ML20148D067
| ML20148D067 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point, Cooper, Sequoyah, Susquehanna, Ginna, Clinton, South Texas, San Onofre, Yankee Rowe, 05000000, Crane |
| Issue date: | 03/17/1988 |
| From: | NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| References | |
| NUDOCS 8803230265 | |
| Download: ML20148D067 (27) | |
Text
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- g-
- I HEADQUARTERS DAILY REPORT i
March 17, 1988 There is NO Daily Report Today.
COC****************************************************************************
l 0FFICE OF SPECIAL PROJECTS DATE: March 17, 1988 rheility: Sequoyah Unit 2 RESTART DAILY STATUS REPORT 1.
Plant Status as of 0600 a.m., March 17, 1988 Unit 2 is in hot standby (mode 3), with three RCPS operating. The RCS is currently at 546 degrees F and 2250 psig through a process of normal RCS charging / letdown.
MSIVs are open.
Pressurizer level is normal.
Motor driven aux 11 airy f eedwater pumps are maintaining steam generator levels in the operating range.
The condensate system is on short cycle and there is a vacuum in the main condenser.
2.
Problems / Major Issues Completion of Mode 2 related items.
Reviewing the need to perform Appendix R work in the containment annulus.
Pesolve rod postion indication problem with control bank D and complete SI-43 rod drop testing.
J.
Major Event s 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 16 the licensee completed trouble shooting / repair of the rod control system and repeated SI-ll rod exercises. On March 17 at approximately 6:30 a.m..
the licensee was performing SI-43 rod drop time tests, and found that the group demand step counter in the control room again differed from the group demand position in the rod control logic cabinet by approximately 6 steps.
This indicated that the rods had moved in but the remote position indication in the control room had not.
The licensee manually opened the reactor t rip breakers as required by TS 3.1.3.3.
All equipment functions and operator actions were acceptable. The licensee intenJs to make an ENS call within four hours.
The licensee is currently evaluating TS 3.1.3.3 to determine if it is tppropriate to initiate a reactor t rip in these misalignment situations.
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-l steps prior to entry into mode 2.
Resolve mode 2 related open items.
Complete TS required surveillances to support mode 2.
Review Appendix R issues.
Investigate the cause of rod control bank D indicating problems.
j SI-43 (rod drop time measurements) 8803230265 880317 q
9 '
PDR ADOCK O R
PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION I MARCH 17, 1988 Licensee / Facility Notification / Subject Ginna 3/17 SRI PC DN 50-244 Forced Outage Update Event On 3/14, the licensee declared an Unusual Event as a result of Reactor Coolant System (RCS) leakage into the B Steam Generator (S/G) greater t han Technical Specification leakage (refer to PN dated 3/15). On 3/17, the licensee idantified a leaking tube on the hot leg side of the B S/G.
The tube had not been previously plugged or sleeved, and was leaking a steady stream under static hegd pressure.
The licensee stated that the review of eddy current testing during the recent refueling outage did not identify the tube as needing repair due to human error in reviewing the computer resnits. Corrective action is to review the computer results for both Steam Generators to insure no other errors were made.
The licensee plans to hydrostatically test the B S/G to look for other leaks, then begin repairs.
Resident inspectors will monitor the licensee *s progress during the course of the outage.
Licensee / Facility Notification / Subject PP&L Co.
3/17 SRI PC Susquehanna Unit 1 Plant Shutdown DN 50-387 Event On 3/16, unit I was shutdown to replace the seal package on the
- A*
recirculation pump.
Previously, during a startup on 3/10 from a maintainenco outage. the licensee had noted the inner seal had failed.
The outer seal remained functional. The design allows for continued operation with only one of the seals operational. The licensee decided to continue to operate at power until replacement parts and equpment were available to changeout the old seal pschage. Duration of the outage is expected to be six days in which the seal package will be replaced and several other maintenance items will be accomplished.
The resident inspector is monitoring the licensee *s activities.
REGION I MDRNING REPORT PAGE 2 MARCH 17, 1938 Licensee / Facility Notification / Subject Three Mile Island (TMI) 3/17 RI PC Unit 1 Failure of a Reactor DN 50-289 Trip Breaker Event On 3/16 the licensee identified a failure of one of four of the d.c.
reactor trip breakers to open on undervoltage (UV).
The shunt trip device functioned properly during the test.
Surveillance testing which is accomplished monthly on each of the f our channels, was being accomplished on Reactor Protective System (RPS) Channel.4 in accordance with an approved surveillance procedure.
The breaker, a GE AK 1-15-2 is wired such that an UV signal will actuate both the UV coil and the shunt trip coil.
In this case, the UV device trip paddle was out of position such that when the armature of the UV coil deenergized, the trip paddle was unable to move to trip the breaker.
This was verified during testing as the UV ind shunt t rip coils are tested separately. If the breaker had been called upon to function in an actual UV condition, the breaker would have tripped.
The licensee is presently examining the breaker to attempt to determine the cause.
The breaker was replaced with a Spare and the RPS channel returned to service.
The residents will follow up on a licensee examination of the subject breaker.
Licensee / Facility Notification / Subject Yankee Nuclear Power Station 3/17 RI Fax DN 50-29 Information Item - Organization Change Event The licensee announced that effective 3/16 T. K. Henderson. Technical Director, has been appointed Assistant Plant Superintendent.
R. A.
Mellor has been appointed Technical Director.
Training and Operations will report to the Assistant Plant Superintendent-Reactor Engineering. Chemistry. Technical Sarwices and Radiation Protection will report to the Technical Director. The Administrative Services Manager and Maintenance will report directly to the Plant Superintendent. This re-organization was implemented as a result of the previous Assistant Plant Superintendent. Mr. Bruce Drawbridge, being appointed to the position of Vice President and Manager of Operations on 3/11.
l REGION I MORNING REPORT PAGE 3 MARCH 17, 1988 Licensee / Facility Notification / Subject Nine Mile Point 1 3/16 ENS DN 50-220 Station employee tested positive for cocaine.
Event At 4:20 p.m. 3/16, the licensee notified the resident inspectors and the HQ Duty Of ficer that a station employee was tested positive for cocaine and had been denied future access to the site.
The individual was employed as a utility mechanic in the Fire Department with firewatch and fire patrol responsibilities which provided him access to vital areas. The individual had participated in t he Employee Assistance Program for an earlier drug problem and was tested in accordance with the rehabilitation followup requirements. Licensee representatives stated that the individual's employment would terminated.
PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION III MARCH 17, 1988 FACILITY / LICENSEE:
NOTIFICATION / SUBJECT CLINTON POWER STATION /
LICENSEE VIA ENS /0PERATION OUTSIDE ILLINDIS POWER COMPANY DESIGN BASIS AS DESCRIBED IN FSAR EVENT EVENT NO: 11768 AT 12:50 P.M. CST ON MARCH 16, 1988, THE LICENSEE IDENTIFIED, DURING AN ENGINEERING REVIEW OF A MAINTENANCE REQUEST. THAT THE STATION'S EMERGENCY DIESEL GENERATOR VENTILATION SYSTEM (VD) WAS APPARENTLY NOT CAPABLE OF PERFORMING AS STATED IN THE FSAR.
DURING THE CONDUCT OF AN ANNUAL FIRE PROTECTION SURVEILLANCE TEST ON MARCH 14, 1988, THE DIVISION II DIESEL VENTILATION FAN FAILED TO TRIP ON ACTUATION OF THE ASSOCIATED CARBON DIOXIDE (CO2) FIRE SUPPRESSION SYSTEM.
THE DESIGN INTENT AS STATED IN THE FSAR (SECTION 9.4.5.1.2 El WAS TO TRIP THE DIESEL GENERATOR VENTILATION FAQ UPON AN ACTUATION SIGNAL OF THE CO2 FIRE PROTECTION SYSTEM.
THIS WOULD ASSURE THAT THE CO2 WAS NOT REMOVED FROM THE DIESEL GENERATOR ROOM BY THE VENTILATION SYSTEM. AFTER THE SURVEILLANCE TEST FAILURE ON MARCH 14, THE LICENSEE ESTABLISHED A CONTINUOUS FIRE WATCH IN ACCORDANCE WITH THEIR FIRE PROTECTION PROGRAM AND INITIATED A MAINTENANCE WORK REQUEST TO INVESTIGATE AND MAKE REPAIRS.
DURING THE REVIEW OF THAT MAINTENtNCE REQUEST ON MARCH B6, IT WAS DISCOVERED THAT THE VD TRIP LOGIC WAS BYPASSfD BY A LOW TEMPERATUS_ SWITCH WHEN DIESEL ROOM TEMPERATURES ARE BELOW 70 DEGREE F.
THE LICENSEE *S INITIAL REVIEW INDICATED THAT THIS TRIP LOGIC BYPASS WAS PRESENT IN ALL THREE DIVISIONS OF THE VD SYSTEM.
THE LICENSEE HAS ESTABLISHED 4 CONTINUOUS FIRE WATCH IN ALL THREE DIESEL GENERATOR ROOMS AND THE DIVISIONAL DIESEL VENTILATION FAN CONTROL SWITCHES HAVE BEEN CAUTION TAGGED TO INSTRUCT CONTROL ROOM OPERATORS TO MANUALLY TRIP THE FANS ON A CO2 ACTUATION ALARM.
THE EMERGENCY DIESEL VENTILATION FANS RECEIVE AN AUTOMATIC START SIGNAL ON START OF THEIR ASSOCIATED DIESEL AND THE ONLY AUTOMATIC TRIP SIGNAL IS THE CO2 ACTUATION. THE PLANT WAS OPERATING AT 90% POWER AT THE TIME OF EVENT DISCOVERY. THE LICENSEE INFORMED THE NRC OPERATIONS CENTER OF THIS EVENT VIA THE EMS AT ABOUT 1:45 P M.
CST ON MARCH 16, 1988.
REGIONAL ACTION:
FOLLOWUP BY RESIDENT INSPECTORS ON LICENSEE'S DETERMINATION OF DESIGN REQUIREMENTS.
PRIORITY ATTENTION REQUIRED MORNING REPORT-REGION IV MARCH 17, 1988 j
LICENSEE / FACILITY NOTIFICATION / SUBJECT HOUSTON LIGHTING & POWER CO.
TELEPHONE CALL TO THE NRC SOUTH TEXAS PROJECT HEADQUARTERS FROM THE STP DN:
50-498 OPERATIONS SHIFT SUPERVISOR 50-499 AT 1:42 A.M.
(EST) ON MARCH 17, 1988, REGARDING THE DECLARATION OF A NOTICE OF AN UNUSUAL EVENT (NOUE)
DUE TO A CREDIBLE THREAT DIPECTED AT THE SITE i
EVENT:
A THREAT AGAINST THE STP PLANT WAS RECEIVED AT THE ELECTRIC TOWER IN HOUSTON AT 11:30 P.M.
(CST) ON MARCH 16 1988.
THE CALLER STATED THAT TWO POWER POLES IN GREENSPOINT NEAR HOUSTON, HAD BEEN CUT DOWN.
THE CdLLER ALSO SAID THAT "THE NEXT TARGET TO BE HIT WILL BE THE BAY CITY POWER PLANT IN 2 HOURS, PLEASE TURN THE LIGHT BACK ON."
STP OPERATIONS WAS NOTIFIED OF THIS CALL AT 11:52 P.M. (CST).
AT 12:16 A.M.
(CST) 00 MARCH 17 1988, STP CONFIRMED THAT TWO WOODEN POWEF
- OLES HAD BEEN CUT DOWN AND THE SITE DECLARED A NOUE.
THE CL3NIZANT SHERIFF. COUNTY, STATE OFFICIALS, AND THE FBI WERE NOTIFIED BY THE LICENSEE. CONTINGENCY PLANS WERE IMPLEMENTED AND THE SITE SECURITY FORCE BEGAN SEARCHES OF THE SITE FOR A BOMB.
VISITOR ACCESS TO THE SITE WAS SUSPENDED, A CONFERENCE CALL WAS CONDUCTED BETWEEN AEOD, NRR, IAT, RIV, AND STP EMERGENCY DIRECTOR AT 1:45 A.M.
(CST) CONCERNING THE SCOPE OF THE LICENSEE *S RESPONSE TO THE EVENT.
THE SITE SECURED FROM THE 1
NOUE AT 4:07 A.M.
(CST) WHEN THE SEARCH WAS COMPLETED AND NO i
EXPLOSIVE DEVICE WAS FOUND.
LICENSEE / FACILITY NOTIFICATION / SUBJECT NEBRASKA PUBLIC POWER DISTRICT TELEPHONE CALL FROM SRI COOPER NUCLEAR STATION ESF ACTUATION DN; 50-298 EVENT:
AT 5:08 P.M.
ON MARCH 16, 1988 WITH THE PLANT IN COLD SHUTDOWN, j
THE NORMAL 4.16KV SUPPLY BREAKdR TRIPPED WHILE THE BREAKER i
OVERCURRENT RELAY WAS BEING REPLACED AFTER TESTING. DIESEL GENERATOR 81 STARTED, BUT DID NOT LOAD BECAUSE THE BUS HAD BEEN I
REENERGIZED FROM THE EMERGENCY TRANSFORMER. THE LICENSEE HAS CETURNED THE SYSTEM TO NORMAL.
THE RESIDENT INSPECTORS ARE MONITORING LICENSEE CORRECTIVE ACTIONS.
PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION V MARCH 17, 1988 LICENSEE / FACILITY NOTIFICATION / SUBJECT I
SAN ONOFRE UNIT 2 3/17/88, RESIDENT INSPECTOR DN 50-361 TO REGION V/ STEAM GENERATOR TUBE LEAK REN N/A FORCED OUTAGE EVENT ON THE EVENING OF MARCH 16 1988 SOUTHERN CALIFORNIA EDISON (SCE) COMMENCED A REACTOR 2
SHUTDOWN AS A RESULT'Of A STEAM GENERATOR TUBE LEAK.
THE LICENSEE FIRST NOTICED A PRIMARY TO SECONDARY LEAK IN FEBRUARY, 1988 (SEE MORNING REPORT OF MARCH 3, 1988).
2 HOWEVER. THE AMOUNT OF TUBE LEAKAGE REMAINED BELOW 60 GALLONS PER DAY (GPD. AS DETERMINED BY CESIUM 138 CONCENTRATIONS) UNTIL MARCH 15, 1988 AT WHICH TIME THE AMOUNT INCREASED i
TO 77 GPD.
THE UNIT TECHNICAL SPECIFICATIONS LIMIi FOR TUBE LEAKAGE IS 720 GPD PER STEAM GENERATOR.
ON THE MORNING OF MARCH 16, THE LEAK RATE NAD INCREASED FURTHER T (,
86 GPD.
AS A RESULT. SCE SCHEDULED A REACTOR SHUTDOWN FOR THE EVENING SHIFT TO EFFECT REPAIRS.
A FINAL MEASUREMENT SHORTLY BEFORE SHUTDOWN INDICATED THAT TU8E LEAKAGE HAD INCREASED TO 200 GPD.
SCE EXPECTS THAT THE OUTAGE SHOULD TAKE 3 TO 4 WEEKS AND HOPES TO HAVE UNIT 2 BACK ON LINE PRIOR TO THE UNIT 3 REFUELING OUTAGE SCHEDULED FOR MID APRIL 1988.
THE RESIDENT INSPECTORS ARE FOLLOWING THE LICENSEE *S ACTIONS.
REGIONAL ACTION: FOLLOWUP PER MC 2515 TO ENSURE ADEQUATE LICENSEE CONTROLS ESTABLISHED.
CONTACT:
P.
JOHNSON (FTS) 463-3745 s
e i'
i
NRC DPERATIONS CENTER i
1 PLANT STATUS REPORT FOR 17-NAR-BO l-UNEVALUATED INFCRMATION PROVIDED BY THE UTILITY REG PLANT NAME PHONE %PWR DOWN RESTART REASON OR COMMENTS 1
BEAVER VALLEY 1 32201 :100 3
1 BEAVER VALLEY 2 32201 100 a
1 :CALVERT CLIFFS 1 32202 : 97 1 :CALVERT CLIFFS 2 2202 302/26 303/28
- MODE 5 -
s'OLD S/D C
MAINTENANCE OUTAGE' 1 :FITZPATRICK 32203 64
- PROBLEM WITH "B" RTR : :
FEED PMP 1':GINNA 32204 303/15 803/27 UNIT S/D DUE TO S/G
- TUBE LEAK >TS MAX.
REFER TO EVENTM11757 :
- DRAINED S/G FOR
- INSPECTION 1 :HADDAM NECK 2205 307/18 303/20 MODE 3 - HOT S/B.
1 HOPE CREEK 1 32206 302/13 304/08 COND 5 -
REFUELING OUTAGE:
FUEL ROD SHUFFLE IN
- PROGRESS.
1 INDIAN POINT 2 2207 3100 30.001 GPM SG TUBE LEAK (1.44 GPD).
1 :!NDIAN POINT 3 32200 3100 1
LIMERICK 1 32209 3100 1 : MAINE YANKEE 2210 3100 1 : MILLSTONE 1 32211 100 1
MILLSTONE 2 2211 e100 a_--------------------------------------
1 MILLSTONE 3 32211 : 99 1 :NINE MILE PDINT 1 2213 312/19 304/01
- COLD S/D.
REFUELING OUTAGE
-=-----------------------------------------
1 NINE MILE POINT 2 2213 :
- 03/13 303/17
- MODE 2 1 30YSTER CREEK 32215 : 99 1 : PEACH BOTTOM 2 32216 :
303/13 :UNK 3COND 5 -
REFUELING CONDITION MAINTENANCE OUTAGE NRC ORDER
....__ l _., _ _ _
m (J
NRC OPERATIONS CENTER PLANT STATUS REPORT FOR 17-MAR-88 UNEVALUATED INFORMATION PROVIDED BY THE UTILITY qp
---_--------__------_-------OWN RESTART REASON OR COMMENTS PHONE XPWR D
~~----
PLANT NAME
303/31-------------------------EFUELING.
a g
- UNK COND 5 - R
- PEACH BOTTOM 3 32216
- PIPE REPLACEMENT.
- DEFUELED
(
NRC ORDER
304/86 307/88 COND 4 -
2217
(
- PILGRIM i
- COLD S/D-----------------
.-----------------------------100---------------------------- TUBE LEAK
- 13 S/G
- S44/M29/T21/W20/T_ g,:
(
32210 SALEM 1 F
GPD.
(
.-----------------------Q218 3100 SALEM 2 3
1.-----------------------------------:- - -
UNK MODE 5 -
(
a :
2219 :
1 SEABROOK 1 COLD S/D
0-----------------------------4 306/08 304/88 COND I
3222 1
SHOREHAM COLD S/D
33/17-------------------------------IR 33/21 RTR S/D FOR REPA 32221
- OF #1 SEAL ON "A"
1 :SUSQUEHANNA 1 3RECIRC PMP
.------------------- ----------------303/05 305/15 PCOND 5 -
a 1
SUSQUEHANNA 2 32221 REFUELING OUTAGE
-----100 l1 :THREE MILE ISLAND 1 32222 3
303/79 UNK 3 RECOVERY 1 :THREE MILE ISLAND 2 32222
--- 24 3100 1
VERMONT YANKEG 22
5:--------------------------- DRAIN PMP HTR 3222 88 1 : YANKEE ROWE
- PROBLEM
_L-_ --------------------------- -------------------------------------------
e 1
i l
NRC OPERATIONS CENTER PLANT STATUS REPORT FOR 17-MAR-88 UNEVALUATED INFORMATION PROVIDED BY THE UTIt.ITY REG PLANT NAME PHONE
%PWR' DOWN RESTART REASON OR COMMENTS 2
BROWNS FERRY 1 617 32229 :
303/05 UNK COLD SHUTDOWN -
REFUELING OUTAGE
- DEFUELED 2
BROWNS FERRY 2_751 32229 :
309/04 UNK COLD SHUTDOWN -
a :
REFUELING OUTAGE
- DEFUELED 2
BROWNS FERRY 3_ 070(!'229 :
03/85 :UNK 3 COLD SHUTDOWN -
- REFUELING OUTAGE
- DEFUELED 2
BRUNSWICK 1 3 22JO 3100 2
BRUNSWICK 2 32230 301/02 304/20
- COND 5 -
tRF. FUELING OUTAGE i
..-------------n----------------------------
2 : CATAWBA 1 32231 : 98 s
2 : CATAWBA 2
-7231 303/09 UNK MODE 3, HOT S/B;
s,-,-.y,---.-------..
--<u------------------L-.----------------------
2 : CRYSTAL RIVER 3 32253 *100 2
FARLCY_1 12734 3100
o-----..-_---__-...---_---___-.._--__----_----_---___-_______-__---
l 2
FARLEv 2 12234 tico l
l 2 : GRAND GULF 1 32235 : 55 3
- INC POWER
,-_.--.~,-_----->.----______-------__---________-__--__-
i 2 : HARRIS 1 32235 1100 1
2 : HATCH 1 32237 100 2
HATCH 2 32237 :
101/13 :UNN COND 4 -
- REFUELING OUTAGE l
2 MCGUIRE 1 3223.9 100 1-s-...---------------------------------------
- I 2
MCGUIRE 2 32239 5100 e
l' 2
NORTH ANNA 1 2240 a 24
- CONDEf3ER TUBE LEAK 1
,.-n-----.
g 2 : NORTH ANNA 2 32240 s 1 0 C-a
,-------------------.-----n------~~..----------
2 :OCONEE 1 32241 31GO g
2 :OCONEE 2 2241 :
.02/04 C/?4 eMOCE 6 -
sREFUELING OUTAGE riiEFUELED g
6 80-0154G'l S/G TURE 2
OCONEE 3 32241 100 LEAK & 3 MALL OMOUNT g
OF FAILFD F{2L
a...--------------..------------
B 1
.i-t 1
PLANT GTATUS REPORT FOR 17-MAR-23 C)
UNEVALUATED INFORMATIDN PROVIDED CY THE UTILITY
-- T REASON OR COMMENTS
---- ----- %PWR i
DOWN RESTAR PHONE
()
PLANT NAME
---.--__-----------------_ LIMITED TO MAX PWR
---_------_-_242 : 60 32 OF 60% BY NRC DUE TO
- ROBINSON 2 ANALYZED FAILURE
()
MODE FOR B1 PUMPS DURING ACCIDENT.
()
--__-- _-_-_-____----_--_- MODE 5 -
-_-_____-_2243 308/85 :UNK
- SEQUOYAH 1 3
COLD S/D -
CONFIRMING EQ OF
()
SAFETY SYSTEMS
.-----_-__ --______-- -2243------__--------------_0 MODE 3 -
.' i 308/85 303/2 SEQUOYAH 2 HOT S/B 3
_--_----__-----_--__-_244.--___-0 g
32 310 iST. LUCIE 1 i
< _ _----- _-___ _____ __-_-___100
- 2244 3 a
ST. LUCIE 2 j
- ---_-_-_- _----_ _----_32245 3100 q
I SUMMER 32246 : 92 Sur"Y 1 3
l
)
32246 3100
(
ll SURRY 2
__-------_-- -------_- MODE 3 MOISTURE
-_-_-_--_-_---2247 23/16 33/31 i
SEPARATOR AND REHTR 3
2 : TURKEY POINT 3 t
- PROBLEM 1
l i !,
-__--__-__--_-_-_____-__2247 3100
,2 : TURKEY POINT 4 1
3
___- -_---- - -------_-_-_100 32248 3
- -____GTLE 1 2
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r PLANT OTATUS REPORT FOR 17-MAR-28 og UNEVALUATED INFORMATION PROVIDED BY THE UTILITY i
tEG PLANT NAME PHONE XPWR DOWN RESTART REASON OR COMMENTS 3
BIG ROCK POINT 82250 : 81 e
LIMITED TO 87% POWER : :
- DUE TO FUEL THERMAL LIMITS.
COASTDOWN.
_---__--__---__-----__--_----------__--__-----_--__--_'EOL 3
BRAIDWOOD 1 2251 301/02 303/31 MODE 4 -
HOT S/D 3 *BRAIDWOOD 2 12251 33/16
- UNK MODE 3 REUTEW OF IS/U TEST s -
3 BYRON 1 32252 : 98 ADMIN LIMIT OF 98%
- POWER DUE TO S/G UPPER NOZZEL FLOW LIMITATIONS 3
BYRON 2 32252 : 67 ADMIN LIMIT OF 94%
- POWER DUE TO FW FLOW LIMITATIONS
- FEEDWATER PMP
- TROUBLESHOOTING l
3 :CALLAWAY 1 32253 100 3
COOK 1
- 2254 : 90
- ADMIN LIMIT OF 91%
- POWER TO EXTEND S/G
- TUBE LIFE 3
COOK 2 2254 : 80
- ADMIN LIMIT OF 81%
- POWER TO EXTEND S/G
- TUBE LIFE 3 : DAVIS-BESSE 1 32255 :
303/10 UNK MODE 5, COLD S/D; a
REFUELING OUTAGE.
\\-_-----_____----_----_-----_____--_--_--__--_----_----_----__-_--_-_-_----_-__-
,,3 :DRESDEN 2 32256 : 93 LOAD FOLLOWING 1 ---____--__------_--------------_-_----_-----_---------------------------------
3 :'DRESDEN 3 32256 : 92
.s.
- LOAD FOLLOWING 3 :DUANE ARNOLD 2257 :100 9
- 2258 :
302/27 304/15
- MODE 4 -
3 : FERMI 2
- COLD S/D MAINTENANCE OUTAGE 3 :KEWAUNEE 2259 :
303/02 304/10 MODE 6 -
REFUELING OUTAGE
- DEFUELED FOR 3
LACROSSE 32260 304/87
- DECOMMISSIONING 3
LASALLE 1 12261 :
303/13 306/15
- COLD S/D.
REFUELING OUTAGE.
NRC OPERATIONS CENTER PLANT CTATUS REPORT FOR 17-MAR-BO UNEVALUATED INFORMATICN PROVIDED BY THE UTILITY REG PLANT NAME PHONE XPWR DOWN RESTART REASON OR COMMENTS 3
LASALLE 2 32261 303/09 UNK
- STARTUP NODE i
3 MONTICELLO 2263 3100 3 : PALISADES 32264 3100 3 : PERRY 1 2265 3100 3 : POINT BEACH 1 32266 3100
______________________________________________________________________,s_______
3 : POINT BEACH 2 32266 3100 3 : PRAIRIE ISLAND 1 32267 3100 3 : PRAIRIE ISLAND 2
'32267 3100 3
QUAD CITIES 1 32268 3100 3
OUAD CITIES 2 32268 : 92
- LOAD FOLLOWING 3 : ZION 1 2269 :
802/25 305/01 MODE 6 -
REFUEL REFUELING OUTAGE 3
ZION 2 32269 : 63 32 S/G SAFETIES OUT
- OF TOLERANCE.
3 :CLINTON 22270 : 90 "A" RECIRC FLOW
- CONTROL VALVE
- PROBLEM e
f 8
0 4
r e
i NRC OPERATIONS CENTER PLANT GTATUS REPORT FOR 17-MAR-88 UNEVALUATED INFORMATION PROVIDED BY THE UTILITY REG PLANT NAME PHONE
%PWR DOWN RESTART REASON OR COMMENTS 4 1 ARKANSAS 1 32271 : 80 FUEL CONSERVATION 4
ARKANSAS 2 32271 302/12 305/88 MODE 6 -
REFUELING OUTAGE
- DEFUELED 4
COOPER 32273 303/05 305/88
- COND 4 -
COLD S/D REFUELING OUTAGE 4 : FORT CALHOUN 1 32274 : 70
- CONSERVING FUEL 4 : FORT SAINT VRAIN '
- 2275 : 77 ADMIN LIMIT OF 78%
POWER DUE TO NRC LIMIT OF 82% POWER.
4 3 RIVER BEND 1 32276 3100 4 : SOUTH TEXAS 32277 303/16 803/19 MODE 3, HOT S/B.
4 WATERFORD 3 32278 3100 4 : WOLF CREEK 1 2279 2100 e
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NRC OPERATIONS CENTER PLANT STATUS REPORT FOR 17-MAR-88 UNEVALUATED INFORMATION PROVIDED DY THE UTILITY REG PLANT NAME PHONE
%PWR DOWN RESTART REASON OR COMMENTS
- M 5 :DIABLO CANYON 1 2281 :
03/06 305/15 NODE 5
~
COLD S/D REFUELING OUTAGE 5 :DIABLO CANYON 2 32281 3100 5 :PALO VERDE 1 12282 95
_____________________________________e______________________________________ ___
5 :PALO VERDE 2 32283 302/20 205/88
- MODE 6 -
REFUELING OUTA
_____________________________________________________________________GE 5 :PALO VERDE 3
- 2284 100 5 3 RANCHO SECO 2285 :
312/05 303/20
- HOT S/D MAINTENANCE
__________________________________________________________________ OUTAGE :
5 SAN ONOFRE 1 2286 302/14 303/31 3 MODE 5
- COLD S/D MAINTENAN
_______________________________________________________________CE OUTAGE 5 : SAN ONOFRE 2 2287 :
33/17
- 4/9
- S/D FOR REPAIR OF
- S/G TUB
_____________________________________________________________E LEAK 5
SAN ONOFRE 3 32287 3100 5 : TROJAN 32288 100 1
5 WNP 2 32289 :100 t
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EVENT REPORT NUMBER 11763 FCcility :
SEQUOYAH Data Notified : 03/16/88 Unit : 2 Tine Notified : 02:19 R0gion : 2 Dat.e of Event : 03/16/88 V ndor : WEST, WEST Tire of Event : 00:36 Operations Officer :
Chauncey Gould Claesification : 10 CFR S0.72 NRC Notified By : SCHOFIELD Category 1 : LCO Ac'clon Statement R2d Release : No Category 2 : SCRAM Cause : Unknown Category 3 :
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Category 4 :
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RTR IN MODE 3. WHILE THE PLANT WAS CONDUCTING A SURVEILIANCE ON THEIR ROD l
CONTROL SYSTEM, THEY DETERMINED THAT THEIR GROUP DEMAND POSITION INDICATOR DIFFERED BY MORE THAN + OR - 2 STEPS (CAUSE UNKNOWN AND BEING INVESTIGATED)
FROM THE DEMAND POSITION. TS REQUIRED THE RTR TRIP BREAKERS BE OPEN l
IMMEDIATELY AND THAT RESULTED IN THE SCRAM OF THE 9 RODS IN CONTROL BANK "D" I
WHICH WERE OUT 6 STEPS FROM THE BOTTOM. PLANT HAD FEEDWATER ISOLATION AND
AUX FEEDWATER WAS ALREADY RUNNING. NOTIFIED RDO SROWNLEE, OSP ZECH k
EVENT REPORT NUMBER 11764 FCcility :
RANCHO SECO Date Notified : 03/16/88 Unit : 1 Time Notified : 02:24 R gicn : 5 Date of Event : 03/16/88 V0ndor : B&W Time of Event : 01:49 Operations Officer :
Chauncey Gould Classification : Unusual Event NRC Notified By : HURLEY Category 1 : LCO Action Statement R1d Release : No Category 2 :
C:uco : Mechanical Failure Category 3 :
Couponent : VALVE PACKING Category 4 :
6 RTR IN HOT S/D. DURING A TEST STROKING OF THE L/D COOLER "A" INLET VALVE "SFV22005", THE VALVE PACKING FAILED CAUSING A RCS LEAK RATE OF APPROX 91GPM (TS 10GPM). THE LEAK WAS TERMINATED WHEN THE VALVE WAS ISOLATED (WITHIN APPROX 3-5 MIN). THERE WAS NO RAD RELEASE TO ATM AND NO PERSONNEL CONTAMINATION. ALL PARAMETERS WERE STABLE SMIN AFTER THE EVENT. THE NOUE WAS TERMINATED AT 02:17ET. NOTIFIED RDO WENSLAWSKI, EO MARSH, MURLEY, JORDAN, FEMA l
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EVENT REPORT NUMBER 11765 Fccility :
NINE MILE PT Date Notified : 03/16/88 Unit : 1 Time Notified : 11:39 R:gion : 1 Date of Event : 03/16/88 Vcndor : GE,GE Time of Event : 11:00 Operations Officer :
John MacKinnon Classification : 10 CFR 50.36 NRC Notified By : FRAN LUKACZYK Category 1 : TS VIOLATION rid Release : No Category 2 :
C;uce : Personnel Error Category 3 :
C0cponent :
Category 4 :
12 UNIT 1 CORE IS DEFUELED. SEE EVENT REPORT f 11237 DATED 01/15/88 9 17:18EST FOR BACKGROUND INFORMATION. FROM ADDITIONAL REVIEW OF IN SERVICE INSPECTION COMMITMENTS SEVERAL EXAMINATIONS NOT PREVIOUSLY IDENTIFIED FROM LER 8.8-01(COULD NOT GIVE TITLE OF LER) WERE FOUND. SYSTEMS THAT WERE AFFECTED WERE REACTOR PRESSURE VESSEL (RPV), SYSTEM 01(MAIN STEAM), SYSTEM 31(FEEDWATER), SYSTEM 32(RECIR PUMPS), SYSTEM 39(EMERGENCY COOLING) AND SYSTEM 4 0(CORE SPRAY). THE PERSON ON THE PHONE COULD NOT TELL WHAT WAS WRONG WITH THE ABOVE SYSTEMS BUT HE SAID IT DID NOT AFFECT PLANT CONDITIONS. HE SAID TMAT THEY HAD NOT MET THE TEN YEAR INSPECTION INTERVAL (ASME CODE SECTION
- 11) ON THESE ABOVE SYSTEMS. THESE WILL BE CORRECTED BEFORE THE END OF THE REFUELING OUTAGE. RI WILL BE INFORMED BY THE LICENSEE. R1DO(MARIE MILLER)
NOTIFIED.
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EVENT REPORT NUMBER 11766 FOcility :
LASALLE Date Notified : 03/16/88 Unit : 1 Time Notified : 12:30 Region : 3 Date of Event 03/16/88 V:ndor : GE,GE Time of Event : 11:00
@ rations Officer :
S. SANDIN Classification : 10 CFR 50.72 B C Notified By : MCCONNAUGHAY Category 1 : b.i Rad Release : No Category 2 :
Cauce : Unknown Category 3 :
Component :
Category 4 :
G UNIT 1 IS CURRENTLY IN MODE 4 (COLD S/D) PROCEEDING TO MODE 5 FOR A SCHEDULED REFUELING OUTAGE.
AT 1000 CST DURING SCHEDULED LOCAL LEAK RATE TESTING TOTAL TYPE "B" AND TOTAL TYPE "C" LEAKAGE WAS OBSERVED TO BE IN EXCESS OF 0.6 L SUB A-(LEAKAGE COEFFICIENT).
ACTUAL THROUGH LINE LEAKAGE HAS NOT BEEN DETERMINED AT THIS TIME.
LICENSEE WILL CORRECT DURING REFUELING OUTAGE AND HAS INFORMED RI.
NOTIFIED R3DO(J. HARRISON).
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EVENT REPORT NUMBER 11767 Fccility :
MILLSTONE Date Notified : 03/16/88 Unit : 1,2,3 Time Notified : 12:56 R:gicn : 1 Date of Event : 02/18/88 VCndor : GE,C-E, WEST Time of Event : 16:20 OperGtions Officer :
John MacKinnon Classification : RETRACTION NRC Notified By : PATRICA WEEKLEY Category 1 : Security R0d Release : No Category 2 :
C;ure : Personnel Error Category 3 :
Co2ponent :
Category 4 :
4 RETRACTED SECURITY EVENT # 11536 REPORTED ON 2/18/88 9 1520EST BECAUSE AFTER DISCUSSION WITH REGION 1(BILL KUSHNER) THEY FOUND OUT THEY HAD MET THE COMPENSATORY MEASURES WITHIN 10 MINUTES. THEY HAVE ENTERED THE EVENT INTO THEIR LOG. RI WLL BE INFORMED BY THE LICENSEE. R1DO(W PASCIAK) NOTIFIED.
- - - ~ -
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EVENT REPORT NUMBER 11768 Fccility :
CLINTON Date Notified : 03/16/88 Time Notified : 14:44 Unit : 1 R:gion : 3 Date of Event : 03/16/88 Vcndor : GE,GE Time of Event : 13:50 Operations Officer :
John MacKinnon Classification : 10 CFR 50.72 NRC Notified By : TAD POND Category 1 : DESIGN ERROR Rtd Release : No Category 2 :
C;une : DESIGN ERROR Category 3 :
Crponent :
Category 4 :
11 REACTOR IS AT 90% POWER. AT 1210EST ON 3/16/88 FIRE PROTECTION ENGINEERING WAS REVIEWING THE AUTO TRIP IDGIC FOR THE 3 EDG's VENTILATION FANS AND NOTICED THAT THE FANS WOULD NOT TRIP WHEN CARBON DIOXIDE INITIATED IN THE ROOM AND ROOM TEMPERATURE IS BEI4W 70 DEGREES F. IF EDG FAN HAS NOT TRIPPED, THE CARBON DIOXIDE USED TO EXTINGUISHED THE FIRE WOULD BE REMOVED BY THE FAN.
THIS INFORMATION WAS VERIFIED BY THE SYSTEM ENGINEER AT 1350EST TO BE A REPORTABLE EVENT. THEY ESTABLISHED CONTINUOUS FIREWATCHES AT THE 3 EDG BAYS AT 1221EST. THEY ARE WORKING ON CORRECTING THIS PROBLEM BUT THEY ARE UNABLE TO GIVE A DATE WHEN THE PROBLEM WILL BE CORRECTED. THIS ABOVE EVENT DOES NOT COMPLY WITH FSAR 9.4.5.1.2.e. RI WILL BE INFORMED BY THE LICENSEE. R3DO(JAY HARRISON) NOTIFIED.
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EVENT REPORT NUMBER 11769 Fccility :
NINE MILE PT Date Notified 03/16/88 Unit : 1 Time Notified : 16:21 Region : 1 Date of Event : 03/16/88 Vcndor : GE,GE Time of Event : 14:37 Operations Officer :
John MacKinnon Classification : Phys.Sec./ Safeguard NRC Notified By : D O'HARA Category 1 : Security R*d Release : No Category 2 :
Cauce : DRUG TEST POSITIVE Category 3 :
C=ponent :
Category 4 4
UNIT 1 IS DEFUELED. UTILITY MECHANIC ASSIGNED TO THE FIRE DEPARTMENT TESTED POSITIVE ON A DRUG TEST GIVEN 03/10/88. PERSON TERMINATED. SEE HOO LOG BOOK FOR FURTHER DETAILS. RI WAS INFORMED BY THE LICENSEE. R1DO(WALT PASCIAl')
NOTIFIED.
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EVENT REPORT NUMBER 11770 Fccility :
COOPER Date Notified : 03/16/88 Time Notified : 18:36 Unit : 1 Date of Event : 03/16/88 R gien : 4 Time of Event : 18:08 VCnder : GE OperOtions Officer :
John MacKinnon Classification : 10 CFR 50.72 NRC Notified By : T RATZLAFF Category 1 : ESF Actuation Rnd Release : No Category 2 :
Cauco : OVERCURRENT RELAY Category 3 :
COCp nent :
Category 4 :
4 11 REACTOR IS IN A REFUELING OUTAGE. WHEN AN OVERCURRENT RELAY (51 DEVICE) WAS REINSTALLED INTO THE "1AF" BREAKER (BY ELECTRICIANS PER A MAINTENANCE.
PROCEDURE) WHICH WAS CLOSED THE BREAKER TRIPPED OPENED DUE TO OVERCURRENT.
THIS TRANSFERRED 4160 VOLTS FROM THE NORMAL STATION BUS TO THE EMERGENCY ELECTRICAL (VITAL) 4160 VOLT BUS ("F" BUS). ALSO f 1 EDG AUTOSTARTED BUT DID NOT PICKUP LOADS. THEY DO NOT KNOW IF THE OVERCURRENT DEVICE IS MISCALIBRATED OR IS DEFECTIVE. THE "1AF" BREAKER IS A "GE" BREAKER BUT THEY DIDN'T HAVE A MODEL NUMBER OR A NAME FOR THE BREAKER. # 1 EDG WAS SECURED AND RESTORED TO A NORMAL LINEUP. THEY DID NOT LOSE POWER. IT JUST TRANSFERRED POWER FROM THE NORMAL STATION POWER LINEUP TO THE EMERGENCY POWER LINEUP. RI WAS INFORMED BY THE LICENSEE. R4DO(DALE POWERS) NOTIFIED.
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EVENT REPORT NUMBER 11771 FCcility SOUTH TEXAS Date Notified 03/16/88 Time Notified : 18:45 Unit : 1 R gion : 4 Date of Event : 03/16/88 Vcndor : WEST, WEST Time of Event : 18:00 Oprations Officer :
John MacKinnon Classification : 10 CFR 50.72 NRC Notified By : DAVID McCALLUM Category 1 : 10 CFR 50.72 2.111 R;d Release : No Category 2 :
Cauce : Unknown Category 3 :
CCIponent :
Category 4 :
13 UNIT IS IN MODE 3(HOT S/D). WHILE PERFORMING A REVIEW OF THE SOLID STATE DESIGN THEY DISCOVERED THAT WHEN YOU RESET THE PROTECTION SYSTEM (SSPS)
SAFEGUARDS TEST CABINET (THEY MAVE 3 OF THEM AND THEY ARE USED FOR SLAVE RELAY TESTING OF THE SSP SYSTEM) MASTER RESET SWITCHES (SWITCHES 121 AND 221 ON EACH OF THE 3 TEST CABINETS) WITH THE REACTOR TRIP BREAKERS OPEN IT WILL BLOCK A SAFETY INJECTION (SI) SIGNAL. SI SIGNAL SHOULD NOT BE BLOCKED ABOVE 1980psig.
THEY COULD NOT TELL ME IF THIS PRESSURE LIMIT CAME FROM TECH SPEC OR FSAR.
THEY HAVE DANGER TAGGED OUT THE SWITCHES TO PREVENT THE OPERATION OF THEM.
THEY ALSO CONTACTED WESTINGHOUSE AND WESTINGMOUSE AGREED THAT THEY HAVE A PROBLEM WITH THE SWITCHES. PRESENTLY THEY HAVE ENGINEERING I40 KING INTR > A WAY TO MODIFY THE SWITCHES SO AN SI SIGNAL WILL NOT BE BLOCKED WHEN PERFORMING THIS MONTHLY TEST AT PRESSURES ABOVE 1980psig. RI WAS INFORMED BY THE LICENSEE. R4DO(DALE POWERS) AND EO(TAD MARSH) NOTIFIED.
ecoccaeacocccococcocooce<cocoeeeeeeeee EVENT REPORT NUMBER 11772 Fccility :
SOUTH TEXAS Date Notified : 03/17/88 Time Notified : 01:42 Unit : 1&2 R;gion : 4 Date of Event : 03/17/88 V ndor : WEST, WEST Time of Event : 00:16 Operations Officer :
Chauncey Gould Classification : Unusual Event NRC Notified By : FITZGIBBON Category 1 : Security R d Release : No Category 2 :
C uce : SECURITY EVENT Category 3 :
C rponent :
Category 4 :
4 RTR IN MODE 3. THREAT AGAINST THE SITE. IMMEDIATE COMPENSATORY MEASURES TAKEN ON DISCOVERY. SEE HOO LOG FOR DETAILS. NOTIFIED RDO POWERS, EO MARSH, AEOD JORDAN,IAT DAVIDSON/GIBSON, FEMA *** UPDATE ***NOUE TERMINATED AT 04:07.
NOTIFIED RDO PASIAK, NMSS EO BELL, IAT DAVIDSON/GIBSON, FEMA i
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EVENT REPORT NUMBER 11773 Fccility : GOLLOB ANALITICAL Date Notified : 03/17/88 Time Notified : 04:55 Unit :
Date of Event : 03/17/88 R:gien : 1 Time of Event : 0 Vandar :
Op3 rations Officer :
Chauncey Gould Classification :
NRC Notified By : FEENEY/NJ BUR ENV RA Category 1 :
red Release : No Category 2 :
CIuce : FIRE Category 3 :
Cc ponent :
Category 4 :
6 THE N.J. BUREAU OF ENVIRONMENTAL RADIATION REPORTED THAT THERE WAS A FIRE AND EXPLOSION WITH TWO PEOPLE REPORTED DEAD AT A NRC LICENSEE (GOLICB ANALYTICAL SERVICES, LICENSE #29-09801-02) IN BERKELEY HEIGHTS IN UNION CITY H.J. THERE WAS NO OTHER INFORMATION AT THE TIME OF THE REPORT. NOTIFIED RDO PASCIAK,NMSS EO BELL *** UPDATE *** THE MATERIALS AT THE LICENSEE WERE KRYPTON 85, TRIDIUM, AND CARBON 14.
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