ML19029B020
| ML19029B020 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 02/28/1977 |
| From: | Public Service Electric & Gas Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19029B020 (107) | |
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The Energy People NOTICE -
THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE DIVISION OF DOCUMENT CONTROL. THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE RECORDS FACILITY BRANCH 016.
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DEADLINE RETURN DATE REGULATORY DOCKET fltE COP11 RECORDS FACILITY BRANCH
_______ J
.*.-.'., ;. *. -**... ~-* -***'-.. :...
ANNUAL OPERATING REPORT SALEM GENERATING STATION PUBLIC SERVICE ELECTRIC & GAS CO.
FOR 1976
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ANNUAL OPERATING REPORT OF SALEM.GENERATING STATION PUBLIC SERVICE ELECTRIC & GAS COMPANY FOR 1976 DOCKET NO. ---'--* _so_-_21_2 __
LICENSE NO.
TABLE OF CONTENTS INTRODUCTION HIGHLIGHTS
SUMMARY
OF OPERATING EXPERIENCE PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY-RELATED MAINTENANCE Amendments to Facility License or Technical Specifications Facility or Procedure Changes Requiring NRC Approval Tests and Experiments Requiring NRC Approval Other Changes, Tests, and Experiments Corrective Maintenance of Safety-Related Equipment LICENSEE EVENT REPORTS OTHER EVENTS OF INTEREST DATA TABULATIONS Net Electrical Power Generation PAGE I
2 3
8 9
11 12 16 20 97 98 99 100 Unit Shutdowns and Forced Power Reductions 101 Number of Personnel and Man/Rem Exposure by Work and Job Function 102 UNIQUE REPORTING REQUIREMENTS 103
INTRODUCTION Salem Generating Station No. 1 Unit *is a four loop pressurized water reactor of.. 109 0 MWe Net Capacity, owned by Public Service Electric and Gas.Company,. Philadelphia Electric Company, Atlantic Electric Company, and DelMarva Power and Light Company;. located in Lower Alloway Creek Township, Salem County, New Jersey.
The nuclear steam supply system was supplied by Westinghouse.
The architect/engineer was Public Ser-vice Electric and Gas Company, and the constructor was United Engineers and Constructors., Inc. of.Philadelphia, Pennsylvania.
The condenser cooling method is a once thru cooling system, and the Delaware River is the condenser cooling water source.
The plant is subject to license DPR-70,. issued August 13, 1976 pursuant to Docket Number 50-272.
The e
date of initial reactor criticality was December 11, 1976, and genera-tion of power began December 25, 1976.
HIGHLIGHTS Operating License No. DPR-70 was issued for Salem No. l Unit on August 13, 1976.
This was a limited operating license permitting 1% of rated thermal power (33.38 MWt) and provided for a sequential approach to power, taking into consideration various incomplete con-struction items, preoperational tests and startup tests.
The initial loading of the core was started on Atigust 17, 1976, and required 55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> to complete.
On December 1, 1976, the operating license was amended to authorize operation of the reactor at 100% of rated core thermal power (3,338 MWt) with a sequential approach and NRC authorization required prior to proceeding to 20, 40, and 90% power stages.
Hot shutdown testing was completed on December 8, 1976 with initial criticality being attained on December 11, 1976 and hot standby and zero physics power testing being completed on December 17, 1976.
Authorization to proceed to Model (Power Operation), not to exceed 20% of rated core power (667.6 MWt), was received on December 17, 1976
- The unit was synchronized to the electric system for the first time powered by nuclear heat on December 25.
The 10% power level test program was in progress at the end of the report period.
SUMMARY
OF OPERATING EXPERIENCE The following is a chronological description of Plant Operations includ-ing other pertinent items of interest for the period August 13, 1976 to*
December 31, 1976.
8-13 Operating license DPR-70 for No *. 1 Unit was issued by the Nuclear Regulatory Commission.
8-17 Initia*l Core Loading was. started.
The first fuel assembly was placed. in position C-4* at 2226 hours0.0258 days <br />0.618 hours <br />0.00368 weeks <br />8.46993e-4 months <br />.
9.,..21 Last fuel. assembly placed in core to complete the Initial Core Loading at 0456 hours0.00528 days <br />0.127 hours <br />7.539683e-4 weeks <br />1.73508e-4 months <br />.
The total core loading time was approxi-mately 79 hours9.143519e-4 days <br />0.0219 hours <br />1.306217e-4 weeks <br />3.00595e-5 months <br />.
o.f. this total, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> were required for repair. of two air-,motor failures on the transfer carriage, manipulator crane position selsyn failure, electrical noise interference with portable detectors and other minor difficulties.
Actual fuel movement. time was approximately 55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br />.
9-23 Received authori-zation from the Nuclear Regulatory Commission to proceed to Operational Mode 4 (Hot Shutdown) pursuant to Attach-ment l to License DPR-70.
This permission was granted based on satisfactory completion of reactor coolant sys*tem primary sensors response. time testing.
11-25 Received authorization from the Nuclear Regulatory Comm:Lssion to
- .proceed. to Operational Mode 3 (Hot Standby) pursuant to Attach-ment 1 to License.DPR...,70..
This permission was granted based on satisfactory completion of the following:
- 1)
Testing operation of Residual He.;it Removal Pumps recirculation valves 11RH29 and 12RH29.
- 2)
Testing motor winding temperatures of Residual Heat Removal Pump Motors Nos. 11 and 12.
- 3)
Testing four specified snubbers on the Residual Heat Removal System.
- 4)
Testing of the Boron Recycle System.
- 5)
Testing process radiation monitors, excluding those required for fuel loading.
- 6)
Demonstration of beta dosimetry capability.
- 7)
Testing Service Water System.
- 8)
Testing chilled: water portion o.f the Control Room Air Con-ditioning System.
- 9)
Preparation of three specified radiochemistry procedures.
- 10)
Replacement of existing standby charcoal filters in the Auxiliary Building Ventilation System with charcoal filters*
capable of removing 90 percent of.the organic iodines.
11-30 At 2239 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.519395e-4 months <br />, R_eactor Trip/Safety Injection was initiated due to high steam line* flow in coincidence with low Tavg.
Plant was in Hot Standby, 540°F Tavg and 2235 psig reactor coolant pressure.
Technicians were working. on No. 12 Steam Generator (SG) steam flow
-Channel 1 which was tripped.
With reactor coolant temperature less than 543.°F, all four channels of low Tavg were tripped.
A pre-mature - lifting of-a -No.. 14 safety valve resulted in a high steam flow. signal.".
With No. 12 SG steam flow tripped and a high steam flow signal on No... 14 SG,. the required two of four signals were available..
This: in coincidence with an actual low Tavg caused the Reactor Trip/Safety Injection.
At 2301 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.755305e-4 months <br />, while recovering from the first inadvertent.safety injection actuation'" a second SI.actuation occurred.
The condi-tions. prior to, cause, and duration of the second ECCS actuation were identical to the first event.
12-1 At 0238,- a Reactor Trip/Safety Injection was initiated due to high steam-line differential pressure P4.
Prior to the event, the unit was in Hot Standby,. at 547°F and 22'35 psig* reactor coolant* pressure.
Based on a review of recorder traces,. a No. 14 SG safety valve again lifted prematurely causing the steam line differential pres-sure P4 safety injection.
12:-3. At 0315, a safety injection _occurred.
Prior to the event, the unit was in Hot Standby with 537°F Tavg and 2235 psig reactor coolant pressure.
No indication of the cause of this event appeared on. the status-panel.
The computer did not print out a sequence of events but did print out "12 Steam Generator b.P Pressure Reactor Trip SI".
Prior to the SI actuation, Technicians were working on No. 12 SG steam flow Channel II.
They had hooked up a brush re-corder to the Channel II transmitter output, channel output, and steam pressure channel.
When hooking up to No. 12 SG steam pres-sure channel III, the SI took place.
After the SI, it was discovered that the Technician mistakenly used grounded test leads
- when.hooking up the brush.recorder to the various steam flow and steam pressure channels.
A special test was conducted in order to demonstrate and verify that the inadvertent Safety Injection that occurred was in fact caused.by a Technician mistakenly using grounded test leads when hooking up a brush recorder.
These test results coincide with the events that took place during the Safety Injection that occurred.
Based on these results, the inadvertent Safety.. Injection was caused by a Technician mistakenly using grounded. leads.
12-5 Received. authorization from the Nuclear Regulatory Commission to proceed to Operational Mode.. 2 (Startup) pursuant to Attachment 1 to License.. DPR-70.
This permission was granted based on satis-factory completion of.the following:
1-)
Testing high temperature* alarm on pressurizer relief line.
- 2)
Testing control. of steam. generator blowdown f-low by valves GB8 and GBlO *
~..
- 3)
- 4) 5 ).
- 6)
Testing upper motor bearing of No. 14-Reactor Coolant Pump.
Testing pump seal of No. 11 Reactor Coolant Pump.
Testing* five specified RTD's* in the Reactor Coolant System.
Testing of 45 specif.ied snubbers associated with the pressurizer.
12-11 No *. 1 Unit Reactor achieved initial criticality at 1936 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.36648e-4 months <br />.
Zero power.physics testing was then started.
e
- 12-17 Zero power physics testing was completed.
At 1_901 hours, No. 1 Reactor tripped due to No. 12 Steam Generator (SG) low level in conjunction. with feedwater/steamflow mismatch.
No. 12 SG steam flow Channel 1 was. in the tripped.position.
This was due to con-
- densate formation in the steam flow feeler line due to incorrect slope.*... On low level of 25% in conjunction with the tripped steam flow channel, a reactor tr.ip occurred.
12-18 No. 1 Reactor taken critical at 0008 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
However, the reactor was taken subcritical at 084'2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to install a sandplug over a reactor.vessel.nozzle that was inadvertently left out of position following a test. Criticality was again achieved at 1952 hours0.0226 days <br />0.542 hours <br />0.00323 weeks <br />7.42736e-4 months <br />.
12-19 At 0250hours, No. 1 Reactor tripped when No. 11 Steam Generator Feed Pump (SGFP) tripped.
No. 12 SGFP was* tripped and the main turbine was tripped.
These conditions initiated a reactor trip.
At O 6 4 0. hours, No. 1 Reactor was again* taken er i tic al..
Another reactor trip occurred at 2128 hours0.0246 days <br />0.591 hours <br />0.00352 weeks <br />8.09704e-4 months <br /> for the same* *reason as that on 12-17 at 1901 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.233305e-4 months <br />.
12-20 At 0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br />,. No. 1 Reactor was taken critical *. At 1056 hours0.0122 days <br />0.293 hours <br />0.00175 weeks <br />4.01808e-4 months <br />, a reactor trip occurred for.the same reason as that on 12-17 at 1901 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.233305e-4 months <br />.. " The plant was then brought to cold shutdown for modi-fication to.steam flow feeler lines on No. 12 SG Ch 1 and No. 14 SG Ch l.to correct slope to eliminate condensate-formation.
12-23 Following modification described above for 12-20, reactor was taken critical at. 1822 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.93271e-4 months <br />.
12-24 -No.. I Turbine-Generator rolled.with. steam from nuclear heat for the first time at 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Experienced numerous SG high-high level turbine. trips due to.manual control of steam generator level.
Turbine-Generator reached synchronous* speed.. (1800 rpm) at 1411 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.368855e-4 months <br />.
The turbine-genera.tor was tripped manually at 1553 hours0.018 days <br />0.431 hours <br />0.00257 weeks <br />5.909165e-4 months <br /> due to.high temperature in exciter cubicle.
The cooling water to the exciter cooler was isolated due to low ambient conditions.
Although monitored regularly,,. the cubicle temperature increased to 180.°F bef.ore corrective action could be taken..
During this shutdown, turbine balance weights were changed to improve vibrations.
12-25 No. 1 Turbine Generator reached synchronous speed at 0059 hours6.828704e-4 days <br />0.0164 hours <br />9.755291e-5 weeks <br />2.24495e-5 months <br />.
A reactor-turbine trip occurred at 0.124 hours0.00144 days <br />0.0344 hours <br />2.050265e-4 weeks <br />4.7182e-5 months <br /> due to lo:--lo level in. No. 14' Steam Generator.
Feedwater control was on manual at the time.
At 0409 hour0.00473 days <br />0.114 hours <br />6.762566e-4 weeks <br />1.556245e-4 months <br />s1 No.. L Reactor was again. taken critical and the turbine~generator reached.synchronous speed at 0943.
The generator was, synchronized to the electric system for the first time powered by nuclear heat. at 1342 hours0.0155 days <br />0.373 hours <br />0.00222 weeks <br />5.10631e-4 months <br />.
At 2113 hours0.0245 days <br />0.587 hours <br />0.00349 weeks <br />8.039965e-4 months <br />, a reactor-turbine trip occurred due. to No. 12 Steam Generator feed flow/steam flow mismatch in conjunction with low level.
Reactor power was 17.5%, generator load 70 MW.
At 2114 hours0.0245 days <br />0.587 hours <br />0.0035 weeks <br />8.04377e-4 months <br />, Safety Injection occurred.due to high steam flow coincident
-with low Tavg*.
Steam dump was in. pressure mode, 980 psig setpoint.
Steam dump. opened on reactor trip which gave high.steam flow signals.
No. *12 Steam Generator steam flow Channel II was already in trip-ped. position for testing.
The high steam flow signal coincident with low Tavg caused the safety injection..
12-26 No. I Reactor was again taken c~i tical at 1735 hours0.0201 days <br />0.482 hours <br />0.00287 weeks <br />6.601675e-4 months <br />..
12-27 No. 1 Generator synchronized at 0701 hours0.00811 days <br />0.195 hours <br />0.00116 weeks <br />2.667305e-4 months <br />.
At 1249 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.752445e-4 months <br />, a turbine-reactor trip occurred due to high-high level in No. 11 Steam Generator.
Reactor power was 17%, generator load 70 MW.
Feedwater control was on manual at the time.
Criticality was
- achieved again at 1414: hours and generator synchroni.zed at 2014 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.66327e-4 months <br />.
At 20 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br />,. a reactor-turbine trip occurred due to lo-lo level in No. 13 Steam Generator caused by loss of suction pressure to No. 11 Steam Generator Feed Pump.
Reactor power was 18%, generator load 55 MW.
Reactor criticality was again achieved at 2243 hours0.026 days <br />0.623 hours <br />0.00371 weeks <br />8.534615e-4 months <br />..
12-29 No. 1 Generator was synchronized at 0811 hours0.00939 days <br />0.225 hours <br />0.00134 weeks <br />3.085855e-4 months <br />.
At 1040 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.9572e-4 months <br />, a turbine-reactor trip occurred due to hi-hi level in No. 12 Steam Generator.
Reactor power was 12%, generator load 20 MW.
Feedwater control was on manual at the time.
Criticality was achieved again at 1223 hours0.0142 days <br />0.34 hours <br />0.00202 weeks <br />4.653515e-4 months <br />.
At 2135 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.123675e-4 months <br />, No. 12 Main Steam Isolation Valve hydraulic operator oil line broke, wetting the SOl.J.th penetration area with oil.
Smoldering of oil soaked insulation occurred.
The plant was brought to cold shutdown starting at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />; reactor was made subcritical at 225.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
12-30 A safety injection due to high steam line differential pressure P2 occurred at 0634-.
Plant was in hot standby, reactor coolant pres-sure 1500 psig, Tavg. 415°F, all main steam isolation valves were closed.
Maintenance personnel were adding* oil to the hydraulic a
operator of No.. 12 Main Steam Isolation Valve.
The foreman in charge failed to place blocking tags on t;he hydraulic oil pump motor.
The. pump was running and as*oil was added, the valve cycled open resulting in high steam line differential pressure P2.
12:-31 No. 1 Reactor achieved critical.ity at 0421 hours0.00487 days <br />0.117 hours <br />6.960979e-4 weeks <br />1.601905e-4 months <br />.
There was a
- delay placing the turbine-generator in service due. to condenser circulating water system problems.
Specifically,. Nos. 12A & B Travelling Screens were inoperable due to severe cold and icing conditions in the river.
At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, plant was in startup mode_, reactor just critical, when construction personnel working on No~-
2 Unit reported water in. No. 2 Boric Acid Evaporator room.
Survey showed activity present.
Leak was traced to open ended sampling line from boron analyzer in the chemistry lab.
Isolation valves were opened in error allowing sample to discharge to No. 2 Unit side.
Isolation
.- valV.es were closed and open line capped.
There was no general area radiation.
Personnel were checked and no contamination
.detected.
PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY-RELATED MAINTENANCE Amendments to Facility License or Technical Specification Facility or Procedure Changes Requiring NRC Approval Tests and Experiments Requiring NRC Approval Other Changes, Tests.and Experiments Corrective Maintenance. of Safety-Related Equipment Amendments to Facility License or.Technical Specifications On September 10, 1976, the Nuclear Regulatory Commission issued Amendment No. 1 to the Facility Operating License for Salem Nuclear Generating Station,. Uni.t No. 1 -
The amendment revises portions of Attachment 1 to License No. DPR-70 and consists* of (1) changing the sequence for conducting certain pre-operational tests.. and. startup tests, and (2) deleting the requirement for testing the feedwater snubbers and (3) deleting the requirement for completing certain maintenance _procedures for the limited operation for testing permitted by License DPR-70.
On September 29, 1976, the Nuclear Regulatory Commission issued Amendment No. 2 to the Facility Operating License for Sale:m Nuclear Generating Station, Unit No. 1 -
The amendment reads as follows:
"Amendment No. 2 to Facility Operating License No. DPR-70 has been issued to correct typographical errors and inadvertent omissions.
The staff has concluded. that the changes are editorial corrections which resolve conflicting requirements involving the containment atmosphere radiation monitoring system.
We have, therefore,. concluded that the changes (1) do not. increase the probability or consequences* of accidents
- previously considered; (2) do not involve a decrease in safety margin nor do they involve new hazards considerations; and (3) that there is reason-able assuran.ce that the changes will not endanger the health and safety of the public."
On December 1, 1976, the Nuclear Regulatory Commission issued Amendment-No. 3 to the Facility Operating License for Salem Nuclear
- Generating Station, Unit No. 1 -
The amendment reads as follows: *
"The Nuclear Regulatory Commission has issued the enclosed Amendment No. 3 to Facility Operating License No. DPR-70.
Amendment No. 3 is effective.. as of the date of issuance~ Facility Operating License No. DPR-.70, as amended,. shall exp.ire at midnight~ September 25, 2008.
In accordance with the Commission's Supplemental Statement of General Policy of November.5,.. 1976, (41 F.R *. 49898, November 11, 1976),. the staff has.. determined. in the enclosed Environmental Assessment, that use of revised.values for reprocessing and waste management would not tilt the cost':"'"benefit balance for Salem Unit No. 1 against issuance of a full power operating license.. Accordingly, Amendment No., 3 to License No. DPR':"'"70 authorizes the Public Service Eiectric and Gas Company to operate the Salem Nuclear Generating Station, Unit No. 1 at a reactor core power level of 3338 megawatts thermal (one* hundred percent of the rated core thermal power).
However, in accordance with Amendment No. 3 and the revised Attachment 1 to License DPR-70, the amended license is conditioned to provide a sequential approach to full power which takes into account a series of incomplete construction i terns,.
preopera.tional tests, startup tests and other items, and provides for further Commission approval at various stages of these activities
- Other changes include (1) the requirement for a long-term means of providing overpressure protection; (2) the temporary limitation of power operation to twenty percent of rated core power until the ECCS performance is.reevaluated by modeling the upper head temperature as the hot.leg temperature; (3) the condition that Facility Operating License.No. DPR-70 is subject to the outcome of the proceedings in Natural Resources Defense Council. v. NRC (D.C. Circuit, July 21, 1976)
Nos.. 74,-1385 and 74-1586,, and (4) changes* to the Appendix A Technical Specifications, in response to your request dated November 81 1976.
Facility Operating License No. DPR-70 initially contained several conditions relating to environmental matters.
Since these conditions
.are included in the Appendix B Technical Specifications, they have been deleted from the li~ense proper."
Facility or Procedure Changes Requiring NRC Approval There were no facility or procedure changes during the report year that required prior approval by the Nuclear Regulatory Commission.
Tests and Experiments Requiring NRC Approval During this reporting period, Public Service Electric and Gas Company received approval from the Nuclear Regulatory Commission to conduct initial core loading and initial criticality, perform zero power physics
.testing, and. perform the power ascension program.
A summary report of
- the tests and. test results is contained in the following paragraphs.
- 1.. Initial. Core Loading Core load. commenced at 2.226 hours0.00262 days <br />0.0628 hours <br />3.736772e-4 weeks <br />8.5993e-5 months <br /> on August 17, 1976 and was completed seventy-nine hours later at 0456, August 21, 1976.
Though the overall loading.effort proceeded smoothly, several short duration delays occur-red. during the. loading... Failure of the transfer system air motor on two occasions caused suspension of loading for a total of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />, while loss of the.fuel handling bridge position indication caused an additional
- 3. hour delay..
During various phases of loading, failures of permanent
- and temporary.source range-channels, difficulty with gripping a fuel assembly with: the manipulator crane mast, and loss of underwater lighting took. place with little effect on the total fuel loading time.
On com-pletion of loading, a video core scan was performed to verify and document the correct location and orientation of all fuel assemblies.
- 2.
SUP 52 - Postponed Phase II Tests and Retests The following tests which were scheduled, but not performed, during hot functional testing, were performed as plant conditions permitted during the periods of cold and hot shutdown.testing.
All results met the specified acceptance criteria.
- a.
Pressurizer Relief Line High Temperature Alarm
- b.
Steam Generator Blowdown Flow Control
- c.
Operation o-f Nos. 11 and 12RH29 Valves d..
RHR Pµmp Motors Winding Temperatures
- e.
No. 11 RCP No. 3 Seal Leakage
- f.
- g.
Pressurizer and Pressurizer.Spray Line Snubber Operation
- h.
Pressurizer Relief Line Operational Hydrostatic Test
- i. Pressure Drop Across Nos. 11 and 12 Mixed Bed Demineralizers
- 3.
SUP 70.1 -
Reactor Coolant Leakage Test Two Operating. Department Surveillance Procedures made up this test whereby RCS leak rate and RCP.controlled leakage was determined.
With the data accumulated over a three hour* period, the calculated RCS leak rate of 0.. 35 gpm was obtained, well within the 1.0 gpm Technical Specification limit.for unknown leakage.
The first measurement of controlled leakage to the Reactor Coolant pumps resulted in an unacceptable value of 50.9 gpm (Technical Specification limit of 40 gpm).
After adjustment of the seal injection throttle valves,. an acceptable test was performed with controlled leakage cal-culated to be. 37. 05 gpm *
-12.-
- 4.
SUP 70.2 RTD Bypass Flow Verification During conduct of.this test, it was determined that No. 14 hot leg RTD bypass loop flow did not meet the minimum flow requirements of 152.1 gpm, assuming a o.* 5 second transport time contribution to the overall RTD. response time..
Communication with Westinghouse revealed that the latest design assumptions. allotted 1.0 seconds, rather than 0.5* seconds, for by.pass loop coolant transport time.
With this resolution, all test objectives* and. acceptance criteria were met
- 5*.
SUP 70 *.3 Reactor Coolant Flow Coastdown Measurements This.test verified* the validity of the safety analysis assumptions on the rate of reactor coolant flow changes due to various combinations of reactor coolant pump trips.
Flow.coastdowns* were performed and analyzed for 2/ 4, 4/ 4, 2/ 3 and 3/3 pump trip. conditions.
In addition,. the delay times for low flow, undervoltage, and underfrequency trips, associated
.with the loss of flow accident, were measured.
All testing results met the acceptan~e criteria.
- 6.
SUP 70.. 4 Pressurizer Spray and Heater Capability and Continuous e
. Spray. Setting The spray and heater effectiveness tests proved function of the system as designed. *The temperature of.one of the two continuous spray lines could.not be increased above the low temperature alarm point.
The alarm point was reset to reflect the lower temperature.
7..
SUP 70.. 5 Reactor Coolant System Flow Measurement Flow measurements were performed with various combinations of pumps operating...
- With all pumps operating, loop flows were found to be 99,250, 97,AOO, 100,000 and 99,050 gpm for loops 11 thru 14 respectively, which is above the design~_limit of 88,.500 gpm/loop.
- 8.
SUP 70. 6 Rod Pos.i tion Indication System Ver.ification of satisfactory performance of indication, alarm and con-trol functions.for each control. rod was accomplished through this procedure with acceptance criteria being met.
- 9.
SUP* 70. 7 Roc;i Drive Mechanism Timing Mechanism timing tests were performed at both cold and hot conditions.
- Test resul.ts. were as predicted except for the* stepp:ing traces of the drive* mechanism.for rod 2D5 in core location H-8.
This drive mechanism is an. "*add-on~',. the f.if.th. mechanism to be supplied power from a cabinet basically designed for four drive mechanisms.
This irregularity is acceptable. for operation.. but is further being evaluated from a design review. by Westinghouse.
10.~.
SUP 70 *. 8. Control Rod Drop Time Measurement This test.was performed at both.hot and cold conditions under both no flow and. full flow. conditions~. All drop times were within the acceptance criteria.. of.2.2 seconds.as specified in Technical Specifications..
- 11.
SUP 70.9 Rod Control System Operation This test demonstrated the-operability of the full length rod control system*control and indicating. functions just prior to performing the approach to initial-criticality.
No problems* were encountered and
.the acceptance criteria were met.
12.:
SUP 7 0.10 *Part
- Length Rod. Mechanism Brake Test Documentation of. the actual operation of the mechanism brake arms was accomplished during this test..
Two repeatable traces were obtained on each mechanism to prove proper operation. of the brake arms with accept-*
able results *..
- 13.
SUP 70.11.Incore Flux Mapping System Checkout of this* system was* accomplished under both cold and hot condi-tions...
Numerous mechanical and electrical problems developed during the tests but were expeditiously resolved by site personnel and/or the vendor.
- 14.
SUP 80 *. 2 Initial Criticality On completion of the cold and hot testing*, initial criticality was.
attained on December 11, 1976 at 1936 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.36648e-4 months <br />.
The rod withdrawal, deboration and the establishment of criticality was achieved without incident~
15 ~-
Zero Power Physics Tests This portion of the startup test program consisted of performance of the following startup procedures:
80.3 80.4 80 *. 5 80.6 Nuclear Design Check Tests Rod and Boron Worth Measurements RCCA Pseudo Ejection Minimum Shutdown Verificati"on and Stuck Rod Worth The specific parameters were measured and compared to the predicted e
- values..
Technical Specifications and FSAR. requirements were minimum shutdown boron. concentration.,. differential boron worth, control bank worths, temperature.coefficients,.power distributions, worth of the most reactive stuck rod,. anq.worth of the most reactive control rod ejected.
Deviations from.procedural acceptance criteria were observed with the measurements of core. power distribution, and the measurement of control bank *c worth.
Nei.ther deviat.ion. was of sufficient magnitude as to impact the results. of safety analysis calculations nor:to limit plant operation and further testing.
- 16.
SUP 80 *. 7 Turbine Control System Checkout and Startup Adjustment of Reactor.Control System Performance of this procedure is accomplished throughout the power es-calation program...
Data required at the hot zero power condition was obtained.
- 17.
Power Escalation and Testing The main turbine was brought. on the line and the generator placed in service on December 25, 1976 at 1342 hours0.0155 days <br />0.373 hours <br />0.00222 weeks <br />5.10631e-4 months <br />.
A maximum reactor power e
of 19 percent was attained during this reporting-period with no addi-
.tiona1. reactor testing being performed.
- 18.
SUP 8l.l.3 Radiation Monitoring and* Shielding Evaluation Tnis procedure provides shielding effectiveness data at various power e
- levels during the power escalation program.
Data was taken at 0% power and all data was as expected by design..
Only 3 data points provided readings above background~
- 19.
SUP 81.*. 14 Effluent Monitoring System Test This procedure is to provide verification of the calibration and alarm setpoints on the plant effluent monitors.
This test requires the actual release of activity from a system and the verification of monitor response..At the 0% power level,. no activity was present in the systems arid therefore the test was inconclusive.
The ~est:is also scheduled.
for higher power levels.
2 0 *.
SUP 81.. 15 Chemistry and Radiochemistry Tests I
This test is to verify the water chemistry control requirements of the RCS at the various power levels during power escalation.
It was.con-ducted at 0% power and all results were acceptable
- Other Changes, Tests and Experiments Plant Design Change ED-0004
- Plant Design Change ED-0004 entitled "Chilled Water System -
Thermowells" has been completed *. The completion of this change resulted in the relocation, and a change in the type of thermo-wells used in three locations within the Chilled Water System.
As a result of this change, a reduced chilled water temperature lag time was realized.
. The safety evaluation for this change determined that there were*
no unresolved safety questions involved.
Plant Design Change ED-0008 Plant Design Change ED-0008 entitled "Replacement of RMS Valves 1VC7 Through 1VC14" has been completed.
This change was required in order to allow the Radiation Monitoring System to operate within it's design requirements.
Specifically., the size of the containment sample valves was changed from 3/4" to l" thus improving sample flow.
The safety evaluation for this change considered it not to be an unreviewed safety question.pursuant to Section 10CFR50.59
- Plant Design Change ED-0017 entitled "1RH26 Extension Yoke" has been completed.
This change was made in order to raise the 1RH26 valve operator above the LOCA "flood~level" within the reactor containment.
A yoke ex~ension was added to raise the valve operator.
The safety evaluation for this change, pursuant to Section 10CFR50.59, did not involve an unreviewed safety question.
e
- p1*a*nt Desig*n: Cha*n*g*e En-0*018
,Plant Design Change ED-0018 entitled "Movement of Reactor Vessel Head Access Platform" has been completed.
The movement of this platform was only a minor arrangement change.
Primarily, the change was made in order to avoid interference with the storage e
position of the upper internals removal tripod.
The engineering safety evaluation made for this change determined that there was no unreviewed safety question involved.
- Pl'ant Design: Cha*nge* ED-0019 Plant Design Change ED-0019 entitled "Service Water Piping -
Reactor Containment" has been completed.
This change required
~16-
I
- the replacement of flexible metal service water connections to the Containment Fan Coil Unit Motor Coolers with* a rigid con-tinuous pipe.
Replacement of these connection pipes to the motor coolers was made in order to minimize the possibility of rupturing the flexible service water lines, due to pressure transients from a dynamic water hammer observed during certain control valve manipulations.
As this Design Change does not functionally alter the service water piping system, it does not present an unreviewed safety question as defined in 10CFR50.59.
Plant Design Chan*ge ED-0020 Plant Design Change ED-0020 entitled "Nuclear Instrumentation -
Instrument Power Feed" has been completed.
This change replaced a 0.5 KVA type LVR Solatron regulator with a 0.25 KVA Solatron CVS regulator in the power feed for Channel IV nuclear instru-mentation.
As a result, the interaction between the regulator and the output stage of the nuclear instrument was reduced
- The engineering review of this change determined that as the change is only an equipment change, where functional requirements are unchanged, ~n unreviewed safety question was not involved.
Plant Design Change ED-0021 Plant Design Change ED-0021 entitled "Service Water System -
Hanger Modification" has been completed.
This change added restraints to reinforce the control valve 1SW49.
These additions were necessary in order to reduce the vibration of an 8" bypass line when 1SW49 was fully opened
- The safety evaluation for this change did not functionally alter the Service Water System; and therefore, an unreviewed safety question was not involved. *
- Plant Design Cha~ge ED-0026 entitled "Service Water Valves 11 and 12SW49 Replacement" has been completed.
This change was performed to increase the reliability of the Service Water System.
The two butterfly type valves 11 and 12SW48 were removed and two piston operated control valves, similar to the existing valves*
11 and 12SW49, were installed.
Thus, the differential pressure seeri by' the valves 11 and 12SW49 would be reduced and thereby a~fo;i:;-d better pressure control as a result of decreased air opetator loading.
The safety evaluation made for this change only served to improve the system's. reliability; and therefore, there was no unreviewed safety ques.tion involved..
Plant Design Change ED"".'0027 Plant Design Change ED-0027 entitled "Service Water Pumps - Motor Alteration" has been completed.
This change was recommended by the motor manufacturer, Allis-Chalmers, so as to preclude further possible fail~res of the pump motor stator windings resulting from cracking end turn insulation.
To this end, the stator windings were first cleaned and dried.
Then a flow coat of room temperature vulcanizing rubber was applied over the affected areas.
The safety*evaluation for this change involved no unreviewed safety questions.
Plant Design Change ED-0047 Plant Design Change ED-0047 entitled "Elimination of Condensate Pocket" has been completed.
This change was performed in order to improve the steam flow sensing ability of two steam flow transducers.
Prior to this time, the sensing legs of these transducers would develop a condensate "pocket" which caused unreliable readings in main steam flow indicators for two of four sensing channels.
The safety evaluation for this change determined that there was no unreviewed safety question involved.
P'l'a*nt Des*i*gn* Chan*ge MD-0009 Plant Design Change MD-0009 entitled "Chilled Water System -
Chillers" has been completed.
This change was made in order to minimize *the clogging of a refrigerant thermal expansion valve~
To this end, dryer filters were installed in the liquid freon lines.
The safety evaluation made for this change found that such a change would only improve the equipment life.
Furthermore, no unreviewed saf.ety questions were involved *
- P'l'ant Desi*gn Cha*n*ge PD.;...0'0'48
- Plant De~ign thange PD-0048 entitled "Service Water to Turbine Building". has been completed.
This change was required to minimize service water system transients.
This was accomplished by providing a time delay in the closing of Isolation Valves 11SW20, 13SW20 and 1SW26, upon receipt of an isolation signal.
The safety e~aluation for this change did not result in any unreviewed safety questions.
Plant Design Change ED-0024 This Design Change was implemented to correct a design deficiency in the testing circuits of the Solid State Protection System.
The safety evaluation indicates there is no unreviewed safety question resulting from this change.
It was completed on December 2, 1976.
Plant Design Change PD-0015 This Design Change was implemented to correct a design deficiency in the contact configuration of alarms feeding to Auxiliary Annunciator System.
The safety evaluation indicates there is no unreviewed safety question resulting from this change.
It was completed on December 12, 1976.
Plant Design Change ED-0031 This Design Change was implemented to correct a design deficiency on the turbine stop valve input to the Solid State Protection System.
The old limit switch configuration would not allow the open limit switch to be adjusted consistent with the requirements of the Technical Specifications.
The present design corrected this deficiency.
The safety evaluation indicates thre is no un-reviewed safety question resulting from this change.
It was completed on December 6, 1976
- Corrective Maintenance of Safety-Related Equipment
- SAFETY REL~ED EQUIPME~
Mechanical and Electrical Maiptenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION AUXI ~IARY FEED WATER NO. 11 AUX FEED PUMP Corrective lA & lB Diesels
/Ill Aux. Feed Pump Tested Feed Pump SEC Test No SU-231 Available. SEC was stopped while Apparent Problem ha"d not been under SEC Lockout reset NO. 11 & NO, 12 ~ux Corrective Circuit Mal-Feed Pumps could Retested circuit, works as
'1 I
FEED PUMPS OD-3445 function not be started from per Schematic Control Room NO. 12 AUX FEED PUMP Preventative Faulty Original Replacement Assem-Replaced Rotating Assembly in MD-0921 Assembly bly Installed, 1/12 Feed Pump with the Original Assembly NO. 13 AUX FEED PUMP Corrective Wiring Error
'J'urbine Malf unc'--
Modification of Wire to 13 AFP TURBINE MD-0591 q_on as per ECN G-16341 11 & 12 AUX FEED 114 Corrective System Attempted Vents appeared Valves Checked and They Worked, 11 AUX FEED 117 OD-2435 to be Vented not to be working No Obstructions Found, VALVE 14AF20 Corrective Valve* Leaked at Valve Failed Valve Disasse~bled and New MD-0176 Pressure Gaskets Pressure Seal Gaskets Installed, AUX FEED VALVES Corrective Stem Rusted Valve will not Valve Stem was Cleaned.
- 11. & 12AF118.
OD-2434 Open SPOOL AF-2065 Corrective Arc Strike Failed Liquid Blended Pipe and Repainted MD-0343 Penetrant Report
- Same, 1R25168 BUILDING & EQUIPMENT DRAI ~s SERVICE WATER SUMP Corrective No Apparent Pump Not Running & Pump Disassembled & Checked.*
PUMP NO. 3 BAY OD-2240 Problem Discharge Line Hot Pump Reassembled & Tested.
I I I
49SAFETY REL~ED EQUIPME9r Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE
, RESULT CORRECTIVE ACTION
.* :s'ORII ~ A<;:ID RECOVERY BORIC ACID EVAP-Corrective Elect. Sys.
Heat Trace.did not Modified as per ECN E-1662
.ORA.TOR MD-0537 (a)
Improperly Wired Work PZR CONTROL GROUP Corrective Blown Fuse Causec Low Amp Reading\\on. Replaced Fuse*
HEATERS*
OD-2921 by Current Surge.One Phase eves BORON RECOVERY Corrective Temp. in Tank not Temperature System Checked*, Nothing Found HOLDING TANK HEATER. OP-4015 Rising When in Remaining Stable Wrong (CONC TANK)
Auto....
VALVE 1BR118 Corrective Valve Installed Improper Operation Valve Cut Out and Rewelded in SU-293
.. Backwards.
.of. System Proper Position VALVE 1BR75 Corrective Valve Leaking Bciron-Wat_er Mixture Replaced Valve Diaphragm~
RC-0448 Leaking out of O Rings, and Gasket Valve Bonnet c ULLED WATER*
NO. 11 & 12 CHILLED Preventative Inspection of Tubes Erroded on No Replacement Parts Available,
'WATER CHILLER UNITS MD-1060 Condenser Tubes
/Ill & /112 Units Will be Modified & Replaced at a Later Date NO. 11 CHILLER UNIT Corrective Low Refrigerant Chiller *is Short.
Unit Recharged OD-3500 Level in Unit Cycling
\\No. 11 CHILLER UNIT Corrective Faulty Gasket Oil Leak at Flange Replace Discharge Flange Gasket i
OD-3499 I
NO. 11 CHILLER UNIT Corrective Valve 11SW92 33/CVO open -
Valve Opened, Operation Tested OD-2914 Closed
. Circuit open -
Chiller Not Running I '
I
SAFETY REL ED EQUIPME.
- Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION I
I
- c1 ILLED'WATER NO. 13 _CHILLED WATER Preventative ECN E-1676 (refer to Design Change New Base Line Data Perform M3C & MllC for Base RECIRC MOTOR SU-0181 Line Data NO. 13 CHILLER UNIT Corrective Sticking Relay Chill.er Cuts In &
Correct.ed Relay., Recharged OD~2683 for Solenoid Vlv *. Out Sporadically Unit NO. 11,12, & 13 Corrective Malfunctioning Trips on Hi Cylinder. Problem.Corrected CHILLER UNITS OD-2117 Switch & Coolant Read Pressure
.. Supply.
I NO. 11 CHILLER muT Corrective Plug Blew Out Leak in Chiller Repaired* with New Plug oD..:..2449 NO. 12 CHILLER UNIT Corrective Faulty Mech. Seal Oil Leak R~placed Seal & Recharged I
MD-1038 Compressor
' NO. 12 CHILLER UNIT Corrective Low Oil Level Compressor Trip Oil Added & Unit Tested OD-4341
~o. 13 CHILLER UNIT Preventat.ive Check for Freon Complete Overhaul Replaced Condenser, All New OD-3570
& Oil.in Chiller of Compressor Parts for Co~pressor
~o. 11 CHILLER COND Correct iv~
Malfunctioning System Malfunction Adjusted Limit Switch on rnCIRC PUMP on.:.3796 Limit.Switch as Result Valve 11SW92
- m. 12 RECIRC PUMP
. Corrective Malfunctioning
- Improper IndiCator Replace Bad Relay Switch OD-3781 Indicator Light On Circuitry I '
I I I
9SAFETY REL~ED EQUIPMEri)
Mechanical and Electrical Maiptenance,.
NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION COMJ ONENT COOLING CC HEAT EXCHANGER /112 Corrective Fouling of Tubes Loss of Cooling Cleaned Debris from Heat I
MD-,1155 Capacity Exchanger -
SW Side CC HEAT EXCHANGER /Ill Corrective Fouling of Tubes Loss of Cooling Cleaned Debris from Heat OD-3633 Capacity Exchanger -
SW Side
/Ill CC PUMP Corrective Union on Drain Loss of Coolant Union Disassembled - Cleaned -
OD-3696 Leaking from System and Reassembled
/Ill cc PUMP
-Corrective Leaking Shaft Loss of Coolant Shaft Seal Replaced on Pump W0-2236 Seal from System I
VALVE lCC187 Corrective Grease Appears Po.ssible Damage_may Grease Inspected and Found to OD-2467 Contaminated Occur to Gears be in Good Condition*
VALVE 1CC190 Corrective Water in Gear Box Possible Damage to Drained Water - Checked MD-0297 Gears & Electrical Electrically - Refilled with Operator Grease - Checked Mechanically All Readings Normal VALVE lCC118 Corrective Closure Time.2 Valve Appears to Valve Checked Out - Closure OD-2562 Sec. Above Norm.
Take Longer to Close Time 9.6 Sec. Well With Specs I
Than Normal
~Ill CC PUMP
- Corrective
- Leaking Nipple Loss. of Coolant Nipple Replaced OD-2289 in Bottoni of Pmp.
f/ALVE 11CC120 Corrective Bad Grease Cannot Grease Valve Cleaned Out Old Dried Grease -
OD-2464 Fitting Installed New Grease Fitting
!ALVE 1CC131 Corrective Present Vlv. Stem Valve Operates New Stem was Installed When MD-0198 was Machined to.
Properly with Modi-Received from Manufacturer Allow Proper fied Stem Operation I I
l I
I I
- esAiETY REL.ED EQUIPMEtlt
- Mechanical and Electrical Maintenance.
NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE
- RESULT CORRECTIVE ACTION COMP ~NENT COOLING VALVE 1CC190 Corrective Packing Gland Loss of Coolant Tightened Packing OD-2361
-... Leaking VALVE 11CC19 Corrective Packing Gland Loss of Coolant Tightened Pa*cking OD-2363 Leaking CC SW PIPE LEAK Corrective SW Pipe Failure
- Pipe Leaking Salt Replaced Pipe with New Pipe MD-0615 Due to Corrosion Water VALVE 1CC131
- Corrective Leak Rate Test
~one Valve was Leak Rate Tested MD-593 After Repairs After Replacement of Stem.
Tested Satisfactory.
VALVE 1CC131 Corrective Grounded Wire Controls for Valve Repaired Pinched Wire PD-1577 Do Not Work VALVE 1CC190 Corrective General Clean-up Motor Operator *noes Cleaned Electrical Components MD-0879 of Valve Oper-.
Not Work of Valve,Replaced Damaged ator Needed Heater Circuit ~ire VALVE 1CC187 Corrective Leak Rate Test None Valve was Leak Rate Tested MD-0874 After Repairs After Repacking - Tested Satisfactory VALVE 1CC187 Corrective Packing Failure Loss of Coolant Installed New Packing MD-0896 VALVE 1CC187 Corrective Water in Valve Failure of Motor Installed Motor Operator MD-0873 Operator Operator From Unit 112 VALVES llCC291, Corrective Change.as per None Nipples and Caps Installed 12CC291,14CC291, and MD-0767
.Memo M-8884 as per Memo 13CC310
- SAFETY REL.ED EgUIPME9r
- Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION
. *coMPO NENT'COOLING VALVE 14CC130 Corrective Packing Leak Loss of Coolant Tightened Packing OD-3458 llCC HEADER LOW Corrective Alarm Not in Alarms at 130 Psi Recalibrated Alarm to Alarm PRESS. ALARM OD-3821
......Calibration at Proper Point
~ALVE 12CC6 Corrective
- -valve Packing Loss of Coolant
.Tightened Pac;!king OD-2831 Needs. Tightening
. 'PRIMARY WATER.RECOVERY Hl PRIMARY WTR PUMP Corrective Relay in Control ;Auto Start Control Replaced Relay OD-3597 Circuit Failed po es ~ot Function eve - OPERATIONS Ll SEAL WATER Corrective 0 Ring Out of Filter Cover Cover Taken Apart and 0 Ring NJECTION SYSTEM OD-2786 Adjustment Leaking Was Adjusted JOJUC ACID FILTER Corrective Bonnet Nuts Leak Diaphragm Valve Was Cleaned OD-2844 Loose on Valve and Put Back ETDOWN HEAT EXCHGR *.
Corrective Loose Flange Leak Tighten Flange SU-218 11 CHARGING PUMP Corrective Spring Fails to Spring Charging Repaired Driving Pawl Stop, KV BREAKER OD-2432 I
Latch Motor Continues to and Replaced Driving Pawl Operate Spring 12 CHARGf.NG PUMP Corrective Loose Flange Spool *Piece Flange Tightened Flange OD-2909 Leak I
- SAFETY REL.. ED EQUIPME9r Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT.
MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION eve..;. c PERATIONS 1SJ4 & 5
Valve Leak Installed New Bonnet Gaskets 1SJ12 & 13 OD-2783 Valve Seat Mal,...
and Lapped Valve Seat
.funtion VALVE 1CV40 Corrective Motor Malfunc-
- valve Dpes Not Motor.Rewound SU-0202
.tion
.Work.Remote~y I
VALVE 1CV41 Correct iv~
. Motor Malfunc-
. :Handwheel Would Not New Motor Installed I
SU-0179 tion
- Disengage.
Motor I
- would Not De-ener-I g_ize ORIFICE FOR FI-150 Corrective Inspection of
. :Equipment Check Orifice Check & Reinstalled SU-:332 Orifice
/Ill BORIC ACID Corrective Mech!lnical Seal Pump Leaking Thru Replace Mechan.ical Seat and TRANS. PUMP OD-2745 Malfunction Packing Gland Realigned Motor BA TRANS. PUMP Corrective Mechanical Seal Pump Leaking Thru Replaced Mech. Seal and Pump 0D"":"2327 Malfunction Mech. Seal Cashing Gasket till & 12 BA TRANS Preventativ:e Uncouple Pump Prevent From Unc*oupled Pump Until Gaskets PUMP su-0200 Working Are Replaced I
Ul & 12 SPENT FUEL PIT PUMPS*
n2 BA PUMP Corrective Unknown Leaking Oil From Repaired Oiler OD-2781 Pump 111 BA PUMP Corrective Threads Dirty Oil Reservoir cteaned and Tef loned Threads OD-2660
& Not Doped Leaking
~12 BA TRANS PUMP Corrective Mech. Seal Set Leak Replaced Mech. Seal & Set OD-2083 Incorrectly According to Seal Print fl2 BA TRANS PUMP Corrective Suct:i,on Line Pump Leak Replaced.Gasket OD-2617 Flange Malfunc-tion I
I I
esAFETY REL ED*EQUIPME I
At.
Mechanical and Electrical Maintenance I
NATURE OF.
LEROR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE
, RESULT CORRECTIVE ACTION I
eve - OPERATIONS H2 BA TRANS PUMP Corrective Bearing Seal Oil Leak Checked and Found Nothing OD-:-2812 Malfunction Wrong
~11 CHARGING PUMP Corrective Motor Malf unc-
. Charging Pump Will Motor Replaced BREAKER OD-2646 tion Not Charge I
I H3 CHARGING PUMP Corrective Flexatalic Head Leak 114 Valve New Flexatalic Replaced OD-4002 Malfunction
'~13 CHARGING PUMP Preventative Change Crank-Clean Oil Added Drained and Refilled Gear case MD-0259 case Oil and Crankcase 13 CHARGING PUMP Corrective Loose Cap Valve Leak Tightened Cap OD-2406
'ALVE l1CV163 Corrective Diaphragm I
Leaking Diaphragm Installed New Diaphragm OD-4398 Malfunction in Valve ALVE 1CV116 Corrective lCVll.6 Push-Light Will Not Realigned Pushbutton i
SU-0190
'butto'n Malfunc-Operate Correctly tion IC 103 & 107*
Corrective Alarm on Bezel Alarm Will Not Problem is in the Annunciator SU-0190 Malfunction Clear Changed to Dual Input ALVES lCV141,lCV241, Preventative New Parts to be Work Performed New Washers and Springs were nd lSJlO MD-0287 Installed Installed & Valves were Checked CV2,1CV4, & 1CV75 Corrective Loose Packing Leaking Valve Tighten Packing to Stop Leak OD-3574 L
9;AFETY RELA
- 1) EQUIPMEN '
- Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION
- eve* 'OPERATIONS VALVE lCV345 Corrective Loose Packing Leaking Valve Tighten Down Packing OD-3459
\\lALVE lCV116 Corrective Valve Malfunc-*
Motor Trips Replaced Motor OD-2813 tion.
VALVE 1CV185 Corrective Faulty Diaphragm *Leaking Valve Diaphragm has been Replaced OD-4015 CONT.1 INMENT SPRAY LCS16 BREAKER Corrective Motor Failure
- Breaker Will Not Rewound Motor SU-0186
- stay Closed I
IALVE 11C62 Corrective Thermal Over-Valve Will Not Reset Overloads SU-223 loads Tripped Operate aREAKER 12CS36 Corrective Short in Control Breaker Will Not
- Installed New Connecting Plug OD-2550 Rm. Console &
Close in Control Rm and Installed Faulty Relay New Relay
)PRAY ADDITIVE TK.
Corrective Valves Not Valves Leaking Cut New Surface on Seats "ACUUM *BREAKERS:
OD-3545 Seating Properly CS12 & 1CS13 ALVE llCS2*
Corrective Operator Motor Breaker Trips Replace Motor OD-2541 Defective (LVE 11CS2 Corrective Overload Relay Breaker Trips Replaced Overload Relay SU-0201 Failure I I.
I I
NATURE OF EQUIPMENT MAINTENANCE VALVE 11CS2 Corrective
. SU-386 02 CAC 2SW107 Preventative MD-0604
- 1 EMERG CONTROL AIR Corrective COMP.
OD-3982 Ill EMERG CA COMP Corrective OD-3940 112 EMERG CA COMP Corrective OD-3621 H EMERG CA GOMP Corrective OD-3518
- n. EMERG CA COMP Corrective OD-3496 I
- SAFETY RELttfED EQUIPM1fr Mechanical and Electrical Maintenance.
- LER OR OUTAGE MALFUNCTION NUMBER CAUSE
. RESULT CONT; INMENT SPRAY Test Time of None Valve Travel CONTRC LAIR.AUX BLDG Design*Change Job Completed CONTROL A R PENET. & CONT AI N' :
Filter Needs
- on Pressure Slow Changing -
- i'.£1 Reaching Full r-By-Pass Vlv.
- Pressure on Gage Needs Adjusting Air Comp. Trip-Cannot Run ping Out on Low Compressor Oil. P.ressure Compressor Not Low Oil Pressure Wired Correctly Trip Will Not Reset Demand on Sys.
Compressor Runs Excessive for Continually
- Comp, Contact or Not Compressor Will Not Adjusted Start Properly.*
CORRECTIVE ACTION Tested Sat isf ac tory*
I Modified i/a/w ECN M-7337 I
Changed Filter,Cleaned Oil Line Readjusted Oil Pressure Relief Valve Wiring Error Corrected Loading and Unloading Points Were Set Satisfactory Readjusted Contact
4tAFETY RELA~D EQUIPMEI\\9
'Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION CONTROL UR PENET. & CONT A IN Ill EMERG CA COMP.
Corrective Broken Cooling Unable to Operate Replaced Union & Soldered Line OD-2775 Water Line Comp.
Ill & 112 EMER AIR Corrective Recalibrate Oil*
Compressors Will Readjusted Setpoint for Oil COMP SU-366 Temp Setpoint Now.Operate@. 180°F Temp from 150' to 180°F
. Instead of 150°F Oil Temp.
112 EMER AIR COMP Corrective Test for Pipe
- Discover Possible Pressure Tested Pipe, and SU-378 Leaks
- Leaks Identified Leaks for Repai~s
- 1 EMER AIR COMP Corrective Test for Pipe
- Discover Possible Pressure Tested Pipe, and SU-377 Leaks
.Leaks Identified LeaRs for Repairs
- 1 EMER AIR COMP Corrective Header Pressure Compressor Operates Compressor Cutouts Adjusted to OD-2686 Will Not Open When Switched to Required Settings - Compressor Cutout Contact Auto Still Operates the Sarne EMER AIR COMP Corrective Header Pressure Compressor Operates Switched Sensipg Lines on MD-0338 Will Not Continually Compressor Operate Contact Ill EMER AIR COMP Corrective Switch Orifice To Aid in Startup For Testing Purposes O~ifice SU-639 in After Test was Switched from Inlet to Condenser butlet of After Condenser 112 EMER AIR COMP Corrective Broken Gage Compressor Taken Replaced Sight Glass SU-264 I
Glass Out of Service
- 1 EMER AIR COMP Corrective Inlet Vlv. Came Unable to Operate Switch Valve from 112 Unit.
SU-313 Apart in Servic~
Compressor Repaired Broken Valve &
Installed in #2 Unit
' \\
- sAFETY RELfrED EQUIPMEfT Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION CONTROL A.IR. PENET ~. &. CONTP. IN Ill & If 2 EMER AIR Corrective Time Delay Compressors Do Not Reset Time Del~y to Specs.*
COMP MD-0397
,Improperly.Set Operate as per Spec CONTROL AIR PIPING Corrective Relocate 111
- Line Relocated as Line Was Relocated as per MD-0653 Control Air LinE per 1nstructions Instructions CONTROL AIR PIPING Corrective Failure of Valves Must be (4) Vent Valves were MD-:-0680 Vent Valves Replaced Replaced VALVE 12CA360 Corrective Check Valve
- Possible Source Disc of Valve Lapped and S0-0139 Leaking of Return Flow Tested
! Ill EMER AIR COMP Corrective Movement of
- Better Operation Bulb was Moved to New I
MD-0589 Sensoi: Bulb to of Comp.
Location New Loc9tion VALVE 11CA330 Corrective Leak Test After Valve Tested Perform Leak Test on Valve MD-600A Valve Repair Satisfactory VALVE 11CA330 Corrective Pressure Test Valve Tested Perform Press. Test. on Valve SU-390 Valve Satisfactory VALVE 11CA330 Corrective Cut on Vaive Valve Leaks Thru Valve was Disassembled and MD-0447 Seat Sea:t the Seat Repaired CONTROL AIR PIPING Corrective Test of Piping Tested Satisfactory Performed Press. Test on Piping MD-0868 Between 11CA330 & 543 I
_;32-I I
I I
~AFETY RELAfED EQUIPME~
i Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE
, RESULT CORRECTIVE ACTION FI RE PROTECTION Ill C02 FP SYS KEY Preventative Change Key Design Change as System was Changed & Testeq INTERLOCK MD-0260 Interlock in ECN C-3967 Switches in DG Area.
FLOOR I RAINS CONTAMINATEI 11 RHR SUMP PUMP Corrective Level Detector
. Pump Will Not Shut Replaced and Calibrated Level OD-2591 Failed
- Pump Will Not Shut Readjusted Micro Switch OD-2513 on Pump Switch Qff in Auto Mode Actuating Arms Out of Calibra-tion 12 RHR SUMP-PUMPS Corrective Found No Problem Pump Operates as Check Out Pump & Motor Found MD-0588 Designed Nothing Wrong 1RV SUMP PUMP Corrective
- Level* Switch Pump Will Not Replaced Faulty Switch OD-2429 Failed Start on High Leve]
ill RHR SUMP.PUMP Corrective Manufacturing Pump Failed ReplaGed with Pump From #2 Unit I
I MD-0642 Defect
!,11 RHR SUMP PUMP Corrective Float Level Need Pump Will Not Shut' Readjusted Float Level &
OD-2326 Adjustment Off at Low Level Limit Switch 11 RHR SUMP PUMP Corrective Level Switch Out Pump Will Not Start Rea4justed Level Switch OD-2430 of Adjustment at High Level I
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SAFETY REL ED EQUIPME
- Mechanical. and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION FUEL HAND I ING & TRANSFER EQl IP
. UPEND ER CABLE Corrective Correct Pins Not Improper Operation I~stalled Proper Pins PULLERS SU-392 Installed in of Upender Cable Up ender Cable Pullers Pullers AIR MOTOR Corrective Motor Failed
. Unable to Operate Replaced With Motor From OD-2785 System 112 Unit FUEL *TRANSFER CAR Corrective Improper Locatior. Idler Wheel Binding Add Shims to.Correct Alignment:
RE-0006 FUEL TRANSFER Corrective Upender Needs
.Possible Failure Added Plates to Increase UP ENDER SU-0216 Stiffening
- if Operated as Strength Fabricated FUEL ELEVATOR Corrective Manufacturing Failure of Pulley Fabricated and Installed New OD-2425 Fault if Used in This Bushings in Pulleys Condition IFUEL ELEVATOR Correct'ive Manufacturing Pulleys Will Not Smoothed & Scraped Bearings -
SU-317 Fault Operate Correctly Aligned & Reinstalled
- FUEL TRANSFE;R Corrective No Grease Possible Failure Fabricated New Pins Containing
!SHEAVES SU-0180
. Fittings Because of Lack.
Grease Fittings & Inst~lled of Lubrication I
CONTAINNEN'f Corrective Loose Coupling Upender Stuck in Tightened Coupling Nut &
UPEN~ER OD-2759 Nut Jamming Up Position Installed New Cotter Pin I
Shaft
'1
~
I I 1
l
~FETY RELA D EQUIPMEN '
Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION I
FUEL RANDI ING & TRANSFER EQl IP CONTAINMENT Corrective Check of Align-Alignment Made Check of Alignment Prior UPEND ER RE-OOll ment Satisfactory to Operation HOIST Corrective Frayed Cable Possible Failure Replaced Cable With One From SU-0167 if Used in This Unit /12 Condition TRANSFER TUBE Corrective Installed Bolts were Fabricate and Install Two BLANK FLANGES MD-0410*
. Improperly
- stripped New Brass Bolts CE k\\NES & HOISTS Ill CASK HANDLING Preventative Inspection
- completed Reported for Deficiencies I
MD-0245 Inspection
& Action Taken AUX HOOK Corrective Hook Radio-Cable Disconnected Hook Checked Out and MD-0192 graphed Reconnected CASK. HANDLING Preventative No Limit Switche~
Crane Can Go Installed Limit Switches MD-0823 Slamming into Wall FUEL HANDLING CRANE Preventative Testing Slow Response to Inspection of Crane Showed OD~2280 Control No Unusual Operation
- RANE Preventative Inspection Find Method of Report File With Work Order I
MD-0197 Cable to Drum
\\
Connections
?UEL HANDLING CRANE Corrective Limit Switch Crane Would Not Repaired Snap Cock Switch on OD-0339 Malfunction Sto"p til it Hit the Gantry Leg Bumpers NATURE OF EQUIPMENT MAINTENANCE FUEL HANDLING CRANE Corrective MD-0270 FUEL HANDLING CRANE Corrective.
OD-2615 CASK HANDLING CRANE Preventative MD-0625 GRIPPER Preventative SU-0173 HOIST JOG-CONTROL Corrective ob-2509 MANIPULATOR Preventative SU-0278
\\fANIPULATOR/FUEL Preventative fRANSFER SU-0273 1ANIPULATOR CRANE Preventative I
SU-0266 1ANIPULATOR Preventative SU-0329 l
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~AFETY REL~ED EQUIPME~
Mechanical and Electrical Maintenance
- LER OR OUTAGE MALFUNCTION NUMBER CAUSE
, RESULT CB ANES & HOISTS Weight Limt Switch Would Bind Switch Malfunc-tion Wire Reconnec-:
- Crane Malfunction tion Error Limit Switches
- Crane Could Go (None)
- Slamming into Wall Gripper Binding
-~ubriCate all
- Gripper Binding
- .Parts Bad Contact Down Button Not Always Operative.
General Maint.
Put Crane in Good Operational Condit.
General Maint.
Prevent Breakdown Gripper Rod Out Gripper Binds of Adjustment Power Cable No Power to Crane Damage I I
. I CORRECTIVE ACTION Made New Pivot Pin and Removed Weld Splatter Test OK after Adjusting Actuating Arm.
Installed and Wired as per Schematic Disassembled & Lubricated Cleaned All Contacts Replace Limit Switch, Installed Brackets on Fan, No Problem With Overload Replaced Manipulator Hose, Dowell Upender Lifting Cranes, Tack Weld Nuts & Bolts, Install Set Screws Connecting Rod - From Air to Gripper Needs Adjustment Replace Cable and Inspected I
~FETY RELAien EQUIPMEN.,
'Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION Cl lANES *& HOISTS MANIPULATOR CRANE Preventative Reverse Bumper They Hit the Wall Bumpers were Repositioned under\\
SU-0268 iµ. Wrong Place Westinghouse Supervision MANIPULATOR CRANE Corrective Limit Switch.
Reverse Doesn't Limit Switch and Control RE-5 Malfunction.
- Work.
Circuit for Proper Operation SELSYN MOTOR Preventative Last Indication
. Gear Check Motor Work Performed OD-2782 POLAR CRANE Preventative Inspection Inspection CompletE Report That Told of DeficiencieE MD-0244 fl 1 POLAR CRANE Corrective Drum Gear Out of : Crane Did Not Drum Gear Was~Realigned MD-0239 Alignment
- Function Properly fll POLAR *CRANE Corrective Broken Shaft on No Limit Switch New Shaft Made & Installed MD-0826 Limit Switch PUEL HANDLING CRANE Correct.ive Excess Weight Improper Function No Work Needed OD-2336
- on Crane of Crane RES II ~AL HEAT REMOVAL tll RHR HEAT Corrective Bad Gasket Leaking Head Installed Gasket, Lower Head*.
~XCHANGER OD-3695*
1UMP MOTORS Preventative Memorandum Checking of Pumps Inspected Pumps and Found OK MD-0809
'!PE SPOOL Corrective Indentation Not Given The Indentation Was Smoothed LRH-47 QA-0008 on Pipe Spool Out and Tested o* ELBOWS Corrective Investigation Report & Maint.
Costing Flashing Removed QA-0010 IPE SPOOL Corrective Arc Strike I Blemish on Pipe The Arc Strike was Blended RH-178 QA-0007 in With a Grinder NATURE OF EQUIPMENT MAINTENANCE RHR Corrective MD-0733 112 RHR SUCTION LINE Preventative OD-3740 SUCTION FLANGE Corrective OD-3678 RHR, CHARGING &
Corrective SAFETY INJ.
OD-2569 I
I
':1112 RHR MOTOR Preventative SNUBBER QA-0012 1112 RHR PUMP DISCH Corrective FLANGE OD-3772 12Rfl-4 VALVE
.Corrective Mn-0333 11RH19 Corrective MD-0347 1RH26 Corrective MD-0927 LlRHR9 Corrective OD-3703 LlRHR38 Corrective OD-3704
~AFETY RELA~D EQUIPME~
Mechanical and Electrical Maintenance
- LER OR OUTAGE MALFUNCTION NUMBER CAUSE RESULT RES II UAL HEAT REMOVAL Loose Suction Must be Welded to Spool the Floor Pad Removal of Temp To.be Replaced by Gage Pipe Cap Suction Flange Leak Malfunction Removal of Strainer Removed &
Strainer & Temp Temp.Gage Holes Gages Were Capped Check for Bind-Removal of Snubber ing Gasket Failure Flange Leak Nut U~tightened Loose Valve Loose Valve Untightened Valve Design c&ange AP8-ED0017 Packing Gland Pack Gland is Down Failure all the Way Packing Gland Removed Old Packing Failure I
.,.JS-I CORRECTIVE ACTION Spool was Welded to Floor Plan I
Removed Valve'and Reducer, Installed SS Cap Replace Flexitalic Gasket RHR Suction Pipe Flushed with DM Water Snubber was Replac.ed After Inspection*
Installed New Gasket Tightened Locking Nut and Staked Nut Tightened Valve Replace Yoke & Stem Repacked Gland Replace with (6) Layers of New Packing
.AFETY RELA D EQUIPMEN
- Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE
, RESULT CORRECTIVE ACTION RES II 1UAL HEAT REMOVAL 11RHR12 Corrective Gasket Failure Sys. Malfunction Inspection of Valv~ -
12RHR12 OD-3701 Installed New Gasket 1RH64 Corrective Cap Leaks Gets the Floor Wet Resealed Cap with Teflon OD-3794 I
1RH26 Corrective Valve Repair Leakoff s Installed Leakoffs as Directed MD-1034 SPENT FUJ L COOLING & SK IMM NG PUMPS Preventative Check for Align-Alignment Check Alignment of Pumps 11 & l~ BA TRANS SU-0200 ment Satisfactory 11 & 12 SPENT FUEL PlT STEAM GENEI lATOR.DRAIN & BLOW DOWN
~ALVE Fa~lty Packing 13GB3 Corrective Valve.Leaking @
Repacked Valve I
OD-2145 Packing Gland STEAM GE N FEED & CONDENSA' 'E HEADER 1EP3X Corrective
.Possiole Faulty Headers Trip Out Check Out Circuit for Shorts BREAKER OD-3542 Breaker
& Grounds Found None - Breaker Working Satisfactory H2 PRESS BACKUP Corrective Transformer Area Heaters Go Off Due Cleaned and Vacuumed Transf orme IBATER OD-2918 Needs Cleaning to Hot Spot Area
~11 STM GENERATOR Corrective Unions Loose Oil Leak Tightened Unions on Snubbers OD-3037 NATURE OF EQUIPMENT MAINTENANCE STEAM FLOW TRANS-Corrective MITTER PIPING MD-1170 l-MS-52 STRAINER Corrective SU-0155 HANGER "F11 CROSS Corrective UNDER PIPE SU-:-0198.
SUPPORT COLUMNS Corrective MD-0929 VALVE 12MS35 Corrective MD-1267 LEAKOFF VALVE Corrective 12MS7 OD-4019 I
VALVE 13MS45 Corrective 1*
OD-4076 VALVE 11MS36 Corrective I
MD-1194 MSR SAFETY VALVES Corrective SU-0170 MAIN STEAM STOP Corrective VALVES OD-2341 I
~YDRAULIC OIL Corrective SNUBBER VALVE SU-204 13MS167
~AFETY RELA~D EQUIPME"
'Mechanical and Electrical Maintenance
- LER OR OUTAGE MALFUNCTION NUMBER CAUSE RESULT MAIN STEAM, REHEAT TURB BYPA SS STEAM Design Change Piping Changed as per ED-0047 Normal Procedure Strainer Changed Checking for Load was' Set at
. Proper LOa~ing
.Proper Loading Improper Bolting Possible Failure if Not Corrected Work Done in 1977 Leaking Gasket Stearn Leaking Improper AsseinblE Valve Leaking Gasket Leak Steam Leaking Manufacturing Valve Leaking Lock Wire Missing Possible Unauthor~
ized Tampering Valves Operating Did Not Trip After as Designed Test Because no Stm Present No Leak.Found Oil Level Low I
I I I CORRECTIVE ACTION Design Change ED-0047 I
I Removed Startup Strainer -
Installed Permanent Strainer Reset Loading of Hanger @
4300#.
Support Columns were Rebolted and Torqued Repaired by Changing Gasket Disassembled Valve Cleaned &
Reassembled Replaced Bonnet Gasket* -
Repacked Valve Welded Valve* Body Installed Lock Wires on Missing Valves Valves Were Jurnpered and Closed Refilled Oil Sump to Proper Level
- AFETY RELA~D EQUIPMEN~
Mechanical* and Electrical Maintenance
.1 I
NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER
'CAUSE RESULT CORRECTIVE ACTION MAIN STEA}!,. REHEAT TURB BYP.il SS **sTEAM VALVE 13MS1.67
- Corrective Relay Needed Indication of Valve Reset Relay (Put in Operate
. OD-2868 Re~etting Position Not Shown Mode)
- .on 1PR4 STM GE~* STABILIZER Corrective Unions Need Oil Lf;!akage Tightened Unions on Oil Lines SS-205
...... Tightening..
VALVES
/
Corrective.
Removing Test Returning Valves to Test Connections Removed &
14MS137 SU-485 Conn.
1 Drawing Configur-Caps Installed on Valves 13MS144 at ion 13MS177 VALVE 1MS909 Corrective Improper Tag fqssible Misappli-Improper Tag Removed ~
SU-488
~ation of Valve*
Proper Tag Installed.
~ALVE 14MS167 Corrective Solenoid* Burned Valve Will*N<:>t Replaced Sol~noid OD-3945 Out Function
~IN* STM 'SLIDE Corrective Improper Improper Fit up InstC;llled Washers as. Necessary SUPPORT SU-480 Insta*llation VALVE 14MS167 Corr~ctive.
Seat Needs Valve Leaking Lapped Seat & Disc.-
OD-4062 Lapping Reassembled Valve VALVE 11MS28 Corrective Limit Arm Out of Valve Won't Operate Readjusted Limit Arm
- PD-1641 Adjustment Properly
- MAn TURBINE & AUX.
STOP VALVES #11,12, Preventative No Sight Glass Cam:iot Visually Glass Windows Installed 3, & 14MS167 SU-0143 in Hydrolic Check Hydrolic Reservoir Fluid I
- AFETY RELA..-:D EQUIPMEN9 Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE
- RESULT CORRECTIVE ACTION RADIATI bN MONITORING SYS1 EM AIR SAMPLE PUMPS Corrective No Spare Pumps Reassemble* (2)
One was Reassembled on the PD-l473 V~cuum Pumps Other 1VC7 - 1VC14 Preventative Design Change Valve Change Replaced Existing Valves with MD-0834 as per AP8ED0008 Copes-Valcan Valves 1VC7 "'."" 1VC14 Preventative Tech - Spec Check For Leaks All Valves Te.sted MD-0836 Surveillance Satisfactorily 13 FCV Preventative Incorporate ECN Design Change Installed 3/4" Cement Lined MD-0703
.C""."16829.
Pipe From Valves as Directed SAMPLE PUMP MOTOR*
Corrective Wiring Error Motor Malfunction Wiring Corrected PD-1851 SAMPLE.PUMP Corrective Pump Breakdown Pump Inoperative Rebuilt Pump PD-1779 MONITOR RA3909 Preventativ*e Desigµ Change Execution of IAW Relocation of 13SW243 MD-0661 ECN M-7683
,ANNUNCIATOR PANEL Corrective High Pressure It Will Not Reset Replaced Panalarm Model' I
104 '
PD-1809 Alarm Malfunc-ACS-82 I
tion EMERGENCY DIESEL & AUXILIAR ES NO. lB DIESEL GOV' l\\.
Corrective Malfunctioning Improper Operation Lubricated Throttle Linkage BOOSTER (LINKAGE)
SU-203 Throttle Linkage of Governor I.
i I
I I
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- . 9sAFETY REL ED EQUIPME Mechanical and.Electrical Maintenance I
NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION
.. EMERGENCY. HES EL.&.AUXILIARI ~S'-
No* *11B DIESEL Corrective Valve to Press Prevention of Shut-Valve Open STARTING AIR COMP OD-~229 Deyice.Shut down of Compressor No. 11 TURBO BOOST Corrective Dirty Intake &
Compressor Will Not Valves Cleaned,. Lap peel ~
~iR COMPRESSOR OD-,2676 Exhaust.. Valves Load..
Reinstalled With New Gaskets
~o. 11 TURBO BOOST Corrective Faulty Gasket*
Air Leaks at Replaced Gasket UR COMPRESSOR MD-0161 Discharge.Flange.
fo. IA DIESEL FREQ Corrective Polarity Reversed Frequency Ind.
Reversed Polarity to "RANSDUCERS SU-233
... on.Outputs.A,n;c. R.ever.sal.
Correct Arrangement
~o. IA DIESEL GEN Corrective Old Heater Burnt aeater Not* Op~r':l"".'.'
- New Heater Installed &
1ACKET WTR HEATER
- MD-0621 Out.
.tional * -
Tested OK fo. lA* DIESEL GEN Corrective Jacket Wtr Heater Shock Hazard Replaced Jacket Water Heaters 1ACKET WTR HEATER oD.:..2762 Leak Into Pre Motor Repaired & Grounded
~.PRELUBE PUMP Lube OLL Pump Elect. Box
- o. lB DIESEL GEN Corrective Loose"Valve Le.a king Around Cleaned Gasket Surface &
NGINE
- OD-371.9 Rocker Box Gasket Tightened Valve Cover o *. lB DIESEL GEN
- Corr~ctive
. Various Cooling Loss of Jacket Replaced Gaskets ACKET. WATER-OD-2223 Water Leaks Cool,ing Water
- o. lB DIESEL GEN Corrective Solenoid Valves Poor Starting Valves Cleared of Mag~ Rust RANKCASE EXHAUSTERS OD-2560 Hanging Up Time (Out of Spec)
Particles & Tested OK
- o. lB DIESEL GEN Corrective Faulty Pipe Lube Oil Leak Replaced Nipple & Resealed*
UBE OIL SYSTEM OD-3681 Nipple Threaded Fittings
- o. lA,lB,lC DIESEL ECN C-16169, 16170~ and ENERATORS MD-0190 16171 Rev. 1 -
NATURE OF EQUIPMENT MAINTENANCE fo. lA & lC DIESEL Corrective rACKET WTR HEATERS MD-0656 1o. lC DIESEL TURBO Corrective IOOST AIR SYSTEM SU-0081 lo. lC DIESEL AIR Corrective
- TART SYS VALVES SU-0079
- oNTROL BEZEL lB Corrective OD-2371 I iMERG DIESEL GEN
- TAR':rING AIR MD-0569 i
TARTING AIR SYS Corrective ALVE 12DA6A SU-0214 MERG DIESEL GEN I
TARTING AIR COMP.
MD-704 *
- b. llB STARTING-AIR Corrective
- lMPRESSOR PD-1189
). lA DIESEL WATER
- corrective
!!:ATER DEVICES OD-2884
~AFETY REL~ED EQUlPME~
Mechanical and Electrical Maintenance
- LER OR OUTAGE MALFUNCTION NUMBER CAUSE
,. RESULT EMERGENCY D ESEL'& AUXILIARIE~
Jacket Water Leak Loss of Jacket Cooling.Water Bad Fittings Failure of Pres~ure Test DR 110735 Malfunctioning Failure of Pressure Valves.
Test DR. /ISS0997 Bulbs Burnt Out Could Not See Lights Replaced Diesel Starting Air Shuttle Va;t.ve & Retested Fouled Internals Leaking Wired Control Circuits & Tested on all Start Air Comp*
Pressure Switch Starting Air Comp~
PD6477 Malfunc-Did Not Cut Out tfon Temperature Contact or Does Not Device Out of Pick Up Calibration.
. CORRECTIVE ACTION
- Cleaned & Re taped.Threads on-Heater Connections Replaced Fittings Replaced Valves
- Replaced Burnt Oµt Bulbs*
ECN M-15290 Cleaned Deposits From Inside
&. Tested OK ECN C-16364 Changed Pressure Switch &
Calibrated as per M3I Recalibrated Devices 7333, 7343, 6463, & 6464
I I
- Mechanical and Electrical. Maintenance OF LER OR OUTAGE MALFUNCTION NATURE RESULT*
CORRECTIVE ACTION EQUIPMENT MAINTENANCE*
NUMBER CAUSE EMERGENCY I IESELS.& AUXILIAR ES fo. *1c DIESEL Corrective Sticking Throttlt Starting Time Over Lubricated Throttle Linkage ENGINE SU-232' Linkage.
10 Sec.
& Te!=Jted OK J
~o. lA DIESEL Corrective No. SL Cylinder Cylinder Not Corxected.Probl.em ~
ENGiNE OD-:-3810 Fue;l.: Linkage Firing Teste~. 01(,
- Locked.Ol)t.
ilo:~ l:B DIESEL.
Corrective Malfunctioning
- Troubl~ Alarm For:**.
Rec:.al!hrat:.e<l'>remp Contipl. *.
~NGlNE JACKET WTR.
OD..,.3590 Temperature * '
S~s:tem Op.er at ion
- . ;Devic~* :,:& * :Iils.tailed lEATEll' CKT Control...
.. *.. : *.. '. :~..
..... ~..*.
fo. lC DIE~Ei.
Corrective Defective Temp
- J,.ube Oii }leater
- Recalibrated TD-7319 &
mGINE*. ;f.UBE OIL UTR OD-,2465*
........Device...
...Failure.Alarm Installed New Te.mp Device
- I
- RANKCASE H.P. IND Corrective Defective Press Malfunction
.Replaced & Recalibrat~d
' ALAfil1.
SU-339 Device Press. Device SM :PLING'SYSTEM
[lSC VALVES*
Corrective Bad Seal In Vlvs Failed Leak Test Disassembled, Lapped, &
su-130 Reassembled REACTOR coc RELI1 LANT PRESS &
F 13 STM GEN Corrective Union Leaking.
Oil Loss Repaired Coupling &
- oD-2837 Reass~mbled
- J.-4 STM GEN Corrective I
Design Change Removal Insul. Pad Work Done as per Westing-:-
MD-0291
& Drill (4) Fixture hom~e Instructions
.Positioning Holes 14 STM GE~
Corrective Inspection Internals Opened Up /114
~tm Gen for MD.,...0280 Satisfactory Westinghouse Inspection.
I
~AFETY RELA~ED EQUIPME~
Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT
- MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION
. REACTOR. COC LANT PRESS & RELIIF f NCORE INST~
Corrective Cleaning &
Parts Cleaned Work Was Completed MD-.0427 I~stallation of Thimbles Installed Drive Unit Boxes
& Thimbles Not
.Comple~.
REACTOR INTERNALS Corrective Improper*
Clevis Insert Bolt Clevis Insert Remachined MD-0284 Manufacturing Holes Do Not Line to Fit
- Up With Holes iii Reactor Vessel I
Glev;i.f;l I
r11i RCP SEALS Corrective Seal Not Seated
- 3rd Seal Leaking
_Pump.Operated to Seat Seal OD-3350 111 RCP BEARING Corrective
.Improper
- Leakil)g Joint Repaired By Resoldering
~OOLER SU-417 Solder Job
'ii' RCP' LOWER Corrective Union Leaking Loss of Water Thru Made Repairs to Union rnARJ;:NG SU-4i5*
Union Seating Surf ace
~PRZ Corrective Weld Test Weld Tested Weld Was Tested, and*
MD-807 Satisfactory Inspected fl SEAL RETUR}f LINE
!11 RCP~~l\\~EX LINES Corrective Improper Possible Failure Lines Relocated as per MD-0802 Installation Engineering Drawing
'IPE SPOOL 1RC75 Corrective Impi;.-oper Possible Defect Ground Out Arc Strike on QA-0006 Installation Spool Piece
- +
..... ~.-...
. *
- SAFETY RELfrED EqUIPMJIT -..
Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE
, RESULT CORRECTIVE ACTION REACTOR.COO LANT'PREss*& RELIEF 1PS4 REMO!E OPERATOR Corrective Travel pf Valve Travel of Valve Was Checked Travel l'1it4 Specs*
OD-2539 May Be.Wrong According to Specs
.. fi.'i, i
PRESSURIZER Corrective Inspection Manwa,y Opened New.Gasket *Installed a.nd MD-0184
- Closed After Manway Closed Up 1,
.. Inspection fit.. GEN.& PRES.SURIZER Corrective Inspectfon Manways Opened &
New Gaskets Installed and MD-0281 Closed After Manways Closed Up
.....*. Insp~ction
?RES~URIZER HEATER Corrective Faulty Breaker
- Pressurizer Heat el;"
Installed New Breaker I
OD-3886 Will Not Operate I
rx1 & /114 RCP MOTORS Corrective Improper Location Possible Failure Relocated Ho~es as* per I
. SU'"'."409 of Flex Hoses Due to.Chafing Engineering Dwg
- tll. RCP OIL COOLJ):R Corrective Valve Leaking Due Vent Valve Leaking Lapped In Valve MD-0764 to Po9r Seat*
114 RCP Corrective Unions Not Made
.Leakage of Water Took Unions Apart, Cleaned su-4+6 Up Properly
& Reassembled lPR5 Corrective Improper Valve Assembled Installed Missing SS Washer
- 1, MD-0179 Assemble.
Without Washer-on Stud lLvs 1PR6 & 1PR7 Corrective Faulty Motor Operation of Valves Rewound Motor on 1PR6 SU-0164 on 1PR6 Slow LVS PR3 & PSl Corrective Possible Under-Possible Leakage Retorqued Valves as per MD-'-0286 Torque of Valve Specs I
EQUIPMENT VALVE 1PS3 VLVS 11RC9~ llRCll NATURE OF MAINTENANCE Corrective PD-1663.
Corrective QD..... 8358.
- sAFETY REL~ED EQUIPMEf'r
'Mechanical and Electrical Maintenance LER OR OUTAGE NUMBER*
MALFUNCTION.
CAUSE RESULT REACTOR COO f.'ANT PRESS & RELIE Ii' Plug Jammed Valve Did Not Operate Packing Glands Valves Need
. Repacking***
..Leak...
- CORRECTIVE ACTION Rebuilt Valve 1--~....-~...--~....-~~-+~__.;..~~~~~-""'.l-:--"'-.~--,~--,.,--~-,---f---'-~....,..--'---,.--:-~~1--~~......,-~~~~~~+---'-.,--,...,~~__;,,*~*-=--:-~--,----.,...*~~
VALVE. :q:>R25 V_LVS -1~~6 & 1PR7
- 1 112 ACCUMULATOR VENT VALVE 12sj2~
H 3 4-CCUMULATOR.
- l/LVS 13SJ22,24,171
~72,320 lALVE 1SJ67
~ALVE 11SS54 TALVE 12SJ33 TALVE lSJl Corrective SU-0137 Corrective*
MD;_,0595 Corrective
- OD-2919 Corrective on~3612 Corrective SU-195 Corrective
. OD-2295.
Corrective SU:--171 Preventative SU-224 I
Valve Does Not*
Close.Tight.
Will Not Pass Leak Test Faulty<;:ouplings _Coup],.ingE;J Leak*
on Leakoff Lines
. S !\\.FETY INJ
- Faulty Valve Le.aky Valve
- Faulty Valve Leaky Valve Malfunctioning No Indication of Position-Ind.
Valve Status Malfunctioning No Indication of
.Position Ind
- Valve Status Water in Motor Motor Would Not Operator Operate Valve Motor Operator.*
Break Power.Feed Burnt Out to Operator t
~--
. -Rese.~teci **&:-'Lapped Valve* -
I>~~i:ieCi ;_ ieak:*ref:it
. )..... '
Fabricateci>& In~talled..
N~w* C011plings:
- New Replacement Valve FA-1.5 Replaced Valves Rewired & Energized Rewired & Engergized I
Rewound Motor So It Will Operate Valve Power Leads Lifted & Marked
NATURE OF EQUIPMENT MAINTENANCE 1112 SI PUMP.LUBE Corrective OIL COOLER
. MD-.1120 fill SI.PUMP LUBE Preventative OIL COOLER MD-1163 f/12 SI PUMP.
Corrective MD-632 1112 SI PUMP Preventa.tive MD-8ll BIT HEATERS Corrective OD-2209 3AFETY INJECTION MD-54~
TALVEl 1SJ30 Corrective OD-2408 TALVE l()Jl Corrective SU-231 tALVE 11SJ54 Corrective OD-2821
'ALVES lSJl & 2 Corrective OD-4243 rALVES 11 & 12SJ44 Corrective OD-2420
- sAFETY REIAEn EQUIPMEfr Mechani~al and Electrical Mainteriance LER OR OUTAGE MALFUNCTION NUMBER CAUSE RESULT.
.. ~ AFETY !NJ.
Fouled By Grass Inspection.
I
.in.HeacJ.
Fouled By Grass
- Inspection
. in.Head..
Misalignment &
~xces9ive Vibration
.. *'..Out Of Balance
. Out. of Spec
- Wiring Error Does Not Operate Defective Oper, Will Not Operate Mo tot' Reinoteiy Defective Oper.
- Will Not Stop Motor & Water in Running or Drive Clutch Assembly Valve Rotted Packing*
Packing Gland Leak
- 1.
Faulty Motor Breakers Tripping Operators Out Dirty - Bad Leaking into Cont Gaskets Sump..
I I
CORRECTIVE ACTION Removed Head & Cleaned -
Installed New Ga.sket
. Removed. Head & Cleaned Out Grass Sent Pump to Mfg~ for Repair Replace with No. 2 Unit *.
Modification of Baseplate Rewired lfeC!,ter at Tank Install Power Lockout For ECCS Valves (ECN E-1672 Rev 2)
Removed Defective Motor -
Installed Rewound Motor New Motor Installed *-
Readjusted Clutch Assembly Removed Old Packing &
Repacked - Also Changed Nuts Replaced Motors & Retested Disassembled, Cleaned, &
- Reassembled with New Gaskets
NATURE OF EQUIPMENT MAINTENANCE 1114 ACCUMULATOR Corrective LEVEL TRANSMITTER
SU-149 ISOLATION VALVES Preventative HEAT Tfu\\CiijG MD,.:;,,B25 i
.1n2 SW STRAINER Corrective OD-3537.
1112 SW AUTO STRAINER Corrective MD-1209 1114 AU'}:'O STRAINER CoJ:'.rective MD-OBB9 1115 SW BREAKER Corrective OD-2577 H6 SW PUMP AUTO Corrective lTRA~NER OD-4099
>W PUMP MOTORS Corrective MD-lllB
- SAFETY REiiTED ECjUIPM'T Mechanical and Electrical Maintenance **
LEROR OUTAGE MALFUNCTION NUMBER CAUSE
,* RESULT
- ~ AFETY !NJ~
Faulty Level Replacemen*t Ne~ded Transmitter
.;a Damaged* Shutter Breaker Cannot Be
.&.Rod Elevator
- I. Pulled Out From Bus Incomplete..,.
Valve Inoperable Circuit from Remote Insufficient Refer "Memo E,....4Q3
.Heat Tracing*
. & 'APB
- sERVICE \\I IA.TER NUCLEAR AREA Diff. Device Strainer Runs Needs Calibra-Continuously tion & Cleanup Strainer Jammed Shear Key Broken Strainer Jammed Shear Key Broken Closing Coil Breaker Trips Failure Strainer Jannned Shear Key Broken Modification To Improve
~AW APB ED0027 Operation I
I '
CORRECTIVE ACTION Removed Old Capillary Tubes I
& *Ballasts &*Put In New as per PCS
. Replaced Shutter Mech~ &
Elevating M~ch, Rod Installed Relay & Relo<ide4 Coil of Contactor Installed Additional H.T~
Cleaned and Recalibrated Diff. Device PD2B6 Replaced Shear Key Replaced Shear Key &
Thrust Brg.
Replaced Closing Coil Replace Shear Key &
Buildup Shoes Replaced Mot.ors With Modified Ones
EQUIPMENT
- SAFETY RELfrED EQUIPMilT
'Mechanical and Electrical Maintenance LER OR OUTAGE NUMBER CAUSE MALFUNCTION SERVICE WA "ER NUCL.EAR AREA RESULT Failure of Clo~~
ing R~lay, Closing Coil, &
Close Latch Monitor Switch.
Pump Does Not Operate CORRECTIVE ACTION Replaced Defective Parts I
~~~.,.--.,.--~.,.--~.,.----t~~.,.--~~..,-.,.--.,.----J..,...,.--.,.--.,.--.,.--.,.--.,.--.,.--.,.--.,.--_,_+.,.--.,.--.,.--__;~~.,.--.,.---1-.,.--.,.--.,.--..,.......,.--.,.--.,.--.,.--~~+---,_..,.--'.~.-,--,-~
.* ~.,.---,.-.,.--.,.--.,.--~-:
Level Device Pump Runs.*
- Reattac:hed Displacer 112 SW J;>UMP 113. sw. :.PUMP MOTOR
!14, SW Pt,JMP 15 SW PUMP 15 SW PUMP 16 SW PU}1P L6 SW PUMP
) SW PUMP Corrective OD-3644 CorrectJve MD-064.:J_
Correct:::J.ve **
OD-2255 Corrective OD-2535 Corrective OD-2547 Corrective OD-2511 Corrective OD-3472 Corrective OD-2737
- I Not Connec~ed.,
Continuo.u~ly
- . to, i~y~.f ~~~i~~
- Tubes of Bearing.
Cooler Plugged With Silt Contrdl Power DeiOn Failed Bearing Cooler*
- Ne~ds Cleaning P.ump Will Not Op~rate
.**** *** *i"
.ci~~n **out:*'c~,al:e,r Replaced Coptrol.Power DeioQ.
Defective Closing Pump Will Not Operate Replaced Defective Closing Relay & Closing Relay & Breaker Closi~g Coil Coil.
Improper
. Adjustment SMLS Jammed Motor Grounded.
Loose Tube Teq-.
sion Assembly
... :**" Pump Will Not OperatE Adjusted 52HL Switch Pump Will Not Run.
Motor Trips Excessive Leakof f of Coolant Repair~d Jammed SMLS Replaced Motor Tightened Tube Tension Assembly L
~_t_*
L,
--1...-------
NATURE OF EQUIPMENT MAINTENANCE VALVE 12SW127 Corrective OD-2392 SW49 PIPING Corrective MD-1056 1115 SW*?UMP Corrective MD-1110 STRAINER BAC~ASH Corrective LINES.
MD-112l SW PUMPS Corrective OD-2101 SW PUMPS Corrective MD-0651 Hl & 1112 CHILLER Corrective
~OND "WTR RECIRC PMP MD-1089 Hl SW J,>uMP Corrective r
MD-0893 r12 SW PUMP
~AFETY RELA~ED EQUIPME~
Mechanical and Electrical Maintenance
- LE:R OR OUTAGE MALFUNCTION NUMBER CAUSE RESULT
- sERVICE.WA'l !ER.NUCLEAR AREA Roll Pin Wrong Excessive Play in S:Lze Operator Revision of Piping Held By New Piping Hanger Improper Expansion Joint Installation*.*.
Distorted.
Reinstall System Returned to Orifices Normal.
Vents Not High Spill on Startup Enough.
Install Orifices Restrict Flow*
Coupling Worn Possible Failure Faulty /Ill SW Switch With 1121 Pump
- Pump Malfunction Switch With /122 Motor Malfunctio1 Springs Didn't Change When Breaker Tripped CORRECTIVE ACTION.
Installed New Roll Pin in Operator Installed New Hanger a~ per Instructions I
Replaced Expansion Joint Rtdnstalled Orifices With New Gaskets Ext.ended Vents Installed Orifices Replaced Flexible Coupling Replaced /Ill With /121 SW Pump Replaced 1112 With //22 Changed Motor and Adj. Latch l
- sAFETY REL~EP EQUIPMEfr
- Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE I RESULT' CORRECTIVE.ACTION
'SERVICE 'WAT gR NUCLEAR.AREA
//12 SW PUMP Corrective Expansion Joint Pump Failure Replaced E:spansion Joint MD-1107 Malfunction i.T Repiaced 1113 SW PUMP Corrective Pump Malfunction Switch With 112,3 '
1113 With. 1123 MD-0815 1113 SW PUMP Preventative Signs of Mal-Starting to Show Will Be Replaced By The OD-2549
.function Wear One on.Unit 112 Side 1113 PUMP SCREEN Corrective ScreenWil.l Not Screen Returns to Replaced* Device PD2733 I DRIVE
.OD-3442
.Work. In.Auto.
.Inch Position
/f 14 SW PUMP Corrective Pumps Rusted Out Switch* with 24 & 2'5 Replaced* 14 & 15 with.
If 15 SW PUMP MD-0832 24 & 25 Respectful~y 1116 SW PUMP Corrective Pumps Rusted Out 1Switch with lt26 Replaced 16 with 26 I
MD-0816 *
/116 SW PUMP Corrective Shaft.Vibrating Excess Noise in Pump Will Be* Replaced with OD-3349 Motor One From Unit /n. Side 1116 SW PUMP '
Corrective Packing Seal Leak Repaired Seal and Leak as pe:i:'.
OD-2624 Blown ECN M-7232 Rev. 1
//16 SW PUMP Corrective Broken Seal Leak Replaced Packing Ring MD-0335 Underlock Nut Tube Assembly 1116 *sw PUMP Corrective Broken Expansion Leak Replaced Expansion Joint
. OD-3691 Joint 1116 SW PUMP Corrective No Bell Ring Bell Ring Must Be Installed Suction Bell Ring MD-1191 Installed..
EQUIPMENT.
1/15 TRAVEL SCREEN.
/Ill SW STRAINER STRAINER 1114 & //15 SW STRAINER 1115 SW STRAINER 1116 SW STRAINER NO. 1 EAC 1112 CIJG PUMP,*
VALVE 12,SW21 12SW23 13SW223 NATURE OF MAINTENANCE
-Corrective OD-3513 Corrective OD-2162 Corrective MD-1102 Corrective 14-0D-2516 15-0D-,.2862 Correctiv.e OD-4343 Corrective OD-3805 Corrective*
MD-1148 Preventative MD... 1161 Corre<;!tive D-3661 Corrective.
OD-3345 Corrective OD-2784
- *sAFETY *. REtAED E~UIPMlfr
'Mechanical and El~ctrical Maintenance MALFUNCTION LER OR OUTAGE NUMBER CAUSE RESULT
. *SERVICE WA'I ER NUCLEAR AREA
(!
CORRECTIVE ACTION Device Out Of.
Calibration.
Screen Press Switch Recalibrate per M3I N.G.
Repack NeE!ded '
Orif !ces Should
. Be. Removed Inspection Made:
Ori~ices Will.Be Removed Brokeµ She"ar Pin Failure Brelitker Won't
.Close.
It Won't Get Any Juice Broken Shear Key Failure Intercooler Tube Inspection Inspection Sheared Shaft Valve Position Hit'ting Insulation Coole*r Lubes OK Failure*
Broken Gasket Malf unc-Blew Out tion..
- a,ep~ck.it1g none. After Insp~d;toij, *
- Orifi~~*s* R_ei:noyed *and Flex.*: ".
Ga.sk~t s*.: Ip.shrl!ed
.. I~s:tC1.iiea
- N~:w
- Shear Pin. 'key*;:
Repa~red Bent In,1:erlo:ck, Replace Shear Pin Key Tubes In.Good Condition Removed Grass Reinstalled Gear On Stem Removed Insulation Repaired
- .SAFETY REL,TED EgUIPM~T Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION SERVICE WA1 ER I.mCLEAR AREA 11SW222 Corrective Valve Stem
- Broken Valve Replaced OD-.J371
.Malfunction 1113 CONT FAN COOLER Corrective Gasket Malfunc-Blown Gasket Replaced OD-3417 tion.
15SW223 Corrective Valve Malfunc-Jammed Closed Replaced Valve I
PD-1588 tion.
I 15SW69 Ccirrecti:ve Valve*Malfunc..,.
Stem Won't Turn Repaired PD-1589
.tion 12SW50 Corrective Position Ind.
No Indication Pointer Installed OD-3344 Missing CONTROL VALVES Preventative Needs New Liners Inspection
~ew Liners Installed SW 7Z's SU-0172 12SW23 & 12~W22 Corr~ctive Mech. Operator Wo.n 't Work New One Installed 23-0D-3686 Malfunction.
22-0D-3685 11SW23 Corrective Manual Operator Valve Won't Open Installed New Gear and OD-3.748 Failure Proper Gaskets 12SW22 Corrective Valve Works Only Valve Does Not Valve Operator Fixed &
OD-3801 Electrically Work Manually Installed - Added New Grease Fitting 12SW49 Corrective Inspection Fixed Scime Valves Replaced Teflon Seat, PD-1656 Installed Valve NATURE OF EQUIPMENT MAINTENANCE 13SW223.
Corrective OD-2472 11 & 12SW48 VALVE
- Preventative MD-1064 F~-1-31 FLEX Corrective CQUPLING MD-0623.
No. 11 CHG*. SUMP Corr.ective LUBE OIL COOLER MD-1143 ACCESS HATCH El.'100 Corrective OD-2604 I
PERSONNEL HATCHES Corrective PD-1269 CONTAIN EQUI~
Corrective HATCH DOOR MD-572 LOCK DEVICE Corrective PERSONNEL HATCH MD-0785 EL. 100 AIR LOCK Correct~ve OD-3385 EL. 130 AIR LOCK*
Corrective OD-3385
- sAFETY REL~ED EQUIPmfT Mechanical and Electrical Maintenance.
LER OR OUTAGE MALFUNCTION NUMBER CAUSE
, RESULT SERVICE WA' 'ER NUCLEAR AREA Gasket Failure Blown Gasket
!.I Switch
- Design Change,*'
Misplac.ed Contra Contrpl Rod Missing
.Rod
. SERVICE
~ 'ATER TURBINE AREA Grass in Tubes Inspection of Cooler*
STRUCTUl U\\L (CONTAINMENT)
Misaligned Door Door Leaks Hatch Door Door Leaks Gaskets Failure Hatch Door Door Leaks Gaskets Failure Door Broken Does Not Open Properly Door Does Not Door Leaks Lock Properly Door Wheel Spins Dangerous Too Freely
- 1
..... I CORRECTIVE ACTION
- Gasket Replaced
~
11 & :t.2SW48 Valves Switched with 21 & 22SW48 Valves Replace Control Rod as per ECN M-7684 Replaced Pipe Eng Plugs &
Cleaned Out. Tubes..
- Aligned Door & Connected Inner Door Leakage Door Gaskets Reversed, and Adjusted Doors Replaced all theG~skets Inst&lled Bearing Adj. Door Closin,g chain Adj. Door Closing Lock
NATURE OF EQUIPMENT MAINTENANCE EL. 130 AIR LOCK Corrective OD-3005 100' CONTAINMENT Corrective*
DOOR MD-0933 CONTAINMENT Preventative
-PLATFORM MD-1119 1PERSONliEL HATCH Corrective I
OD-3936 100' & 130' INNER Corrective AIRLOCK DOOR OD-4074 OD-4063 PERSONNEL HATCH Corrective MD-1223
'.ilo
- 11 AUX BLDG Cor:rective EXHAUST FAN MD-915 IJo. 12 AUX BLDG Corrective
!:XHAUS'J;' FAN OD-0919
~HARCOAL FILTERS Corrective MD-797. '
fo. 11 FILTER UNIT Corrective OD-2558
- sAFETY
- R~L!En EQUIPMEfr
- Mechanical and Electrical Maintenance
- LER OR OU'l'AGE MALFUNCTION NUMBER CAUSE
' RESULT
- sTRUCTU RAL (CONTAINMENT)
Malfunctioning Gasket Blowout of Gasket Groove when Opening Door_
Broken_ Roller Door Malfu:nction Design Change AP8-ED0018 Bad Gasket Door Leak Latch Malfunction Leaky Door Door Out of Leaking Do9r Adjustment VENTILATIO ~ AUX BLDG EQUIPME NT Adjusting Snap Coupling Adjusted.
.Rings Came Loose Past Stops Bad Outboard Excessive Noise Bearing.
Paint on Filter Filters Need Unit'Boxes_
Changing Temporary Filter RF Filters Has High*
& Debris in Unit Diff Press Across Them e:
CORRECTIVE. ACTION
- I Cleaned Gasket and Replac.ed*
Gasket Rep~aced Roller New CRDM Vent Fan lie Parts New Gasket Reinstalled and Tested Adj. Lock Strike Bar.-
Tested OK Door Adj. and New Set Screw & Bolts Installed Pully.R.epaired & Reinstalled Replaced Outboard Bearing Replaced Filters Replaced Filters &. Vacuumed Out
--- ------ --- -- -- ------ ~
EQUIPMENT No. 11 & 12.SUPPLY BLOWERS LOUVER COVER PLATE No. 11 AUX BLDG EXHAUST FAN No. 11 AUX BLDG EXHAUST FAN No. 11 EXHAUSTER HEPA FILTERS ALL No. 11,12,13 EXH FILTERS SUPPLY & EXHAUST BL~WER MOTOR SHEAVE NATURE OF MAINTENANCE Preventative MD-326 Corrective MD-456 Corrective MD-892 _-
Corrective OD-2693 Corrective SU-422 Cprrective SU-356 Corrective MD-7°66 No~ 13 ROLL-0-MATIC Corrective FILTER SU-271
.* -SAFETY REJ!~rED EQUIPM'1T*
Mechanical and Electrical Maintenance LER OR OUTAGE NUMBER CAUSE RESULT
... VENTILATIOJ AUX BLDG EQUIPMEHT I
CORRECTIVE ACTION Equipment D~ficiency Grease Fittings Installed Grease Fittings Not Installed*
Equipment Problem Relief Doors Removed Doors Blocking Back Draft Dampe+s VENTILATION -
AUX BLDG, PENETRA' ~ION,
. '(CONTROL.AR A). &. SWITCH.GEAR -1~
Cracked Adj Nut Belts Loose Replacement Needed*
Replijcement Needed Replacement Needed Scaffolci_Plac~d Up Against Roll Cannot Adjust Contact Ground
. Replacement Required Replacement Required Replacement.
Required Would Not Permit Roll to Roll Replaced Adjusting Nut Replaced Belts.
Replacement Made Replacement' Made Replacement Made.
Removed Scaffold.
DAMPER IND ECN C-16233 Changed 2 Amp Brea_ker to
+-~MD
__ -_2_0_1 ________ -+------'--------------+-----------------11--------------------+--s __
A_m_p __
B_r_ea_k_e_r ____________ ~_
CONTROL.AREA SUPPLY FAN DAMPERS Corrective OD-2488 Limit Switches Not Operating No Start Lights -
No Stop Lights Adjustment of Limit Switches
~---------_l__ _______
___L ___________
- SAFETY RE~ED EQUIPME'T Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION*
I EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION I
VENTILATION - D ESEL & FUEL HANDLJ NG BLDG No. 11 FUEL.HAND-Corrective Loose Fan Belt Sounds Like Loose Belt Cover Tightened LING BLDG EXH FAN OD-:2484.
....Cover.
Fan Belt No. 11 & 12 EXH Corrective Damaged Need Replacing Replaced FHB Exhaust HEPA i FILTERS SU-423 Filters No. 12 FHB EXH. FAN Corrective Drive Belts Shot Belts Came Loose Replaced with New Belts OD-4143
.~ Tore Up No. 12 FHB. EXH FAN Corrective Low Setpoint Causes Trip on Reset Overload Trip Point OD-3824 *.
.on Trip Overload to Higher Amp VENTILATION REACTOR CONTAINMEl T*
FILTER
. Preventative*
Design Change AP8-ED0045 Filter* Installation MD-1169 1.5. FAN COOLER Corrective Stripp~d Nut Unable to Position Welded Nut OD-2519 Vanes 11 FCU MOTOR COOLER Corrective*
Missing Bonnet Leak Replaced Bonnet Nut OD-36.89 Nut
_11, 12' 13' 14' & 15 Prev;entative Design *Change AP8-ED0019 Replace Flexible Hose.with FCU' s *
- MD"'.""1044
. Piping MD-1045 MD-0923 MD-1046 MD-0922 11,12,13,15 FCU's Corrective High Vibration Investigation Balance Fans MD-0392
~s9-
__ _____r.
EQUIPMENT PLUG PEDISAL' CONT VENT NATURE OF MAINTENANCE Corrective MD,;_0591 Corrective MD-0539 Corrective MD-0457
- SAFETY RELft.ED EQUIPMiflh.
- Mechanical and Electrical Maintenance LER OR OUTAGE MALFUNCTION NUMBER CAUSE RESULT CORRECTIVE ACTION VENTILATI01 REACTOR'CONTAINMlNT Modification.
ECN M-18440 Installed by qE&C Piping Weld Failure ** '
- Weid.
- Repait'ed* *
~emo PSE-245
- ("
Investigatioll
- Repafi.-~d:* Hpr~~-:.. :
- ' *:/
.Holes in Vent I
-::-:~~~~~-,.-~~-+-__,.__;_~__,.__,.__,__,.-f-__,.-,.-~__,.~~~'--~....+~-'--~--'--..;_;_~__,.~+-~....,-~~__,.~~_;.;.,_.....-+-~
... ~._;.;.~
.. ~
....,,..,,,.~.~
.....,...,....,,..~__,,~....,.--~.-
14.com~ FAN coot.ER.
I l4 'FGU' MOTOR COOLING UNIT
- 13 & 14 FCU 15 FCU
.corrective OD-3809 corrective OD-3443*
Preventative MD-0277*
Corrective OD-2079 Corrective OD-2940 Corrective OD-2931 Corrective MD-0186 Motor Malfunc"-
Trip~ Out
.*A<lJust¢d* Ifa,mpers tion*..
'I Gasket Blown Motors Disc;on-nected Fan Problem Ruptured Line Diaphragm Malfunction Oversized*Keys Motor Sent Out For Repair Trips Out Leak of SW Leak Needs Replacing l*'*
Motors Rein~talled ~
Checked Sent *to Westingqouse and Sent.Back Installed Flex Connections from No. 2 Side.
Replaced Diaphragm.and 0 Rings Replaced Keys & Test~d 1
NATURE OF LER EQUIPMENT MAINTENANCE CONT HVAC 47 Corrective MD-0515.
15 FCU Cor.rective MD-0278 lfl4 FAN*
Corrective MD-0419 VC1 & VC4 Corrective OD-2721
~1VC1 to 1VC6 Corrective I
MD-0635 ISOLATION,VLV 1VC4 Corrective OD-2384 1VC5 & 6 Corrective MD-0707 (12 vc VALVE Corrective MD-1066 H2 WASTE GAS COMP*
Corrective*
SU-240 1ALVE 1NT24 Corrective PD-1491 OR
- sAFETY REL~ED EQUIPMEfr
'Mechanical and Electrical Maintenance OUTAGE MALFUNCTION NUMBER CAUSE RESULT
. VENTILA TION CONTAINMENT*
Switch Needs Set New Setpoint
...... New Setting Motor Switched*
Old One.set Out
{1/12)
Bad Bearings Fan Vibrations Defective Bu]_b Trip Valves Tested Defective Valyef?
- Valve *won't Close Va1ve *stays Open
'Qesign Change ECN M-7729 Flange Needs Slip Too Large Safety Cage WASTE DISPOSAL GAS Possible Blockage System Operation Question I
Rust & Foreign Valve Leaks Thru Matter on Seat
- CORRECTIVE ACTION Switch Recalibr!;lt:ed*
1122.
Repl.aced Mo1;9r with
~
Bearfrtgs Replac~d and
- aaia~ced Fan<* *
. Rei>l~ced L:f$J:it. Bulb.
... ~:.... :........
- switch with Unit 112 Valves'*
.\\
Replaced En.tin~ Valve From.
Unit Ill.
Change ]flange Cut Down Safety Flange and* Reinstalled in Removed Check Valve - Checked for Debris & Proper flow -
Reassembled Disassem~led Valve, Cleaned*
and Reassembled
NATURE OF EQUIPMENT MAINTENANCE VALVE 1WG66 Corrective OD-4056 VALVE 1WG6
- Corrective OD-2718 VLVS 1NT25 & 26 Corrective SU-0140 VALVE 12WG24 Corrective SU-262 VALVE lWG?O Corrective SU-280 No. 1 SPENT ;RESIN Corrective STORAGE TANK SU.... 228 I~ FEED BREAKERS Corrective MD-0272
- sAFETY RELfrED EQUIPME'T Mechanical and Electrical Maintenance
- LER OR OUTAGE MALFUNCTION NUMBER CAUSE
, RESULT WASTE DISPOSAL GAS BA Eyaporator Operation of Evap...-
Not Venting orator not as Spec Properly States
- .i Plastic in Line
- flow thru Valve Restricted Leakage.. Between Valves Will Not Seat.& Disc Pass Leak Test Possible Valve Lifts at Wrong Improper Setting Pressure*
Spring Tension Will Not Allow on Check too Passage of Gas at High
. WASTE DISPOSAL LIQUID Malfunctioning Strainers 4KV VITAL Improper Design Certain Buses Do Not Auto Switch in Blackout if Certain Events Occur CORRECTIVE ACTION Removed Bonnet of 1WG66 to Veµt Gas, Made Repairs to I
Valve 1WG70 to Correct Problem Disassembled Valve &
Removed Piece of Plastic -
Reassembled Valve Relapped Seats on Both Val yes Removed Valve & Bench Te$ted Valve Lifted Within Specs Made Adjustment to Spring to Allow Proper Operation Strainers Replaced &
Welded in Place System Redesigned & Changed to Allow Auto Switching to Diesel Power Source with Loss of Voltage
EQUIPMjT
. *sAFETY REtfrED Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION*
4KV VITAL 12ASD 4KV BKR Corrective Faulty Relay Breaker Will Not Replaced Faulty Relay.
OD-3423 Clo'se SS1143 & SS1144 Corrective Faulty Closing Breaker Will Not Replaced Faulty Clos~ng.
Spring Bearings*
4KV BKR SU-402..
Spring.Bearings
- Operate Correctly
- 125*vnc 1B.125V BATTERY GRD Correctiv*e Ground in $ystem Ground Shown On When Investig?tiOn Wa,$ M~de.. -
OD-2855
.Ground -Detector Grouncl Had Be_en Clec:i.red*
1C2 125V BATT CHG Corrective Float Adjustment Charger Not Working Reset Float Adjustment. -.
J i
oD~3619 Not Correct -
l/30_BREAI\\EJ1 IN lCCDC Corrective Ground in System Ground Shown on Meggereci Out Breaker OD-2558 Ground Detector
- .Found No Ground
'1116 &. 1118 BREAKERS Corrective Ground in.System Ground Shown on Meggered Out Found No IN lBDC OD-2215 Ground Detector Ground 1118 BREAKER** IN lBDC Corrective Ground in System Ground Shown on Found No Gro11nds OD-2479 Ground Detector 11128: BREAKER IN lDDC
.Corr~ctive Ground in Valve Ground Shown on Repaired Valve - Ground OD-2810 1SJ166 Ground Detector Cleared 1130 BREAKER IN lDCC Corrective Ground in Snap Ground Shown.on Dried Out Switch -
OD-3023 Lock Switch Ground Detector Cleared Ground
'.le BATT BUS Corrective Wiring Faulty Ground Shown on Replaced Wire$ 1 & 5 in I
OD"'.'2977 Ground Detector Cable 1UNT29PA-CT Fqr Valve 1VC6
- sAFETY REtf.rED EgUIP~T Mechanical and Electrical Maintenance
- l NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 125 VDC lC VITAL INST BUS Corrective Blown Fuses Low Voltage Output Replaced (2) 100 Amp Fuses -
INVERTER OD-2141
- Tested Unit -. Test Satisfactory lC VITAL INST BUS Corrective Blown Fuses Low V.oltage Output Replaced Blown Fuses. -
INVERTER OP-2113 Tested Unit & Found It Operating Satisfactory lC VITAL INST BUS Corrective Transistor Low Voltage Output
. Charged Transistor* ~
INVERTER MD,....0207
.Fa:ilure.
Checkout System*
VITJL INSTRU BUS lA,lB,lC ViTAL INST Corrective Low.Voltage Voltage Out Of Spec Increased.Volt~ge on BUS OD-2726 Meters Out of
- 4.8.2.1 lA,lB,lC Buses.*
Calibration lA *&.lC VITAL INST Corrective Blown Fuses Voltage Out of Spec Replaced Fuses & Retested BUS OD-2645 HEAT TRACING VITAL J;IEAT TRACE Corrective Defective 3 RTDs Must Be Replaced*
- Installed. RTD' s and.Checked MD-0592 V.M.T.
Corrective N.G. Ckt. 62 Must Be Replaced Replqced Heat Trace OD-3481
'SAFEGUARD~ EQUIPMENT CONTROI No. lA SEC CAB Corrective Door Micro Switcl Causing Door Open Replaced Part Needed OD....,2593 Arm Missing Alarm in CR
EgUIPMifr
.
- SAFETY. RELAED Mechanical and Electrical Maintenance NATURE OF LER OR OU'I'.AGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE I
RESULT CORRECTIVE ACTION
'i ECN C-16338 MD-352 I
I..
NATURE OF EQUIPMENT MAINTENANCE I AUX FEED WATER PUMPS Preventative I
MD..:..0315 I
NO. 11 SCREEN WELL.
Corrective SUMP PUMP OD-4066 SERVICE WATER SUMP Corrective I PUMP NO. 1 BAY OD-2689 I
NO. 11 SCREEN WELL Corrective SUMP PUMP OD-2377 I
SERVICE WATER SUMP Corrective PUMP NO. 1 BAY OD-2743 SERVICE WATER SUMP Corrective PUMP NO. 3 BAY.
- oD-2302 EX. TANK LEVEL Preventative MD-561 (PT3771 & PT3773)
Preventative 11CH9 & 12CH9 PD-1466
~SAFETY REL!!-ED EQUIPME~
Instrumentation and Control Equipment Maintenance LER OR OUTAGE MALFUNCTION NuMBER CAUSE RESULT AUXI,IARY FEEDWATER Faulty Logic In Malfunction Of Control Circuit Equipment BUILDING & EQUIPMENT DRAINS Faulty Control Pump Runs Device (Level)
Continuously Faulty Level Pump Runs Control Device Continuously Faulty Level
],"ump Does Not.
Control Device Start Faulty Level Pump Does Not Control Device Start Faulty Level
~ump Does Not Control Device Start C:ULLED WATER Refer to:
System Modifi-
~ys~em Modif i,,,.
ECN C-:-16278
- cation Needed cation Done
_System Modifi-
~ystem Modifi-
- cation Needed cation Done -------
CORRECTIVE ACTION Retest as per ECN C-16237 *
- Remounted Displacer on Level Device Replace Adjustment Screw on Level Device
- Adjusted Contacts on Level Device
- Cleaned Switch Which was Corroded
- Adjusted Level Device &
- Tested
- Added Alarm as Per ECN C-16278
-Welded Adaptors on Valves to
- Allow Placement of Instruments
" esAFETY REL/4ED EQUIPHEI9 Instrumentation and Control Equipment Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION
'RESIDl IAL HEAT.REMOVAL Adjusted 11RM29 Corrective Pushbutton Valve Will Not*
Repaired and SU-0178 Failure Work in Auto Pushbutton on Console
'VENTILATIO:N AUX'BLDG'EOUIPMEl'T PD-7540 Corrective Improper Cannot Adjust Switch Replaced With a MD-622 Ins tall a tion Setpoints*
- Panel 230 & Rewi'red 115VAC lC VITAL INSTRU.
Corrective Short Citcuit Fuses Opened" Replaced Components INVERTER OD-2901 i
I
~
EQUIPMENT PANEL*40l-l REDUNDANT AIR REGULATOR TO SU-165 & V-1CC149 REACTOR PROTECTiON CHANNEL lLT-518 RADIATION MONITORING SYS 1RR3.
- 1AIN STE~ TRA~SMirTER lFT-523
~AFETY INJECTION - REFUELING IATER STORAGE TANK LEVEL f.AFETY INJECTION ~- REFUELING
~ATER STORAGE TANK LEVEL
- ONTAINMENT VENT VALVES VC1;2,3,4,5 rASTE DISPOSAL -
RMS ALARM LIGHT fEED & CONDENSATE 12BF40 SU546 EED & CONDENSATE 11BF40 SU548 PCLEAR INSTRUMENTATION N31 i
SOURCE RANGE
~2 STM GENERATOR STM FLOW TRANSMITTER FT-522 1N1J~UMENTATI~ AND CONTR'j-CORRECTIVi MAINTENANif WORK ORDER NO..
PD-1285 PD-1286 PD-1316
-~
PD-1322 PD-1324 PD-1325 PD-1329 PD-:"1330 PD-1335 PD-1336 PD-1343 PD-1345 LER OR OUTAGE NUMBER MALFUNCTION CAUSE.
.. RESULT Leaking Diaphram Air r;fot Switching
- ,J>
U_*.*
Functional Test Out of Spec Interaction Bet-Intermitteµt ween Recorder ancl Al~rms Al~.PllS -
- \\~....
"*;:"*:*~
.~.
TranslQitter Extreme Z~ro Malfunctioning.
Shi'ft.
Level Device Out Incorrect Level of. Calibration..
Level D.evice Out I Incorrect Level of Calibration Lack of QAF19 TDR-075 for Installed Vlvs N/A.
.. N/A.
Solenoid Valve Not Valve Leaks Past Seating Correctly Seat Solenoid Valve Not Valve Leaks Past Seating Correctly. Seat Connector in Penetration Bad Transmitter Malfunctioning Failure of Channel Excessive Zero Shift
- CORRECTIVE ACTION I Replaced Regulator Recalibrated Trip Points for 1LC518A
& 1LC518~
Neeq Independant Power Sµpply Recommended *
\\
I Replaced Transmitter Calibrated LT-921
\\
& LA-5905 !B Strapped 1LC-920C
& Performed Loop Che*
Replaced Valves Perform ECN 16363 Replaced Valve Internals Replaced Valve Internals Wrote DR-0224 Replaced Transmitter
& Recalibrated
- -- --- ~_:_~ ___
____l ___
_____,L______:_ _____
IN.RUMENTATIC9 AND CONTRA CORRECTI\\9 MAINTENANA:
\\'.i LER OR OUTAGE MALFUNCTION EQUIPMENT WORK ORDER NO.
NUMBER CAUSE.
RESUL'f CORREC1IVE AC~IO~
REACTOR PROTECTION fT-532 PD-1348 Comparator Functional Check Replace4 Comparato~
1FC5~0A-B Out of.Spec
& Performed Malfunctioning 1PD2.2.048 &*
1PD2.6.048
~UCLEAR INSTRUMENTATION PD-l352 Balancing Motor Pen ;J.s. Bindin&
Replaced Balancing NR45 RECORDER
&,!functioning Motor REAClOR PROTECT.ION CHANNEL
- PD-1353 1FM530B Out of Functional Check Recalibrated lFT-530
.... Calibration...... Out.of.$pee.....
1FM530B REACTOR PROTECTIO~ CHANNEL PD-1354 iFM520B & 1FM520C F~nctional Check Recalibrated lfM520l, iFT,...526 Out of Calibration *out of Spec
& 1FM520C IAW 1PD2.2.036.
H3 STM GEN STM FLOW TRANS-PD-1379
'I;ransmitter
~~c;:essive Zero Replaced Transmitter MITTERtlFT-532
..Malfunctiori.:ing*.. *: '.
.& Recalibrated s11i£t......
I I
- vc BORIC ACID COUNTER lYM-110 PD-1384 Transmitter Has Readirys High Reset Zero
.. High Zero Adjustment i
JASTE.DISPOSAL GAS 1WG41 PD-1385 Pilot Stem Valve/ *Won "t Open Reconnecte<;l Spring
. Retaining Spring
. I Disconnected W>IATION MONITORING SAMPLER PD-1386 0 Ring Was Broken Leakage From.Device Replace 0 Ring FOR 1Rl3C tADIATION MONITORING VACUUM PD-1387 Sample Valves &
Failure of Pump Changed Sample Valve
>UMP FOR 1RllA~lR12A,lR12B Vent Return Line
& Rerouted Vent
....*.Not Correct Return Line rQLID STATE PROTECTION SYSTEM PD-1391 Design Annµnciator Alarms DCR PD0015 Issued 10-,14-76 I
IN~RUMENTATI~ AND CONTR~ CORRECT!~ MAINTENANlli!
e,.
LER OR OUTAGE MALFUNCTION I
I EQUIPMENT WORK ORDER NO.
NUMBER
- CAUSE.
RESUL'.f CORREC'PVE ACTION I
4 T. PROTECTION TE-421 A/B PD.;...1398 Signal Isolator Functional Te~t -
Replace Signal
~
1TM421G Bad, &
BS422D Out of Isolator 1TM421G &
1TC421A,1TM421G, Tolerance Recalibrated 1TC42
& 1TM422F Out of 1TM421G & 1TM422F
.Calibration I
REACTO~ COOLANT FLOW PD-1427 lFC416 Had Drifted Channel Function Performed Calibrati*
~
... '..Check.~.Q~t.of.Spec & Reset 1FC4l6 Trip REACTOR COOLANT lLT-460.
- fD-1432 N/A Sensor Calibration Recalibrated Sensor Out of Spec NUCLEAR INSTRUMENtATION' PD-1448 N/A Positive Rate Trip Completed PD16.1003 IN43 POWER RANGE
.Actuat~d.Ot3%.Rate.Satisfactory
/iT PROTECTION LOOP TE43i A/B PD-145l iow Level Amps &
Functional Ch~ck
- Recalibrated Low Lel I
. Fune t ion Gen~
put of Sl>ec Amps & Function Gen I
1QM-431A Out pf
. Calibration
~...............
PROTECTION LOOP l~T-543 PD1452 1FM-543C &
Function~! Check Completed Cal Check 1FM-543D Out of Out of Spec
& Adjusted lnf543C Calibration
'& 1FM543D NUCLEAR INSTRUMENTATION PD-1470 N/A N/A Perform Calibnation N31 SOURCE RANGE Check, In Spec REACTOR COOLANT PR-2 PD-1477 A
Clogged Vent Tube PR-2 Does Not Replace Clogged Ven1 Close Once It is Tube Opened REACTOR PROTECTION CHANNEL PD-1483 N/A Functional Test Completed Channel FT-520
........ Out.of Spec... :*...Calib.Check..
SAFETY INJECTION #11 ACCUMU-PD-1486 N/A N/A Reset High & Low LATOR LEVEL TRANSMITTERS Setpoints :£or LT934l.
EQUIPMENT SAFETY INJECTION #12.ACCUMU-LATOR LEVEL TRANSMITTERS SI #13 ACC~LATOR LEVEL TRANSMITT.ERS SI #14 ACCUMULATOR LEVEL TRANSMITTERS f
INS'fRUMgNTATION AND CONTROL CORRECTIVE MAINTENANCE
.LER OR* OUTAGE MALFUNCTION WORK ORDER NO.
NUMBER CAUSE RESULT PD-1487 N/A N/A PP-1488 N/A N/A PD-1489 N/A N/A CORRECTIVE ACTION Reset High & Low I
Setpoints for ~T-931
. &. LT""."935B
-Reset High &,Low Setpoints for LT~~3l
& LT-935C Reset High & Low Setpoints for L+-931
& LT""."935D.
I I ~~~--..~~~__,.~~~~~~-1-__,._,,,~~--..--..--..-+o--..--..~__,.__,,~--f
~~--..~~--..~--..-+---..~.....,......-...--~~--t--__,.~__,,__,,~~~~-
! RP CHANNEL lFT-542 FEEDWATER 11 & 12BF19 Valves FEEDWATER 13 & 14BF19 Valves REFuELING WTR STORAGE'TK.LEVEL INDICATION & *ALARM**.*
REACTOR PROTECTION* CHANNEL.
- FT.... 540 '
- PD-1493 PD~1so2 PD-1503 PD-1514.
PD-1517 CONTAINMENT VENT 1VC7 thru 1VC14 PD-1521 Solenoidei Not
.. *.*..... sized. Propei1:Y.
Solenoids Not
.S:i.zed Properly.
- .Grou.nd Problem in Annunciators
& Inst. Out of
.. Calibration 1FC540 A/B Output 112 Out of Calibration Limit Switches Solenoids &
. Tub:i.ng in Error
- -11-.
Functional Test Out.of.Spec.. **
Completed Channel Calib. Check Valves Not Closin ~ Replace Soltmoids
.in.Time.Allowed Valves Not Closing Rep.lace Solenoids.
in Time Allowe<J Level.Indication is Different by 3 1 & High Alarm
. is. Alarming.....
Setpoint for FC540.A/B Out o~
Spec..
Calibrated 1LT~921
& Cleared Grou~d Reset 1FC540 A/B Output 112 Valves Not Replaced Limit Switc Operating Proper-Solenoids & Tubing ly.....
.......... Restroked Valves
**--~~---------
~QUIPMENT MAIN STEAM FT-541 NUCLEAR IN~TRUMENTATION N3:J_ & N35 eve lMCllOB CONTAINMENT'VENT 1VC6 REACTOR PROTECTION LOOP #13 AT/TAVE NUCLEAR INSTRUMENTATION SAMPLING 1SS107 CONTAINMENT VENT 1VC6 NUCLEAR INSTRUMENTATION N36 INTE~EDIATE RANGE IN8rRUMENTATI~ AND CONTR~ CORRECT!~ MAINTENAN4J' WORK ORDER NO.
PD-1525 PD.:.1527 PD-1550 PD-1551 PD-1557 PD,-1558 PD-1559 PD-1561 PD-1563 LER OR OUTAGE NUMBER MALFUNCTION CAUSE RESULT CORRECTIVE ACTION Trip & Reset Points Not Cal-cu,lated Correct-ly Noise Servo S~tpoint
- Amplifier Failed Furictional 'fest Out of Spec Recalculated Trip &I' Reset Points
- Functional Test*.. iµ Spec..
Sporatic Spiking See PD Work Order
.on.Channel Nll :... PD~l558 Setpoint Does Not Track ~roperly in Manual Replaced Servo Setpoint's Amplifie Adjusted Gain & *
................................... -,*.. *.. -.*.'. *:-.*.. *.*.. *.. *: *.*cai.Pot...
- Summator & Lead-Lag & Function Generator Out of
.. Calibration....
Inner to Outer Shield Resist-ance Reading Out N/A Remove & Repl~ce Tubing & Solenoids_
................. for Maintenance Functional Tei;t Out of Spec*
Sporadic Spiking Recalibrated Summat Lead-Lag & Functio~
Generator
.Qt;.Spec.Low...........................
Open Limit Switch.Will Not Stay Rea4justed Limit 1
.... Constantly Closed. Closed.............. Switch &.Cycled Val Ground on Limit Sw:ltches Low Ground Reading Replaced Cams & Mic Switches & Restroke Valves Noise Problems ON *N36 SUR Problem Cleared Whe CU Cable was DiscoD nected at the Detector
EQUIPMENT IN~RUMENTATicf AND CONTRlf. CORRECTivf MAINTENAN~.
WORK ORDER NO.
LER OR OUTAGE NUMBER.
MALFUNCTION CAUSE.
RESULT..
CORRECTIVE ~CTION REACTOR PROTECTION CONT. PRESS*
PD-1566 PT-948A Out of Recorder' Does.Not Completed Calibratic 1
CHftN IV
..........Calibratio11.. '.... Read Z~ro ::Ps:i.... *: *:. Check * *... :..
i ~~~~~~~~~~~~~~-1-~--.~--.~--.~-1-~..,..-~~~~~~~~~~~~--.-1-~--.--.--.~~~~-t-~~--.~--.--.~~
REACTOR ~ROTECTION CONT. PRESS CHANN III
.. REACTDlLPROTECTION*CON!E-P.RESS CHAN II
. REACTOR PROTECTIQN CONT PRESS CHAN I NUCLEAR INSTRUMENTATION N32 & N36 NUCLEAR INSTRUMENTATION N~3 REACTOR COOLANT CHANNEL PT-405 NUCLEAR INSTRUME~TATION NEUTRON DETECTOR FOR N31 & N35.
NI SOURCE & INTERMEDIATE RANGE" N31 & N35 DETECTORS SAFETY INJECTION PANEL 235.
SAMPLING SYSTEM PANEL 245 PD-1567 PD-1568 PD-1569 PD-1572 PD-1573 PD-1585 PD-1587 PD-1593 PD-1597 PD-1598 1PC948B/E Power Supply Capacitors
.Failed.
Recorder po~s Not Read Zero*Psi Replaced Capacit.ors
& Recalibl'.'ated Sensor *PT~948C Transmitter Output Completed Sensor Out of Calibra-43mu Low Calibration
.~i:ioii... ** **.. * ** **...... *.**.*. ** **. *~.*. *:.. -~.*. *.**~. **
Sensor PT-948D
- out of Calibra-
.. _... _.. _... *.:ti.on*... _*. *.: **. *.* *......
- Low Inner to Outel'.' Shield Tr.anslllitter Output Completed Sensor
~~~. ~ig~
C~libratio~
WO Specified to*~ea~
Cables Only
....... *.*.*.. :Resistance. :.... *. * *.*. *: *:. *: *:...... *:.....
Bist_able Out of
..... Calibration.
Cold Solder Joint on Indi-.
ca tor Bad Neutron Detector N/A Salt Water Deposits Salt Water Deposits.....
Functional Tes~
Out 'of.Spec Indication is.
Erratic N/A
~.:.
Reset NC308 PRN43 Bistable Fixed Cold Solder Joint & Calibrated
- Press Indicator &
TraQ.smitter Replaced Neutron Detector Removed & Cleaned Detectors & Reinsta Cleaned Panel ~
. Components..
Cleaned Panel &
Components
I~TRUMENTAT~ AND CONT~L CORRECTI~*MAINTENA~E LER OR OUTAGE MALFUNCTION EQUIPMENt WORK ORDER NO.
NUMBER CAUS$.
RESULT...
CORRECTIVE ACTION Nl NEUTRON DETECTOR N32 & N36 PD~l600 Detector Faulty....
.Repla.ce.Detector RM 1Rl3 & SAMPLER PD-1602 Ruptured Liner tea~ing System Replaced Liner &
I
& Faulty 0 Rings
.. 0 Rings.*.
CONT VENTILATION 1VC6 PD-1604 Salt Water Cleaued Salt Deposi Deposits from Tubing, Soleno I
and Terminal Boxes CONT VENTIL!TION 1VC2 & 1VC3 PD-1605
- Salt Water Cleaned Salt Deposi I
- Deposit El from Tubing,Solenoi I
& Termin<!-1 Boxes I
i PRESSURIZER.RELIEF 1PR15 & 1PR17 PD-1606
- salt Water j
Cleaned Salt Deposi
...... :Deposits
.......... *.i...... :..........
CONTAIN VENT &
' )I SI PANELS.
PD-1607 Water
'. 1/
i No Water Damage I' ** I
..Found
......... i*..............
I SI PANEL 2*41 & JT-479 PD-1609 Salt Water
. N/A./
Clean Panels &
. : Components
......... *r. *'..........
f SERVICE WATER 13SW223 PD-1610 N/A Mamial,A.ctuato"f Cleaned & Lubricate
.. Cannot.Engage..
Actuator NI N32 & N35 DETECTORS PD-1633 N/A N/A Clean & Reinstall Detectors DR PD024lt Issued NI CABLE 1NIS2CQ-AQ
- pn-1640 N/A Low Resistance Removed **2* &
Reading Reinstalled Connect
- f.*......
. Reading.Satisfactot NUCLEAR INST N32 & N36 PD-1642..
... bei~ciar*:iaii1tj.
.. Detector Replaced NI N32 SOURCE RANGE PD-1(>49 Cable in Cont, &
Sp:Lkes to 2000cpa Moved preamp &
Placement of Replaced Cables See
- i.
Preamp.
....DR~s PD0266,0267 I!
I :
~~RUMENTA~I~ AND CONTRIL CORRECT!"' MAINTENANIE LER OR OUTAGE MALFUNCTION I
EQUIPMENT WORK ORDER NO.
NUMBER CAUSE.
RE~ULT CORRECtIVE ACTION 4T PROTECTION 1112 LOOP AT PD..-1655 Tran~istors Q2 &*.C.T Ind:l,c~t.OJ:'
Replaceq Q2 & Q3.
Q3...
. Er~atic*.*.... :~..... *....
CONTAINMENT VENT 1VC6 PD-1662 N/A Iii/ A Repl~ced Conduit I
I
'... ~..
- to Solenoi<l Valve I
NUCLEAR INSTRUMENTATION PD-1666 N/A N/A Replace Signal "B
Connector at Rear i
of Cabinet.
SI 11~4 ACCUMULATOR LT-934D PD-1667 LT-934D Out of Instr. Reading~ 7% Instrument CalibratE I
.. Calibration....
.Differ~nce.... *.
SI 1113 ACCUMUtATOR LT-934C PD-1669
- LT-934C *Out of Instr~ Read:f.ng ""5% Instrument CalibratE
- ."ca1ihrafioii.
........Difference.*.......
\\
I 14-SW223 PD-1680 N/A N/A Lubricate Hand Jack, Inspect Gears NUCLEAR INSTR. *IRN 36 PD-1694 N/A N/A Checkout Spare Power SUJ>ply REACTOR PROTECTION PD-1716 N/A N/A Change Capacitor C-2 from O.lMFD to O.OlM Per ECN C-16161 I
I
INtl'RUMENTATicit AND CONTR~ CORRECTI~MAINTENAN~
LER OR OUTAGE MALFUNCTION EQUIPMENT WORK ORDER NO.
NUMBER CAU$E RESULT CORRECTIVE ACTION-REACTOR PROTECTION 1PM'"".506B PD-1717 N/A N/A Change. Capacit.or C21 From o.lmfd to 0,0lmfd Per ECN 16161 REACTOR PROTECTION "CHANNEL PD'"".,1718 sq*. Root Ext:i;ac~
Fu~cttonal T~~t:
Calibrated Sq; Root
- -----*i*FT-511* *-*:***.. ------... --**---.-**
tor Out:.of Cali-Out of Spec Extractor
.b~ation..
I
*~ --
REACTOR PROrECTION C~NEL*
PD~l719
- Sq. Root Extrac-Functional Test calibrated Sq. Root 1FT-S21
- tor Out of Cali~
Out.of Spec Extractor I
. .........................:bration....
REACTOR PROTECTION C114NNEL PD-1720
- Sq. Root Extrac-Functional Test:*
Calibrated Sq. Root lFT-531
- tor Out of Cali-*
Out of Spec Extractor
.. brat:ion.
REACTOR PROTECTION CHANNEL
'PD-172l
- Sq. Root Extrac-Furtctional Test Calibrated Sq, Root lFT-541 tor Out of Cali-Out of Spec Extractor
.. *. :µr.atioii
.......... I.
MAIN *sTM*//11 STM GEN LEVEL PD-1723.
N/A N/A Recorder Tracking RECORDER With Indicator ieve SAMPLING 12SS94 PD-1726 Pushbutton Switch Valve Will Not
- ~epaired Open Was Sticking.St:ay Closed REACTOR COOLANT PT-405 PD-1744
~
Out of.Calibra-PT403 & 405 Read Replaced Indicato~
tion & Bad Indi-
/"U 20011 nif f ere11ce
& Recalibrated
.cator
.REACTOR PROTECTION CHANNEL PD-1764
- Functional Test Calibrated Chc:mnel FT-416 Out.of Spec RADIATION MONITORING SAMPLE PMP PD-1780 N/A N/A Replaced Pump With Spare...
I~RUMENTATICjf AND CONT~ CORRECTill MAINTENA!jlE Q
LER OR OUTAGE MALFUNCTION EQUIPMENT WORK ORDER NO.
NUMBER CAUSE
- RESULT CORRECTIVE ACTION I SAFE1Y INJECTION FLOW TRANS-PD-1802 N/A N/A Recalibrate to Agr~
HITTERS FT946,FT947,¥T956,FT957.
...................With.New Orifices. \\
MAIN STEAM /Ill & 13 STEAM PD-1810 Recorder Out of Recorders Not Recalibrated Recore GENERATOR RECORDERS Calibrat;l.on
... '.Indicating Zero REACTOR PROTECTION lFT-540 PD-1829 Sq. Root.Extrac-Functional,. Test Recalibrated Sq~ Re tor Out of Cali-Out;*of Spec Extractor
.bra,t:ion.
i REACTOJ.l PROTECTION lFT-530 PD-1830 Sq. Root Extrac-Functional Test Recalibrated Sq. Re I
.*tor Out of Cali-Out.of Spec Extractor
.... brat ion REACTOR PROTECTION lFT-522 PD-1831
- sq. Root ~xtrac-Functional Test **
Recalibrated Sq
- Ro
. tor Out of Cali-O'"t of Sp~c Extractor I
. *bration I'
' 'I I
ii:
I RADIATION MONITORING SAMPLE VLVS PD".""1833 N/A N/A I Tighten Solenoi4 1VC7 Thur 1VC14 Valves Mounting l
rlates
- i RADIATION MONITORING SAMPLE PMP PD-1842 N/A N/A I.
Replace Present 1RllA,1Rl2A,lR12B Pumps With Spares REACTOR PROTECTION FT-531 PD-1844 Instruments Out Functional Test Calibrated Sq. Root CHANNEL of Calibration Out of Spec Extractor & Channel A
II FW Flow Indicat;o I
~......
'1 REACTOR PROTECTION FT-543
- PD-1847 Instrument Out Functional T~st Calibrated Sq. Root CHANNEL
. of Calibration Out.of.Spec.
Extractor.
REACTOR PROTECTION CHANNEL PP-1848 Instrument Out Functional Test Recalibrated Instr.
lFT-533
.of Calibra*tion..
.. Out of Spec'.... '..
- REACTOR PROTECTION FT-523 PD-1849 Instrument Out Fun~tional Test Recalibrated. Instr~
I
. of. Calibration Out of Spec I
i I
I
(..
INIJRUMENTATI<lf AND CONTR9. CORRECTI\\9 MAINTENAN.
('.'t LER OR OUTAGE MALFUNCTION
- EQUIPMENT WORK.ORDER NO.
. NUMBER CAUSE RESULT.
. CORRECTIVE AC'.f ION SW /Ill HEADER PRESS TRANSMITTER PD--1856 PA-2747-Z Replaced & Cali-
..brated.PA~2747~z
..... Failed.....
SW 11SW49, 11SW305 i>D-1857 Balls Ar~ in Limitiµg flow Restroked Valves
.. Flow.Path.... :....
SOLID STATE PROTECTION SYSTEM PD-1860
.N/A N/A Design Change
... !AW DCR#ED~0024 SW 12SW49,.l-:ZSW305
- pn-1866
- N/A N/A Remove.Spacers
& Restroke Valves I
REACTOR PROTECTION CHANNEL PD;...1874
. : Instr. Out of Functional Te~t Performed TE-411A/B
. :.Calibration Out.of.Spec Calibration SOLID STATE PROTECTION.TURBINE PD-,1876.
.N/A N/A Perform DCR#ED-0031 STOP1VALVES.
I NI ~43 POWER RANGE PD-1917 N/~
N/A Calibrate Recorder
\\
.. NR42 & NR4~.
NI N35, N36 INTERMEDIATE RANGE PD-1919 Noise Oscillat:Jng SUR Took NoiSe Readings Indication RADIATION MONITORING 1Rl3i\\,
pn..:.1922 Service Water Cleaned Equipment 1Rl3B SAMPLERS Sprayed.
RADIATION MONITORING 1R31A, PD-2012 A
N/A Diff ereµt Readings Performed Compariso
. 1R31B, 1R31C
- Between Ch~nnels*
Between Channels I
.. Sat.
STEAM FLOW TRANSMITTER PD-2014 N/A N/A Performed Ca~ibrati1 Checks.& Record Dat<
REACTOR COOLANT FLOW TRANSMITTER PD-2015 N/A N/A Perform~d Calibrati4
............ Checks &'Record Dat~
EQUIPMENT lFT-532 lFT...:444
... M~lA'llON.-.MONITORING--.llU3A. ***
LT-1'~88 I
lFT.;.53:i.
. lFT-446 lFT-444 MAIN TURBINE SSPS lFT-435 lFT-445 lFT-434 lFT-436
. Il'jl'RUMENTATI'if AND CONTRjL CORRECTIW MAINTENAi'Wi WORK ORDER NO.
PD-2016 PD-20.p PP-2018 PD-2021
. PD~2022.
PD-2029 PD-2030 PD..:.2032 PD-2033 PD-2034 PD~2036 PD-2038 LER OR OUTAGE NUMBE~
~............
MALFUNCTION.
CAUSE.
~ESULT Out of C~libr~tio1 F~ncti9n~l fest
...-oiit.*of. spec.-.... *.
Per:forme<J Calibratj
.C:hecks.......
Def ectiye Transmitter Indicate~ 60% :flow Performed Calibratj Checks, Issued w.o llPD-2030 D~f ective Rate Card PB3
- cannot Determine Out of.Spec LT-1688 lnstrumen~
Line Freezing Performed C~libratj Checks~ Replaced Rate card PB3 Heat Tracing Sat, Perform Calibratior Checks*
.. *.*...... N/A:..
.Out.of :*spec.
None Required
.Out of Calibra-Performed Calibrat:l
....... tion.
Zero Shift
. ~a~~ot C~lih.rate
- Cnstalled New
................... Transmitter.
Out of Cali bra-Out of: Spe~
Performed Cal~l>rati
.tion.
Checks Out o:f C~libra-Out of Spec Performed Calibrat~
.tion Checks Out of Calibra_.
Out of Spe'?
Perf orme4 Calibrati tion.
Checks Out of Calibra-Out of Spec Performed Calibrati
.tion Checks Out of Calibra-Out of Spec
. Perfonµed Calibrati1 tion Checks.
I~RUMENTATI~ AND CONT~ CORRECT!~ MAINTENA~
EQUIPMENT
~FT-414,415, & 416 lFT-425
- WORK. ORDER.NO.
PD-2039 PD-2040 LER OR OUTAGE NUMBER MALFUNCTION CAUSE.
RESULT CORRECTIVE ACTION Out of C!!libration Qut of ~pe<!
Performed Calibrat:f 1
.............. Checks.
Out of Calibration Out of Spec Performed Calibr*at~
...... Checks lFT-426~ 42.4 PD-2048 Out of C~libration Out of Spec Performed Calibrati Checks FEED SYSTEM po. 11 SGFF.
PD-:'2049...
FEED SYSTEM ~~* 12.SGFF FEED SYSTEM NO. 13 SGFF.
........ PD-:'2051.........................
FEED SYSTEM NO~ 14 SGFF*
lTC-421 G/H PD-Z060 lFT-531 A&B
- PD-2066 lFT-415 PD-2069 LT-538 PD-2081 NIS-N44
- PD-2085 RADIATION MONITORING CONTAIN.
PD-2086 VENT APD lFT-424 PD-2107. N/A...
....... N/A.... *.,.........
N/a*........... :*.*. *:.. *.N/A................
.N/A...
Out of Calibratior f
O~t o~ Spec 1
I.
Out of Calibratior Out df Spec
..... /
Leaking Sensor Line I
Intermittent Low Flow Alarm
.Defective.LT-:'538.
Drifting Out of Calibratior Upper Flux Amp Output Out of Spec Defective Low Low Speed Does Speed Drive.Motor Not.Operate Defective Bulk-head Fitting.
Leafing in Panel Cal. Due I
Cal. Due*
I
. Cal. Due Cal *. Due Performed Calibrati Checks Performed Calibrat:IJ
. Checks..
Repaired Lea~s on High Pressure Senso Line Replaced Unit Performed Calibrati Checks Replaced Low Speed Drive Motor Replaced Bulkhead
.Fitting
---,--.-----~
IN.RUMENTATI~ AND CONTRIA CORRECTiva MAINTENAN.
(lj.
LER OR OUTAGE MALFUNCTION
~ORR~~~VE ACTION
~QUIPMENT I
WORK ORDER NO.
NUMBER CAUSE RESULT RADIATION MONITORING 1Rl4 PD-2147 Defective High Channel Alar1ntng Replaced liigh Volt;:
Voltage Pwr Power Supply and
.Supply. -.
.. '.. Recal:J.brated SV:-545 PD-2160 Defec~iye SV-545 Cannot "Open 12BF40 Rebuilt SV-545 FEED FLOW TRANSMITTERS PD-2161
.Leaking Tubing Unable to Place Repair Tubing &
&. Fittings Instruments in Tighten Fittiµg~
Service Due to i
Leak1;1
~
TE.,...441 I
PD-2171
- out of Calibra-OQ~ of f!pec Performed Calibrat:I
..... :tion Checks
'I NIS
- 1 PD-2178
- Defective Meter Inoperable Repla~ed Current NI301 & Switch Meter & Switch 5301... _
' '\\'*'I
- 1PA-54ll-IB PD-2184 Out of *Calibra-No. 12.Accum.
Performed Calibrat:I tion Press Bezel Indic.
Checks Differs 40psi From Local Indicator lFT.-522 PD-2186 Out of Calibra-Out of Spec Performed CaU.brat:I
.... tion..
Checks lFT:-523 l?D-2187 A
Sensing Line 1112 Stm Gen Stm Drain Sensing Line Full of Oonden-
- Flow Increasing
.............. sate
.Continuously.....
lFT-522 PD-2189 N/A N/A
~erform Functional
......Checkout.
STEAM FLOW TRANSMITTERS J,>D-2190 N/A N/A Vente_d Each Condens Pot & Zeroe4 Set Ee1 Transmitter Under Pressure I '
~
1i-erRUMENTATll9l AND CONTR9J.. CORRECT!. MAINTENA~
(';
LER OR OUTAGE
.MALFUNCTION EQUIPMENT
.WORK.ORDER NO.
NUMBER CAUSE RESULT CORRECTJVE AC!lON FEED FLOW TRANSMITTERS PD-2191 N/A N/A*
set all Traq.smi t t~1 f oi: Static Shift l~T-543 PD-2193 Buildup of 1114 Stm Flow l{aq Vented Cond~nsate*
Condensate Err a ti~ lndica~ion Pot*
*--i:3BF19. "
. *-*-.,******--*-................. ~---...
pn..:2196
.Out of Alignment:.
Does ~ot Provide Re stroked & Verifi1
.*Ti~ht. Shut":"of f..
Tight Shut":"of f
-*----~ *--* --------. -----. *. *..
NO. 12 STJill1 GENERATOR.LEVEL PD-2204
- out of Calibra-Reactor Tripped P'erforin Channel tion at.30% Level Calibration Checks!
I Reset Point QUt ()f.
Spec LT-528
- pn...;2205
- Out of Cali bra-Out of Spec Perf <>rmed Calibrat
................. tion:......
Check~
LT-5Z9 PD-2206
- Out of Calibra-
'Reads 4% High Drained Sensing*Li tion
& Performed Calibr.
................. tion Checks 1LM-500Y PD-2207 Out of Cali bra-:-
1113 Stm Geµ Level Performed Calibrat
..1;'.ion Controls Low Checks 125 VDC BUS PD-2212 Not Determined Ground Ground Cleared Befc Troubleshooting
........... Started lLT-315 PD-2213 Instrument Line Boric Aci~ t:v~p..,..
Blewdown In,strumen Clogged orator Level Lines,Vented*and IndicatiQn"Incor-Put into Service s rect lFT-523 PD-2222 Buildup of Channel II Stm-Blewdown Inst rumen Condensate in Flow Indicati11g Linei:;. Put intp
.Instrument.Lines.. : 40~. With No. Flow... Service. Sat
- NIS PD-2223 NR-41 Out of Red Pen Out of Adjusted Span Calibration Spec.on-Calibra-::-*
'.'.'"82-tion Check I
NIS N41 POWER RANGE SERVICE WATER 15SW57 REACTOR PROTECTION CHANNEL TE-411 A/B RADIATION MONITORING Rl4 MONITOR RADIATION MONITORlNG RllA,12A, 12B *"
AUX FEED #13 AUX FEED WTR PUMP Ql2 ST~ GEN LEVEL CHANNEL I MAIN STEAM 14MS10 REACTOR PROTECTION CHANNEL FTf543 I
- 11 AUX FEED FLOW TO 11 STM GENERATOR REACTOR COOLANT PANEL TRANS-MITTER FITTINGS lNtl!'RUMENTATIC. AND CONTRe. CORRECTI\\9 MAINTENANtl!:.
WORK.ORDER NO.
PD-2224 PD-1928" PD-1933 pn.:..1941 PD-1942
... 'r..
pn.:..1947 PD-1949 PD-1951 PD-1954 PD-1955 PD-1960 LER OR OUTAGE NUMBER MALFUNCTION
. CAUSE RESULT CORRECTIVE ACTION R354 Had Inter-Negative Rate Replace~ Rl54 mittent Open Clevis Link Needs
............. Replacement..'......
.1QM-204A Failed
- *Sheer Pin :f.n
- Drive Mechanism
.. :sheered..
- Governor Oil
- Level.High & Air
.... *... *.. :Present <...'.'. *: *
. Tr:(.p. Won't. Lock*. I11 Functional Test
.Ou~.of. Spec......
N/A.
Filter Failµ-.:-e Alarm
'Sieed Contrpl
}fimti°'1g I
..... j............
I Chanflel :f.s.
.... **..........'Err,~*ic*:.. '........
Rework 15SW57 ***
Replaced Sheer Pin Vented Governor Oil System
. Power Supply Valve Does Not Replac*ed Power
...... Failed :.......... *.. Work. in. Auto.. *..... Supply. DR//PD0293 Comparator Out of Spec Wires Disconnect-ed From Trans. to
.Sq, ~oot Ext.
- No Tape on Vent;
. Plugs. *:.
Functional Test Out of Spec Loss of Indication on.Console Leaks Calibrated the Comparator lFC541 A/B Reconnected Wires Taped Vent Plugs
INJ!RUMENTATIO, AND CONTR~! CORRECTIV, MAINTENANC' EQUIPMENT WORK ORDER NO.
- 13 AUX FEED PUMP PD-1964 MAIN STEAM lFT-540 PD-1983 RADIATION MONITORlNG 1Rl4 PD-1985 PD-1988 RADIATION MO?UTORING lR.18 I
RADIATION MONITORiNG l~i3B PD-1989 RADIATION ~ONITORING 1Rl3C PD-1990
~IN STEAM GAUGES PD-1993 LER OR OUTAGE NUMBER
- MALFUNCTION CAUSE.
RESULT 1MS132 Restricted Speed W:J,11 Not.
.. Steam Flow...
Increase > 2000~pm lFT-540 Out.of Calibration Detector & Preamp
. Functional Te~t Out of Spec failure Alarm
.. Failed........................
Relay Contacts Not Mak:l,ng
.Properly..
. Top & Bottom 110 11 Rings Need Replacement N/A Spurious Alarm
~ampler Leak:f.ng N/A CORRECTIVE ACTION P~rf ormed Channel Calibration I
I
\\
Replaced Detector * ~
1 Preamp Clean & Dry-out
- \\
Sampler & Connector Fixed Relay Replaced 110 11 Rings Install Temp G~uges to Test;: Relief Valves
INSTRUMENTATfJ:ON AND CONTROL CORRECTIVE MAINTENANCE
\\.
1.. ~
I LER OR OUTAGE MALFUNCTION I
EQUIPMENT WORK ORDER NO.
NUMBER CAUSE RESULT CO~RECTIVE ~CTION SERVICE WATER 12SW122 OD-2705 N/A 12SW122 Will Not Stroked Valve Sat.-
.Open I
CONTAINMENT PURGE 1VC3 OD-2708 Wiring Error Valve Indicates
. Changed Valve Limit I
- Open & Closed Switch Wiring frpm *- -*
N.C. to ~.o. to Agree Wi;th Dwg. &
Set Switche~
l,2~FJ.9 DEMAND METER
. OD-2746 Defectiye Meter Demand Meter Cleaned Meter Move-Reads Wrong*&
ment, Repaired C:ase Needle Vibrates Short, Replaced Shl.lnt
& Recalibrated 12BF19 OD-2747 Solen~id Valve 12BF19 Doesn't Changed Solenqid *:
Restricted Air Shut Fast Enough Valve !AW ED-0007.
- to Meet SP(O)
See WOl/PD1S02 & 150~
- supply Flow
- 4. 05""."V.
13MS18
- OD-2761 Leaking Diaphram Air Leaks Around Replaced Diapbram Operator Head eves BORON FLOW CONT lFCllO OD-27_67 System Was Not*
Flow Indication Tuned lFCllO for ~II Tuned Swinging + 20gpm Stroke of lCV172.
from Setpoint and Revised Procedure Oscil~ating.
2.1.007 for Rate 100 NO *. 12 CONT.FAN.QOIL.UNIT
,!QD-2811 Exis.ting Limit HEPA Filter Inlet Replace.a Limit Switch Brackets Damper,Open Close Switc'Q Brackets do not Provide Lights Both Fine Adjustment Energ:f_zed
-as-
EQUIPMENT
~IATION MONITORING SAMPLE VALVE lVCll 1CC215 NO. 11 NOZZLE SUPPORT VENT FAN RADIATION MONITOR 1-RllA PANEL 241-1 PANEL 2l5*'
12SW49..
OVERHEAD ANNUNC~TOR POINT n.:..12 lPI-403 INSTRUMENTATION AND CONTROL CORRECTIVE MAINTENANCE LER OR OUTAGE MALFUNCTION WORK ORDER NO.
NUMBER CAUSE
- RESULT OD-2847 Valve Limit No Close Indica.,..
Switch out of tion I
Adjustment OD-2903 Valve Limit Valve Does Not Switch out.of Cycle in~ 10 sec Adjustment OD-2917*
Limit Switch Sequence Complete Couplings Missing Light Does Not Energize.
OD-2926 High Concentra~
Hi Rad.Alarm tion of Welding Cannot Be Reset Particulate in
.. Sampler.Area.
c OD-2938 N/A S~lt Water in Panels & Ground
- oD-2939 N/A Salt Water in Panels & Ground.
OD-2964 Worn Ring Seal Valve Leaks Thru OD-2985*'*
Blown Fuse Boron Inj. Tk.
High Disch Press
.Alarms OD-3002 Defective Signal Hot Leg Pressure Summa tor 1PM403D Loop II not Indicating
. correctly.
- CORRECTIVE ~CTION Readjusted Valve Limit Switch
- Adj'usted I.imi.t switch
. Stroked in< 10 sec Now as Indicated on
.Bezel.
Installed Limit Switcf Couplings & Springs and Adjusted Switch None Required I
See WO#PD1577,1585~.
1607, & 1609 See WO/IPD1597 Replaced "Sea1 Ring &
Restroked Replac.ed Samp Fuse on lPC-942 Replaced 1PM403D
IN~UMENTATIOJ.9AND CONTROitCORRECTIV~INTENANC~
EQUIPMENT WORK ORDER NO.
1CV172 OD-3004 SI -
COLD LEG INJECTION FLOW
.. -.. ~*----*-*'---~~"--**----...
-NOo-l--l-GHI-bL-ER.-- * - -- --*---* **
15swe23 1WL16 NO. 15 FCU DRAIN FLOW ALARM YIC-110 11SW49 & 12SW49 LIMIT SWITCHES PR948A & PR948B
.NO. 11 BORIC ACID TANK TEMP INDICATOR OD.,..3359 OD-3370 OD-3372 OD-3375 OD-3383 OD-3389 OD-3396 OD-3476 OD-3516 LER OR OUTAGE NUMBER MALFUNCTION CAUSE RESULT CORRECTIVE.ACTION Controller lFCllC was not Tuned to tl\\e System
. Blown Fuse Vlv 11SW92 Limit Switch Out of
- Adjustment
- Defective Valve
- Open* Limit Switcl
- Out of Adjust-...
. ment Out of Calibra-
.. tion.
Out of Calibra-tion Valve Limit Switches Out of
..'Adjustment... *.*
Out of Calibra-tion Temp Transmitter Out of Calibra-lCVi72 Hunts Dui'ing Auto
.Op~ration Indicator Failed Dowri Scale.....
Will Not Run Valve Causes
.Flow.Oscillations
. \\.
V~lve Will Not Stay Open Energized All the rime.
Boric Acid Flow Register Does Not
. Indicate * *
.Tuned Controller lFCllO While in
. Service.
Replace* Power
.Supply Fuse Readjusteq 11SW92 Valve Limit Switch Replaced Valve Reset Opening Limit Switch Readjusted Diff.
. Contro:ller Recalibrated Loop Continuous Alarm Readjusted Valve Limit Switches
- Recorders Do Not Recalibrated Recorders Agree with Each Other..
- Boric Acid Tk Tem1 Recalibrated Temp Indicates 15~
Transmitter ECN tion Hi~her. Low Temp
...... :Alarm. :Energized.
Required to Revise
.Alarm.Buttons
EQUIPMENT 1PR18
- VITAL HEAT TRACING NO. 11 NOZZLE SUP~ORT FAN LIMIT SWIT:H.
NO. 12 STEAM GENERATOR 1
1 SOLID STATE PROTECTION SYSTEM 1SS49 RADIATION MONITORING lRllA 12SW40 SV541 & SV553 RADIATION MONITORING CONTAIN.
VENT APD IN~RUMENTATiof AND CONTRO~ CORRECTIV~MAINTENANc:P WORK ORDER NO.
OD-3521 OD-3537 OD-3538 OD-3553 OD-3568 OD-3571 OD-3582 OD-3624 LER OR OUTAGE NUMBER MALFUNCTION CAUSE RESULT Valve Limit Switcl Valve Position Out of Adjustment Indication Does Due to Loose Vlv.
Not Work
. Components.
CORRECTIVE ACTION Removed Bonnet,Tighte~
Diaphram Stem Locknut. 'I Restroked & Set ~imit Switches.
Pipe Insulation Missing at This Time Recorder Temp Does Equipment Sat. Pipe to Not Agree With be Insulated Later Local Temp Indica-
.tors Defective Limit
- S~iicih:
No Sequence complete. Light....
Repaired Limit Switch Out of Calibra-tion No Power.Avail-able to Test Circuit. Design
. Deficienci~
Valve Limit Switch Out of Adjustment Due to Loose Vlv Compon-
.......... ents......
Check Source
.~olerioid ~iucik Feedwater Flow Recorder Indicat~
.. i#g *wrong Flow.
Recalibrated Recorder IhitiJied IC SEC APB Initialed Sys. Actuation When rrs602,TS604,
&.tS~lO in:Test.:..
Val.Je Will Not Stay Open. No Vlv.
Position Indica-,. ':
tion Disassembled Valve to Tighten Locknut.
Stroked & Readjusted Limit Switches Indicates High Lubricated and
.Radiation Levels.. Recaiibrated Detector L6ose P~cikiiig:Nui.Air:te~ks......... Tightened Packing Nut OD-3625 Worn Internals Air Leaks Replace Solenoid Valve Internals OD-3650 Defective Gas Pump Failed Replaced Gas Pump Pump
IN~RUMENTATIO~AND CONTRO~ CORRECTIV~INTENANC..
\\'.f LER OR OUTAGE MALFUNCTION EQUIPMENT WORK.ORDER NO.
NUMBER CAUSE RESULT CORRECTIVE ACTION 1FT957, 1FT947, & 1FIC-641B OD-3658 Loose Fittings Leaking l?ittings Tighten Fitti:pgs
.......... to. Flow.. Transmitters NO. 13 FCU FLOW INDICATION OD-3699 Open Flow No Flow Indication Closed Flow Tran~-
FA-3541Z-l Transmitter mitter Equalizing Equalizing Vlv.
.......Valve 1A2 28VDC CHARGER OD-3724
- Sys. Voltage Low 28VDC Recalibrated Sys.
Meter Out of Voltage.Meter
...... :*Calibration...
1FT542 & lFT543.
OD-3734
- Condensate Accu-Wrong Stm Flow fot: Changed Sl9pe of mulation Due to 1114 Steam Gen~
Instrument line
- Insufficient
- *. lristr. *tirie Slope AUX FEED-WTR FLOW INDICATOR OD-3736 Out of Cali bra-
\\Wrong Feedwater Recalibrated Loop 14
... Flow* Indication..
TO NO.
.... *tion.
1FL1593 OD-3774 Out of Calibra-Flow Indicates Recalibrated Loop tion lOOgpm When Vlv is Shut 15SW24 OD-3799 Valve Seat Chew-Valve Does Not None - Ref ~red to
.. ed Up
....Open.
.... '..Matnt. Dept
- RADIATION.MONITORING CONTAIN.
OD-3802
~
Loose Winding High Filter Paper Disassembled &
VENT APD Reel Alarm Repaired Winding Reel Shaft 14SW223 OD-3814 Valve Limit Overhead Trouble Readjusted Valve Switch *out of Alarm Will Not Limit Switch Adjustment Eµergize When Vlv
.Goes.Shut Recalibrated NO. 11 ACCUMULATOR LEVEL INDIC.
OD.,.3815 Out of* Calibra-Wrong L.~vel tion 1LT935A
-89".".
EQUIPMENT.
PRESSURIZER CHANNEL I NO~ 12 RHR LOCAL FLOW INDICATION
- - -* ---------------~----
- -...,.. ---y-------......,,,..._......__
1---voLUME-CbNTROL-TANKLOW --- -
PRESSURE ALARM I
I i
1CV3~
1FT425 & 1FT426 I
NO. 11 AUX BLDG EXHAUST FAN 12AF21 1MS132 NO. 14 S.G. FLOW CHANNEL 2 14AF21 INSTRUMENTATION AND CONTROL CORRECTIVE MAINTENANCE LER OR OUTAGE MALFUNCTION WORK ORDER NO.
NUMBER CAUSE.
RESULT OD-3816 Transmitter Was No Indication Isolated OD-3817*
Incorrect Flow 12RHR29 Opened at
_Setpoint 300gpm Instead of
.500gpm OD-3818 Defective Low No Low Pressure Pressure *com-Alarm arator OD-3820
- Wrong Level Valve Does Not
- Observed by Divert on VCT
- Ope!ator
.High Level OD-3827
- Defective
- ,No Flow Indica-
... Transmitters.
.tions OD-3838 Per Design Discharge Dampers Do Not Close When
.. Fan. is Stopped
- Valve Positioner Valve Leaks Thru Out of Cali bra-tion OD-3846
~
Rupture Diaphram Valve Will Not Close OD-3860 Out of Calibra-Indicates 20%
tion Flow With No Actual Flow OD-3864 Valve Stroke Out Valve Does Not of Adjustment Provide Tight
- .Shut'"'."off
-90....,
CORRECTIVE ACTION Open Transmitter Isolatio~ Valves Reset Low Flow Set point Replaced Low Pressure Comparator*
None Required System Working Sat.
Replace Transmitters None.
Damper Controls Independant of.Fan Operation Restroke Valve artd Adjusted Positioner
& Tension *spring Replaced Diaphram Recalibrated Loop Readjusted Positioner Spring & Stem
IN~RUMENTATIO,.AND CONTR~ CORRECTIV1"MAINTENANC~
LER OR OUTAGE MALFUNCTION EQUIPMENT.
"WORK ORDER NO.
NUMBER CAUSE.
RESULT CORRECTIVE ACTION RADIATION MONITORING 1Rl3B OD-3867 See WOl/PD-:-1990.
No Alarm See WO//PD-l990 I
OD-3871
.Per Design No Flow Indication Calibration Check When 12AF21 Open Sat. Transmitte:i:***Has 11% and SG Level Low Flow Cutout is Increasing 1%
...... Minute.
l.1AF21 OD-3877 Valve Limit No Closed Indica-Readjusted Valve.
- Switch Out of tion Limit Switch
- Adjustment NO. 11""'."15 FCU's HEPA FILTER OD-3882
- Burned Out Indi-Damper Position Change Burned Out DAMPER POSITIONS
... Operation 1119 lBBDC BKR.
OD-3883
- No Apparent Breaker Tripped Checked Out Sat.
Problem Durine SEC PRESSURIZER LEVEL CONTROLLER OD-3893 Out of Cali bra-Getting Letdown Recalibrated Recorder tiori Isolation
& Checked Trip Point ROD POSITION - ROD BOTTOM 2C2 OD-3958 Out of Cali bra-Bank.C Rod Bottom Recalibrated Rod tion Light Will Not Bottom Light
. De":"energize NO. 13 AUX FE~D PUMP PAT3964 OD-3964 A
Broken Wire on No Loss of ll5VAC Broken Wire on Wiper PAT3964
- Alarm. No Speed..
in PAT3964 nemand Indication NO. 14 ACCUMULATOR. LEVEL.
OD-3985 Out of Calibra-Low Level Alarm Recalibrated Level tion Energized When
& Comparator Level is Correct CONTAINMENT PRESSURE INDICATION OD-3993 Recorder Press-.
Containment Press* Checkout Sat. Compute1 ure Increments ure as Indicated Printout Pressure is
- Cannot be Read on Bezel Recorder Being *used Instead Accurately Exceeds STS Specs.
INS~UMENTATIO~AND CONTRO~CORRECTIVE~INTE~ANC~
LER OR OUTAGE MALFUNCTION EQUIPMENT WORK ORDER NO.
NUMBER CAUSE RESULT CORRECTIVE ACTION lLT-538 OD-3997 Out of Cali bra-No. 13 SG Level Recalibrated tion Channel II Indicating Higher Than Normal I
I
~
J INSTRUMFNTATION AND CONTROI COHRECTTVE MAINTENANCE
. LER OR OUTAGE MALFUNCTION EQUIPMENT WORK ORDER NO.
NUMBER CAUSE RESULT CORRECTIVE ACTION eves - PRIMo WTR FLOW CONT OD-4022 Defective Cont-Excessive Flow Replace lFCllO lFCllO roller RWST - LEVEL CONT lLT-920 OD-4036 lLT-920 Isol.
Wrong Level Open lLT-920 Valve Closed Isol. Valve i\\UX FEEP 12AF40 OD-4047 Valve Limit No Open or Closed Reset Valve Limit Switches out of Valve Indication.
Switches Adjustment SERVICE WATER. 15SW?8 OD-4058 Burned Out Light No Open Valve Replace Bezel Light Bulb
... Indication.
Bulb i
REACTOR CONTROL - RECORDER N-45 OD-4073 Defective Slow Will Not Run in Replace Set Screw in Speed Drive Shaft Slow SJ?eed Drive Shaft &
I
...... *.Set. Screw Recalibrated I
CONT lPT-535 OD-4078 Leaking Fittings Water in Panel Tighten Fittings and on lPT-535 686-lC Drained Water From Panel NO.* 13 ST. GEN LEVEL.*.
OD-4091 Reference Leg Wrong Level Drained Reference
.Filled.With :water Leg AUX FEED - //12 PUMP. DISC OD-4094 PA-1082 & PA-5732 Wrong Pressure Recalibrated PRESS IND IB out of Calib-Indication ration PRESSURIZER LEVEL - lLT-459 OD-4095 lLT-459 out of*
Wrong Level Recalibrated
- Calibration REACTOR COOLANT FLOW OD-4096 Instr. out of Low Flow Indica-Recalibrated 11 & 14 RCP CONSOLE IND Calibration tion
INSTRUMENTATION AND CONTROL CORRECTIVE MAINTENANCE LER OR Ol!TAGE MALFUNCTION.
EQUIPMENT WORK ORDER NO.
NUMBER CAUSE RESULT CORRECTIVE ACTION NO~ 12 STEAM GENERATOR OD-4098
.Design Failed Trip <m Simulated Trip*Sat~
FEED Pffi1P Hi Hi Steam
.Generator.Level lB 125VDC BUS OD-4100 N/A Ground Indication See Work Order PD-2212 eves BORON EVAP LEVEL OD-4115 Clogged Instr, Wrong Level
-Flushed Instr* Lines' LT:--315 & LT..,.306
.Lines.
I NO. 11 FCU EMERG. DAMPER OD-4148 N/A HEPA Damper Open Operated Solenoid
.in Hi Speed Fan
- Valve & Stroked Damper Sat.
RADIATION MONITORING 1Rl4 OD-4000 Defective High Radiation Replace Bistal;>~e
..'I~istabie*.
... Aiar~ Not Working I
11CA330 SU-467 Out of Adjust-Does Not Provide Restroke Valve &
Tight.
ment Shut-off Reset Spring 11SW49 SU-419 Valve Limit No Alarm Reset Valve Limit Switch Out of Switch
.Adjustment I
I FA-3176..,.Z3..
SU-436
.. Defective.. *.*
.. Cannot.Calibrate.
Replaced Instrument I
12SW122*
SU-398 Broken Pipe Valve.Does Not Replaced Broken Pipe Nipple on Valve Maintain Proper Nipple on Valve fositioner/Regu-Flow Positioner/Regulator lator
- FA-3169(E/P)
SU-358 Dirt Inside No Output
- Cleaned Restrictot Restrictor and Recalibrated LD-2727 SU-351 Alarm Switches Screen Trouble Recalibrated Alarm*
Change Cali bra..,.
Alarms at Wrong Switches & Installed*
tion Due to Lack Set point L_ocking Device13,..
of Locking Device INS'I'RUMENTATION AND CONTROL CORRECTIVE MAINTENANCE
---~----~----~---::--~--r--:----::----:------~~-----1 EQUIPMENT LD-2725 LD-2726 SV-833 & SV-569 SV-563
- LD-4729 SV-.562.
1SWV3 1WR80 WORK ORDER NO.
SU-342 SU-343 SU-344 SU-345 SU-346 SID'-347 SU-348 SU-174 LER OR OUTAGE NUMBER MALFUNCTION CAUSE RESULT Alarm Switches Screen Trouble Change Calibra-Alarms at Wrong tion Due to Lack Setpoint of Locking Device Silt Buildup Inside of.SWI$
P1;Jmp Cells Defective SV's Indicates 2.2H20" All The Time Bay 1 SWIS Prop~
.Damper Does Not Operate Thru Full
.si~oke..
CORRECTIVE ACTION Recalibrated Alarm
- Switche~ & Insta!led Locking Devi<;:es
~.-
Blew Down Bubbler Tubes,Recalibrated
& In~tal!ed Alarm Switch Locking Deyice Repaired Solenoid Valvei; Open Coil
, Df1,mper 1SWV8 Does Replaced Coil 1Ndt Close When #12 Alarm Switches Change Calibratio1 Due to Lack of
.Locking Devices Open Coil Binding Diaphram SV507 Restricting
.Exhaust.Air S:W Veitt.Fan Stops.
I Scree~ Trouble Alarnis at Wrong Setp~int Recalibrated Alarm Switches & Installed Locking Devices Damper 1SWV7 Does Replace Coil Not Close When #11 SW Vent.Fan.Stops Damper Does Not
.Operate Opening Time Too Long.
Lubricated Diaphram
&.Restroked Sat.
None. Valve Will Close.in 2 Sec,
EQUIPMENT 1PR17 1CC215 1WL98, 1WL12, 1WL17, 1WL13, 1WR80; TA-745C TA-6416,6417, & 6418 1WL7 IN~RUMENTArrot AND coNrRcf! coRREcrrvftMAINTENANC~
WORK ORDER NO.
SU-175 SU-176 SU-188 SU-229 SU-307 SU-310 LER OR OUTAGE NUMBER MALFUNCTION CAUSE.
RESULT Valve Limit Switch Will Not Stay.:
Out.of Adjustment.. Cl9sed.
N/A Bent Limit Switch Actuator Rod Wrong Type Do Not Close in
.Solenoid.Vaive
. *: :.c:.10 Sec *......
CORRECTIVE ACTION Readjusted Valve Limi1.
Switch.
Tightened Limit,,.
Switch Actuator Rod
& Readjusted Limit
.Switches Replaced.Solenoid Valves Out of Calibrq-t:ion Low Output at.. * " Recalibrated
.120'F.
Wrong Thermowell
.Installation Output Responds Too Slow to Chill-
- ,ed Water Tempera-.
. ture *Changes....
Leaking Diaphram Air Leaks Around Valve Operator
.Head.
Thermowells Relo*cated Replaced Diaphram
LICENSEE EVENT REPORTS During this reporting period, a total of thirty-one (31) events occurred which resulted in Licensee Event Reports.
Each of these events occurred at a reactor power level of less than 20% design power and are not applicable to or included in this report.
OTHER EVENTS OF INTEREST
- Main. Steam Generator Safety Valves - Setpoint Change Following certain Unit #1 Startup Tests, there were indications that several Main Stearn Generator safety valves were weeping.
In order to correct this problem, the vendor was requested to lap the valve seat for each safety valve.
In addition, the vendor was queried as to whether or not seat lapping would affect the lift pressure.
The vendor's response was that this action would not affect the lift setpoint
- Upon the completion of seat lapping, Unit #1 was again brought
. to normal operating temperature.
During the subsequent heatup, several Main Stearn Generator safety valves lifted at a below normal pressure.
Accordingly, all steam generator safety valves were tested pursuant to Maintenance Department Procedure M9E, "Stearn Generator Safety Valve Testing".
After testing, nine (9) out of twenty (20) safety valves were found to have needed minor lift setpoint adjustments.
Fuel Perf orrnance During the receipt of the initial 193 fuel assemblies (October 1975 -
January 1976), a small percentage*o"f assemblies showed minor discolora-tion, which was termed rust, on the top nozzles.
After an on-site inspection and subs.equent investigation by Westinghouse, it was concluded that the rust was cosmetic in nature and there was no opera-tional impact.
The vendor hand cleaned all observable discolorations.
Initial criticality was achieved on 12-11-76.
As of 12-31-76, the core had a total exposure of 1600 MWD (18 MWD/MTU).
During hot zero power physics testing, a core quadrant tilt of 2.5 to 4.5%, depending on control rod position, was measured.
The tilt appears to be centered about.fuel assembly locations defined by the intersections of columns B, M, N and rows 13 and 14.
These assemblies are running 10 to.15 per.cent above the predicted relative power
- Technical specifications do not address radial power tilts below 50%
power.
Hot channel factors are monitored above 5% power for Technical Specification comp'Iiance.
The effect of the tilt on F and F liH will be rnoni to red..
xy At higher power levels, the leveling effect of xenon and doppler will tend to minimize the tilt.
Core exposure will also aid in flattening the flux
- DATA TABULATIONS Net Electrical Power Generation Unit Shutdowns.and Forced Power Reductions Number of Personnel and Man/Rem Exposure by Work and Job Function NET ELECTRICAL POWER GENERATION 1976 Number of hours the reactor was critical Reactor reserve shutdown hours Hours generator on-line Unit reserve shutdown hours Gross thermal energy generated (MWH)
Gross electrical energy generated (MWH)
Net electrical energy generated (MWH)
Reactor service factor Reactor availability factor Unit service factor Unit availability factor Unit capacity factor (using MDC)
Unit capacity factor (using design MWe)
Unit forced outage rate
-100-CUMULATIVE 301.6 0.0 40.3 0.0 48697 3230 0
N/A N/A N/A N/A N/A N/A N/A
UNIT SHUTDOWNS AND POWER REDUCTIONS Type F: Forced Duration Date S: Scheduled (Hours) 12/25/76 F
33.7 12/27/76 F
7.4 12/27/76 F
11.6 12/29/76 F
61.3 (1) Reason:
A -
Equipment Failure (Explain)
B - Maintenance or Test C - Refueling D
Regulatory Restriction Method Of <2 >
Shutting Down Reason(!)
The Reactor Or Reduci:ng Power G
3 H
3 H
3 A
3 E - Operator Training and License Examination F - Administrative G
Operational Error (Explain)
H Other (Explain)
-101-Reportaple Occurrence Number Corrective Action~/Conunents 76-1 Feedwater Flow in Manua1~12 Steam ~enerator Low, Low Level Trip~
76-2 11 Steam Generator Feed Pump Trip on Low Suction Pressure-13 Steam Generator Low, Low Level Trip.
76-3 12 Steam Generator Feed Pump Trip on Low Suction Pressure-11 Steam Generator High Level Trip.
76-4 12 Steam Generator Feedwater Regulating Valve -
12 Steam G~nerator High Level Trip.
(2) Method:
1 - Manual 2 ~ Manual Scram.
3 - Automatic Scram.
4 Other (Explain)
Number of Personnel and Man-Rem by work and Job Function Number of Personnel (>100 mrem>
Tota1 Man-Rem Work ' Job Function Stat1on Utility Contract Workers Station Utility Contract workers F.mnlovees Rmnlovees And Others Emnlouees Emolovees And a.there REACTOR OPERATIONS ' SURVEILLANCE Maintenance Personnel 0
0 0
13 0
25 Operating Personnel 0
0 0
172 0
0 Health Physics Personnel 0
0 0
45 0
225 Chemistry Personnel 0
0 0
369 0
5 Supervisory Personnel 0
0 0
119 0
25 Engineering Personnel 0
0 0
0 0
0 I & c Personnel 0
0 Q
31 0
0 Security Personnel 0
0 0
0 0
13 ROUTINE MAINTENANCE Maintenance Personnel 0
0 0
70 0
61 Operating Personnel 0
0 0
0 0
0 Health Physics Personnel 0
0 0
l 0
0 Chemistry Personnel 0
0 0
6 0
3 Supervisory Personnel 0
0 0
23 0
32 Engineering Personnel 0
0 0
0 0
0 I & C Personnel 0
0 0
102 0
0 Security Personnel 0
0 0
0 0
0 INSERVICE INSPECTION Maintenance Personnel 0
0 0
0 0
0 Operating Personnel 0
0 0
75 0
0 Health Physics Personnel 0
0 0
70 0
0 Chemistry Personnel 0
0 0
0 0
0 Supervisory Personnel 0
0 0
110 0
0 Engineering Personnel 0
0 0
0 0
0 I ' C Personnel 0
0 0
0 0
0 Security Personnel 0
0 0
0 0
20 SPECIAL MAINTENANCE Maintenance Personnel 0
0 0
138 0
183 Operating Personnel 0
0 0
2 0
0 Health Physics Personnel 0
0 0
0 0
0 Chemistry Personnel 0
0 0
0 0
0 Supervisory Personnel 0
0 0
9 0
22 Engineering Personnel 0
0 0
0 0
0 I & C Personnel 0
0 0
36 0
0 Security Personnel 0
0 0
9 0
9 WASTE PROCESSING Maintenance Personnel 0
0 0
0 0
0 Operating Personnel 0
0 0
0 0
0 Health Physics Personnel 0
0 0
0 0
0 Chemistry Personnel 0
0 0
0 0
0 Supervisory Personnel 0
0 0
0 0
0 Engineering Personnel 0
0 0
0 0
0 I & c Personnel 0
0 0
0 0
0 Security Personnel 0
o*
0 0
0 0
REFUELING Maintenance Personnel 0
0 0
0 0
0 Operating Personnel 0
0 0
0 0
0 Health Physics Personnel 0
0 0
0 0
0 Chemistry.Personnel 0
0 0
0 0
0 Supervisory Personnel 0
0 0
0 0
0 TOTAL 221 0
269 Maintenance Personnel 0
0 0
Operating Personnel 0
0 0
249 0
0 Health Physics Personnel 0
0 0
116 0
225 Chemistry Personnel 0
0 0
375 0
8 Supervisory Personnel 0
0 0
261 0
79 Engineering Personnel 0
0 0
0 0
0 I & C J.>ersonnel 0
0 0
169 0
0 Security Personnel 0
0 0
9 0
42 GRAND 'l'OTAL 0
0 0
1400 0
.623
UNIQUE REPORTING EQUIREMENTS
-103-
PRIMARY COOLANT CHEMISTRY - 1976 DECEMBER 11 - 31 Disso.lved Suspended Gross Gross pH Conductivity
- Chlorides Fluoride Solids Boron Lithium Hydrogen Silica Activity Activity Tritium Iodine-131 At 25°G (umhos/cm)
(ppm)
(ppm)
Oxygen (Crud)
(ppm)
(ppm)
(cc/kg)
. (ppm) 15~ Min.
7 Day
(µci/!111)
(µCi/ml)
(ppb)
(Ppm)
(µCi/ml)
(µci/ml)
MAX.
6.80 12.0 0.149 0.014 93 6.9 1974 0.69 28.8 1.8 2.8xl0 -2 1.3xl0 -4 5.lxlO -3
- -5 2.0xlO AVG.
5.75 6,16 0.079
<0.011 15 6.9 1244 0.49 12.5 0.93
-3 3.3xl0
. -5 2.3xl0
-4
- 8. 7xlO
- 4.8xl0-6 *
-6
-6
-8
-7 MIN.
5.40 2.72 0.026
<0.011
'<2 6.9 665 0.36 7.0
.27 7.lxlO l.3xl0 5.5xl0 2.5xl0
-104-