ML20148H662
| ML20148H662 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Perry, Indian Point, Fermi, Grand Gulf, Brunswick, North Anna, River Bend, Diablo Canyon, Callaway, McGuire, 05000000, Trojan |
| Issue date: | 01/15/1988 |
| From: | Lanning W Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-88-002, OREM-88-2, NUDOCS 8801270275 | |
| Download: ML20148H662 (16) | |
Text
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%[o 73 UNITED STATES f
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g NUCLEAR REGULATORY COMMISSION 5-f j WASHINGTON, D. C. 20555
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FEh0RANDUll FOR:
Charles E. Rossi. Director Division of Operational Events Assessment Office of huclear Reactor Regulation FROM:
Wayne Lanning. Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation
SUBJECT:
THE OPERATING REACTORS EVENTS MEETIhG January 12. 1988 - MEETING 88-02 On January 12. 1988 an Operating Reactors Events meeting (88-00) was held to brief senior managers from NRR. RES. AE00 and Regional Offices on events which occurred since our last reeting on J3nuary 5,1988.
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, a summary of reactor scrams, and a comparison of this week's statistics with iredustry averages.
One significant event was iden-tified for input to NRC's performanca indicato program.
Wa e Lanning. Chief Events Assessment Bra Division of Operational Events Assessment Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ Encl.:
See Next Page ff i
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h;.ciY p fr h 9 8801270275 880115 PDR ORG NRRB P8
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T. Murley J. Sniezek F. Miraglia M. Slosson E. Jordan R. Capra J. Taylor E. Beckjord W Russell. RI
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J. Nelson Grace..RI!
R. D. Martin RIV J. B. Martin. RV t
W. Kane. R1 L. Reyes, RII C. Norelius. RIII J. Callan RIV D. Kirsch. RV i-S. Varga D. Crutchfield B. Boger G. Lainas G. Holahan L. Shao J. Partlaw 1
B. Grimes F. Congel E. Weiss S. Black T. Martin J. Stone R. Hernan H. Bailey J. Guttmann A. Thadani S. Rubin
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l ENCLOSURE 1 i
L_IST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (88-02)
January-12, 1988 NAME ORGANIZ,,A_ TION NAME ORGANIZATION-P. Baranowsky NRR/00EA R. Woodruff _
NRR/00EA M.L. Reardon NRR/00EA W. Minners RES/0RPS O. Neighbors NRR/PD 1-1 G. Klingler NRR/PMAS R. Scholl, Jr.
NRR/DOEA J. Stang OSP/TVA J. Carter NRR/00EA V. Benarcya AE00/DSP OE00 N. Fields NRR/00EA M. Johnson
~
NRR/PMAS
- 8. Boger NRR/ADRI J.B. Henderson W. Jensen NRR/DOEA E.L. Jordan AE00 R.A. Capra NRR/PD l-1 A. Thadani NRR/ DEST E. Sylvester NRR/F0 4 C.J. Haughney NRR/CRIS M.L. Slosson NRR/PD I-1 F. Congel NRR/0RSP W. Bateman NRR/DLPQ R. Lobc1 NRR/00EA B. Elliott NRR/EMTB R. Wright NRR/0RSP E. Weiss AE00/00A C.R. VanNeil NRR/0 REP D.B. Matthews NRR/DREP R.A. Meck NRR/0 REP l
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9 ENCLOSURE 2 7
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OPERATING REACTORS EVENTS PRiFFIFG 88-0T TUESDAY, JANUARY 12, 1988 THIS INFORMATION MAY ALSO BE OBTAINED BY DIAO NG EXTENSION 2717I4, INDIAN P0lFT 2 STEAM GENERATOR B0llED DRY GENERIC ISSUE SOLEN 0ID VALVE PROBLEMS GENERIC ISSUE EMERGENCY PREPAREDNESS / EMERGENCY i
ACTION LEVEL i
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INDIAN POINT UNIT 2 STEAM GENERATOR BOILED DRY JANUAPY 3, 1988 PROBLEM PLANT OPERATORS ALLOWED AN UNIDENTIFIED FTEAM LEAK TO DRY OUT A STEAM GENERATOR, SIGNIFICANCE o
APPARENT LACK OF C0hMUNICATION PETWEEN OPERATORS AFP PANAGEMENT, o
OPERATION WITH A DRY HOT STEAP GENERATOR AND SUBSE0 VENT PEFILL MAY LEAD TO UNEVALVATED CONSEQUENCES, DISC _USSION o
PLANT WAS BEING HEATED TO 350'F FOR A HYDR 0 TEST USING TWO RCS
- PUMPS, o
BOTH RHR LOOPS OUT OF SERVICE, o
1 MOTOR DRIVEN AFW PUMP AND TWO STEAM GENEPATORS AVAILAELE FOR HEAT REMOVAL, o
AFW PUMP 23 WHICH SUPPLIES SG 24 AND SG 23 WAS OUT OF SERVICE, o
INSUFFICIENT STEAM TO OPERATE TURBINE DRIVEN AFW PUMP, o
AT 11:30 P.M. JANUARY 1, SG 23 LEVEL WAS NOTED DRIFTING
- LOWER, o
AT 8:00 A.M. JANUARY 3, SG 23 LEVEL OFF SCALE ON WIDE RANGE, o
HYDRO TEST COMPLETED 10:50 A.M. JANUARY 3.
o AT ABOUT 8:00 A.M. JANUARY 9.
STATION MANAGEMENT WAS INFORMED OF DRY OUT CONDITION FROM CHEMISTRY DEPARTMENT, c
TESTINC 0F AFK FUMP 23 CAUSED A COLD WATER SLUG TO BE ADDED TO DPY STEAM GENERATOR, o
SG 23 REFILLED ON JANUARY 5, 1988 BY TRANSFER OF WATER HEATED FROM SG 01 THROUGH A BLOWDOWN LINE, o
SG 23 DRY FOR ABCUT 40 HOUPS, o
IN GENERAL, REACT 0P OPERATORS VEPF AWAPE OF 0C 23 CONDIT!0N, BUT TOOK NO ACTIOM, UFCERTAINTY AS TO WHETHER SHIFT WATCH SUPERVISORS
- INFORMED, o
COULD HAVE MAINTAINED LEVEL WITH CONPENSATE PUMP, CONTACT:
W. JENSEN
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17
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. FOLLOWUP 0
AIT TEAM AT' SITE T0. DETERMINE CAUSE AND' ASSESS SIGNIFICANCE.
- c. -
o REGION.1: ISSUED CONFIRMATORY ACTION LETTER.
O.
LICENSEE'IS INVESTIGATING:CAUSE.0F STEAM LEAK AND EFFECT OF COLD WATER = SLUG.
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GENERIC ISSUE SOLEN 0ID VALVE PROBLEMS PROBLEM S0LEN0ID VALVE FAILURES ARE CONTINUING TO AFFECT BLOCK VALVE OPEPABILITY, CAUSE o
ELASTOMER DETERIORATION -
HIGH TEMPERATURE / CONTAMINANTS o
STICKY MATERIAL UNKNOWN SIGNIFICANCE o
S0LEN0 IDS WIDELY USED WITH ISOLATION VALVES, o
REACTOR ISOLATION OR CONTAINMENT INTEGRITY MAY BE COMPROMISED FOLLOWING ACCIDENT / TRANSIENT, DISCUSSION o
GENERIC COMMUNICATIONS IE CIRCULAR 81-14 VARIOUS FACILITIES 17 BWR a PWR IE IN 85-17 GRAND GULF 4 4 VI7 MSIV INP0-SER 57-85 BRUPSWICK 2 MSIV IE IN 86-57 BRUNSWICK 2 MSIV o
RECENT PROBLEMS PERRY 1 4 0CTOBER 29, 1987 MSIV (3)
NOVEMBER 3, 1987 MSIV (2)
NOVEMBER P9, 1987 MSIV (1)
BRllNSWICK 2 g34 JANUAPY
?, 1988 DRYWELI. DRAIN ISOLATION val.VES (4)
FOLLOWUP o
REGION il IS CONSIDERING A TIA, o
REGI0f' III IS CONSIDERING AN INFORMATION NOTICE, o
EAB IS CONSIDERiflG THE NEED FOR A GF.t'FRIC ACTIVITY, CONTACT:
J. CARTER L
GENERIC iSSUF EMERGENCY PREPAREDNESS /EMEPGENCY ACTION LEVEL NOTIFICATION OF UNUSUAL EVENTS (NOUE) o NOUE IS A SPECIFIED EMERGENCY CLASS IN REGULATIONS (10 CFR 50, APPENDIX E, IV,C ; NUREG-0654 BY REF.)
o DESCRIPTION:
- 1) POTENTIAL SAFETY DEGRADATION
- 2) NO RELEASE REQUIRING OFFSITE RESPONSE EXPECTED o
EXAMPLES:
ECCS INITIATION 8 DISCHARGE RADIOLOGICAL EFFLUENT ) TECH SPECS
-FUEL DAMAGE INDICATION COOLANT TEMFERATURE/ PRESSURE TECH SPECS PRIMARY / SECONDARY LEAK 5 TECH SPECS LOSS OF 0FFSITE POWER NATURAL PHENOMENA CONTAMINATED,' INJURED PERSON MOVED OFFSITE CONTACT:
D, MATTHEWS
EMEPGENCY PREPAREDNESS / EMERGENCY ACTION LEVEL (C0f!TINUED) o CONTROVERSIAL AN EMERGENCY?
PRECURSOR?
VARIABILITY IN CLASSIFICATION RAND 0M TEST OF NOTIFICATION AND EQUIPMENT LICENSEE CREDlBILITY 8 PUBLIC RELATI0tlS o
DATA:
YEAR NOUE ALERT PRECURSOR 1983 205 7
1984 224 8
1-1985 312 11 2
1986
?09 9
0 1987 9
1
- NOT AVAILABLE o
HISTORY & STATUS ELIMINATION AS AN EMERGENCY CLASS FEMA / STATES' POSITION RESULT - NO CHANGE
i ENCLOSURE 3 LONGTERM FOLLOWUP ASSIGNMENTS _TO BE COMPLETED-ORGANIZATION LONGTERM FOLLOWUPS OUTSTdNDING Of705/88 - _01/12/88 SPLB 6
6 EMTB 1
1 OGCB 5
5 RVIB 4
4 SRXB
-2 2
PD2-3
.1 1
OSP 2
2 ESGB 2
2 AE00 2
2 SICB 3
3 SELB 6
6 P02-2 2
1 PDS 3
1 RV 1,
1 SICB 3
3 PD3-2 1
1 DPLQ 1
1 OTSB o
1
REACIOR SCRAM
SUMMARY
NEEKENDINS 01/10/88
!. PLANT SPECIFIC DATA DATE SITE UN!! POWER SIGNAL CAUSE COMPLI-YTD Y10 yid CAi!0NS ABOVE BELOW TOTAL 151 151 01/04/2BCALLAhAfN 1
100 A PERSONNEL NO 1
0 1
01/07/88 M;6UIRE B M p NORTH ANNAde' M {i 76 A EQUIPMENT NO 1
0 1
I 100 M EQUIPMENT NO 1
0 1
01/09/86 5
01/08/69 DIABLO CANY0 0 7 M f 100 A E90lPRENT N0 1
0 1
01/08/ES TROJAN 91 4 1 100 A E90lPMENT NO 1
0 1
01/10/98 FERMI *i1 2
54 A E9VIPMENT N0 1
0' I
01/10/60 RIVERBEND4 1 100 A PERSONNEL NO 1
0 1
~
01/10/69 BRAND SULF 1
93 A EDUlPMENT N0 1
1-2
II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS'FOR WEEK ENDING C1/10/88 SCRAM CAUSE POWER NUMBER 1988 1987 1986^ WEEKLY 1985 OF WEEKLY WEEKLY. WEEKLY SCRAMS (5)-
AVERAGE AVERAGE AVERAGE AVERAGE YTD (3) (4)
(8) (9)
- . POWER >15%
EQUIP. RELATED
>15%
6 5.0 3.9 4.3 5.4 PERS. RELATED(6) >15%
2 1.4 1.3
- 1. :8 2.0 OTHER(7)
>15%
0 0.0 1.2 0.4 0.6
- Subtotal **
8 6.4 6.4 6.5 8.0
- POWER <15%
EQUIP. RELATED
<15%
0 0.0 1.2 1.4 1.3 PERS. RELATED
<15%
0 1.4 0.6 0.8 0.9 OTHER
<15%
O O.7 0.3 C.2-O.2
- Subtotal **
O 2.1 2.1 2.4 2.4
- Total ***
8 8.5 8.5 8.9 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1988 1987 1986 1985 OF WEEKLY-WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE' AVERAGE AVERAGE AVERAGE YTD MANUAL SCRAMS 1
1.4 1.4 1.0 1.0 AUTOMATIC SCRAMS 7
7.1 7.0 7.9 9.4 i
l 1
i
FOTES 1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST.
PERIOD IS HIDNIGHT SUNDAY THRODGH *,
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.
E.
RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAN.
3.
1986 INFORMATION DERIVED FROM ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1986. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
4.
IN 1986, THERE WERE AN ESTIMATED TOTAL OF 461 AUTOMATIC AND FMNUAL UNPLANNED REACTOR TRIPS AT 104 REACTORS (HOLDING OPERATING LICENSES).
THIS YIELDS AN AVERAGE RATE OF 4.4 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 8.0 TRIPS PER WEEK FOR ALL REACTORS.
5.
BASED ON 109 REACTORS HOLDING AN OPERATING LICENSE.
6.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
7.
'OTHER" INCLUDES AUTOMATIC SOL AMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
8.
1985 INFORMATION DERIVED FROM AN ORAS STUDY OF UNPLANNED REACTO IN 1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 VEEKS/ YEAR.
9.
IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR YEAR AND AN AVERAGE RATE OF 10.3 TRIPS PER WEEK FOR ALL REACTORS.
t
.. ~..
1 Pap' No. ~ ^ l 01/11/88 PERFORMANCEljlDICATORS$1GNIFICANTEVENTS PLMT MA"i EVENT EVENTIESCRIPTION GTR SIGNIFICANCE DATE INDIAN P0lWT 2-01/03/88 biEAM SENERATOR ALLOWED TO DRY DUT.IN V!DLATION OF :
- 0 ADMINISTRATIVE PROCEDURAL AND i
PROCEDURES. PLANI MANA6EMENT NOT IEORMED BY OPERATORS ConmalCATION PROBLER e
r 6
-(
L MEMORANDUM FOR:
Charles E..Rossi. Director Divirion 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 January 12, 1988 - MEETING 88-02 On January 12. 1988 an Operating React'rs Events meeting (88-02) was held to o
brief senior managers from NRR RES. AE0D and Regional Offices on events which occurred since our last meeting on January 5.1988.
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, a summary of reactor scrams, and a comparison of this week's statistics with industry averages. One significant event was iden-tified for input to NRC's performance indicator program.
Wayne Lanning. Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated j
cc w/ Encl.:
See Next Page DISTRIBUTION, 1CeritralffleR EAB Reading File Circulating Copy EA8 Staff MLReardon. EA8 00udinot. EAB LKilgore. SECY PDR OFC
- EABTNRR
- C:EA NRR
.....:....s.v.'...:
HA.ME :ML[diflo'n' ing DATE :01////88
- 01/N/88 l
ITFFICIAL REC 010 COPY s w me.