQUIPMENT DUE_ID ElfVATED DRYWELL TEMPERATURES NOVEMBER 15, 1988 t

EB03LES SAFETY-RELATED EQUIF.EliT DEGRADED DUE TO HIGH TEMPERATURE IN UPPER REGION OF DRYWELL.

thDBE INADECUATE VEllTILAT10N.

SAEEIY SIGNIFICAufE DEGRADATION OF SAFETY-RELATED EO EQUIPMEllT AND ELECTRICAL WlRING.

DISCUSSJdB c DURING THE REFUELING OUTAGE, LICENSEE DISCOVERED EVIDEflCE THAT THE PAINT IN ThE DRYWELL WAS EXPOSED TO ELEVATED TEMPERATURES.  ;

o FURTHER IfiVESTIGATION REVEALED THE LIMITORQUE OPERATOR Off THE i STEAM SUPPLY VALVES TO THE HPCI AND ISOLATION CONDEllSER HAD EVIDENCE '

OF EXCEEDIliG THE E0 DF. SIGN TEMPERATURE (DEGRADED GREASE AND DAMAGE TO OllE DEARING), ALSO THERE WAS SOME CRACKING OF CABLE INSULATION.

o MAJOR DAMAGE RESTRICTED TO LEVEL 4 WITH MINOR DAMAGE TO CABLE SEAL TIGHT JACKETS Oli LEVEL 3. l 0 ELEVATED TEMPERATURE RESULTED FROM FOUR VEllTILATION PORTS (2 SUPPLY l AND 2 RETURil) EEING LEFi I!1 CLOSED POSIT 10!! SINCE APRIL 19. 1987. l BOTH fiANWAY HATCHES WERE OPEll, i 0 MAINTEflANCE PROCEDURE HAD WORDS THAT SAID "HATCHS ARE OPEN". PERSONNEL ,

THOUGHT THAT HATCH REFERRED TO THE LARGE MANWAY COVERS AND DIDil'T '

CHECK THE OPEN!!'GS Oft VEf4TILAT10N DUCTS, o HPCI AND ISOLATION CONDENSER VALVES DO NOT NEED TO OPEfi IN CASE OF A LOCA (THEY ARE h0RMALLY OPEN). HOWEVER, THEY D0 tiEED TO OPERATE ,

FOR CollTAINMENT ISOLATI0!i. ,

i C0 fit ACT: T. GREENE

REFERENCE:

MORf!!NG REPORT 11/15/88 s

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DRESDEN UtilT 2 88-47 o SURVEILLAfiCE TESTIliG PERFORMED WEEKLY AfiD MONTHLY FOR VALVES, o LICENSEE HAS FORMED A TASK FORCE, o LICEf1SEE PLANS TO REPLACE ALL CABLES IN LEVEL 3 AND 4.

o PAINT AND GREASE HAS BEEli SENT OUT TO BE ANALYZED.

o MARK I CONTAINMEliTS HAVE HISTORY OF HIGH DRYWELL TEMPERATURES, TEMPORARY IllSTRUCTION (T/I) 2515/98, "INFORMATION OF HIGH TEMPERATURE If. SIDE C0fiTAINMEfiT/DRYhELL IN PWR Al4D BWR PLANTS" WAS ISSUED ON 06/30/88, RESP 0fiSES TO T/I ARE SCHEDULED FOR MID-DECEMBER.

FOLLOWUP o LICEliSEE IS FREPARIf!G PROCEDURES TO CLARIFY THAT BOTH MANWAY AND VEliTILATION EUCTS ARE TO EE OPEN, o LICEfiSEE PLAfiS TO IfiSTALL TEMPERATURE DETECTORS If1 UPPER REG 10ft,

- 0 DOEA IS WORKING WITH SPLB TO DETERMINE IF Afi INFORMATION NOTICE OR

> OTHER STRONGER ACTION IS NECESSARY,

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. Page No.- 1 11/29/83 ..

PERFORMANCE INDICATORS SI6NIFICANT EVENTS

• PLCT NAME EVENT EVENTDESCA!Pil0N OTR S!6N!FICANCE DATE MC6UIRE 1 11/18/88 CROS! CONNECTS FRCM DIESEL STARTING AIR TO INSTRUMENT AIR 0POTENilALFORORACTUALDE6RADATION TANKS PA0 VIDE BACKUP A!R. HOWEVER, THIS COULD RESULT IN OF SAFEif-RELATED EQUIPRENT.

AN INADE00 ATE SUPPLY OF STARTING AIR DUR!h6 A BLAC100T.

MC6UIRE 2  !!/18/98 CROSS CONNECTS FROM O!ESEL STARi!NG AIR TO INSTRUMENT AIR 0 POTENTIAL FOR OR ACTUAL DEGRADAi!ON TANKS PROVIDE BACKUP A!R. NCWEVER, THIS COULD RESUt,T IN OF SAFETY RELATED EQUIPMENT.

AN INAIEDUATE SUPPLY OF STARTING AIR DURING A BLACK 0UT.

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6 REACTOR SCRAR

SUMMARY

NEEKEmelN611/27/M

!. PLANT SPEttFl DATA HIE S!it UNIT PONER 5!ENAL CAUSE COMPLI- YTD YTD YTD Call 0NS A80VE MLON TOTAL L

!$1 151 11/21/93 I!6 RCCK PO!NT 1 93 A EDU!PMENT NO 2 2 4 I

11/22/84 'ht!AN PJINT 2 100 A EDUlFMENT N0 3 1 4 11/23/88 CATANIA 2 48 M PERSONNEL NO I 1 9 11/23/98 COOK 1 90 A EOUIPMENT N0 3 0 3 11/26/06 thDIAN POINT 2 100 A EOUIPMENT N0 4 1 5 r 11/27/88 DRESHN 3 17 A E90!PMENT NO 1 0 1 ;

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NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL PEVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 109 REACTORS HOLDING AN OPERATING LICENSE.

2. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.

3. r RSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLE!!S.

4 "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.