ML20196H635
| ML20196H635 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Palisades, Palo Verde, Fermi, Sequoyah, Pilgrim, Susquehanna, Seabrook, Surry, South Texas, San Onofre, Rhode Island Atomic Energy Commission, 05000000 |
| Issue date: | 03/08/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUDOCS 8803110170 | |
| Download: ML20196H635 (24) | |
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HEADQUARTERS DAILY REPORT March 8,
1988 DIVISION OF RADIATION PROTECTION AND EMERGENCY PREPAREDNESS. NRR RADIATION PRufECTION BRANCH I. Spickler will be on t ravel March 7 1988 through March 9 1988 at Rescho Seco to followup on the Emergency Preparedness Restart Issue R. Pedersen is assessing the Region V implementation of the radiological protection inspection program, as a member of the Headquarters Assessment Team esamining regional implement at ion of MC 2515 (week of Marc h 7-10),
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OFFICE OF SPECIAL PROJECTS DATE: March 8, 1988 Facility: Sequoyah Unit 2 RESTART DAILY STATUS REPORT 1.
Plant Status as of 0600 a.m., Marc h 8, 1988 Unit 2 is in hot standby (mode 3), with four RCPs operating.
The RCS is currently at 450 degrees F and 1750 psig through a process of normal CCS charging / letdown. MSIV's are open.
Pressurizer Jevel is normal.
Motor graven auntliary feedwater pumps are maintaining steam generators level in the operating rangc.
The condensate system is on reciruciation and there is a vacuum in the main condenser.
2.
Problems / Major Issues IDI deficiencies and other mode 2 related items.
3 Major Events During the Past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> On March 7, 1988, the post modification test for AFW pump 2A-A was performed.
The pump did not meet the acceptance criteria of 440 GPM and was declared inoperable. The situation is presently being evaluated.
Un March 7, 1988, the 447 F plateau performance of SI-488 RTD Cross Cal, was completed satisfactorily.
4.
Projected Major Events for the Next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
)
(note: based on 7:00 a.m.
turnover without TVA management input from 9:00 a.m
- war room" meeting)
Complete remaining GOI-1 steps prior to entry into mode 2.
Resolve IDI deficiencies and other mode 2 related open items.
Complete TS required surveillances to support mode 2.
Evaluate / resolve AFW pump 2A-A test re s ul t s..
8803110170 880303 PDR ADOCK 05000 R
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PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION I MARCH 8, 1988 Licensee / Facility Notification / Subject Paansylvania Power & Light Co.
ENS Call Susquehanna Unit 1 ESF Actuation DN 50-387 Evant OA 3/4 at 12:07 p.m.,
a Main Generator Load Rc;ect signal caused the main turbine to trip.
The turbine control valves closed and an automatic Reactor Scram occurred. Reactor vessel level dec reased to approximately 8 inches before being restored to normal levels by the reactor feedwater pumps.
No Emergency Core Cooling systems actuated and the plant trip response was normal.
Investigation by the licensee determined that an operator working in the 230 KV Switchyard bumped against the S an Protection Auxiliary Relay causing it to actuate which generated a Main urbine Trip Signal Tha licensee has decided to retain the unit in a shutdown condition for tpproximately 5 to 7 days to perform selected maintenance work.
The unit is expected to return to power operation during the weekend of 3/12/88.
Th3 resident inspectors are monitoring the licensees activities.
Licensee / Facility Notification / Subject PP2L Co.
3/8 SRI PC Susquehanna Unit 2 Second Refueling Outage /
D3 50-558 Spurious RHR Isolation Signal Event At 5.00 p.m.
on 3/4, shutdown of the unit for its second refueling outage commenced. The generator output breaker was opened at 12:31 a.m.
and the reactor pote switch placed in shutdown at 01:59 a.m. on 3/5 to officially start the 59 day outage. Major activities for the outage include: replacement of 236 fuel Deadles, 24 control rod drives, and cog lete overhaul of the main turbine gsserator including replacement of the Low Pressure Turbine Rotors. Major modifications to address issues associated with Loss of Offsite Power, Asticipated Transient Without Scram Appendix R, inadequate drywell cooliag, and residual heat removal waterhammers are also scheduled to be accomplished.
Tha unit is expected to return to power operation during the week of 5/1.
While placing the unit in the RHR Shutdown Cooling Mode of operation, a spurious isolation signal occurred. The licensee immediately determined that an actual isolation condition did not exist, reopened the affected RHR valve and continued to place the unit in the shutdown cooling mode. The cause of the spurious signal is still under evaluation by the licensee.
The resident inspectors are monitoring the licensee's activities.
REGION I MORNING REPORT PAGE 2 MARCH 8, 1988 Licensee / Facility Notification / Subject Pilgrim 03/07 SRI PC 50-293 Missed Surveillance Test
Event On 3/4 during a Quality Assurance audit, the licensee identified that a once per cycle surveillance test of the "B" emergency diesel generator (EDG) may not have been performed as required during the last cycle.
Pilgrim Technical Specifications require that the each EDG be started and loaded once per cycle with the control circuits isolated from the cable spreading room to demonstrate remot e shut down capability, No record of test performance for the "B" EDG during the last operating cycle could be found.
The test records were available for "A" EDG testing.
The licensee informed the NRC of the missed test via ENS at 4:45 p.m.
The resident inspectors will monitor licensee followup.
"REGION I MORNING REPORT"
PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION II Ma rc h 8, 1988 Licensee / Facility Notification / Subject VEPCO/Surry 2 Senior Resident Inspector Potential.for High Radiation Dose to Workers Event Event No. N/A Oa March 3, 2 Inst rument and Control (I&C) technicians and a Health Physics (KP) technician entered Unit 2 containment to free a stuck incore detector.
Uait 2 was at 100% power.
The containment was sub-atmospheric.
The I&C technicians disconnected the detector drive cable from the drive mechanism located outside t he polar c rane wall (bioshield) and began slowly with-d rtwing the cable by hand.
The I&C technicians were to withdraw the detector through the ten-path rotary transfer mechanism to the five-path rotary transfer mechanism where a limit switch was to be activated and the withdrawal stopped.
Bath the ten-path and the five-path transfer machanisms are located in the 1 score room located within t he polar c rane wall. An I&C supervisor was in the control room and in sound-powered phone communications with the technician in containment. The I&C supervisor was observing radiation levels in the incore room and watching for a light indication that the detector had reached the limit switch. When the supervisor received the indication that the detector had reached the limit switch he advised the technicians to stop the withdrawal. Communication problems occurred at this point and the technicians continued the withdrawal. By the time the supervisor repeated the message, the HP technician at the job site noted that radiation levels were rapidly increasing and ordered an evacuation of the area.
The IAC technician pushed the detector back in approximately one foot as he was leaving. Radiation levels at the crane wall penetration were greater than 1.000 R/hr.
The workers' TLDs were read.
Highest dose received was 510 mrem.
The licensee *z investigation is contzauing. Latest information indicates that the detector was not pulled beyond the shielding provided by the polar crane wall.
Radiation levels at t he polar c rane wall with general area levels of petet rations were 100 R/hr on March 7,s at tempt s - to ret urn t he detec tor 2-2.5 R/hr.
On March 7 the licensee i
CEGION II MORNING REPORT PAGE 2 Ma rc h 8 1988 to storage were unsuccessful. The detector remains in the crane wall penetration.
On March 8 the licensee will attempt to use a specially ftbricated tool to grip the cable and puse the detector back into the incore room.
The drive cable will be reattached to the drive mechanism esd t he detector driven into storage.
Rsgional Action: The Resident Inspections and a regional-based radiation specialist are onsite.
The Commonwealth of Virginsa has been informed.
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PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION III MARCH 8, 1988 FACILITY / LICENSEE NOTIFICATION / SUBJECT PALISADES / CONSUMERS POWER SRI PC/ ORGANIZATION CHANGE EVENT EVENT NO. INFORMATION CONSUMERS POWER COMPANY (CPC] AND ITS HOLDING COMPANY, CMS ENERGY CORPORATION ELECTED SEVERAL NEW OFFICERS OK MARCH 7, 1988 AS A RESULT OF THE RESIGNATION OF JOSEPH H.
PAQUETTE. JR., WHO WILL BECOME CHAIRMAN AND CEO OF PHILADELPHIA ELECTRIC COMPANY.
S. KINNIE SMITH, JR.,
57 WILL BECOME THE PRESIDENT OF CMS ENERGY CORP.
WHILE RETAINING HIS POSITION AS VICE CHAIRMAN OF CPC, FCEDERICM W. BUCKMAN. 41, WILL BECOME PRESIDENT AND CHIEF OPERATING OFFICER OF CPC.
GORDON HEINS, 58 WILL REPLACE DR. BUCKMAN AS SENIOR VICE PRESIDENT OF ENERGY SUPPLY OF CPCO.
MR. HEINS WAS FORMERLY THE VP FOR FOSSIL AND HYDRO OPERATIONS, VICTOR J. FRYLING, 40, WILL BECOME EXECUTIVE VICE PRESIDENT AND CHIEF FINANCIAL OFFICER OF 80TH CMS ENERGY AND CPC.
NO PLANS WERE ANNOUNCED FOR THE FILLING OF THE VICE PRESIDENT NUCLEAR OPERATIONS POSITION.
REGIONAL ACTION:
REGION III MORNING REPORT PAGE 2 MARCH 8, 1988 INFORMATION ONLY FACILITY / LICENSEE NOTIFICATION / SUBJECT DAMAGED MOISTURE SEPARATOR REHEATERS /
FERMI 2 RESIDENT INSPECTOR DETROIT EDISON EVENT EVENT NO. N/A ON MARCH 2.
1988 WHILE PERFORMING DRAIN LINE MODIFICATIONS TO THE MOISTURE SEPARATOR REHEATERS. THE LICENSEE DISCOVERED DAMAGED MESH AND STEAM DEFLECTION BAFFLES.
THE BAFFLES ARE LOCATED ON THE COLD STEAM INLET TO THE EAST AND WEST MOISTURE SEPARATOR REHEATERS. SEVEN OF ElGHT COLD STEAM INLET AREAS WERE DAMAGED.
THE LICENSEE IS REMOVING THE DAMAGED COMPONENTS FOR ANALYSIS BY THEIR ENGINEERING RESEARCH DIVISION TO DETERMINE THE FAILURE MECHANASM.
THE PLANT IS CURRENTLY IN AN EXTENDED LLRT OUTAGE.
CEGIONAL ACTION FOR INFORMATION ONLY.
DAILY REPORT REGION III DATE: 3/8/88 l
FACILITY / LICENSEE NOTIFICATION / SUBJECT DAVIS-BESSE ENS / STATION ALERT l
EVENT EVENT NO. II668 THE LICENSEE DECLARED AN "ALERT" AT 6:43 P.M.
(EST) ON MARCH 4, 1988 AFTER i
83TH TRAINS OF THE DECAY HEAT REMOVAL (DHR) SYSTEM WERE DECLARED INOPERABLE.
THE ALERT. WHICH ONLY LASTED 12 MINUTES. WAS PRECIPITATED BY THE FAILURE OF A SEkVICE WATER (SW) VALVE TO REMAIN IN THE FULLY OPEN POSITION. AS REQUIRED.
THE PROBLEM WITH THE SYSTEM WAS DISCOVERED WHEN THE LICENSEE WAS THOUBLESHOOTING THE SW VALVE AND 16 WAS PLACED IN ITS FAILSAFE POSITION (FULLY OPEN).
AN HOUR AND A HALF LATER THE VALVE WAS FOUND TO HAVE DRIFTED TO A 30% OPEN POSITION.
SINCE THE COMPONENT COOLING WATER (CCW) VALVES IN THE DHR SYSTEMS ARE OF THE SAME TYPE, IT WAS CONCLUDED THAT THEY COULD HAVE THE SAME PROBLEM AND THEREFORE, BOTH DHR TRAINS WERE TECHNICALLY INOPERABLE.
LOSS OF BOTH DHR TRAINS CONSTITUTED AN ALERT.
THE PLANT WAS REMOVED FROM THE ALERT STATUS BY MANUALLY BLOCKING OPEN A CCW VALVE IN ONE DHR TRAIN. THUS RESTORING THAT TRAIN TO SERVICE.
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REGION III MORNING REPORT PAGE 3 MARCH 8 1988 CEGIONAL ACTION THE LICENSEE IS INVESTIGATING THE CAUSE OF THE SW VALVE PROBLEM.
REGION III AND THE RESIDENT INSPECTORS ARE MONITORING THC LICENSEE *S COURSE OF ACTION.
THE UNIT WILi. BE SHUT DOWN FOR A SIX MONTH REFUELING / MAINTENANCE OUTAGE BEGINNING MARCH 10, 1988.
s NEW FORMAT FOR DAILY REPORTZ DO NOT ENTER TABS IN TEXT - SPACE TO MIDDLE OF PAGE IF NECESSARYZ, 1
EVENT MR. H. J. MILLER. DIRECTOR. DIVISION OF REACTOR SAFETY IS HOSTING THE COUNTERPARTS MEETING WITH REPRESENTATIVES FROM REGIONS I, II. IV AND V ALONG WITH REPRESENTATIVES FROM HEADQUARTERS. THIS MEETING IS BEING s
HELD AT THE RADISSON HOTEL IN DOWNERS GROVE ON MARCH 7 AND 8 1988.
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PRIORITY ATTENTION REQUIRED MORNING REPORT-REGION IV MARCH 8, 1988 LICENSEE / FACILITY NOTIFICATION / SUBJECT HOUSTON LIGHTING & POWER CO.
TELEPHONE CALL FPOM SRI SOUTH TEXAS PROJECT, UNIT I INITIAL CRITICALITY D3:
50-498 EVENT:
AT 5:08 A.M.
(CST), ON MARCH 8 1988 UNIT 1 0F THE SOUTH TEXAS PROJECT ACHIEVED INITIAL CRITICALITY.
PRELIMINARY EVALUATION INDICATES THE REACTOR WAS WITHIN PREDICTED PARAMETERS. ALL SHUTDOWN AND CONTROL RODS WERE FULLY WITHDRAWN 9259 STEPS)
EXCEPT CONTROL BANK "D" WHICH WAS AT 170 STEPS IN ACCORDANCE WITH THE STARTUP PROCEDURE.
CRITICALITY OCCURRED AT A BORON CONCENTRATION OF APPROXIMATELY 950 PARTS PER MILLION (PPM).
P;EDICTED CONCENTRATION WAS 917 PPM WITH ALL RODS OUT.
THE PLAUT WAS BROUGHT TO 10E-8 AMPS ON INTEF MEDIATE RANGE NUCLEAR INSTRUMENTATION IN ORDER TO RECORD PHYSICS DATA.
THE APPROACH TO INITIAL CRITICALITY WAS OBSERVED BY THE NRC IZSFECTOR TO BE PROFESSIONALLY CONDUCTED AND IN AN ORDERLY, CO3 TROLLED MANNER.
THE NRC INSPECTORS ARE MONITORING THE LICENSEE *S ACTIVITIES.
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R0 portable Event number 11684 Facility :
PALO VERDE Date Notified : 03/07/88 Unit : 1 Time Notified : 01:45 Rcgion : 5 Date of Event : 03/06/88 Vcndor : C-E,C-E,C-E Time of Event : 21:50 Op3 rations Officer :
Dick Jolliffe Classification : 10 CFR 50.72 NRC Notified By : MUHS Category 1 : UNPIANNED S/D Red Release : No Category 2 : RCP VIB INDICATION Cause :
Category 3 :
Component :
Category 4 :
EVENT DESCRIPTION :
UNIT 1 IN MODE 2 (S/U) 9 10E-3% POWER - DURING LOW POWER PHYSICS TESTING, 1 OF 2 VIBRATION MONITOR CHAYNELS (CHANNEL Y) FOR RCP flB SPIKED HI TO 8 MILS (MAX ALLOWED VIBRATION ON ANY 1 CHANNEL IN LICENSEE ADMIN CONTROL PROCEDURE)
& ALARMED 9 10 MILS (ALARM SETPOINT) IN THE CONTROL ROOM.
THESE INDICATED VIBRATIONS WERE NOT STEADY & OCCURRED 4 TIMES OVER A 25 MINUTE TIME PERIOD
& WERE OBSERVED BY LICENSED & TRAINED LICENSEE ENGINEERS.
LICENSEE SUSPECTS THESE ALARMS ARE NOT VALID BASED ON THE FOLLOWING INDICATIONS: 1) THE OTHER VIBRATION CHANNEL INDICATION (CHANNEL X) WAS CONSTANT WITHIN ACCEPTABLE i
RANGE 2) ORBITAL MONITORING EQUIPMENT INDICATED NO INCREASED VIBRATION BEYOND ACCEPTABLE RANGE 3) SPECTRAL ANALYSIS BY LICENSEE ENGINEERS INDICATE NO INCREASED VIBRATION BEYOND ACCEPTABLE RANGE.
CURRENT AVERAGE DATA VALUES ARE 2 TO 4 MILS ON X & Y CHANNELS ON PERMINENTLY INSTALLED PLANT EQUIPMENT.
LICENSEE HAS DETERMINED THAT THE SPIKING IS INDICATIVE OF AN INSTRUMENTATION ANOMOLIE.
FURTHER DATA COLLECTION IS BEING PERFORMED PRIOR TO PUMP SHUTDOWN.
IN ACCORDANCE WITH LICENSEE ADMIN CONTROLS & COMMITTMENTS MADE TO NRC (REGION 5), LICENSEE IS INSERTING THE CONTROL RODS INTO THE CORE TO SHUT UNIT 1 DOWN 1
& MAS ENTERED MODE 3 (HOT S/D) 0 0347 ON 03/07/88.
LICENSEE PLANS TO INVESTIGATE THE PROBLEM & REPAIR / REPLACE CHANNEL Y VIBRATION RECORDING EQUIPMENT & THEN RESUME TESTING.
LICENSEE WILL INFORM RI.
NOTIFIED RSDO PHIL JOHNSON.
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R: portable Event number 11685 FGcility :
SAN ONOFRE Date Notified : 03/07/88 Unit : 3 Time Notified : 03:06 R;gion : 5 Date of Event : 03/07/88 VCndor : WEST,C-E,C-E Time of Event : 01:08 Opsrations Officer :
Dick Jolliffe Classification : Phys.Sec./ Safeguard NRC Notified By : BILLINGS Category 1 : Security Rad Release : No Category 2 :
Cauge :
Category 3 :
Ccmponent :
Category 4 :
EVENT DESCRIPTION :
UNIT 3 0 100% POWER - SAFEGUARDS SYSTEM DEGRADATION RELATED TO VITAL ARIA DOOR ALARM FUNCTION.
IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY.
SEE HOO LOG FOR DETAILS.
LICENSEE WILL INFORM RI.
NOTIFIED R5DO PHIL JOHNSON.
['
R0 portable Event number 11686 Fccility :
SEABROOK Date Notified : 03/07/88 Unit : 1 Time Notified : 04:05 R0gion : 1 Date of Event : 03/07/88 V0ndor : WEST, WEST Time of Event : 03:05 Op0 rations Officer :
Dick Jolliffe Classification : Phys.Sec./ Safeguard NRC Notified By : BEMIS Category 1 : Security Rtd Release : No Category 2 :
Cauce :
Category 3 :
Component :
Category 4 :
EVENT DESCRIPTION :
PLANT IN MODE 5 (COLD S/D) - SAFEGUARDS SYSTEM DEGRADATION RELATED TO POTENTIAL UNAUTHORIZED, UNDETECTED ENTRY FROM NON-VITAL AREA INTO VITAL AREA.
SEE HOO LOG FOR DETAILS.
LICENSEE WILL INFORM RI.
NOTIFIED RlDO McCABE.
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Report Me Event number 11687 FEci ty NUCLEAR SCIENCE CTR Date Notified : 03/67/88 Unit Time Notified : 04:c1 R';gion : 1 Date of Event : 02,07/88 V0ndor : 2 MW RESEARCH 9.TR Time of Event : 04:31 Opsrations Officer :
Dick Jolliffe Classifica cion : Phys.Sec./ Safeguard NRC Notified By : DiMeglio Category 1 : Security Rad Release : No Category 2 :
.-I Cause : Electrical Failure Category 3 :
Component : TELEPHONE LINES Category 4 :
l' EVENT DES,CRIPTION :
g RHODE ISLAND NUCLEAR SCIENCE,' CENTER, A 2 MW RESEARCH REACTOR, LICENSEE #R95, DOCKET #50-193, LOCATED IN NARRAGA11SETT, RI, REPORTED A LOSS OF OFFSITE COMMUNICATIONS.
SEE HOO LOG FOR CONTACT & DETAILS.
NOTIFIED RlDo McCABE.
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s R:p3rtable Event number 11688
'l Fccility : NONE Date Motified : 03/08/88 Unit :
Time Notified : 06:37 R0gion : 1 Date of Event : 03/08/88 Vcndor :
Time of Event : 99:99 Op0 rations officer :
Dick Jolliffe Class'ification : INFO NRC Notified By :
Category 1 :
R0d Release : No Category 2 :
COute :
Category 3 :
Ccmponent :
Category 4 :
A EVENT DESCRIPTION :
1 s
NO EVENTS THUS FAR TODAY...
STAY TUNED...
FLASH:
SOUTH TEXAS ACHIEVED INITIAL CRITICALITY TODAY 9 0608 e
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.. m NRC Dharationc Ccntcr Plant Stctus for Tucedcy Mcrch 8,1988 Unes a1uated Information provided by the Utility s
REG PLANY NAMd PHONE RESTART REASON OR COMMENTS
_ _ _.. _ _...._ _ _ _ _ _.... _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _'/.P W R D O W N 1 : BEAVER VALI..EY 1 2201 3090 :
- NUCLEAR INGTRUMENTS CALIBRATION 1 : BEAVER VALLEY 2
- 2201 3100 :
1 CALVORT CLIFFS 1
- P.202 097 :
1 CALVERT CLIFFS 2 32202 000 #00/26 303/28
- MODE 5 -
COLD S/D t
MAINTENANCE OUTAGE 1
FitZPATRICK 2202 :100 :
1 :GINNA 12204 3000 :02/05 303/09 iMODE 3 -
HOT S/B 1.:HADDAM NECK 2205 :000 07/10
- 03/11
- MODE 5 -
COLD S/D 1
HOPE CREEK 1 2206 :000 :02/13 04/08
- COND 5 -
REFUELING OUTAGE 1.2 INDIAN POINT 2
- 2207 100 t 1
INDIAN POINT 3
- 220P 1100 1.LIMEDICK 1 2209 :100 :
1 : MAINE YANKEE
- J210 3100 :
_____-____-__.____..____..____.....a__..___
1 :MILLGTCHE 1 12211 100 :
1 sMILLSTONE 2 12211 100 :
2 tMILLGTONE 3 12211 3099 :
__________________....a___..______...._________________________________________...
1 :NINE MILE POINT 1
- 2213 :000 :12/19 t04/01
- COND 5 -
- REFUELING OUTAGE
?. eNINE MILE POINT 2 n2213 3000 03/05 03/09
- COND 4 -
\\
COLD S/D 1 30YSTER CREEK 12215.100 :
y 1 : PEACH BOTTOM 2 322?.6 :000 03/13 UNK COND 5 -
- REFUELING CONDITION s
MAINTENANCE OUTAGE
)
INRC ORDER l
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NRC Operot ionc Ccntcr-Picnt Statuo for Tuccdoy
.M rch 8,1988 Uncvoluctcd Infcrmation provid;d by th3 Utility REG PLANT NAME PHONE
%PWR DOWN RESTART REASDN OR COMMENTS 1 : PEACH BOTTOM 3 12216 3000 303/31
- UNK COND 5 -
REFUELING OUTAGE
- DEFUELED NRC DRDER 1 : PILGRIM 1 32217 :000 t04/06 307/88 COND 4'-
CDLD S/D 1
SALEM 1 22218 100 :
370 GPD TUBE LEAK IN #13 S/G 1 : SALEM 2 32218 1100 :
1 :SEABROOK 1 32219 3000 :- - -
UNK MODE 5 -
- COLD S/D 1 :SHOREHAM 2220 :000 306/08 304/88
- COND 4 -
- COLD S/D
~
1 :SUSQUEHANNA 1 12221 3000 303/04 03/08 COND 4 -
COLD S/D 1
SUSGUEHANNA 2 12221 3000 303/05 305/15 COND 4 -
COLD S/D REFUELING OUTAGE 1
THREE MILE ISLAND 1 2222 1100 :
1 THREE MILE ISLAND 2 32222 3000 103/79 UNK
- RECOVERY 1 : VERMONT YANKEE
- 2224 1100 :
1 YANKEE ROWE 12225 100 :
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NRC Optrations CcntGr Picnt Stotuo for Tuoedcy M:rch 0,1908 Unevaluated Information provided by the Utility REG PLANT NAME PHONE
'/.PWR DOWN RESTART REASON OR COMMENTS 1
2 BROWNS FERRY 1 617 12229 3000 103/85 UNK 3 COLD SHUTDOWN -
tREFUELING OUTAGE
- DEFUELED 2 : BROWNS FERRY 2_751 12229 3000 109/84 UNK COLD SHUTDOWN -
- REFUELING OUTAGE
- DEFUELED 2 : BROWNS FERRY 3_ 0700 :2229 3000 03/85
- UNh
- COLD SHUTDOWN -
- REFUELING OUTAGE
- DEFUELED 2 : BRUNSWICK 1 2230 1100 :
2
- BRUNSWICK 2 12230 000 301/02 04/20
- COND 5 -
REFUELING OUTAGE 2
CATAWBA 1 2231 3098 :
2 : CATAWBA 2 2231 2001 :
MODE 2 -
- STARTUP i
2 CRYSTAL RIVER 3 12233 3010 :
- INCREASING POWER 2
FARLEY_1 2234 3100 :
2 tFARLEY 2
- 2234 1100 :
2 GRAND GULF 1 2235 2005 :
INCREASING POWER j
2 HARRIS 1 2236 3100 :
2 HATCH 1
- 2237 1100 :
2 HATCH 2 12237 000 301/13 803/14 COLD 5 -
REFUELING OUTAGE 2
MCGUIRE 1 2239 1100 :
2 :MCGUIRE 2
- 2239 100 :
2 : NORTH ANNA 1 2240 :100 :
2 : NORTH ANNA 2 2240 :100 :
2 OCONEE 1 2241 2100 :
2 OCONEE 2 12241 3000 102/04 104/14 i MODE /> -
REFUELING OUTAGE
- DEFUELED I
i 1
NRC Opcrotions Ccntcr i
Plcnt Statuo fcr-Tuccdcy Mirch 8,1988 Uncvoluctcd Infccmstlen providcd by tho Utility 1 REG PLANT NAME PHONE
OCONEE 3
- 2241 :100 :
30.02 GPM S/G TUBE LEAK & SMALL AMOUNT OF FAILED FUEL
-__________________________________________________________e__________________
2 : ROBINSON 2
- 2242 000 301/29 03/09 MODE 4 -
HOT S/D 2 :SEOUOYAH 1 32243 3000 108/85 UNK iMOCE 5 -
COLD S/D -
4
- CONFIRMING EQ OF SAFETY SYSTEMS 2 ISEOUDYAH 2
'2243 3000 08/85 303/20 MODE 3 -
HOT S/B 2
ST. LUCIE 1
- 2244 3100 :
2 ST. LUCIE 2 32244 100 :
2 : SUMMER 2245 100 :
2 SURRY 1 12246 :100 :
_________________________________~,__________________________________
2 SURRY 2 32246 100 :
2 TURKEY POINT 3 12247 3100 :
2 : TURKEY POINT 4 32247 3050 :
- REPAIRING LEAK IN
- 4A S/G MFW PUMP 2
VOGTLE 1 2248 100 :
.......m...
1 NRC Op;rotions C ntcr Picnt Stotuo for Tuordoy M:rch 8,1928 Unevaluated Inform: tion previdcd by the Utility
' REG PLANT NAME PHONE
%PWR DOWN RESTART REASON OR COMMENTS 3
BIG ROCK POINT
- 2250 3084 :
LIMITED TO 07% POWER : :
- DUE TO FUEL THERMAL LIMITS 3 :BRAIDWOOD 1 2251 3000 301/02 03/31
- MODE 5 -
- COLD S/D 3 *BRAIDWOOD 2 32251 000 :- - -
303/08 MODE 2 -
- STARTUP 3
BYRON 1 2252 098 :
ADMIN LIMIT OF 98%
POWER DUE TO S/G
- UPPER NOZZEL FLOW LIMITATIONS 3
- BYRON 2 32252 1083 :
ADMIN LIMIT OF 94%
- POWER DUE TO FW i
FLOW LIMITATIONS LOAD FOLLOWING s
3 CALLAWAY 1 2253 100 :
3 : COOK 1
- 2254 3090 :
ADMIN LIMIT OF 91%
- POWER TO EXTEND S/G TUBE LIFE 3 : COOK 2
- 2254 080 :
ADMIN LIMIT OF 81%
- POWER TO EXTEND S/G
- TUBE LIFE 3 : DAVIS-BESSE 1 12255 t061 :
- POWER LIMITED TO 85%
- DUE TO 3 GAGGED MS
- DAFETY VALVES -
- COASTDOWN TO REFUEL 3 :DRESDEN 2 12256 1097 :
3 :DRESDEN 3 12256 3096 :
3 :DUANE ARNOLD
- 2257 1100 :
3 FERMI 2
- 2258 3000 102/27 304/15
- COND 4 -
COLD S/D MAINTENANCE OUTAGE 3 :KEWAUNEE 2259 :000 103/02 304/10 MODE 6 -
- REFUELING OUTAGE
- DEFUELED FOR 3
LACROSSE 32260 1000 104/87
- DECOMMISSIONING I
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NRC Op;rotionc C:ntcr Plcnt Stccuo for Tucedcy M:rch 8,1988 Un3voluctcd inforaation provid;d by tho Utility GEG PLANT NAME PHONE XPWR DOWN RESTART REASON OR COMMENTS 3
LASALLE 1 32261 3090 :
ADMIN LIMIT OF 96%
J
- POWER DUE TO HIGH
- STEAM FLOW -
REPAIRING Rx RECIRC FLOW CONTROL VALVE 3
LASALLE 2 32261 3066 :
REPAIRING STEAM LEAK **:
ON MAIN TURBINE 3 :MONTICELLO 12263 3100 :
3 : PALISADES
- 2264 1099 :
3 : PERRY 1 32265 100 :
3 : POINT BEACH 1 2266 3100 :
3 : POINT BEACH 2 32266 3100 :
3 : PRAIRIE ISLAND 1 32267 1100 :
3 : PRAIRIE ISLAND 2
- 2267 3100 :
i 3
OUAD CITIES 1 12268 100 :
3 OUAD CITIES 2 32268 3092 :
LOAD FOLLOWING 3
ZION 1 32269 3000 302/25 305/01
- MODE 5 -
COLD S/D REFUELING OUTAGE 4
3 1210N 2 32269 3099 :
3 :CLINTON
- 2270 100 :
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NRC Op;rotionc C:ntcr Plant Stotuo for Tu;;dcy March 8,1988 Un0voluctcd Inform tion provid:d by tha Utility REG PLANT NAME PHONE
FUEL CONSERVATION 4
ARKANSAS 2 2271 3000 302/12 105/88 iMODE 6 -
REFUELING OUTAGE
- DEFUELED 4 : COOPER 12273 2000 03/05 105/88
- COND 4 -
COLD S/D REFUELING OUTAGE 4
FORT CALHOUN 1 12274 3070 :
- CONSERVING FUEL 4
FORT SAINT VRAIN 12275 1077 :
- ADMIN LIMIT OF 78%
- POWER OUE TO NRC LIMIT OF 82% POWER 4
RIVER BEND 1 12276 3075 :
- REPAIRING
'B' MFW
- PUMP 4
SOUTH TEXAS 12277 :000 303/08
- MODE 2 -
- STARTUP 4
WATERFORD 3 12278 3100 :
4 WOLF CREEK 1
- 2279 100 :
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NRC Op3rotleno C nter Plant Status for Tuesday March 8,1988 Unevaluated Information provided by the Utility REG PLANT NAME PHONE
5 :DIABLO CANYON 1 2281 3000 303/06 305/15
- MODE 3 -
HOT S/8 i
REFUELING OUTAGE 5 :DI ABLO CANYON 2 32281 1100 :
5 :PALO VERDE 1 2282 3001 :
MODE 2 -
STARTUP 5 :PALO VERDE 2 12283 3000 102/20 205/88 iMODE 6 -
REFUELING OUTAGE 5 :PALO VERDE 3
- 2284 100 :
5 3 RANCHO SECO 2285 3000 :12/B5 303/20 MODE 3 -
HOT S/B 4
- MAINTENANCE OUTAGE 4
5 SAN ONOFRE 1 32286 3000 102/14 303/31 iMODE 5
- COLD S/D 1,
MAINTENANCE OUTAGE 5
SAN ONOFRE 2 12287 100 :
355.2 GPD TUBE LEAK IN #E-088 S/G 5
SAN ONOFRE 3 12287 1100 :
5 : TROJAN 12288 3100 :
l 3
WNP 2 12289 1079 :
- INCREASING POWER l
l l
- - REASON OR COMMENT HAS CHANGED IN THE PAST 24 HOURS.
4 O - REACTOR SCRAM IN THE PAST 24 HOURS.
NOTE - REACTOR STATUS DATA COLLECTED BETWEEN 4
4 A.M.
AND 8 A.M.
EACH DAY.
ALL TIMES ARE BASED ON EASTERN TIMES (ET).
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