ML20147E898

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Summary of Operating Reactors Events Meeting 88-006 on 880209
ML20147E898
Person / Time
Site: Catawba, Vogtle, 05000000
Issue date: 02/26/1988
From: Lanning W
Office of Nuclear Reactor Regulation
To: Rossi C
Office of Nuclear Reactor Regulation
References
OREM-88-006, OREM-88-6, NUDOCS 8803070181
Download: ML20147E898 (12)


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' MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation FROM: Wayne Lanning, Chief '

Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING February 9, 1988 - MEETING 88-06 On February 9, 1988 an Operating Reactors Events meeting (88-06) was held to brief senior managers from NRR, RES, AE0D and Regional Offices on events which occurred since our last meeting on February 2, 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. The Enclosure 3 presents a tabulation of long-term followup ,

assignments to be completed and a sumary of reactor scrams. No significant events were identified for input to NRC's performance indicator program.  !

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Wayne Lanning, Chief ,

Events Assessment Branch '

Division of Operational Events Assessment 1 Office of Nuclear Reactor Regulation

Enclosures:

1 As stated i l

cc w/Enclo.:

See Next Page DISTRIBUTION -

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C. Norelius, RIII J. Callan, RIV D. Kirsch, RV S. Yarga D. Crutchfield B. Boger G. Lainas G. Holahan L. Shao J. Partlow B. Grimes F. Congel E. Weiss S. Black T. Martin J. Stone R. Hernan H. Bailey J. Guttmann A. Thadani l S. Rubin l 1

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FEB 2 s 1g89 MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation FROM: Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation l 1

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING l February 9, 1988 - MEETING 88-06 1

l On February 9,1988 an Operating Reactors Events meeting (88-06) was held to i brief senior managers from NRR, RES, AE00 and Regional Offices on events which I occurred since our last meeting on February 2, 1988. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of tMse events are presented in Enclosure 2. The Enclosure 3 presents a tabulation of long-term followup assignments to be completed and a sumary of reactor scrams. No significant events were identified for input to NRC's performance indicator program.

I e anning, Chie Ev ts Assessment ranch Division of Operational Events Assessment Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/Enclo.:

See Next Page

b ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (88-06)

February 9, 1988 NAME ORGANIZATION NAME ORGANIZATION W. Lanning NRR/00EA J. Mauck NRR/SICB R. Lobel NRR/DOEA V. Thomas NRR/ICSB P. Baranowsky NRR/00EA T. Silko AE00 E. Rossi NRR/D0EA J. Stoltz NRR/PDI-4 M. Malloy- OSP/CPPD G. Holahan NRR/DRSP M.L. Reardon N?R/00EA P.S. Tam NRR/DRP F.R.Orr NRR/DRP L.B. Marsh NRR/ DEST R.A. Capra NRR/PDI-I R.W. Woodruff _NRR/D0EA G. Hamer NRR/ DEST C. Schulten NRR/DOEA J. Partlow NRR/DRIS K. Eccleston NRR/DRPI-II J. Thompson NRR/00EA E. Murphy NRR/ENTB K. Jabbour NRR/PD II-III M. Williams AEOD/TPAB W. Troskoski OED0

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e ' ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 88-06 TUESDAY, FEBRUARY- 9, 1988, 11:00 A.M.

THIS INFORMATION MAY ALSO BE OBTAINED BY DIALING EXTENSION 21161.

V0GTLE 1 GATE VALVE PRESSURE LOCKING PROBLEMS CATAWBA 2 FOREIGN OBJECTS IN STEAh GENERATOR CALVERT CLIFFS 2 LOSS OF ANNllNCIATORS DUE TO FIRE (TELECON)

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V0GTLE UNIT 1 GATE VALVE PRESSURE LOCKING PROBLEMS l FEBRUARY 3, 1988 PROBLEM BOTH RHR CROSS-CONNECT TIE VALVES FAILED TO OPEN DURING SURVEILLANCE TESTING.

CAUSE THE VALVES FAILED DUE TO PRESSURE LOCKING OF THE VALVE DISKS BY THERMAL EXPANSION OF WATER TRAPPED BETWEEN THE DISKS.

SIGNIFICANCE DOUBLE DISK WEDGE-TYPE GATE VALVES ARE USED EXTENSIVELY THROUGHOUT SAFETY RELATED SYSTEMS AND MAY BE REQUIRED TO OPEN DURING OR FOLLOWING DESIGN BASIS EVENTS.

DISCUSSION o FEBRUARY 3, 1988 - TWO RHR CROSS-CONNECT VALVES FAILED TO OPEN DUE TO PRESSURE LOCKING 0F THE VALVE DISKS, THE MOTOR OPERATORS BURNED-UP WHILE ATTEMPTING TO OPEN THE VALVES DURING SURVEILLANCE TESTING.

o THIS PROBLEM IDENTIFIED IN 1977 BY NRC IE CIRCULAR 77-05, "LIQUID ENTRAPMENT IN VALVE BONNETS."

o 1981, IE INFORMATION NOTICE 81-31, "FAILURE OF SI VALVES TO OPERATE AGAINST DIFFERENTIAL PRESSURE."

o 1981, GE SIL LETTER #368, "RECIRCULATION DISCHARGE ISOLATION VALVE LOCKING." i o 1983, INP0 FOREIGN REACTOR EXPERIENCE REPORT, "FAILURE OF RHR SUCTION VALVES." NO SUGGESTED PECOMMENDATIONS TO ADDRESS DOMESTIC PROBLEMS.

o JULY 1984, AE0D REPORT ON PRESSURE LOCKING OF FLEXIBLE DISK WEDGE- l TYPE GATE VALVES. I o AE0D AND IE AGREED TO ALLOW INP0 TO ADDRESS THIS PROBLEM. j o DECEMBER 1984, INP0 REPORT (SOER 84-07) ON PRESSURE LOCKING OF l FLEXIBLE DISK WEDGE-TYPE GATE VALVES.

CONTACT: J. THOMPSON

REFERENCE:

50.72# 11404

7 o INP0 SOER 84-7 DID NOT ADDRESS NORMALLY OPEN VALVES WHICH CLOSE AND CANNOT BE RE0PENED.

o THIS PROBLEM APPEARS TO BE LIMITED TO VALVES SUBJECTED TO PRESSilRE/ TEMPERATURE CHANGES (E.G., RHR (PWR/BWR).

FOLLOWUP o INP0 TEAM DISPATCHED TO V0GTLE SITE FOR EVENT ASSESSMENT AND TO GATHER NEW INFORMATION FOR ISSUANCE OF A SUPPLEMENT TO THE 1984 INP0 SOER.

o LICENSEE PERFORMING SAFETY ANALYSIS TO DETERMINE OTHER AFFECTED VALVES.

o V0GTLE MODIFICATION TO THE RHR VALVES WILL BE TO DRILL A PRESSURE RELIEF H0LE IN VALVE DISK ON THE DOWNSTREAM SIDE.

o EAB CONSIDERING INFORMATION NOTICE ON V0GTLE VALVE FAILURES DEPENDING ON THE ADEQUACY OF THE UPDATED INP0 SOER.

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, CATAWBA 2 FOREIGN OBJECTS IN STEAM-GENERATOR JANUARY 22, 1988

. PROBLEM DEBRIS FOUND ON THE SECONDARY SIDE OF STEAM GENERATORS HAS APPARENTLY CAUSED TUBE THINNING.

CAUSE INADEQUATE QA.

SIGNIFICANCE o POTENTIAL FOR TUBE FAILURES.

o BREAKDOWN IN QA APPARENTLY AT WESTINGHOUSE AND DUKE.

DISCUSSION o DURING 8/87, EDDY CURRENT (EC) TESTING OF SGs A AND D INDICATED NO AN0MALIES.

O DURING 12/87, EC TESTING OF SGs B AND C DISCLOSED WORN TUBE IN SG B.

o VISUAL INSPECTION DISCLOSED PRESENCE OF 3 JACKING STUDS (2-3" LONG BY 2-1/4" IN DIAMETER) ON TUBE SHEET BETWEEN TUBE WRAPPER AND BUNDLE.

o STUDS WERE APPARENTLY EXTRAS INADVERTENTLY LEFT IN SGs DURING FABRICATION.

o SUBSEQUENTLY, VISUAL INSPECTION OF SGs A AND D DISCLOSED THE PRESENCE OF A CARBON STEEL BLOCK (1-1/2" X 2" X 3") AND A SEMICIRCULAR SLIVER OF STEEL 8" X 3/8" THICK.

o IN SGs A AND D, PLUGGING OF 1 TUBE EACH WAS REQUIRED BECAUSE OF TUBE WALL WEAR.

o ADDITIONAL DEBRIS FOUND INCLUDES SMALL GAUGE WIRE, 1 NAIL, A PIECE OF WELD ROD, WELD SLAG, AND ROCKS.

O SOME OF THE METAL PIECES FOUND ARE BELIEVED TO BE FIT-UP PIECES.

o PREVIOUS EC TEST DATA WERE REVIEWED FOR SGs A AND D AND A BAD TUBE WAS IDENTIFIED.

o EC TESTING OF 100% OF PERIPHERAL TUBES IN SGs A AND D WAS PERFCRMED.

FOLLOWUP o LICENSEE AND WESTINGHOUSE ARE DETERMINING CAUSE.

o OEAB INTENDS TO DRAFT AN INFORMATION NOTICE, o OEAB WILL REQUEST STATUS OF UNIT 1 SGs, CONTACT: R. WOODRUFF

REFERENCE:

50.72# 11407

ENCLOSURE .'

LONGTERM FOLLOWUP ASSIGNMENTS TO BE COMPLETED LONGTERM FOLLOWUPS OUTSTANDING ORGANIZATION 01/19/88 01/26/88 02/02/88 02/09/88 AE0D 2 2 0 0 EAB 1 1 2 2 l EMTB 1 1 0 0 -

ESGB 2 1 1 1 ICSB 3 2 2 2 OGCB 3 2 1 1 OSP 2 2 0 0 OTSB 2 2 2 1 PD2-2 1 1 1 1 PD2-3 1 1 1 1 .

PD3-2 1 1 1 1 PDS 0 2 2 2 RIII O O O O t RVIB 4 4 4 4 SELB 5 5 5 5 ,

SPLB 6 6 5 5 SRXB 2 2 2 2  ;

TOTAL 36 35 29 28

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' REACTOR SCRA",t e?ARY WEEK ENDINS 02/07/88

1. PLANT SPECIFIC D/TA IATE SITE UNIT F0hER 5154AL Cli)SE CSPFLI- YTD YTD YTD CAT!2NS APOVE SELCW TOTAL 151 151 M/02/53 !!6 F;CK P31NT I 0A FERSONNEL h3 0 1 1 02/02/91 1%31aN PDI%T 3 100 M EQUlFP.ENT ND 1 0 1 01/04/E3 h%P 2 100 A fen 5ChNEL %0 1 0 1 02/05/E3 !!6 ROCK PO!hi  ! 10 M U%tM3W1 NO O 2 2 02/05/23 31NNA 1 0A EG' JIFF.ENT N3 0 1 1 I

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1. PLANT SPECIFIC OATA SASEC Ch INITIAL REVIEll 0F 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SLf;0AY THROUGH MIDNIGHT: SUt'OAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R00 MOTION AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTOOWN IN ACCORDANCE WITH A PLANT PROCECURE. THERE ARE 109 REACTORS HOLDING AN OPERATING LICENSE.
2. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UhRELATED TO CAUSE OF SCRAM.
3. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR. PROCEDURAL DEFICIENCIES. AND MANUAL STEAM GENERATOR LEVEL CONTROL i PROBLEMS.
4. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING). SYSTEM DESIGN, OR UNKNOWN CAUSE.

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