ML20248K376

Summary of Operating Reactors Events Meeting 89-014 on 890405.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams for Wk Ending 890402 Encl

ML20248K376
Person / Time
Site:	Calvert Cliffs, Palo Verde, 05000000
Issue date:	04/10/1989
From:	Lanning W Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-89-014, OREM-89-14, NUDOCS 8904170316
Download: ML20248K376 (12)

Text

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APR 1.0139 )

l MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Wayne D. Lanning, Chief j Events' Assessment Branch ,

Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING i April 5, 1989 - MEETING 89-14 i

On April 5, 1989, an Operating Reactors Events meeting (89 14) was held to brief senior managers from NRR, RES, Comission Staff, and Regional Offices

- on events wM ch occurred since our last meeting on March 29, 1989. The list of attendees.is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. A summary of. reactor scrams for the week ending 04/02/89 is presented in Enclosure 3. No significant events were identified for input into the NRC performance indicator program. l Wayne D. t.anning, Chief Events Assessment Branch Division of Operational Events Assessment  !

Enclosures:

As stated cc w/ Encl.: i See Next Page i

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-  % .q, YlE APR10110 MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Wayne D. Lanning, Chief Events Assessment Branch Division of Operational Events Assessment SUEJECT: THE OPERATING PEACTORS EVENTS MEETING April 5, 1969 - MEETIliG 89-14 On April E, 1989, an Operating Reactors Events meeting (89-14) was held to l brief senior managers from NRR, RES, Commission Staff, and Regional Offices on events which occurred since our last meeting on March 29, 1989. The list ,

I of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. A summary cf reactor scrams for the week ending 04/02/89 is -

presented in Enclosure 3. No significant events were identified for input into the NRC performance indicator program.

Vayne D. Lanning, h ef Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated l cc w/ Encl.:

See Next Page l

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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (89-14)

April 5, 1989 NAME ORGANIZATION NAME ORGANIZATION E. Adensam NRR/DRP C. McCracken NRR/ECEB-R. Pedersen NRR/PRPB R. Capra NRR/PD1-1 B. Boger NRR/ADR-1 J. Cumins _NRR/DRIS S. Guthrie NRR/DRIS J. Guillen NRR/DOEA V. Thomas NRR/ DEST W. Lyon NRR/ DEST

5. Newberry NRR/ DEST ll. Balukjian NRR/ DEST C. Naughney. NRR/DRIS C. Rossi NRR/DOEA ,

W. Minners RES/DSIR B. Grimes NRR/DSIR -

J. Partlow. NRR/ADP P. Baranowsky NRR/00EA i R. Lobel NRR/00EA B. Clayton OEDO

11. Reardon NRR/D0EA i

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ENCLOSURE 2L OPERATING _ REACTORS EVENTS PRIEFING 89-14 i EVENTS ASSESSMENT' BRANCH LQCATION: 12E-11, WHITE FLINT

. WEDNESDAY, APRIL 5, 1989, 11:00 A.M. ,

CALVERT CLIFFS UNIT 1 SULFATE INTRUSION IN PRIMARY SYSTEM PALO VERDE UNIT 3 MID-LOOP OPERATION PROBLEM (VERBAL PRESENTATION, SLIDES NOT INCLUDED)

GENERIC ISSUE PART 21 - ROSEMOUNT TRANSMITTERS 1

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CAlVERT CLIFFS UNIT 1 SULFATE _lNTRDSION IN PRIMARY SYSTEM MARCH 29, 1989 PROELES HIGH SULFATE C0tlCENTRAT10N lt, REACTOR COOLANT SYSTEM.

CADSE UNCERTAIN. POSSIBLY FROM CHEMICAL VOLUME CONTROL SYSTEM 10N l

EXCHANGER RESIN.

SAEEIX SIDblElLABLE SULFATES MAY PROMOTE INTERGRANNULAR ATTACK OF INCONEL AT HOT CONDITIONS AND MAY AGGRAVATE FERROUS METAL CORROSION.

DlSEDSSIDS o CALVERT CLIFFS UNIT 1 EXPERIENCED SULFATE CONCENTRATION FLUCTUATIONS UP TO 18G6 PPE WHILE SHUTDOWN FROM MARCH 2 TO MARCH 29, 1989.

o EPRI GUIDELINES SUGGEST CONCENTRATE 0tl 0F.LESS THAN 100 PPB.

c ON MARCH 29, 1989, CALVERT CLIFFS UNIT I INITIATED SHUTDOWN FROM 60% POWER SHORTLY AFTER STARTINC UP, DUE TO INCREASING SULFATE CONCENTRATION.

o LICENSEE HAS CLEA!!ED PRIMARY BY RECIRCULATING REACTOR COOL THROUGH TWO 10N EXCHANGERS.

o ON APRIL 4, 1989, SULFATE CONCENTRATION WAS DOWN TO 39 PPB.

o iICENSEE PLANNING PHASEL HEATUP WITH A HOLD TIME AND CHEMI ANALYSIS AT EACH TEMPERATURE LEVEL.

0 EPRI WATER CHEMISTRY EXPERT AND CE OWNERS GROUP SPECIALIS ON SITE.

EDLLOWDP  !

NRC PROJECT MANAGER AND CHEMICAL ENGINEERING SPECIALIST ON S 4

SIGEVENT: _ND_

CONTACT: L. CUDINOT

REFERENCE:

MORNING REPORT 03/30/E9

89-14 i

LENERIC ISSUE f ELET 2] - ROSEMOUNT TRANSMITTERS EBDELEB MALFUNCTION OF ROSEMOUNT MODEL 1153 AND 1154 PRESSURE AND DIFFERENTIAL PRESSURE TRANSMITTERS.

i LADEL LOSS OF SILICONE OlL FROM THE TRANSMITTER'S SENSING CELL.

SAFETY SIGNIFICANCE lhAblLITY OF PRESSURE AND DIFFERENTIAL PRESSURE TRANSMITTERS TO PRGVIDE PROPER SIGNALS TO SAFETY-RELATED SYSTEMS SUCH AS REACTOR PROTECT!0N SYSTEM.

DISLUSSJ0E o MILLSTONE UNIT 3 EXPERIENCED FIVE FAILURES OF ROSEMOUNT MODEL 1153 DIFFERENTIAL PRESSURE TRANSMITTERS IN 1986 AND 1987, o ROSEMOUNT INITIALLY INDICATED THAT FAILURES WERE RANDOM.

c IN 1988, MILLSTONE SUBMITTED 10 CFR PART 21 NOTIFICATION INDICATING THAT CAUSE WAS LOSS OF OlL IN THE SENSOR MODULE OF TRANSMITTERS.

o IN FEERUARY 1989, RCSEMOUNT INFORMED THEIR CUSTOMERS OF PCTENTIAL FAILURES OF MODEL 1153 AND 1154 TRANSMITTERS.

o FAILURE MODE IDENTIFIED AS LOSS OF SILICONE OIL FROM i

TRANSMITTER SENSING MODULE POSSIBLY DUE TO POOR BONDING OF SEALS AROUND Dil CHAMBERS.  !

c LOSS OF 0IL RESULTS IN REDUCED PERFORMANCE OF TRANSMITTER:

- CRIFT IN EITHER DIRECTION OF ABOUT 1/4% OR MORE PER MONTH, i

- LACK OF RESPONSE OVER TRANSMITTER'S FULL RANGE,

- INCREASE IN TIME RESPONSE, CONTACT: J. CUILLEN SIGEVENT: NO

REFERENCES:

10 CFR PART 21 NOTIFICATIONS FROM MILLSTONE AND ROSEMOUNT, INP0 SEN, INPO 08MR, AND GENERAL ELECTRIC l SIL a__-___

GENERIC ISSUE 88-14 o ACCORDING T0 ROSEMOUNT ALL FAILURES HAVE OCCURRED DURING FIRST 30 MONTHS OF SERVICE ANE TRANSMITTERS THAT.HAVE BEEN IN SERVICE FOR MORE THAN 36 MONTHS ARE NOT LIKELY TO EXPERIENCE THESE PROBLENS.

o ROSEMOUNT HAS INITIATED TESTING PROGRAM TO IDENTIFY ROOT CAUSE OF DEFICIEhCY AND POSSIBLE CHANGES TO MANUFACTURING PROCESS.

I c ROSEMOUNT WILL PROVIDE REPORT LATER THIS MONTH DETAILING RESULTS OF PROGRAM AND WILL ALSO PROVIDE ADDITIONAL RECOMMENDATIONS TO CUSTOMERS. ,

lh1USTRY ACTIONS e INP0 ISSUED OPERATIONS AND MAINTENANCE REMINDER (08MR) ON ,

PRESSURE AND DIFFERENTIAL TRANSMITTERS IN 1988. .

O MIL'LSTCNE ISSUED'10 CFR PART 21 IN 1988 AND WILL ISUUE A SUPPLEMENT IN APRIL 1989, 1 o INSTITUlE OF NUCLEAR POWER OPERATIONS (INP0) ISSUED A SIGNIFICANT EVENT NOTIFICATION (SEN) TO ALL UTILITIES IN FEBRUARY 1989, c GENERAL ELECTRIC ISSUED SERVICE INFORMATION LETTER (RCSIL) TO ALL EWR OWNERS IN DECEMBER 1988.

EDLLOWUP c CENERIC COMMUNICATIONS BRANCH, INSTRUMENTATION AND CONTROL ,

SYSTEhS BRANCH, AND VENDOR INSPECTION BRANCH TO REVIEW RECENT MILLSTONE INFORMATION, ROSEMOUNT APRIL REPORT, ANE OTHER INDUSTRY INFORMATION. )

o NRC WILL CONSILER NEED FOR INFORMATION NOTICE OR BULLETIN AFTER EVALUATING INDUSTRY ACTIONS.

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GENERIC ISSUE, PART 21 - ROSEMOUNT TRANSMITTERS Model 1153 Series D Pressors fransulHers LEADWIRES - -

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GENERIC ISSUE, PART 21 - ROSEMOUNT TRANSMITTERS

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4 REACTOR SCRAM

SUMMARY

_ ENCLOSURE 3 WEEK ENDING 04/02/89

1. PLANT SPECIFIC DATA COMPL1- YTD YTD YTD DATE SITE UNIT POWER SIGNAL CAUSE CATIONS ABOVE PELOW TOTAL 15% 151 1 0 1 93 A EGulPMENT NO 1

03/28/89 RANCHO SECO 1 0 1 NO 03/29/89 F0lNT PEACH 2 100 A PERSONNEL 1 3 N3 2 03/29/89 SALEM 2 1A PERSONNEL NO 2 0 2 03/30/89 ROBINSON 2 100 A EQUIPMENT 2

h0 2 0 3 70 A EQUIPMENT 03/30/69 DRESDEN 0 1 NO 1 04/01/89 SUMMER 1 30 A EQUIPMENT l

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_ _ - - - _ -- 1

i NOTES

.I. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 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 R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. THEPE ARE 111 REACTORS HOLDING AN OPERATING LICENSE.

2. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONMEL ERRORS UNRELATED TO CAU5E OF SCRAM.

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

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

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