ML20100L265
| ML20100L265 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/31/1984 |
| From: | Baran R, Fiedler P, Notigan D GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA) |
| References | |
| NUDOCS 8412110515 | |
| Download: ML20100L265 (11) | |
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l10NTHLY OPERATIDNS REIORT October 1984 Throughout most' of the report period, preparations continued for initial s tart up which occurre d on October 29, 1984.
Major events and tasks completed leading up to and including plant startup are as follows:
System valve lineup, system checks and surveill.uce testing continued throughout the report -period up to plant initial criticality.
Completion of surveillance testing was the last major item completed before s t a rtup.
Procedural problems caused the maj or delays on c omple ting surveillance testing.
Resolution of equipment pro ble.c.s identified during post maintenance testing and system checkouts also presented major obstacles for plant startup.
The flush of the feedwater system was completed on October 13, 1984.
During the flush, a failed seal was identified on "A" condensate pump which was subsequently replaced. A successful feedwater system hydro was completed prior to the feedwater flush.
The last reac tor leak test was completed on Oc tob er 8,
1984.
No major deficiencies were identified during the tests.
This final leak test was required af ter repairs to the "A" reactor recirculation pump flange and "D"
re actor re circ ulation pump mechanical seal were completed. Various valve packing glands were also inspected.
A number of dif fere nt re actor recirc ulation pump problems were resolved prior to plant s t a rtup.
The problems ranged from start and trip problems to monitoring support equipment associated with the pump s.
The start / trip problem. ha ve all been resolved.
- However, v arious monitoring support equipment problems still exist.
The temperature monitoring resis tance temperat ure detectors ( RTDs) are inoperable on C&D reactor re circ ulation pumps.
However, alternate means were provided by Engineering to monitor these parameters.
In addition, a problem exists with the reactor re circ ulation pump seal flow swit che s.
All of the low seal flow alarms are constantly annunciated (along with some of the high seal flow alarms at press u re).
Initially, it was believed tha t the alarus would clear when the plant was brought up to operating pre ssure and temperature but this was not the case.
Engine ering is investigating.
This remained an outstanding item at the end of the report period.
The oil in all reactor recirculation pumps was changed and a reac t or recirculation pump trip circuitry test was satisfactorily performed before startup.
8412110515 881031 PDR ADOCK 05000219 R
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Monthly Operations Report Page 2 Numerous trip problems were experienced with both Reactor Protection System (RPS) motor generator set output breakers.
Adjustment of the undervoltage trip devices on the breakers has resolved the problem.
There have been numerous problems associated with the intake circulating water pumps.
The major item is the degradation of the pumps' motor collecting rin;;s and brushes.
These items were replaced on all the pumps in October.
Subsequent to this month ly report period (early Novemb er), an in spection revealed a pitting problem again on the rings and brushes.
Plant Eng ineering is involved in resolving the problem.
The elec trical/ mech anical modifications for both Standby Gas Treatment Systems were completed.
The inspections and re quire d re pa ir s for the Environmental Qualification program were completed. Also, all motor-operated valve limitorque testing (MOVATS) was completed.
On Cstober 16, ~1984, an insulator-for "B" phas e of the Substatio n J69361 transmitter line failed. The power surge caused various vital power panels to tran sf er to their alternate power s up plie s.
The Cleanup System tripped and normal reactor ventilation tripped.
At the time, SGTS No. I was the selected system and the exhaust fan for SGIS No. 1 (EF 1-8) tripped.
Systems logic transf erred to SGTS No. 2 which operated properly.
The trip of SGTS No.
I was traced to a faulty relay which was replaced.
The system was tested and declared operable on Oc tober 17, 1984.
SGTS No. 2 had to be taken out of standby readiness for approximately one half hour on October 18, 19 84 to purge out the newly installed air line.
The system was retes te d and declared operable the morning of October 18, 1984.
On October 17, 1984, th ree (3) of the scram discharge volume (SDV) valves failed to close within the time limit specified in the technical specifications (30 second s).
Immediate maintenance was initiated to identify and c orre ct the problem.
An adminis tra tive control rod block was put in place until the system was tagged out for maintenance at which time the reactor mode switch was placed in s hutdow n.
Repairs were completed on October 21, 1984.
Installation of the emergency D.C. powere d Control Room lights was completed and tested.
Labeling of the disconnected wires in the Control Room was completed during the report period.
A walkdown/verificacion of the labeling was also completed.
Plant Engineering has issued a preliminary report on the D.C. grounds experienced during the outage.
The incidents taken as a whole indicate wire dre s s and workmanship as the key contributors.
A followup report is penuing.
M
.--Mo;,thly Opsrationn Report Pag e - 37
. During surveillancei testing.. it was noted that some = of - the torus to
-drywell, vacuum - breakers position switches were loosely ~ mounted.
Repairs were made' and the vacuum'~ breakers were satisfactorily tested -
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prior to startup.
' On Oc tober. 25,.19 84,. the ' diesel generator fast start test (loss of power test) was completed. -Both diesel generators ' fast-started. and -
loaded-properly.
However, af ter, the. test, : diesel. generator ; No. ;2
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-would not. start.and idle 1 when given a manual start' signa 1.
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. Investigation revealed one of-the atart-batteries' for the diesel generator was weak.
- lRMil3 (detector) cs replaced during the report period.
All SRMs',
IRMs and LPRMs ~ werc tested and calibrated-before startup.
The drive systems for SRM 22 and IRM 11/18 were also repaired.
The: Core Spray System fill pump modification was completed.
Repairs to core spray minimum flow valve V-20-93 and main block. valve.V-20-18 were also completed.
All leaks on the main generatorc hydrogen. cooling system were repaired.
The cooling system was purged with hydrogen and placed 'in service.-
The replacement o'f all condensate demineralizer resin and the Cleanup System resin we a completed. -
Replacement of the "A" station batteries was completed, - tested --and placed back in service.
-During the containment isolation test, it was discovered that the
- drywell vent and purge valves V-27-1, 2,.3 aM 4 would not close upon :
a loss' of air (i.e., valve operators are air' to open, air.to close). -
(The valv'es 'were gagged in the closed position for startup).
Ne'w a ir
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L accumulators are being installed.
This task continued at the ~ end of the report period.
A radiator hose in fire; diesel pump No. 2 had to be replaced.
The
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- fire diesel pump was inoperable from October 23.to October 27, 1984.
Air compre ssor No.
I was out of service - from October 1,
1984.to October 3, 1984 for breaker maintenance / inspection.
Air compressor
'No. 2 was inoperable from October 12, 1984' to October 18, 1984 due to inner stage relief ' valve repairs.
Air compressor' No. 3 was out-of service 1for" preventive maintenance for a one-day period. on October 7, 1984.
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. Repairs to - the fuel zone level instrumentation, Channel" "B",
were completed before startup.
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l Monthly Operations Report Page 4 Me chanical vacuum pump problems were encountered throughout the startup activitie s.
The vacuum pump trip problems were resolved the first week in November.
At 2:00 a.m.
on October 29, 1984, duri ng the calibration of reactor low low water level trip c ircuit, sensor RE02B instead of sensor RE02D was accidentally activated initiating Core Spray System I and injected torus water into the reactor.
In the 18 to 20 seconds the system operated, reactor water level incre ased from 158" to 180" TAF.
All the required notifications were made and a critique was held.
Af terward s, Plant Chemistry sampled the reactor water and verified that it remained within spec ification s.
Subsequently, the remaining Core S pray System surveillances were satisfactorily completed.
The same morning, all precritical checks were completed, and at 0710 hours0.00822 days <br />0.197 hours <br />0.00117 weeks <br />2.70155e-4 months <br />, the reactor mode switch was placed in the " Start-Up" position.
Reactor startup commenced.
The reactor was critical at 1315 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />5.003575e-4 months <br /> the same day.
During the next 24-hour period, the reactor was used for Control Room operator proficiency operations.
Licensed personnel practiced or observed bringirg the reactor critical along with taking local manual control of the reactor recirculation pumps.
On October 30, 1984, after th ree shifts participated in pulling reactor criticals, power was increased to the point of adding heat, and reactor pressure was increased in stages while inspections were made to identify steam leaks.
Various minor leaks were repaired as they were identified.
While power and reactor pre ssure were being increased, some difficulty was experienced establishing initial vacuum in the main tripping after c ondens er s.
The mechanical vacuum pump was approximately 10 to 15 minutes of run time.
A vacuum of 29 inches (Hg) was eventually re ache d with a combination of the mechanical vacuum pump and the steam jet air ejectors (SJAE).
At 1810 hours0.0209 days <br />0.503 hours <br />0.00299 weeks <br />6.88705e-4 months <br /> on Oc tober 30, 1984, "C" re ac tor feed pump (RFP) was started but immediately tripped due to incorrect wiring on a current transformer for phase differential protection.
Reactor pressure was approximately 200 psig and reactor water level was controlled by the condensate pumps and CRD flow to the vessel.
The inlet valve to "A"
- eedwater s tring tripped as it was being opened.
Subsequently, pressure was held constant until the limit switch was replaced.
The CSS was advised not to run "B" RFP unless it was an emergency because the Plant Engineering Group suspected it may have the same problem as "C"
RFP.
Af ter repairs to V-2-7 ("A" feedwater string inlet valve) were completed the plant recommenced rairing reactor power (pressure) and started to warm up the turbine steam chest.
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Monthly Opsraticas Report Page 5.
- Whenl reactor pressure approached the point where condensate pump header pressure would be insufficient to allow flow -into the' reactor '(pressure ;
t approximately : 330 -to 350 psig). the "A" ( RFP was started - (0325. hours).
Personnel in the plant re' ported extreme vibration on "A" -RFP.
The "A" s
.RFP was --secured at 0328 ho'urs.
Control' Room personnel' started L nserting i
rods to : reduce reactor? pressure.so that condensate header _ pressure could s tart controlling. level' again.. ' As level, continued. to decrease, - a decision was made' to start "B" RFP.
Jus t a s : '.'B" RFP wa s ' st arted, 'the
- reactor ' scrammed on ' low water level.
The "B" - RFP remained operating
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' until reactor water level was re-established and ucier control and then the pump was secured. The Post Trip Review Group held a full critique of the event.
The cause was determined to be failure to establish feedwater flow due to failure of 'the : feedwater pumps during warmup.-
(NorE:
"B" RFP is not normally used on reactor, startup because the "B" feedwater-string does not have a low flow feedwater control' valve).
Repairs were initiated on all three feedwater pumps.
Problems with the RFPs were as follows:
1.
"A" RFP had a bad seal and was out of alignment.
2.
"B" RFP had a leaky-check valve flange.
3.
"C" RFP current transformer was wired incorrectly.
Also, while reactor pressure was being increased ' (early on October 30, 1984) problems were encountered while placing the gland seal system ~in-service.- Gland exhaust blower 1-1 tripped on overload.
The discharge valve on gland exhaust blower 1-2 '(V-7-39) was discovered to. have'.its flapper-(butterfly valve) installed backwards.
The gland seal system was placed in service using gland exhaust blower 1-2.
The operator-compensated for' the fact that the position of _ V-7-39 was reversed.
Repairs were completed on B and C reactor: feedpumps early on November 1,
'1984.
Gland exhaust blower 1-1 was' also repa ired.
Inspection. of, the mechanical vacuum pump by the pump's vendor uncovered no problems.
With "A RFP still out of service, the decision was made to start up.
Reactor startup - was c ommenc ed a t 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br /> on November '1, 1984.
The i
reactor was critical at 1208 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.59644e-4 months <br />.
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The following Licensee Event Reports (LERs) were submitted during the month of October:
Licensee Event Report 50-219/84-020 - While transferring from parallel to single unit substation operation (480 VAC), power was lost to l A2 and 182 buses, resulting in a full scram, reactor primary containment and secondary containment isolation, and loss of both SGTS trains.
Licensee Event Report 50-219/84-009 - Both doors of a reactor building personnel access airlock were opened simultaneously by contractor personnel in order to bring a length of pipe into the building.
The interlock was purposefully defeated to accomplish this. As a result, secondary containment integrity was degraded for a short while.
Licensee Event Report 50-219/84-021 - While tes'.ing 1-2 Emergency Service Water Pump during maintenance activities, personnel safety grounds were left on 3 phases of the 4160 volt switchgear. Tags were released to allow a jog of the motor to check for rotation. A bolted fault occurred when the control switch was closed causing a trip of the pump and a flash which caused sufficient ground current flow to trip the main 4160 volt bus "lC" breaker.
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-AVERAGE DAILY POWER LEVEL NET MWe DOCKET #........
50-219-UNIT.......... 0yster Creek #1 REPORT'DATE...... '. NOVEMBER 05,'1984 COMPILED BY....... DONALD V. NOTIGAN TELEPHONE #......
609-971-4695 MONTH OCTOBER, 1984 4
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OPERATING DATA REPORT-
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OPERATING STATUS 1.
DOCKET:
50-219 2.
REPORTING PERIOD:
October, 1984 3.
UTILITY CONTACT:
JOSEPH R. MOLNAR 609-971-4699 4.
LICENSED THERMAL POWER (MHt):
1930 5.
NAMEPLATE RATING (GROSS MWe):
687.5 X 0.8 - 550 6.
DESIGN ELECTRICAL RATING (NET MWe):
650 7.
MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):
650 8.
. MAXIMUM DEPENDABL CAPACITY (NET MHe):
620 9.
IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:
NONE 10.
POWER LEVEL TO HHICH RESTRICTED, IF ANY (NET MWe):
N/A 11.
REASON FOR RESTRICTION, IF ANY: NONE MONTH
-YEAR CUMULATIVE 12.
REPORT PERIOD HRS 744.0 7320.0 130248.0 13.
H00P.S RX CRITICAL 18.8 18.8 34642.7 14.
RX RESERVE SHTDHN HRS 0.0 0.0 468.2 15.
HRS GENERATOR ON-LINE 0.0 0.0 82693.8 16.
UT RESERVE SHTDHN HRS 0.0 0.0 0.0 17.
GROSS THERM ENER (MHH) 0 0
136224729 18.
GROSS ELEC ENER (MWH) 0 0
46056905 19.
NET ELEC ENER (MHH)
-5628
-28306 44257377 20.
UT SERVICE FACTOR 0.0 0.0 63.5 21.
UT AVAIL FACTOR 0.0 0.0 63.5 22.
-0.6 54.8 23.
-0.6 52.3 24.
UT FORCED OUTAGE RATE 0.0 0.0 9.7 25.
FORCED OUTAGE HRS 20.3 20.3 8937.1 26.
SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
NA 27.
IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME:
11/8/84
,c Oystir Creek Stttion #1 Docket No. 50-219 REFUELING INFORMATION - October, 1984 Name of Facility: Oyster Creek. Station-#1 I
Scheduled date for next refueling shutdown:
November 30, 1985 Scheduled date for restart following refueling: June 1, 1986-Will refueling or resunption of operation thereafter require a Technical-Specification change or other license amendment?
-Yes Scheduled date(s) for submitting proposed licensing action and supporting information:
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June, 1985 Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
~1. General Electric Fuel Assenblies - fuel design and performance analysis methods have been approved by the NRC..New operating procedures, if necessary, will be submitted at a later date.
- 2. Exxon Fuel Assemblies - no major changes have been made nor are there any anticipated.
Se number of fuel assemblies (a) in the core 560
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(b) in the spent fuel storage pool =
980 The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in nunber of fuel assemblies:
Present licensed capacity:
2,600 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
Reracking of the fuel pool is in progress. % ree out of ten (10) racks have been installed to date.
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50-219 UNITSifUTDOWNS AND POWER REDUCTIONS :
DOCKETNO. Oyster Creek UNIT NAME.
DATE 11/8/84
.. COMPLETED By R.'Baran REPORTMONTll October 1984 TELEPHONE 971-4640
L 5g "g
I4 Licensee Et t
Cause & Corrective No.
Date g
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Event gg pO.
Action to i
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3 gg g Report #
mO Prevent R:currecce o
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31 2-11-83 S
15072 C
1 N/A
.ZZ ZZZZZZ Start of the 1983 Refueling and Maintenance Outage.
i 2
3 4
F: Forced Reason:
Method:
Exhibit G-Instauctions S: Scheduled A-Equiprnent Failure (Explain) 3-Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-'
D-Regulatory Restriction 4-Other (Explain) 0161)
E Operator Training & Ucense Exananation F-Administrative 5
C-Operaticaal Esrue (Explain)
Exhibit I-Same Source 19/77)
II-Other(Explain)
9
_O' GPU Nuclear Corporation NMQIgf Post Office Box 388 Route 9 South Forked River,New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:
November 15, 1984 Director Office of Management Infonnation U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Monthly Operating Report In accordance with the Oyster Creek Nuclear Generating Station Operating License No. DPR-16, Appendix A, Section 6.9.1.C, enclosed are two (2) copies of the Monthly Operating Data (gray book information) for the Oyster Creek Nuclear Generating Station.
If you should have any questions, please contact Mr. Drew Holland at (609) 971-4643.
Very truly yours,
) 12 J P
edler Vice President and Director Oyster Creek PBF: dam Enclosures cc: Director (10)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Dr. Thomas E. Hurley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station
[N Forked River, NJ 08731 4 'l GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
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