ML20055D293

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Summary of Operating Reactors Events Meeting 90-18 on 900627.List of Attendees & Significant Elements of Discussed Events Encl
ML20055D293
Person / Time
Site: Yankee Rowe
Issue date: 06/27/1990
From: Baranowsky P
Office of Nuclear Reactor Regulation
To: Rossi C
Office of Nuclear Reactor Regulation
References
OREM-90-018, OREM-90-18, NUDOCS 9007060121
Download: ML20055D293 (10)
v • d • e


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I' June 27,1990 MEMORANDUM FOR:

Charles E. Rossi, Director Division of Operational Events Assessment FROM:

Patrick W. Baranowsky, Actin 9 Chief Events Assessment Branch l

Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS he.ETING June 27, 1990 MEETING 90 18 On June 27, 1990, weconductedanOperatingReactorsEventemeeting(90-18) to inform senior managers from NRR, liCRS, Commission staff, and regional offices of selected events that occurred since our last briefing on June 20, 1990. lists the attendees. presents the e

significant elements of the discussed events. contains reactor scram statistics for the week ending 06/24/90.

No significant events were identified for input into the NRC performance 1

indicator program.

Orl hal Wgned by E

Patrick W. Baranowsky, Acting Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated i

cc w/ Encl.:

See Next Page 5

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ENCLOSURE 1 a

LIST Or. ATTENDEES OPERATING.REACTOPS. EVENTS.0RIEFING (90 18)

June 27, 1990 NADE ORGANI?ATION NAME ORGANIZATION C. Rossi NRR/DOEA J. Roe MPP./0) PO P. Boehnert ACRS P. Baranowsky NRR/DOEA M. Reardon NRR/DOEA P. Sears NRR/PD1-3 D. Fischer NRR/DOEA N. Kadambi NRR/DOEA J. Scarborough OCM/KR W. Troskoski OE P. Kotay NRR/DRIS L. Norrholm OCM/KC S. Varga NRR/DRP S. Wu HRR/ DST A. Young NRR/DOEA l

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YANKEE R0WE UNIT 1 STUCK CONTROL RODS JUNE 23, 1990 PROBLEM STUCK KESTINGHOUSE-DESIGNED CONTROL RODS (UNIQUE DESIGN),

CAUSE THE LICENSEE SUSPECTS B0 WING.

SAFETY SIGNIFICANCE MULTIPLE STUCK CONTROL RODS COULD RESULT IN INADEQUATE SHUTDOWN CAPABILITIES (OR ANTICIPATED TRANSIENT WITHOUT SCRAM).

BACKGROUND t

o YANKEE R0WE REACTOR IS A UNIQUE DESIGN, SIMILAR TO NAVAL NUCLEAR REACTOR DESIGN, CONTROL R0D DESIGN IS ALSO UNIQUE--

CRUCIFORM SHAPE SOLID AG-lN-CD ENVELOPED IN AN INCONEL SHELL 24 CONTROL RODS IN CORE o

YANKEE R0WE HAS HAD THREE INSTANCES OF CONTROL R0D INSERTION PROBLEMS IN THE PAST.

IN 1972, RODS #18 AND #19 DID NOT INSERT PROPERLY DURING t

R0D DROP TESTS.

CAUSE WAS CONTROL R0D FOLLOWER B0W, IN JANUARY 1979, R0D #22 FAILED T0 INSERT FOLLOWING A REACTOR TRIP.

CAUSE MAY HAVE BEEN CRUD BUILDUP, IN MAY 1981, R0D #17 FAILED TO INSERT DURING A CONTROLLED PLANT SHUTDOWN DUE TO FOLLOWER B0W.

o IN 1972, THE CONTROL R0D DESIGN WAS CHANGED TO MAKE THEM LESS SUSCEPTIBLE TO B0 WING, HOWEVER, THE AB0VE INSTANCES OF R0D INSERTION PROBLEMS AND RESULTS OF ROD DROP TESTS RAISE QUESTIONS 1

AS TO THE EFFECTIVENEE$ OF THE 1972 DESIGN CHANGE, CONTACT:

A. P YOUNG SIGEVENT:

YES

REFERENCES:

10 CFR 50,72# 18756, PN0-1-90-51, AND MORNING REPORT 06/25/90

o YANKEE R0WE UNIT 1 90-18 n

BACKGROUND (CONTINUED) o THE OLD DESIGN IS SCHEDULED TO BE PHASED-0VT OVER THE NEXT 2 REFUELING OUTAGES (7/90 AND 1/92),

o THE 2 RODS AFFECTED ARE FROM THIS BATCH OF OLD DESIGN, o

CRITERIA FOR R0D REMOVAL IS BASED ON R0D BOW MEASUREMENTS TAKEN EVERY REFUELING OUTAGE.

o ROD B0W DURING LAST OUTAGE FOR THESE 2 RODS WERE 0,16 AND 0,21 INCHES, RESPECTIVELY, MAXIMUM ALLOWABLE IS 0.30 INCHES, DISCUSSION o 'DURING R0D DROP TESTING, AS LICENSEE WAS COOLING DOWN FOR A SCHEDULED REFUELING OUTAGE, 2 CONTROL RODS DID NOT FULLY INSERT, o

2 SHUTDOWN RODS (#17 AND #18) HAD STUCK AT THE 36-INCH AND 32-lNCH POSITIONS, RESPECTIVELY, FULL-0VT POSITION IS 90 INCHES, o

" PULL-DOWN" C0lLS WERE USED TO DRIVE THE CONTROL RODS IN, o

CONTROL RODS WILL BE RAISED FROM THE CORE AND EXAMINED IN REFUELING CAVITY TO DETERMINE AND VERIFY EXTENT OF R0D B0W, o

LICENSEE EXPECTS TO INSPECT 2 RODS IN MID-JULY, E0LLOWUP REGION AND NRR ARE FOLLOWlHG LICENSEE'S ACTIVITIES, i

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. II. OMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK INDIN3 06/24/90 s

SCRAM CAUSE POWER NUMBER 1990 1989 1988 1987 1986 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS (5)

AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD (3)(4)

C* PCWER >15%

SQUIP. RELATFD

>15%

2 3.1 2.9 3.1 3.9 4.3 PERS. RELAT E 6) >15%

0 0.5 1.0 1.0 1.3 1.8 OIMER(7)

>15%

0 0.0 0.1 0.5 1.2 0.4 C

  • Subtotal *
  • 2 3.6 4.0 4.6 6.4 6.5 i ** POWER <15%

PQUIP, RELATED (15%

1 0.5 0.4 0.5 1.2 1.4 PERS. RELATED

<15%

0 0.2 0.3 0.3 0.6 0.8 CfrHER

<15%

0 0.0 0.7 0.1 0.3 0.2

    • Subtotal **

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0.7 1.4 0.9 2.1 2.4

      • Total ***

3 4.3 5.4 5.5 8.5

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MANUAL VS Al@ SCRAMS i

TYPE NUMBER 1990 1989 1988 1987 1986 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE' AVERAGE AVERAGE AVERAGE YTD t

MA! RIAL SCRAMS 0

1.0 0.9 1.0 1.4 1.0 ALTTCHATIC SCRAMS 3

3.1 3.8 4.5 7.0 7.9 s

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WOTES 0.

1.

PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST.

PERIOD IS HIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D HOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLAT *ED SHUTDOWN IN ACCORDANCE j

WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN i

OPERATillG LICENSE.

2.

COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED To cAust 0F SCRAM.

3.

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

4.

CAUSES(LIGHTNING),SYSTEMDESIGN,ORUNKNOWHCAUSE.

OEAB SCRAM. DATA Manual and Automatic Scrams for 1986 ------ ----------- 461 Manual and Autoratic Scrams for 1987 ------------------ 439 Eanual and Automatic Scrans for 1988 ------------------ 287 Manual and Automatic Scrams for 1989 ------------------ 244 ManualandAutomaticScramsfor1990-(YTD06/24/90)--- 93 l-

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