ML20207A522

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Summary of Operating Reactors Event Meeting 87-13 on 870507 Re Events Which Occurred Since 870428.List of Attendees, Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20207A522
Person / Time
Site: Calvert Cliffs, Dresden, Perry, Oyster Creek, Byron, Arkansas Nuclear, Vogtle, Zion, 05000000
Issue date: 05/15/1987
From: Lanning W
Office of Nuclear Reactor Regulation
To: Rossi C
Office of Nuclear Reactor Regulation
References
IEB-82-02, IEB-82-2, IEIN-86-108, OREM-87-013, OREM-87-13, NUDOCS 8705280190
Download: ML20207A522 (13)
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3AY 15 IW7 MEMORANDUM FOR:. Charles E. Rossi', Director-Division of Operational Events Assessment

FROM: Wayne Lanning, Acting Chief

. Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

OPERATING REACTORS EVENTS MEETING i- ON MAY 5, 1987 - MEETING 87-13 l 'On May 5,1987, an Operating Reactors Events meeting (87-13) was held to brief senior managers from NRR, RES, AEOD and Regional Offices on events-which occurred since our last meeting on April 28. The list of attendees is included as Enclosure 1.

The events discussed and the significar.t elements of these events are presented in Enclosure 2. Enclosure 3 provides a _ sumary of those presented events that will be input to NRC's perfomance indicator program as significant events.

Original Signed by Wayno D. Lazuaing Wayne Lanning, Acting Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

See Next Page i

DISTRIBUTION GentrahFile }

NRC PDR EAB Rdg Oudinot Rdg w/o Enclosure EAB Members.

(SEE ATTACHED FOR PREVIOUS CONCURRENCES *)

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PEMORANDUM FOR:

s Charles- E. Rossi, Director'

, 3 N Division of Operat.ional Events Assessment FROM: \- Wayne Lanning.- Acting Chief.

\ Events AssessmenttBranch'-

. \ Division of Operational Eyents Assessment ,

SUBJECT:

SUMARY OF THE OPERATING REACTORS EVENTS -

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MEETING'ON MAY 5,1987 - MEETING 8713 -

On.May 5,1987, an Operating Reactors Events meeting (8h-13) was' held to-

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, brief senior managers _ from NRR, RES, AE00.and Regional. 0ffices.on events -

which occurred since our last meeting on April 28 tThe list of attendees

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=is included as' Enclosure 1. . ,

TheeventsdiscussedaNdthesignificantelemen'tsof$theseev'entsa' represented in Enclosure 2. Enclosure 3- provides a summary of those presented events' that .

will be input to NRC's performance indicator program as significant events..

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\ Original Signed by Wepe D. Lanning

'\

' ,i Wayne Lanning, Acting Chief Events Assessment Branch

-\- Division of Operational 1dvents Assessment

Enclosures:

As stated ,

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Those Listed MAY 1519r7 cc: T. Murley L.J. Cunningham l J. Sniezek J. Wigginton R. Starostecki J. Calvo J. Taylor R. Lee E. Jordan S. McNeil E. Beckjord R. Capra W. Russell, Reg. I J. Nelson Grace, Reg. II B. Davis, Reg. III R. D. Martin, Reg. IV J. B. Martin, Reg. V W. Kane, Reg. I L. Reyes,-Reg. II C. Norelius, Reg. III -

E. Johnson, Reg. IV D. Kirsch, Reg. V l

S. Varga D. Crutchfield B. Boger G. Lainas

G. Holahen F. Schroeder L. Shao l J. Partlow B. Grimes F. Congel

. H. Miller E. Weiss S. Black T. Martin, EDO F. Miraglia E. Merschoff J. Guttmann l

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' ENCLOSURE 1 FIST OF ATTENDEES OPERATING PEACTORS~ EVENTS BRIEFING (87-13)

MAY 5, 1987 NAME DIVISION NAME DIVISION J. Sniezek NRR N. Fields NRR E. Rossi NRR S. Black NRR W. Lanning NRR R. Scholl NRR E. Weiss AE00 S. Mackay NRR -

R. Lobel NRR P. Polk NRR S. Rubin AE0D R. Baer RES C. Miller NRR J. Richardson NRR S. Nelsen ORNL R. Hernan NRR G. Murphy ORNL W. Haass NRR L. Cunningham NRR T. Chan NRR

' J. Heltemes AEOD D. Crutchfield NRR

.. G. Lainas NPR A. Thadani NRR J. Calvo NRR T. Speis RES l J. Clifford NRR S. Varga -NRR-B. Troskoski EDO -J. Amenta IRM I F. Schroeder NRR J. Partlow NRR D. Brinkman NRR P. Baranowsky NRR 4

C. Schulten NRR R. Lee NRR H. Miller NRR B. Boger NRR

"' R. Woodruff NRR l

i

ENCLOSURE 2

.MAY 5, 1987 '

APKANSAS 2 - LEAK AT PRESSilR12ER HEATER PENETRATION PPOPLEM: ON 4/24/87 AT 100% POWER, A NON-ISOLABLE LEAK WAS F0lTD AT THE BOTTOM OF THE PRESSilRIZER CAUSE: THE CAUSE OF LEAKAGE HAS FOT BEEN IDENTIFIED SIGNTFICANCE: BORIC ACID CORROSION OF CARBON STEEL COMPONENTS IN REACTOR COOLANT SYSTEMS DISCUSSION:

BECAUSE OF LOSS OF LEVEL IN SIT, LICENSEE ENTERED CONTAINMENT TO INSPECT S!T AND SURVEY OTHER AREAS A LEAK 0F 1 DROP /SEC WAS FOUND AT HEATER PENETRATION AND THE IINIT-WAS SHUT DOWN PER TECH SPEC INSPECTION REVEALED A PIT 1-1/2 INCHES IN DIAMETER AND 1/? TO 3/4 INCH DEEP NEAR THE PENETRATION CONFIGURATION OF HEATER PENETRATIONS IS SHOWN IN ATTACHED PI AGRAM TWO HEATERS INSTALLED IN 1982 HAVE FAILED, LEAVING A STUB 0F 8-30INCHESPP0JECTINGABOVEBOTTOMUFPRESSURIZER COLOR PHOTOGRAPHS OF THE DAMAGE ARE AVAILABLE . .

CORROSIVE ATTACK HAS OCCURRED AT CALVERT CLIFFS 2,~ ARKANSAS 1, AND TURKEY POINT 4

BULLETIN 82-02 AND INFORMATION NOTICE 86-108 AND SUPPLEMENT 1 TO THAT NOTICE HAVE BEEN ISSUED THE BULLETIN STATES THAT WASTAGE DUE TO CORROSIVE ATTACK BY P0RIC ACID CAN EXCEED 1 INCH / YEAR l CE AND B&W RCS HOT LEGS AND COLD LEGS ARE FABPICATED FROM CARBON STEEL AND ARE CLAD ON THE INNER SURFACE WITH STAINLESS STEEL ASME CODE, SECTION XI, 1983, RE0lllRES VISUAL EXAMINATION OF SYSTEMS CONTAINING B0 RATED WATER DtlRING INSERVICE INSPECTIONS FOLLOWUP

EAD IS DRAFTING SUPPLEMENT 2 TO INF0PMAT10N NOTICE.,

EAR EXPFCTS TO TRANSFER EVENT TO CEE i

CONTACT: P0GER WOODRUFF

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MAY 5, 1987 OYSTEP CREEK - DEGRADED CONTA!PMENT INTEGPITY PP0ELEM: OPERATORS MANUALLY BLOCKED OPEN CONTAINMENT VACUllM BPEAKERS TO AlD DEINERTING PROCESS DURING PLANT SFl!TDOWN CAllSE: (1) COGNITIVE EPROR BY SR0 AND STA 4

4 (2) POSSIBLY ALSO: - INADEQUATE PROCEDURES

- INADEQUATE SAFETY REVIEW '

- PROCEDURE VIOLATIONS STFMIFICANCE: - LOSS OF CONTAINMENT INTEGRITY AND/0P CONTAINMENT OVERPPESSURIZATION IN EVENT OF LOCA t

DISCUSSION:

PLAMT VAS SHUTTING DOWN APRIL 23-24; DEINERTING CONTAINFENT i

ABOUT 10:00 PM, 4/23 ONE REACTOR BUILDING-TO-TOPl!S VACUUM' BREAKER i -

BLOCKED OPEN--CONTINUOUSLY ATTENDED PER LONG-STANDING LICENSEE

!' PROCEDURES ABOUT-3:30 AM, 4/24, SHIFT SUPERVISOR PROCESSED TEMP 0F.APY MOD TO BLOCK OPEN TWO DRYWELL-TO-TORUS VACUUM BPEAKERS WITH PLAFT ABOUT 5% POWER, ABOUT 7:15 AM, DRYWELL-TO-TORUS VACilllM BREAKERS RESTOPED WHEN ONCOMING OPERATIONS STAFF ENGINFEP. NOTED PROBLEM-FOLLOWUP:

LICENSEE IHITT ATED INVESTIGATION AND CPIT!0UE ON-SITE NRC C0FDUCTING SPECIAL INSPECTION AND EVALUATING NFED FOR ADDITIONAL ACTIONS LICENSEE HAS SET UP A SPECIAL COMMITTEE, INDEPEND,ENT OF SITE PEPSONNEL, TO REVIEW THIS EVENT 1

i CONTACT:

R. BLOUGH, DPP, RI t

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CALVERT CLIFFS 1 R ? - BREAVDOWN OF MATERTAL COPTPOL PROBLEM: USE OF COMMERCIAL GRADE MATERIAL IN ANSI B3] 7 PIPING SYSTEMS CAUSE: THE DA PROGRAM WAS REVISED TO ALLnW USE OF COMMERCIAL. GRADE MATERIAL UNDER CEPTAIN CONDITIONS IN OTHER SAFETY-PELATED APPLICATIONS BUT FAILED TO PROVIDE FOR ADEQUATE SEGREGATION OF B3] 7 MATERIAL i S!GNIFICANCE: BREAKDOWN OF QA MANAGEMENT DISCUSSION: QA PP0 GRAM WAS REVISED 5 OR 6 YEAPS AG0 PROBLEM WAS DISCOVERED APOUT 2 WEEKS AG0 DURING IMPLEMENTATION OF A LATER VERSION OF SECTION XI 0F THE ASME CODE INSTALLED MATERIAL INCLUDES FDLTS, NUTS, PIPE, CAPE, ETC, THIS MATERI AL HAS BEEN INSTALLED IN CLASS 1, II, AND III SYSTEMS FOR UNIT 1, 22,000 MAINTENANCE ORDERS HAVE PEEN SCREENED BY COMPUTER FOR CLASS I AND 11 SYSTEMS TO IDENTIFY THOSE WRITTEN FOR PRESSURE RETAINING COMPONENTS 

 .          4100 HAVE BEEN IDENTIFIED FOR FURTHER REVIEW OF 1300 MAINTENANCE ORDERS REVIEWED, 27 IIAD IDENTIFIED PROBLEMS AND 120 HAD QUESTIONABLE ITEMS DEFTCIENCIES INCLUDE LACK OF MARKIFC, CERTIFICATION, AND NONDESTRUCTIVE EXAMINATION OF PUFCHASED MATERIAL E0TH UNITS WILL REMAIN SHUTDOWN PENDING RESOLUTION FnLLOWUP:

THERE IS A MEETING OF NPR, REGION, AMD LICENSEE THE REGION IS SENDING A RESTART TEAM TO THF S?TE TiiE PM WILL MANAGE REVIEW OF APPLICATIONS FOR EXEMPTIONS FROM 10CFR50,55A, CODES AND STANDARDS CONTACT: ROGER WOODRUFF - _4 

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REASTDR SCRA?. SL?TJEY , WEEK EN31NS C5/03/97 

                                   *-              1. PLANT $FECIFIC CATA                                       b l

1:TE SITE UWli POWER RPS CAL'5E CCP.PL1- YTD YTD TTD CA110NS AID"E IELOW TOTAL 

                                                                                 !!I 11 C4/27/E7IVEON           2     E9 A EE'JIPMENT           R3          2     3      5 04/29/E7VCETLE           1    75 A EGUlPEENT            N3          4     6     10 Ct/30/37!!ts             1      0A Uhr.N0kW             W3          0     1      1 05/01/E7 FIE?.Y          1    53 R EEU1F/EICH.          N3          2     2      4 C5/C2/E7 3YEDN           1      0A EG'JIP/EL!ti.        h3          0     1      1 05/02/B7iMI-             0    93 A FEESchNEL            N3          1     0       1 C:/03/E7IEEEIEN         2     31 A PERSDNNEL            k3          1     0       1 05/04/87 EYROM           2    E9 A EE'JIP/ ELECT        W3          3     3      6 1

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II. COMPARISON OF WEEKLY STATISTICS WITH INDUST SCRAMS FOR WEEK ENDING

  • 05/03/87 ,

i-i- 1 NUMBER .1987 1986 1985 SCRAM CAUSE POWER WEEKLY OF WEEKLY WEEKLY SCR AMS (5) AVERAGE AVERAGE AVERAGE YTD (3) (4 ) lE) (9) i ( **' POWER 15% 4; E.4 

                                             '15%              4           0.7

[ EOJ1P. RELATED 2 1.7 1.9 2.0 l PERE. RELATEDt6) 415% 0 1.2 0.4 0.6 

           ,             OTHER(7)           >15%
                       ** Suttetal #4                                      6.6         6.5         E.O 6
                       ** POWER <15%                                       1.1          1.4        1.3
                                             <25%               1 ECUIP. RELATED                                    0.9          0.9        0, 9-PERS. RELATED       <15%               0 0.4          0.2        0.2 OTHER               <15%                1
                        ** Subtetal 1*                                     2.4          2.4        2.4        ,

2 I 1vs Total *** 9.0 E.9 10.4 8 1 k MANUAL VS AUTO, SCRAMS NUMBER 1987 .1986 1935 

   /*.                    TYPE                                          WEEKLY     WEEKLY      WEEKLY OF SCRAMS       AVERAGE AVERAGE AVERAGE YTD 1          1.5        1.0         1.0 MANUAL SCRAMS                                     7.6         7.9        0.4 AUTOMATIC ECRAMS                        7 e

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1. PdNT SPECIFIC DATA BASED ON INITIAL RENdLDF 50.72 REPORTS
                ,                   FOR THE WEEK OF[ INTEREST. PERIOD IS MIDN[GHT SUNDAY THROUGH

( MIDNIGHT SLEAi SCRAMS ARE PFFINED f 5 REACTOR PROTECTIVE s ACTUAT10NS V8ICP PESULT IN ROD MOTION, AND EXCLUDE PLANNED ' t TESTS DR SCRIN.S AS PART OF PLANNED'SHbTDOWN IN ACCORCANCE 

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2. RECOVERY COMPLICATED BY EQUIPMENT FAILU3ES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM. e
3. 19P6 INFORMATION DERIVED FROM ORAhSTUDY OF UNyLANNED REACTOR TRIPS IN 1986. . WEEKLY DFA DETERNINED BY TAKING TOTAL TRIPS ,

[ 7N A GIVEN CATEGORY AND DIVIDING SY 'Sd WEEKS / YEAR.

4. 'IN 1986, THERE WERE AN ESTIMATED TOTAL OF 461 NUTOMATIC SND MA5UA5.dHPLANNEDREACTORTRIPSAT104 REACTORS (HOLDING
            ,                       OPERATINGLICENSES). THIS YIELDS AN AVEPJGE RATE OF 4.4 TRIPS
            \                       PER REACTOR PER YEAR AND'AN AVEF3.GE RATE DI8.8 TRIPS PEIKEEK y

FOR ALL REACTORS. 

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5 '. BASED ON 107 REACTORS HOLDING AN OPERATING LICENSE. / 9

6. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL
 ,                                  DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

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7. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONFEt:TAL
                            , CAUSES (LIGHTNING)4 SYSTEM DESIGN, OR UNKNOWN CAUSE.

( , i 1 P. 3985 INFORMATION DEPIYED FROM AN ORAS STUDY OF l'NPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN I CATEGORY AND DIVIDING BY 57 WEEKS / YEAR. 

                               .                                                                                                                       i 9 .*             IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL.                                               !
                                                                                                                      ~

UNPLkNNED REACTOR TRIPS AT 93 REACTORS (FDLDING FULL POWER LICEtlSES). THIS YIELDS AN AVEPAGE RATE OF 5.8 TRIPS PER REACTOR YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOP ALL REACTORS. . l

ENCLOSURE 3 1 r E!Esi~!Ct.C EVEP.TE FFIE'.EO E:~;W':.~E IC ':~ N:. l 6;

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