ML19029B020

Annual Operating Report, Salem Generating Station, Public Service Electric & Gas Co. for 1976

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)

Text

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• • .O ANNUAL OPERATING REPORT SALEM GENERATING STATION PUBLIC SERVICE ELECTRIC & GAS CO.

FOR 1976 The Energy People

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- NOTICE -

1* 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. PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE(S) FROM DOCUMENT FOR REPRODUCTION MUST BE REFERRED TO FILE PERSONNEL.

DEADLINE RETURN DATE r.

I REGULATORY DOCKET fltE COP11

• RECORDS FACILITY BRANCH

• • '----*-------------- _______J I*... . .

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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. DPR-70

-. TABLE OF CONTENTS PAGE INTRODUCTION I HIGHLIGHTS 2

SUMMARY

OF OPERATING EXPERIENCE 3

• PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY-RELATED MAINTENANCE 8 Amendments to Facility License or Technical Specifications 9 Facility or Procedure Changes Requiring NRC Approval 11

• Tests and Experiments Requiring NRC Approval Other Changes, Tests, and Experiments 12 16 Corrective Maintenance of Safety-Related Equipment 20 LICENSEE EVENT REPORTS 97

• OTHER EVENTS OF INTEREST 98 DATA TABULATIONS 99 Net Electrical Power Generation 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) 5)

Testing of the Boron Recycle System.

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) Testing upper motor bearing of No. 14- Reactor Coolant Pump.

~

4) Testing pump seal of No. 11 Reactor Coolant Pump.

5 ). Testing* five specified RTD's* in the Reactor Coolant System.

• 6) 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 O6 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 - DPR-70.

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 - DPR-70. 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 - DPR-70. 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.

f.

g.

No. 11 RCP No. 3 Seal Leakage RCS RTD Cross Calibration 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 Nuclear Design Check Tests Rod and Boron Worth Measurements RCCA Pseudo Ejection 80.6 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-

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.

I 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 FEEDWATER 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

'1

~ux Corrective Circuit Mal- Feed Pumps could Retested circuit, works as FEED PUMPS OD-3445 function not be started from per Schematic I 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 II

• * *

• 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 OD-3499 NO. 11 CHILLER UNIT Corrective Valve 11SW92 33/CVO open - Valve Opened, Operation Tested OD-2914 Closed . Circuit open -

Chiller Not Running I '

• * * *

• SAFETY REL ED EQUIPME. * * * *

• Mechanical.. and Electrical Maintenance EQUIPMENT NATURE OF MAINTENANCE LER OR OUTAGE NUMBER

. CAUSE MALFUNCTION RESULT CORRECTIVE ACTION

, I I

• *c1 ILLED'WATER O. 13 _CHILLED WATER Preventative ECN E-1676 (refer to Design Change New Base Line Data Perform M3C & MllC for Base ECIRC MOTOR SU-0181 Line Data O. 13 CHILLER UNIT Corrective Sticking Relay Chill.er Cuts In & Correct.ed Relay., Recharged

. OD~2683 . . . . . for Solenoid Vlv * . Out Sporadically Unit O. 11,12, & 13 ... Corrective Malfunctioning Trips on Hi Cylinder. Problem .Corrected HILLER UNITS OD-2117 Switch & Coolant Read Pressure

. . . . . . . . . . . . . Supply. ' . I O. 11 CHILLER muT Corrective Plug Blew Out Leak in Chiller Repaired* with New Plug oD..:..2449 O. 12 CHILLER UNIT Corrective Faulty Mech. Seal Oil Leak R~placed Seal & Recharged MD-1038 Compressor O. 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 nCIRC 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 C HEAT EXCHANGER /112 Corrective Fouling of Tubes Loss of Cooling Cleaned Debris from Heat I MD-,1155 Capacity Exchanger - SW Side C 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

ALVE lCC187 Corrective Grease Appears Po.ssible Damage_may Grease Inspected and Found to OD-2467 Contaminated Occur to Gears be in Good Condition*

ALVE 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 ALVE 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. -

/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 II 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

ALVE 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 ALVE 14CC130 Corrective Packing Leak Loss of Coolant Tightened Packing OD-3458 .. ' ..

lCC HEADER LOW Corrective Alarm Not in Alarms at 130 Psi Recalibrated Alarm to Alarm RESS. 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 l SEAL WATER Corrective 0 Ring Out of Filter Cover Cover Taken Apart and 0 Ring NJECTION SYSTEM OD-2786 Adjustment Leaking Was Adjusted OJUC 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

• * * *

• SAFETY REL..ED EQUIPME9r Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT. MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION eve . ;. cPERATIONS SJ4 & 5 *corrective Bonnet Gasket & Valve Leak Installed New Bonnet Gaskets SJ12 & 13 OD-2783 Valve Seat Mal,... and Lapped Valve Seat

.funtion *,.

ALVE 1CV40 Corrective Motor Malfunc- :valve Dpes Not Motor.Rewound

. SU-0202 . . . ......... .tion .Work .Remote~y I

ALVE 1CV41 ,. Correct iv~ . Motor Malfunc- .:Handwheel Would Not New Motor Installed SU-0179 tion :Disengage. Motor I I

would Not De-ener- I g_ize RIFICE 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 RANS. PUMP OD-2745 Malfunction Packing Gland Realigned Motor A TRANS. PUMP Corrective Mechanical Seal Pump Leaking Thru Replaced Mech. Seal and Pump 0D"":"2327 .. Malfunction Mech. Seal Cashing Gasket ill & 12 BA TRANS Preventativ:e Uncouple Pump Prevent From Unc*oupled Pump Until Gaskets PUMP ,

I su-0200 Working Are Replaced 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 At. ED*EQUIPME * * *

• I Mechanical and Electrical Maintenance I NATURE OF. LEROR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE , RESULT CORRECTIVE ACTION I

eve - OPERATIONS 2 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 REAKER OD-2646 tion Not Charge I

I 3 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

' 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

• * *

• 9;AFETY RELA 1) EQUIPMEN

• Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE . MALFUNCTION RESULT CORRECTIVE ACTION EQUIPMENT MAINTENANCE NUMBER CAUSE

• eve* 'OPERATIONS ALVE lCV345 Corrective Loose Packing Leaking Valve Tighten Down Packing OD-3459 ALVE lCV116 Corrective Valve Malfunc-* Motor Trips Replaced Motor OD-2813 tion.

ALVE 1CV185 Corrective Faulty Diaphragm *Leaking Valve Diaphragm has been Replaced

" OD-4015 CONT.1 INMENT SPRAY CS16 BREAKER Corrective Motor Failure :Breaker Will Not Rewound Motor SU-0186 :stay Closed I ALVE 11C62 Corrective Thermal Over- Valve Will Not Reset Overloads SU-223 loads Tripped Operate REAKER 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

• * * *

• SAFETY RELttfED EQUIPM1fr *

• Mechanical and Electrical Maintenance .

NATURE OF LER OR OUTAGE MALFUNCTION ..

EQUIPMENT MAINTENANCE NUMBER CAUSE . RESULT CORRECTIVE ACTION CONT; INMENT SPRAY ALVE 11CS2 Corrective Test Time of None Tested Sat isf ac tory*

. SU-386 Valve Travel CONTRC LAIR.AUX BLDG '

I I

2 CAC 2SW107 Preventative Design*Change Job Completed Modified i/a/w ECN M-7337

..* MD-0604 ...

CONTROL A R PENET. & CONTAI N' :

1 EMERG CONTROL AIR Corrective - Filter Needs :on Pressure Slow Changed Filter,Cleaned Oil Line OMP. OD-3982 Changing - :i'.£1 Reaching Full r- By-Pass Vlv. *Pressure on Gage Needs Adjusting ll EMERG CA COMP Corrective Air Comp. Trip- Cannot Run Readjusted Oil Pressure OD-3940 ping Out on Low Compressor Relief Valve Oil .P.ressure 12 EMERG CA COMP Corrective Compressor Not Low Oil Pressure Wiring Error Corrected OD-3621 Wired Correctly Trip Will Not Reset H EMERG CA GOMP Corrective Demand on Sys. Compressor Runs Loading and Unloading Points OD-3518 Excessive for Continually Were Set Satisfactory

• . Comp,

n. :

EMERG CA COMP Corrective Contact or Not Compressor Will Not Readjusted Contact OD-3496 Adjusted Start Properly.*

I

• * *

• 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. 1 EMER AIR COMP Corrective Test for Pipe *Discover Possible Pressure Tested Pipe, and SU-377 Leaks .Leaks Identified LeaRs for Repairs

1. 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. 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 1 11 *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 I :Better Operation Bulb was Moved to New 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 *off in Auto Mode Detector 11 RHR SUMP PUMP Corrective Actuating Arms *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 RV 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 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

• * * * *SAFETY REL ED EQUIPME * * * *

• Mechanical. and Electrical Maintenance NATURE OF LER OR OUTAGE . MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION FUEL HANDI 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  : i f 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 FUEL 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 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

~

I l 1 -

~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 PEND ER RE-OOll ment Satisfactory to Operation HOIST Corrective Frayed Cable Possible Failure Replaced Cable With One From SU-0167 i f Used in This Unit /12  !

Condition RANSFER TUBE Corrective Installed Bolts were Fabricate and Install Two LANK FLANGES MD-0410* . Improperly :stripped New Brass Bolts CE k\NES & HOISTS ll CASK HANDLING Preventative Inspection :completed Reported for Deficiencies MD-0245 Inspection & Action Taken I UX 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

• * * * ~AFETY REL~ED EQUIPME~

Mechanical and Electrical Maintenance

• * * * .I NATURE OF LER OR OUTAGE MALFUNCTION MAINTENANCE NUMBER CAUSE , RESULT CORRECTIVE ACTION EQUIPMENT CB ANES & HOISTS UEL HANDLING CRANE Corrective Weight Limt Switch Would Bind Made New Pivot Pin and MD-0270 Switch Malfunc- Removed Weld Splatter tion  ;*

UEL HANDLING CRANE Corrective. Wire Reconnec-: *Crane Malfunction Test OK after Adjusting OD-2615 tion Error Actuating Arm. *-

ASK HANDLING CRANE Preventative Limit Switches *Crane Could Go Installed and Wired as per MD-0625 (None) :Slamming into Wall Schematic RIPPER Preventative Gripper Binding -~ubriCate all Disassembled & Lubricated SU-0173 *Gripper Binding

• .Parts OIST JOG-CONTROL Corrective Bad Contact Down Button Not Cleaned All Contacts ob-2509 Always Operative.

ANIPULATOR Preventative General Maint. Put Crane in Good Replace Limit Switch, Installed SU-0278 Operational Condit. Brackets on Fan, No Problem

' With Overload fANIPULATOR/FUEL Preventative General Maint. Prevent Breakdown Replaced Manipulator Hose, RANSFER SU-0273 Dowell Upender Lifting Cranes, Tack Weld Nuts & Bolts, Install Set Screws ANIPULATOR CRANE Preventative Gripper Rod Out Gripper Binds Connecting Rod - From Air to SU-0266 of Adjustment Gripper Needs Adjustment I

ANIPULATOR Preventative Power Cable No Power to Crane Replace Cable and Inspected SU-0329 Damage l I I I I

• * * * ~FETY RELAien EQUIPMEN., * * * *

'Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE '

MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION Cl lANES *& HOISTS ANIPULATOR CRANE Preventative Reverse Bumper They Hit the Wall Bumpers were Repositioned under\

SU-0268 iµ. Wrong Place Westinghouse Supervision ANIPULATOR CRANE Corrective Limit Switch . Reverse Doesn't Limit Switch and Control RE-5 Malfunction.  : Work. Circuit for Proper Operation ELSYN MOTOR Preventative Last Indication . Gear Check Motor Work Performed OD-2782 ...

OLAR CRANE Preventative Inspection Inspection CompletE Report That Told of DeficiencieE MD-0244 1 POLAR CRANE Corrective Drum Gear Out of  : Crane Did Not Drum Gear Was~Realigned MD-0239 Alignment  : Function Properly ll POLAR *CRANE Corrective Broken Shaft on No Limit Switch New Shaft Made & Installed MD-0826 .. Limit Switch UEL 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*

UMP 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 RH-178 Corrective QA-0007 Arc Strike I Blemish on Pipe The Arc Strike was Blended in With a Grinder

• * * * ~AFETY RELA~D EQUIPME~ * ** *

• Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION RES II UAL HEAT REMOVAL HR Corrective Loose Suction Must be Welded to Spool was Welded to Floor Plan MD-0733 Spool the Floor Pad I

12 RHR SUCTION LINE Preventative Removal of Temp To.be Replaced by Removed Valve'and Reducer, OD-3740 Gage Pipe Cap Installed SS Cap UCTION FLANGE Corrective Suction Flange Leak Replace Flexitalic Gasket OD-3678 Malfunction HR, CHARGING & Corrective Removal of Strainer Removed & RHR Suction Pipe Flushed AFETY INJ. OD-2569 Strainer & Temp Temp.Gage Holes with DM Water Gages Were Capped 1112 RHR MOTOR Preventative Check for Bind- Removal of Snubber Snubber was Replac.ed After NUBBER QA-0012 ing Inspection*

112 RHR PUMP DISCH Corrective Gasket Failure Flange Leak Installed New Gasket LANGE OD-3772 2Rfl-4 VALVE .Corrective Nut U~tightened Loose Valve Tightened Locking Nut and Mn-0333 Staked Nut 1RH19 .. Corrective Loose Valve Untightened Valve Tightened Valve MD-0347 RH26 Corrective Design c&ange AP8-ED0017 Replace Yoke & Stem MD-0927 LlRHR9 Corrective Packing Gland Pack Gland is Down Repacked Gland OD-3703 Failure all the Way LlRHR38 Corrective Packing Gland Removed Old Packing Replace with (6) Layers of OD-3704 Failure New Packing

.,.JS-I - _I -- ----

• * ** .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 1RHR12 Corrective Gasket Failure Sys. Malfunction Inspection of Valv~ -

2RHR12 OD-3701 Installed New Gasket RH64 Corrective Cap Leaks Gets the Floor Wet Resealed Cap with Teflon OD-3794 I

RH26 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 1 & 12 SPENT FUEL PlT ..

STEAM GENEI lATOR.DRAIN & BLOW DOWN ALVE 13GB3

. Corrective Fa~lty Packing Valve .Leaking @ Repacked Valve 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 -

• * * * ~AFETY RELA~D EQUIPME"

'Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE . MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION MAIN STEAM, REHEAT TURB BYPA SS STEAM STEAM FLOW TRANS- Corrective ' Design Change Piping Changed as Design Change ED-0047 MITTER PIPING MD-1170 per ED-0047 , I I

l-MS-52 STRAINER Corrective Normal Procedure Strainer Changed Removed Startup Strainer -

SU-0155 Installed Permanent Strainer HANGER "F11 CROSS Corrective Checking for Load was' Set at Reset Loading of Hanger @

UNDER PIPE SU-:-0198. ... . Proper LOa~ing .Proper Loading 4300# .

SUPPORT COLUMNS Corrective Improper Bolting Possible Failure i f Support Columns were Rebolted MD-0929 Not Corrected and Torqued VALVE 12MS35 Corrective Work Done in 1977 Leaking Gasket Stearn Leaking Repaired by Changing Gasket MD-1267 LEAKOFF VALVE Corrective Improper AsseinblE Valve Leaking Disassembled Valve Cleaned &

12MS7 OD-4019 Reassembled VALVE 13MS45 Corrective Gasket Leak Steam Leaking Replaced Bonnet Gasket* -

OD-4076 Repacked Valve VALVE 11MS36 Corrective Manufacturing Valve Leaking Welded Valve* Body

' MD-1194 MSR SAFETY VALVES Corrective Lock Wire Missing Possible Unauthor~ Installed Lock Wires on SU-0170 ized Tampering Missing Valves MAIN STEAM STOP Corrective Valves Operating Did Not Trip After Valves Were Jurnpered and VALVES OD-2341 as Designed Test Because no Stm Closed Present I

~YDRAULIC OIL Corrective No Leak.Found Oil Level Low Refilled Oil Sump to Proper SNUBBER VALVE SU-204 Level 13MS167 I

I I I -

• * * *

• 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 ALVE 13MS1.67

• Corrective Relay Needed Indication of Valve Reset Relay (Put in Operate

. OD-2868 Re~etting Position Not Shown Mode)

. . . .... *.on 1PR4 TM 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 &

4MS137 SU-485 Conn. Drawing Configur- Caps Installed on Valves 3MS144 at ion 3MS177 . . . . . . ... . ' . . . . . . . . . . . .. 1 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

• * * *

• 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 ..

I 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' 104 ' PD-1809 Alarm Malfunc- ACS-82

' 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 I

• * * ** *. 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'-

o* *11B DIESEL Corrective Valve to Press Prevention of Shut- Valve Open TARTING AIR COMP OD-~229 .. Deyice.Shut down of Compressor

o. 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 R COMPRESSOR MD-0161 . . . . .. . .. . . ., ... . .. . . Discharge .Flange .

o. 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 &

ACKET WTR HEATER *MD-0621 " . Out. .tional * - Tested OK

o. lA* DIESEL GEN Corrective Jacket Wtr Heater Shock Hazard Replaced Jacket Water Heaters ACKET 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

• * * ~AFETY REL~ED EQUlPME~

Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE ,. RESULT . CORRECTIVE ACTION

• EMERGENCY D ESEL'& AUXILIARIE~

o. lA & lC DIESEL Corrective Jacket Water Leak Loss of Jacket Cleaned & Re taped .Threads CKET WTR HEATERS MD-0656 Cooling .Water on-Heater Connections

o. lC DIESEL TURBO Corrective Bad Fittings Failure of Pres~ure Replaced Fittings OOST AIR SYSTEM SU-0081 Test DR 110735

o. lC DIESEL AIR Corrective Malfunctioning Failure of Pressure Replaced Valves ART SYS VALVES SU-0079 Valves. Test DR. /ISS0997 NTROL BEZEL lB Corrective Bulbs Burnt Out Could Not See Lights *Replaced Burnt Oµt Bulbs*

OD-2371 MERG DIESEL GEN ' Replaced Diesel ECN M-15290 TAR':rING AIR MD-0569 Starting Air Shuttle .

" Va;t.ve & Retested ARTING AIR SYS Corrective Fouled Internals Leaking Cleaned Deposits From Inside LVE 12DA6A SU-0214 &. Tested OK MERG DIESEL GEN I Wired Control ECN C-16364 ARTING AIR COMP. MD-704

• Circuits & Tested on all Start Air Comp*

b. llB STARTING-AIR Corrective " Pressure Switch Starting Air Comp~ Changed Pressure Switch &

lMPRESSOR PD-1189 PD6477 Malfunc- Did Not Cut Out Calibrated as per M3I tfon

. lA DIESEL WATER *corrective Temperature Contact or Does Not Recalibrated Devices 7333,

!:ATER DEVICES OD-2884 Device Out of Pick Up 7343, 6463, & 6464 Calibration

• I I *

• Mechanical and Electrical. Maintenance .-

NATURE OF LER OR OUTAGE . MALFUNCTION '. '

EQUIPMENT . MAINTENANCE*

NUMBER CAUSE RESULT* ..

CORRECTIVE ACTION

. EMERGENCY I IESELS .& AUXILIAR ES

o. *1c DIESEL Corrective Sticking Throttlt Starting Time Over Lubricated Throttle Linkage ENGINE SU-232' Linkage. 10 Sec. & Te!=Jted ..

OK J

. lA DIESEL Corrective No. SL Cylinder Cylinder Not Corxected.Probl.em ~

. Teste~. 01(, *

• .

ENGiNE OD-:-3810 Fue;l.: Linkage Firing

. . Locked .Ol)t. .. .. . . *.*. ..... '*

o:~ 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

• Control. . .

ATEll' CKT

. ; ... . . *;* . ...' ,* . . ... ~ . .* . .. ..

• :~.

o. lC DIE~Ei. Corrective .. Defective Temp :J,.ube Oii }leater

• Recalibrated TD-7319 &

GINE*. ;f.UBE OIL UTR OD-,2465*  :"* . . ..... .Device ... . . . . . . .Failure.Alarm Installed New Te.mp Device

• I ANKCASE 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 LANT PRESS & RELI1 F 13 STM GEN

. Corrective

• oD-2837

Union Leaking. Oil Loss Repaired Coupling 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.

• * * * ~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 NCORE INST~ Corrective MD-.0427 Cleaning &

of Parts Cleaned Thimbles Installed Work Was Completed I~stallation Drive Unit Boxes

& Thimbles Not

.Comple~. . . . *.

EACTOR INTERNALS Corrective Improper* Clevis Insert Bolt Clevis Insert Remachined MD-0284 Manufacturing Holes Do Not Line to Fit *

Up With Holes iii

.. Reactor Vessel

' .. ' . Glev;i.f;l 11i RCP SEALS Corrective Seal Not Seated ;3rd Seal Leaking _Pump .Operated to Seat Seal OD-3350 . . . . ' . ' ....

11 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 nARJ;: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

• Corrective Loose Flange LeaJc .On Seal Return Tightened Flange Baits OD-2870 Bolts 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 CAUSE , RESULT CORRECTIVE ACTION EQUIPMENT MAINTENANCE NUMBER REACTOR.COO LANT'PREss*& RELIEF PS4 REMO!E OPERATOR Corrective Travel pf Valve Travel of Valve Was Checked Travel l'1it4 Specs*

OD-2539 May Be .Wrong According to Specs i

RESSURIZER Corrective Inspection Manwa,y Opened ..fi.'i, New.Gasket *Installed a.nd MD-0184

• Closed After Manway Closed Up

. . ,.. .. .. Inspection 1, it ..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

-- OD-3886 . . . .. Will Not Operate I

x1 & /114 RCP MOTORS Corrective Improper Location Possible Failure Relocated Ho~es as* per

. SU'"'."409 .. of Flex Hoses Due to .Chafing Engineering Dwg

• ll. RCP OIL COOLJ):R Corrective Valve Leaking Due Vent Valve Leaking Lapped In Valve

. MD-0764

.to Po9r Seat*

14 RCP Corrective Unions Not Made .Leakage of Water Took Unions Apart, Cleaned su-4+6 Up Properly & Reassembled PR5 Corrective Improper Valve Assembled Installed Missing SS Washer

• MD-0179 Assemble. Without Washer- on Stud Lvs 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

• * * * *sAFETY REL~ED EQUIPMEf'r

'Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION .

EQUIPMENT MAINTENANCE NUMBER* CAUSE RESULT *CORRECTIVE ACTION REACTOR COO f.'ANT PRESS & RELIE Ii' ALVE 1PS3 Corrective Plug Jammed Valve Did Not Rebuilt Valve PD-1663. Operate LVS 11RC9~ llRCll Corrective Valves Need Packing Glands QD . . . 8358. .Repacking*** . .Leak . . . ..

--~....-~...--~....-~~-+~__.;..~~~~~-""'.l-:--"'-.~--,~--,.,--~-,---f---'-~....,..--'---,.--:-~~1--~~......,-~~~~~~+---'-.,--,...,~~__;,,*~*-=--:-~--,----.,...*~~

ALVE. :q:>R25 Corrective Valve Does Not* Will Not Pass . -Rese.~teci **&:-'Lapped Valve* -

SU-0137 Close.Tight. Leak Test I>~~i:ieCi ;_ ieak:*ref:it

. ) ..... '

_LVS -1~~6 & 1PR7 Corrective* Faulty<;:ouplings _Coup],.ingE;J Leak* Fabricateci>& In~talled .

• . *1 *'

MD;_,0595 on Leakoff Lines . N~w* C011plings: * . ***; *

. S !\.FETY INJ

• 112 ACCUMULATOR VENT Corrective

• Faulty Valve Le.aky Valve New Replacement Valve FA-1.5 VALVE 12sj2~ OD-2919 H 3 4-CCUMULATOR .

• Corrective *Faulty Valve Leaky Valve Replaced Valves

/LVS 13SJ22,24,171 on~3612

~72,320 .

ALVE 1SJ67 Corrective Malfunctioning No Indication of Rewired & Energized SU-195 Position-Ind. Valve Status

~ALVE 11SS54 Corrective Malfunctioning No Indication of Rewired & Engergized

. OD-2295. .Position Ind

• Valve Status I TALVE 12SJ33 Corrective Water in Motor Motor Would Not Rewound Motor So It Will I

SU:--171 Operator Operate Valve Operate Valve TALVE lSJl Preventative Motor Operator.* Break Power .Feed Power Leads Lifted & Marked SU-224 Burnt Out to Operator

• * . -' * *sAFETY REIAEn EQUIPMEfr ** ** ** ** I Mechani~al and Electrical Mainteriance I

NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT. CORRECTIVE ACTION

.. ~

AFETY !NJ.

112 SI PUMP.LUBE Corrective Fouled By Grass Inspection . Removed Head & Cleaned -

OIL COOLER . MD-.1120 ' ' ' I ' * .in.HeacJ. Installed New Ga.sket ill SI .PUMP LUBE Preventative Fouled By Grass *Inspection . Removed. Head & Cleaned OIL COOLER MD-1163 . .. ... .. . . .. . '*. *, . . in .Head .. ..

Out Grass .

/12 SI PUMP. Corrective Misalignment & ~xces9ive Vibration Sent Pump to Mfg~ for Repair MD-632 ." . .* ' . .Out Of Balance .Out . of Spec

• Replace with No. 2 Unit * .

112 SI PUMP Preventa.tive Modification of Baseplate MD-8ll . . . . .. ..

BIT HEATERS Corrective Wiring Error Does Not Operate Rewired lfeC!,ter at Tank OD-2209 . . . . ... . . . . .. . . . . . . '

3AFETY INJECTION Install Power Lockout For MD-54~ . . . . . . . . . . .. ECCS Valves (ECN E-1672 Rev 2)

TALVEl 1SJ30 Corrective Defective Oper, Will Not Operate Removed Defective Motor -

OD-2408 Mo tot' Reinoteiy Installed Rewound Motor TALVE l()Jl Corrective Defective Oper. *Will Not Stop New Motor Installed *-

SU-231 Motor & Water in Running or Drive Readjusted Clutch Assembly Clutch Assembly Valve tALVE 11SJ54 Corrective Rotted Packing* Packing Gland Leak Removed Old Packing &

- OD-2821 1. Repacked - Also Changed Nuts

'ALVES

. lSJl & 2 Corrective Faulty Motor Breakers Tripping Replaced Motors & Retested OD-4243 Operators Out rALVES 11 & 12SJ44 Corrective Dirty - Bad Leaking into Cont Disassembled, Cleaned, &

OD-2420 Gaskets Sump

• Reassembled with New Gaskets

• ** *

• SAFETY REiiTED ECjUIPM'T Mechanical and Electrical Maintenance NATURE OF LEROR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE ,* RESULT CORRECTIVE ACTION

• ~ AFETY !NJ~

114 ACCUMULATOR Corrective Faulty Level Replacemen*t Ne~ded Removed Old Capillary Tubes I EVEL TRANSMITTER :t;>D-1029 Transmitter & *Ballasts &*Put In New

.;a as per PCS 112 SI 4KV *BREAKER Corrective Damaged* Shutter Breaker Cannot Be . Replaced Shutter Mech~ &

OD-.2440 - . ' . . ' .&.Rod Elevator *I . Pulled Out From Bus Elevating M~ch, Rod ALVE 12SJ49 Corrective* Incomplete Valve Inoperable Installed Relay & Relo<ide4 SU-149 . . . . . Circuit from Remote Coil of Contactor SOLATION VALVES Preventative Insufficient Refer "Memo E,....4Q3 Installed Additional H.T~

EAT Tfu\CiijG MD,.:;,,B25 . . . . . - .Heat Tracing* . & 'APB

• sERVICE \I IA.TER NUCLEAR AREA . I n2 SW STRAINER Corrective Diff. Device Strainer Runs Cleaned and Recalibrated OD-3537 . Needs Calibra- Continuously Diff. Device PD2B6 tion & Cleanup 112 SW AUTO STRAINER

. Corrective Strainer Jammed Shear Key Broken Replaced Shear Key MD-1209 114 AU'}:'O STRAINER CoJ:'.rective Strainer Jammed Shear Key Broken Replaced Shear Key &

' MD-OBB9 Thrust Brg.

115 SW BREAKER Corrective Closing Coil Breaker Trips Replaced Closing Coil OD-2577 Failure H6 SW PUMP AUTO Corrective Strainer Jannned Shear Key Broken Replace Shear Key &

lTRA~NER OD-4099 Buildup Shoes W PUMP MOTORS Corrective Modification To Improve Replaced Mot.ors With MD-lllB ~AW APB ED0027 Operation Modified Ones I

I

• * * *

• SAFETY RELfrED EQUIPMilT * *

'Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION EQUIPMENT SERVICE WA "ER NUCL.EAR AREA 2 SW 4KV BREAKER Corrective Failure of Clo~~ Pump Does Not Replaced Defective Parts OD-3563 ing R~lay, Operate Closing Coil, &

Close Latch Monitor Switch.  ::*. I

.,.--.,.--~.,.--~.,.----t~~.,.--~~..,-.,.--.,.----J..,...,.--.,.--.,.--.,.--.,.--.,.--.,.--.,.--.,.--_,_+.,.--.,.--.,.--__;~~.,.--.,.---1-.,.--.,.--.,.--..,.......,.--.,.--.,.--.,.--~~+---,_..,.--'.~.-,--,-~ .* ~.,.---,.-.,.--.,.--.,.--~-:

2 SW J;>UMP Corrective Level Device Pump Runs.*

• Reattac:hed Displacer OD-3644 Not Connec~ed. , Continuo.u~ly *. *. to, i~y~.f ~~~i~~ *

.**** *** *i"

13. sw. :.PUMP MOTOR ..

CorrectJve Tubes of Bearing. Bearing Cooler* * .ci~~n **out:*'c~,al:e,r

- MD-064.:J_ Cooler Plugged Ne~ds Cleaning With Silt 4, SW Pt,JMP Correct:::J.ve

• Contrdl Power P.ump Will Not Replaced Coptrol .Power OD-2255 DeiOn Failed Op~rate DeioQ.

5 SW PUMP Corrective Defective Closing Pump Will Not Operate Replaced Defective Closing OD-2535 Relay & Closing Relay & Breaker Closi~g Coil Coil.

5 SW PUMP Corrective Improper Pump Will Not OperatE Adjusted 52HL Switch OD-2547 . Adjustment 6 SW PU}1P Corrective SMLS Jammed Pump Will Not Run. Repair~d Jammed SMLS OD-2511 6 SW PUMP Corrective Motor Grounded. Motor Trips Replaced Motor OD-3472 I

SW PUMP Corrective Loose Tube Teq-. Excessive Leakof f of Tightened Tube Tension OD-2737

• sion Assembly Coolant Assembly

-- . --*_ _ _____L_ _~_t_*_ _____L,___ _ --1...-------

• * * ~AFETY RELA~ED EQUIPME~ * * ** *

• Mechanical and Electrical Maintenance NATURE OF LE:R OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION.

- *sERVICE.WA'l !ER.NUCLEAR AREA ALVE 12SW127 Corrective Roll Pin Wrong Excessive Play in Installed New Roll Pin OD-2392 . . . .... . ....... S:Lze Operator in Operator W49 PIPING Corrective Revision of Piping Held By New Installed New Hanger MD-1056 .. . .... Piping Hanger a~ per Instructions

.. I 115 SW*?UMP Corrective Improper Expansion Joint Replaced Expansion Joint '

MD-1110 . . . . . . . . . Installation* .* . Distorted.

TRAINER BAC~ASH Corrective ' Reinstall ., System Returned to Rtdnstalled Orifices INES. MD-112l .. _ Orifices Normal . With New Gaskets W PUMPS Corrective

. . . Vents Not High Spill on Startup Ext.ended Vents OD-2101 .. .. Enough. . .

W PUMPS Corrective Install Orifices Restrict Flow* Installed Orifices MD-0651 Hl & 1112 CHILLER Corrective Coupling Worn Possible Failure Replaced Flexible Coupling

~OND "WTR RECIRC PMP MD-1089 Hl SW J,>uMP Corrective Faulty /Ill SW Switch With 1121 Replaced /Ill With /121

' MD-0893 Pump SW Pump r12 SW PUMP *Corrective

• Pump Malfunction Switch With /122 Replaced 1112 With //22 MD-0890 n2 SW PUMP 4KV Corrective Motor Malfunctio1 Springs Didn't Changed Motor and Adj. Latch 3REAKER OD-3490 Change When Breaker Tripped

. 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 113 SW PUMP Corrective Pump Malfunction Switch With 112,3 ' Repiaced 1113 With. 1123 MD-0815 ' ' . . . . . .. . ' ' .

113 SW PUMP Preventative Signs of Mal- Starting to Show Will Be Replaced By The OD-2549 . . . . ' ' '

.function Wear One on.Unit 112 Side

113 PUMP SCREEN Corrective ScreenWil.l Not Screen Returns to Replaced* Device PD2733 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 .

f 15 SW PUMP MD-0832 24 & 25 Respectful~y I

116 SW PUMP Corrective Pumps Rusted Out 1Switch with lt26 Replaced 16 with 26 MD-0816

• 116 SW PUMP

. Corrective OD-3349 Shaft.Vibrating Excess Noise in Motor Pump Will Be* Replaced with One From Unit /n. Side 116 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

• * * * *sAFETY *. REtAED E~UIPMlfr * **

'Mechanical and El~ctrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT. MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION

., . *SERVICE WA'I ER NUCLEAR AREA 1/15 TRAVEL SCREEN. -Corrective Device Out Of . Screen Press Switch Recalibrate per M3I OD-3513 Calibration. N.G.

/Ill SW STRAINER Corrective Repack NeE!ded ' Inspection Made: :a,ep~ck.it1g none. After OD-2162 Insp~d;toij, STRAINER Corrective Orif !ces Should Ori~ices Will.Be

• Orifi~~*s* R_ei:noyed *and Flex.*: ".

. .. MD-1102 .Be .Removed

. . . Removed Ga.sk~t s*.: Ip.shrl!ed 1114 & //15 SW Corrective Brokeµ She"ar Pin Failure .. I~s:tC1.iiea *N~:w *Shear Pin. 'key*;:

STRAINER .. ... .** .... * *.. _*, . . . . :

14-0D-2516 15-0D-,.2862 1115 SW STRAINER Correctiv.e Brelitker Won't It Won't Get Any Repa~red Bent In,1:erlo:ck, OD-4343 .Close. Juice 1116 SW STRAINER Corrective Broken Shear Key Failure Replace Shear Pin Key OD-3805 NO. 1 EAC Corrective* Intercooler Tube Inspection Tubes In.Good Condition MD-1148 1112 CIJG PUMP,* Preventative Inspection Coole*r Lubes OK Removed Grass MD ... 1161 VALVE 12,SW21 Corre<;!tive Sheared Shaft Failure* Reinstalled Gear On Stem D-3661

12SW23 Corrective. Valve Position Broken Removed Insulation OD-3345 Hit'ting Insulation 13SW223 Corrective Gasket Malf unc- Blew Out Repaired OD-2784 tion

• *.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

• **** *sAFETY REL~ED EQUIPmfT

• 1 Mechanical and Electrical Maintenance . . ...

.. I NATURE OF LER OR OUTAGE MALFUNCTION

, CORRECTIVE ACTION

• EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT SERVICE WA' 'ER NUCLEAR AREA 13SW223. Corrective Gasket Failure Blown Gasket Gasket Replaced OD-2472

~

!.I 11 & 12SW48 VALVE *Preventative Switch *Design Change,*' 11 & :t.2SW48 Valves Switched MD-1064 with 21 & 22SW48 Valves F~-1-31 FLEX Corrective Misplac.ed Contra Contrpl Rod Missing Replace Control Rod as per CQUPLING .* MD-0623. .. .Rod . . .. .. ECN M-7684 '

. SERVICE ~ 'ATER TURBINE AREA No. 11 CHG*. SUMP Corr.ective Grass in Tubes Inspection Replaced Pipe Eng Plugs &

LUBE OIL COOLER MD-1143 of Cooler* Cleaned Out. Tubes ..

• STRUCTUl U\L (CONTAINMENT) .. . .

ACCESS HATCH El.'100 Corrective Misaligned Door Door Leaks Aligned Door & Connected OD-2604 Inner Door Leakage I

PERSONNEL HATCHES Corrective Hatch Door Door Leaks Door Gaskets Reversed, PD-1269 Gaskets Failure and Adjusted Doors CONTAIN EQUI~ Corrective Hatch Door Door Leaks Replaced all theG~skets HATCH DOOR MD-572 Gaskets Failure LOCK DEVICE Corrective Door Broken Does Not Open Inst&lled Bearing PERSONNEL HATCH MD-0785 Properly EL. 100 AIR LOCK Correct~ve Door Does Not Door Leaks Adj. Door Closin,g chain OD-3385 Lock Properly EL. 130 AIR LOCK* Corrective Door Wheel Spins Dangerous Adj. Door Closing Lock OD-3385 Too Freely

' *.. * * *sAFETY *R~L!En EQUIPMEfr

• Mechanical and Electrical Maintenance NATURE OF LER OR OU'l'AGE MALFUNCTION . '"

MAINTENANCE NUMBER CAUSE ' RESULT CORRECTIVE .ACTION

• EQUIPMENT

- *sTRUCTU RAL (CONTAINMENT)

I L. 130 AIR LOCK Corrective Malfunctioning Gasket Blowout of Cleaned Gasket and Replac.ed*

OD-3005 Gasket Groove when Opening Gasket Door_ -*-

00' CONTAINMENT Corrective* Broken_ Roller Door Malfu:nction Rep~aced Roller ' -

DOOR MD-0933 ONTAINMENT ,

Preventative Design Change AP8-ED0018 New CRDM Vent Fan lie Parts

-PLATFORM MD-1119 .. ,*. .- . . . . . . . . . . . . - . - .

PERSONliEL HATCH Corrective Bad Gasket Door Leak New Gasket Reinstalled OD-3936 ..... - and Tested ,_

;:-":

00' & 130' INNER Corrective Latch Malfunction Leaky Door Adj. Lock Strike Bar . .-

AIRLOCK DOOR OD-4074 .. Tested OK OD-4063 ERSONNEL HATCH Corrective Door Out of Leaking Do9r Door Adj. and New Set MD-1223 Adjustment Screw & Bolts Installed VENTILATIO ~ AUX BLDG EQUIPME NT ilo

• 11 AUX BLDG Cor:rective Adjusting Snap Coupling Adjusted. Pully.R.epaired & Reinstalled XHAUST FAN ' MD-915 .Rings Came Loose Past Stops Jo. 12 AUX BLDG Corrective Bad Outboard Excessive Noise Replaced Outboard Bearing

XHAUS'J;' FAN OD-0919 Bearing .

~HARCOAL FILTERS Corrective Paint on Filter Filters Need Replaced Filters MD-797 . ' Unit'Boxes_ Changing fo. 11 FILTER UNIT Corrective Temporary Filter RF Filters Has High* Replaced Filters &. Vacuumed OD-2558 & Debris in Unit Diff Press Across Out Them

• * * .* -SAFETY REJ!~rED EQUIPM'1T*

Mechanical and Electrical Maintenance , .. I NATURE OF LER OR OUTAGE EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION

... VENTILATIOJ AUX BLDG EQUIPMEHT No. 11 & 12.SUPPLY Preventative Equipment Grease Fittings Installed Grease Fittings BLOWERS MD-326 D~ficiency Not Installed*

LOUVER COVER PLATE Corrective Equipment Relief Doors Removed Doors MD-456 Problem Blocking Back Draft Dampe+s VENTILATION - AUX BLDG, PENETRA' ~ION,

. '(CONTROL .AR A) . & . SWITCH .GEAR -1~

No. 11 AUX BLDG Corrective Cracked Adj Nut Cannot Adjust Replaced Adjusting Nut EXHAUST FAN MD-892 _-

No. 11 AUX BLDG Corrective Belts Loose Contact Ground Replaced Belts.

EXHAUST FAN OD-2693 No. 11 EXHAUSTER Corrective Replacement . Replacement Replacement Made HEPA FILTERS ALL SU-422 Needed* Required No. 11,12,13 EXH Cprrective Replijcement Replacement Replacement' Made FILTERS SU-356 Needed Required SUPPLY & EXHAUST Corrective Replacement Replacement. Replacement Made .

BL~WER MOTOR SHEAVE MD-7°66 Needed Required No~ 13 ROLL-0-MATIC Corrective Scaffolci_Plac~d Would Not Permit Removed Scaffold .

FILTER SU-271 Up Against Roll Roll to Roll 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 Corrective Limit Switches No Start Lights - Adjustment of Limit Switches FAN DAMPERS OD-2488 Not Operating No Stop Lights

~---------_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 i

No. 11 & 12 EXH Corrective Damaged Need Replacing Replaced FHB Exhaust HEPA 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.;

• ** * .. **

• SAFETY RELft.ED EQUIPMiflh.

• Mechanical and Electrical Maintenance

,.,*;

NATURE OF LER OR OUTAGE . MALFUNCTION RESULT CORRECTIVE ACTION EQUIPMENT MAINTENANCE NUMBER CAUSE '*

VENTILATI01 REACTOR'CONTAINMlNT LUG Corrective Modification. ECN M-18440 Installed by qE&C Piping MD,;_0591 PEDISAL' Corrective Weld Failure ** ' ~emo PSE-245

• Weid.

• Repait'ed*

MD-0539  : (" ...

CONT VENT Corrective Investigatioll .Holes in Vent *

• Repafi.-~d:* Hpr~~-: .. :

MD-0457 *:.......... * **' *:/ *; . ::;...:; '. . '*

• .* '* **:*;:, ** .* I

-:~~~~~-,.-~~-+-__,.__;_~__,.__,.__,__,.-f-__,.-,.-~__,.~~~'--~....+~-'--~--'--..;_;_~__,.~+-~....,-~~__,.~~_;.;.,_.....-+-~~._;.;.~~..,,..,,,.~.~.....,...,....,,..~__,,~....,.--~.- . ....,.,;.,-.*

14 .com~ FAN coot.ER. .corrective Motor Malfunc"- Trip~ Out .*A<lJust¢d* Ifa,mpers OD-3809 tion*.. 'I * **** .* * * * * ***** * *.:*:.':** *" *  : _._ ......

l*'*

l4 'FGU' MOTOR . corrective Gasket Blown COOLING UNIT OD-3443*

13 & 14 FCU Preventative Motors Disc;on- Motor Sent Out For Motors Rein~talled ~

MD-0277* nected Repair Checked 15 FCU Corrective Fan Problem Trips Out Sent *to Westingqouse OD-2079

• and Sent.Back Corrective Ruptured Line Leak of SW Installed Flex Connections OD-2940 from No. 2 Side.

Corrective Diaphragm Leak Replaced Diaphragm.and OD-2931 Malfunction 0 Rings Corrective Oversized*Keys Needs Replacing Replaced Keys & Test~d MD-0186 1

• ** * *sAFETY REL~ED EQUIPMEfr

'Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE . MALFUNCTION ..

EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION

. . VENTILA TION CONTAINMENT*

ONT HVAC 47 Corrective Switch Needs Set New Setpoint Switch Recalibr!;lt:ed*

MD-0515. . .. . . . . . . . . ... .. New Setting . ...

5 FCU Cor.rective Motor Switched* Old One .set Out Repl.aced .Mo1;9r .

with 1122 .

~

MD-0278 {1/12) fl4 FAN* Corrective Bad Bearings Fan Vibrations Bearfrtgs Replac~d and

. . MD-0419 . .

aaia~ced

.. * ;., .****.

Fan<*...

• C1 & VC4 Corrective OD-2721 Defective Bu]_b Trip *...',*.

.Rei>l~ced L:f$J:it. Bulb.

... ~: . ..  :.. .

• .

1VC1 to 1VC6 Corrective Valves Tested Defective Valyef? * *switch with Unit 112 Valves'*

.. *- MD-0635 . . ..

.\

SOLATION,VLV 1VC4 Corrective Valve *won't Close Va1ve *stays Open Replaced En.tin~ Valve From.

OD-2384 , Unit Ill .

VC5 & 6 Corrective 'Qesign Change ECN M-7729 Change ]flange MD-0707 12 vc VALVE Corrective Flange Needs Slip Too Large Safety Cut Down Safety Flange

. MD-1066

Cage and* Reinstalled WASTE DISPOSAL GAS H2 WASTE GAS COMP* Corrective* Possible Blockage System Operation in Removed Check Valve - Checked SU-240 Question for Debris & Proper flow -

.. I Reassembled 1ALVE 1NT24 Corrective Rust & Foreign Valve Leaks Thru Disassem~led Valve, Cleaned*

PD-1491 Matter on Seat and Reassembled

• * * * *sAFETY RELfrED EQUIPME'T * * *

• Mechanical and Electrical Maintenance NATURE OF LER OR OUTAGE MALFUNCTION

, CORRECTIVE ACTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT WASTE DISPOSAL GAS VALVE 1WG66 Corrective BA Eyaporator Operation of Evap...- Removed Bonnet of 1WG66 to OD-4056 Not Venting orator not as Spec Veµt Gas, Made Repairs to I Properly States Valve 1WG70 to Correct

• .i

... ..* Problem VALVE 1WG6 _.., *Corrective Plastic in Line :flow thru Valve Disassembled Valve &

OD-2718 Restricted Removed Piece of Plastic -

.' .. Reassembled Valve VLVS 1NT25 & 26 Corrective Leakage . Between Valves Will Not Relapped Seats on Both SU-0140 .. Seat .& Disc Pass Leak Test Val yes VALVE 12WG24 Corrective Possible Valve Lifts at Wrong Removed Valve & Bench Te$ted SU-262 Improper Setting Pressure* Valve Lifted Within Specs VALVE lWG?O Corrective Spring Tension Will Not Allow Made Adjustment to Spring SU-280 on Check too Passage of Gas at to Allow Proper Operation High

. . WASTE DISPOSAL LIQUID No. 1 SPENT ;RESIN Corrective Malfunctioning Strainers Replaced &

STORAGE TANK SU .... 228 Strainers Welded in Place 4KV VITAL I~ FEED BREAKERS Corrective Improper Design Certain Buses Do Not System Redesigned & Changed MD-0272 Auto Switch in to Allow Auto Switching to Blackout i f Certain Diesel Power Source with Events Occur Loss of Voltage

• . *sAFETY REtfrED EQUIPMjT * ..

...  ;

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 .

4KV BKR . SU-402 .. Spring .Bearings

• Operate Correctly Spring Bearings* ..

• 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 . -.

oD~3619 Not Correct - .

-, J 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 1128: 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 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 ..

• .* SAFETY. RELAED EgUIPMifr ** * * ** ' -'

Mechanical and Electrical Maintenance .. .'

NATURE OF LER OR OU'I'.AGE MALFUNCTION '

EQUIPMENT MAINTENANCE NUMBER CAUSE I RESULT CORRECTIVE ACTION

• SAFEGUARDi EQUIPMENT CONTROI TEST EQUIPMENT ECN C-16240 MD-193

'i SEC.CAB lA,lB,lC ECN C-16338 MD-352 ..

I ..

I

• ** * * ~SAFETY REL!!-ED EQUIPME~

Instrumentation and Control Equipment Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NuMBER CAUSE RESULT CORRECTIVE ACTION AUXI ,IARY FEEDWATER I AUX FEED WATER PUMPS Preventative Faulty Logic In Malfunction Of Retest as per ECN C-16237

• I MD..:..0315 Control Circuit Equipment

. BUILDING & EQUIPMENT DRAINS I

NO. 11 SCREEN WELL . Corrective Faulty Control Pump Runs *Remounted Displacer on Level SUMP PUMP OD-4066 .. Device (Level) Continuously Device SERVICE WATER SUMP Corrective Faulty Level Pump Runs Replace Adjustment Screw on I

I PUMP NO. 1 BAY OD-2689 Control Device Continuously Level Device NO. 11 SCREEN WELL Corrective Faulty Level ],"ump Does Not. :Adjusted Contacts on Level SUMP PUMP OD-2377 Control Device Start Device I

SERVICE WATER SUMP Corrective Faulty Level Pump Does Not *Cleaned Switch Which was PUMP NO. 1 BAY OD-2743 Control Device Start Corroded SERVICE WATER SUMP Corrective Faulty Level ~ump Does Not :Adjusted Level Device &

PUMP NO. 3 BAY. *oD-2302 Control Device Start *Tested

- C:ULLED WATER EX. TANK LEVEL Preventative Refer to: System Modifi- ~ys~em Modif i,,,. *Added Alarm as Per ECN C-16278 MD-561 ECN C-:-16278 *cation Needed cation Done (PT3771 & PT3773) Preventative _System Modifi- ~ystem Modifi- -Welded Adaptors on Valves to 11CH9 & 12CH9 PD-1466 *cation Needed cation Done

• Allow Placement of Instruments

• * ** * ** " esAFETY.

REL/4ED EQUIPHEI9 Instrumentation and Control Equipment Maintenance NATURE OF LER OR OUTAGE MALFUNCTION NUMBER CAUSE RESULT CORRECTIVE ACTION EQUIPMENT MAINTENANCE

'RESIDl IAL HEAT.REMOVAL 11RM29 Corrective *'

Pushbutton Valve Will Not* Repaired and Adjusted 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 C VITAL INSTRU.

. Corrective Short Citcuit Fuses Opened" Replaced Components NVERTER -* OD-2901 .. .. . .. i

. I .

~

.

1N1J~UMENTATI~ AND CONTR'j- CORRECTIVi MAINTENANif LER OR OUTAGE MALFUNCTION .

WORK ORDER NO. . NUMBER CAUSE. . RESULT CORRECTIVE ACTION I EQUIPMENT

\

ANEL*40l-l REDUNDANT AIR PD-1285 Leaking Diaphram Air r;fot Switching Replaced Regulator EGULATOR TO SU-165 & V-1CC149  ;

• • ,J>

U_* .*

EACTOR PROTECTiON CHANNEL PD-1286 Functional Test Recalibrated Trip lLT-518 Out of Spec Points for 1LC518A

.. & 1LC518~

ADIATION MONITORING SYS 1RR3.

• PD-1316 Interaction Bet- Intermitteµt Neeq Independant ween Recorder ancl Al~rms Power Sµpply

.;

,, Recommended

• Al~.PllS -  :\~....

-~

.. "*;:"*:*~

,_ ..,..-

.***. .~

I AIN STE~ TRA~SMirTER lFT-523 PD-1322 TranslQitter Extreme Z~ro Replaced Transmitter

. . . . . . . . . ... Malfunctioning . Shi'ft.

AFETY INJECTION - REFUELING PD-1324 Level Device Out Incorrect Level Calibrated LT-921 \

ATER STORAGE TANK LEVEL . . . . . .. . . of . Calibration .. & LA-5905 !B I

AFETY INJECTION ~- REFUELING PD-1325 Level D.evice Out Incorrect Level Strapped 1LC-920C ATER STORAGE TANK LEVEL ' of Calibration " & Performed Loop Che*

ONTAINMENT VENT VALVES PD-1329 Lack of QAF19 TDR-075 Replaced Valves VC1;2,3,4,5 .. for Installed Vlvs ASTE DISPOSAL - RMS ALARM LIGHT PD-:"1330 N/A. . . N/A . .. .. Perform ECN 16363 EED & CONDENSATE 12BF40 SU546 PD-1335 Solenoid Valve Not Valve Leaks Past Replaced Valve Seating Correctly Seat Internals EED & CONDENSATE 11BF40 SU548 PD-1336 Solenoid Valve Not Valve Leaks Past Replaced Valve Seating Correctly. Seat Internals PCLEAR INSTRUMENTATION N31 PD-1343 Connector in Failure of Channel Wrote DR-0224 SOURCE RANGE Penetration Bad

~2 STM GENERATOR STM FLOW PD-1345 Transmitter Excessive Zero Replaced Transmitter TRANSMITTER FT-522 Malfunctioning Shift & 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~

EACTOR 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* .. *: '. s11i£t ... . .. . " .. .& Recalibrated

' 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 Retaining Spring Valve/ *Won "t Open

.I Reconnecte<;l Spring 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 I

10-,14-76

• *

• IN~RUMENTATI~ AND CONTR~ CORRECT!~ MAINTENANlli! * *

• e,.

I LER OR OUTAGE MALFUNCTION I EQUIPMENT WORK ORDER NO. NUMBER

• CAUSE. RESUL'.f CORREC'PVE ACTION I 4 T. PROTECTION TE-421 A/B PD.;...1398 Signal Isolator 1TM421G Bad, &

Functional Te~t BS422D Out of

- Replace Signal 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 N43 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 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

• * * * . *

• f INS'fRUMgNTATION AND CONTROL CORRECTIVE MAINTENANCE

.LER OR* OUTAGE MALFUNCTION EQUIPMENT WORK ORDER NO. NUMBER CAUSE *. RESULT CORRECTIVE ACTION SAFETY INJECTION #12.ACCUMU- PD-1487 N/A N/A Reset High & Low I LATOR LEVEL TRANSMITTERS Setpoints for ~T-931

. & .LT""."935B . .*

SI #13 ACC~LATOR LEVEL PP-1488 N/A N/A -Reset High &,Low TRANSMITT.ERS Setpoints for LT~~3l

...  ! & LT-935C SI #14 ACCUMULATOR LEVEL PD-1489 N/A N/A Reset High & Low '

TRANSMITTERS Setpoints for L+-931

... .... .... ........................... ... .. . . . . . . . .. . . . . . . . . . . & LT""."935D . . I

~~~--..~~~__,.~~~~~~-1-__,._,,,~~--..--..--..-+o--..--..~__,.__,,~--f~~--..~~--..~--..-+---..~.....,......-...--~~--t--__,.~__,,__,,~~~~-

RP CHANNEL lFT-542 PD-1493 Functional Test Completed Channel Out .of .Spec .. ** Calib. Check FEEDWATER 11 & 12BF19 Valves PD~1so2 Solenoidei Not Valves Not Closin ~ Replace Soltmoids

..* .* . . . . . sized .Propei1:Y . .in.Time.Allowed FEEDWATER 13 & 14BF19 Valves PD-1503 Solenoids Not Valves Not Closing Rep.lace Solenoids.

.S:i.zed Properly. in Time Allowe<J REFuELING WTR STORAGE'TK.LEVEL PD-1514. * .Grou.nd Problem Level.Indication Calibrated 1LT~921 INDICATION & *ALARM**.* *. *: *.*.: ... in Annunciators is Different by & Cleared Grou~d

& Inst. Out of 3 1 & High Alarm

. .Calibration . is .Alarming .....

REACTOR PROTECTION* CHANNEL. PD-1517 1FC540 A/B Setpoint for Reset 1FC540 A/B

• FT.... 540 '

• Output 112 Out of FC540.A/B Out o~ Output 112

'. Calibration Spec ..

CONTAINMENT VENT 1VC7 thru 1VC14 PD-1521 Limit Switches Valves Not Replaced Limit Switc Solenoids & Operating Proper- Solenoids & Tubing

.Tub:i.ng in Error ly.. . . . . ......... Restroked Valves

• -11-.

---

**--~~---------

• *

• IN8rRUMENTATI~ AND CONTR~ CORRECT!~ MAINTENAN4J' LER OR OUTAGE MALFUNCTION

~QUIPMENT WORK ORDER NO. NUMBER CAUSE RESULT CORRECTIVE ACTION MAIN STEAM FT-541 PD-1525 Trip & Reset Furictional 'fest Recalculated Trip &I Points Not Cal- Out of Spec Reset Points

• cu,lated Correct- Functional Test* .. iµ ly Spec.. ..

NUCLEAR IN~TRUMENTATION PD.:.1527 Noise Sporatic Spiking See PD Work Order N3:J_ & N35 .on.Channel Nll : ... PD~l558 eve lMCllOB PD-1550 Servo S~tpoint Setpoint Does Not Replaced Servo

Amplifier Failed Track ~roperly in Setpoint's Amplifie Manual Adjusted Gain & *

................................... -,* .. * .. -.* .'. *:-.* . .* .* ..* .. *: * .*cai .Pot... . ....

CONTAINMENT'VENT 1VC6 PD-1551 N/A Remove & Repl~ce Tubing & Solenoids_

. . . . . . . . . . . . . . . . . for Maintenance REACTOR PROTECTION LOOP #13 PD-1557 *Summator & Lead- Functional Tei;t Recalibrated Summat AT/TAVE Lag & Function Out of Spec* Lead-Lag & Functio~

Generator Out of Generator

.. Calibration ....

NUCLEAR INSTRUMENTATION PD,-1558 Inner to Outer Sporadic Spiking Shield Resist-ance Reading Out

.Qt; .Spec .Low. . . ....................... .

SAMPLING 1SS107 PD-1559 Open Limit Switch .Will Not Stay Rea4justed Limit

. . . . Constantly Closed. Closed .............. Switch & .Cycled Val CONTAINMENT VENT 1VC6 PD-1561 Ground on Limit Low Ground Reading Replaced Cams & Mic Sw:ltches Switches & Restroke Valves NUCLEAR INSTRUMENTATION N36 PD-1563 Noise Problems Problem Cleared Whe INTE~EDIATE RANGE ON *N36 SUR CU Cable was DiscoD nected at the Detector

• IN~RUMENTATicf AND CONTRlf. CORRECTivf MAINTENAN~.

• LER OR OUTAGE MALFUNCTION EQUIPMENT WORK ORDER NO. NUMBER. 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 PD-1567 1PC948B/E Power Recorder po~s Not Replaced Capacit.ors CHANN III Supply Capacitors Read Zero*Psi & Recalibl'.'ated

.Failed. . ..

. REACTDlLPROTECTION*CON!E-P.RESS PD-1568 Sensor *PT~948C Transmitter Output Completed Sensor CHAN II Out of Calibra- 43mu Low .

• Calibration

.~i:ioii ... ** ** .. * ** ** ...... *.**.* . ** ** . *~ .* . *: .. -~ .* . *.**~ . **

. REACTOR PROTECTIQN CONT PRESS PD-1569 Sensor PT-948D Tr.anslllitter Output Completed Sensor CHAN I :out of Calibra- ~~~. ~ig~ C~libratio~

... _.. : .* . *. : . : .' .. _.. _. .. _.. _. .. * .:ti.on* ... _* . *.: ** . *.* * .. .. ..

NUCLEAR INSTRUMENTATION PD-1572 *Low Inner to WO Specified to*~ea~

. N32 &N36 Outel'.' Shield Cables Only

. . . . . . . *.* .* ..:Resistance. : ....* . ** .* . *: *: . *: *: . ..... *: .....

NUCLEAR INSTRUMENTATION PD-1573 Bist_able Out of Functional Tes~ Reset NC308 PRN43 N~3 ..... Calibration. Out 'of .Spec Bistable REACTOR COOLANT CHANNEL PT-405 PD-1585 Cold Solder Indication is. Fixed Cold Solder Joint on Indi-. Erratic Joint & Calibrated ca tor *Press Indicator &

TraQ.smitter NUCLEAR INSTRUME~TATION NEUTRON PD-1587 Bad Neutron Replaced Neutron DETECTOR FOR N31 & N35 . Detector Detector NI SOURCE & INTERMEDIATE RANGE" PD-1593 N/A N/A Removed & Cleaned N31 & N35 DETECTORS Detectors & Reinsta SAFETY INJECTION PANEL 235 . PD-1597 Salt Water ~.: .

Cleaned Panel ~

. . Deposits . . . . . . . .. . . . . . . . .. ' .... . . . .Components ..

SAMPLING SYSTEM PANEL 245 PD-1598 Salt Water Cleaned Panel &

Deposits 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 I

RM 1Rl3 & SAMPLER PD-1602 Ruptured Liner tea~ing System Replaced Liner &...

& Faulty 0 Rings .. 0 Rings.*.

CONT VENTILATION 1VC6 PD-1604 Salt Water Cleaued Salt Deposi Deposits from Tubing, Soleno

. . . . . . . . . . . *. *, . . . . . . . . . and Terminal Boxes I

CONT VENTIL!TION 1VC2 & 1VC3 PD-1605 *Salt Water Cleaned Salt Deposi

Deposit El from Tubing,Solenoi I

I

. I

. . *' . . . . ..... . . '. ....*' .... . . . .. . ... & Termin<!-1 Boxes i

PRESSURIZER.RELIEF 1PR15 & 1PR17 PD-1606 .. . ..

salt Water , ..j *. ,'.. .. Cleaned Salt Deposi

. . ... . . . . ' . . . . . . . . . . . :Deposits . . .. . . . . .. *.i . . . . . . : . . . . . . . . . . ..

.. ' )I CONTAIN VENT & SI PANELS. PD-1607 Water .. '. 1/ i No Water Damage

. . . . . ... .. I'i* ..... ** I ......... . .Found I

SI PANEL 2*41 & JT-479 PD-1609 Salt Water . N/A ./ ..

Clean Panels &

. . ... . . . . *r. *' .. .. . . . . .. . :Components .....

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.* ....... . . . '

\

SERVICE WATER 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

• *

• 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 I

-- ------ ... . . . . .b~ation .. . . . . . .

---

.---- -----*~

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-brat ion Out.of Spec Extractor 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 RADIATION MONITORING SAMPLE VLVS PD".""1833 N/A . N/A ii: I Tighten Solenoi4 1VC7 Thur 1VC14

• i l

I Valves Mounting rlates 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 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 I

i

.of .Calibration Out of Spec I

I

(..

• INIJRUMENTATI<lf AND CONTR9. CORRECTI\9 MAINTENAN. * * ('.'t LER OR OUTAGE MALFUNCTION

• WORK.ORDER NO. . NUMBER CAUSE RESULT. . CORRECTIVE AC'.f ION EQUIPMENT '

SW /Ill HEADER PRESS TRANSMITTER PD--1856 PA-2747-Z .. ... ..

Replaced & Cali-

. . . ' . . . . . . . . . . . . . . Failed. . . . . . .. . . . . . . . . . . . . . . .. . . . . . . . .brated.PA~2747~z 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 Remove .Spacers

N/A N/A

............... ' . .. & 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~

• • * * . Il'jl'RUMENTATI'if AND CONTRjL CORRECTIW MAINTENAi'Wi LER OR OUTAGE MALFUNCTION.

EQUIPMENT WORK ORDER NO. NUMBE~ CAUSE. ~ESULT lFT-532 PD-2016 Out of C~libr~tio1 F~ncti9n~l fest Per:forme<J Calibratj

. . .-oiit .*of .spec.- .... *. .C:hecks. . .....

lFT...:444 PD-20.p Def ectiye Indicate~ 60% :flow Performed Calibratj Transmitter Checks, Issued w.o llPD-2030

.M~lA'llON.-.MONITORING--.llU3A. *** PP-2018 D~f ective Rate Out of .Spec Performed C~libratj Card PB3 Checks~ Replaced Rate card PB3

• LT-1'~88 I PD-2021 :cannot Determine LT-1688 lnstrumen~ Heat Tracing Sat,

' Perform Calibratior

. ~ . . . .. . . . .. . .

Line Freezing

• Checks*

lFT.;.53:i .PD~2022. .. *.* ...... N/A: .. .Out .of :*spec. None Required

.lFT-446 PD-2029 .. .Out of Calibra- Performed Calibrat:l

. . . . . tion.

lFT-444 PD-2030 .... Zero Shift .. .. .~a~~ot C~lih.rate :Cnstalled New

. . . . . . . . . . . . . ...... Transmitter .

MAIN TURBINE SSPS PD..:.2032 Out of Calibra- Out of: Spe~ Performed Cal~l>rati

. . . . .tion. .. Checks lFT-435 PD-2033 .. ' Out o:f C~libra- Out of Spec Performed Calibrat~

.tion Checks lFT-445 PD-2034 Out of Calibra_. Out of Spe'? Perf orme4 Calibrati tion. Checks lFT-434 PD~2036 Out of Calibra- Out of Spec Performed Calibrati

.tion . . .. Checks lFT-436 PD-2038 Out of Calibra- Out of Spec . Perfonµed Calibrati1 tion ' .. Checks.

• *

• I~RUMENTATI~ AND CONT~ CORRECT!~ MAINTENA~

LER OR OUTAGE MALFUNCTION EQUIPMENT WORK .ORDER .NO. NUMBER CAUSE. RESULT CORRECTIVE ACTION

~FT-414,415, & 416 PD-2039 Out of C!!libration Qut of ~pe<! Performed Calibrat:f 1

.............. Checks.

lFT-425

• PD-2040 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. . . .N/A ... . ...... N/A .... *., ........ . Cal. Due I

FEED SYSTEM ~~* 12, .SGFF Cal. Due* I FEED SYSTEM NO. 13 SGFF. . ....... PD-:'2051 ........................ . N/a* ........... :*.*. *: .. *.N/A ............... . . Cal. Due FEED SYSTEM NO~ 14 SGFF* .N/A ...

. f Cal *. Due Out of Calibratior O~t o~ Spec 1

lTC-421 G/H PD-Z060 Performed Calibrati I. Checks I I

lFT-531 A&B *PD-2066 Out of Calibratior Out df Spec Performed Calibrat:IJ

..... / '.... *........ . .Checks.. I I

lFT-415 PD-2069 Leaking Sensor Intermittent Low Repaired Lea~s on Line Flow Alarm High Pressure Senso Line LT-538 PD-2081 .Defective.LT-:'538. Drifting Replaced Unit NIS-N44 *PD-2085 Out of Calibratior Upper Flux Amp Performed Calibrati Output Out of Spec Checks RADIATION MONITORING CONTAIN. PD-2086 Defective Low Low Speed Does Replaced Low Speed VENT APD Speed Drive.Motor Not.Operate Drive Motor lFT-424 PD-2107 Defective Bulk- Leafing in Panel Replaced Bulkhead head Fitting. .Fitting

• ** IN.RUMENTATI~ AND CONTRIA CORRECTiva MAINTENAN.

• * (lj.

---,--.-----~

LER OR OUTAGE MALFUNCTION

~QUIPMENT I

WORK ORDER NO. NUMBER CAUSE RESULT ~ORR~~~VE ACTION 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-

tion . . .

OQ~

of f!pec Performed Calibrat:I 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 Erra 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 Calibra- 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 1113 Stm Geµ Level Performed Calibrat 1LM-500Y PD-2207 . Out of Calibra-:-

.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-::-*

tion Check

'.'.'"82- I ' - - - ---- - - - - - -

• • **

• lNtl!'RUMENTATIC. AND CONTRe. CORRECTI\9 MAINTENANtl!: . **

• LER OR OUTAGE MALFUNCTION WORK.ORDER NO. NUMBER . CAUSE RESULT CORRECTIVE ACTION NIS N41 POWER RANGE PD-2224 R354 Had Inter- Negative Rate Replace~ Rl54 mittent Open . Tr:(.p .Won't .Lock*. I11 SERVICE WATER 15SW57 PD-1928" Clevis Link Needs Rework 15SW57 ***

. . . .......... Replacement . .' ..... .

REACTOR PROTECTION CHANNEL PD-1933 .1QM-204A Failed Functional Test *Replaced 1QM-204A TE-411 A/B .Ou~ .of. Spec ..... . Adjusted 1TM-441A RADIATION MONITORING Rl4 MONITOR pn.:..1941 N/A. Install Detector Adjust H.V.

RADIATION MONITORlNG RllA,12A, PD-1942 * *Sheer Pin :f.n Filter Failµ-.:-e Replaced Sheer Pin 12B *" :Drive Mechanism Alarm

• . . . . . . . 'r . . .. :sheered ..

AUX FEED #13 AUX FEED WTR PUMP pn.:..1947 *Governor Oil 'Sieed Contrpl Vented Governor

Level.High & Air }fimti°'1g I . .

Oil System

. . . . * ...* . .:Present <.. .' .' .*: * ..... j . .......... .

Ql2 ST~ GEN LEVEL CHANNEL I PD-1949 I

Chanflel :f.s.

.... ** ......... .'Err,~*ic*: .. '. ...... .

MAIN STEAM 14MS10 PD-1951 . Power Supply Valve Does Not Replac*ed Power

. . . ... Failed : ..........* .. Work. in. Auto .. * ..... Supply .DR//PD0293 REACTOR PROTECTION CHANNEL PD-1954 Comparator Out Functional Test Calibrated the FTf543 of Spec Out of Spec Comparator I

lFC541 A/B

1. 11 AUX FEED FLOW TO 11 STM PD-1955 Wires Disconnect- Loss of Indication Reconnected Wires GENERATOR ed From Trans. to on.Console

.Sq, ~oot Ext.

• REACTOR COOLANT PANEL TRANS- PD-1960 No Tape on Vent; Leaks Taped Vent Plugs MITTER FITTINGS . Plugs. *:. ...*....

• *

• INJ!RUMENTATIO, AND CONTR~! CORRECTIV, MAINTENANC' *

• LER OR OUTAGE MALFUNCTION EQUIPMENT WORK ORDER NO. NUMBER CAUSE . RESULT CORRECTIVE ACTION 13 AUX FEED PUMP PD-1964 1MS132 Restricted Speed W:J,11 Not. I

.. Steam Flow. . . Increase > 2000~pm I

\

AIN STEAM lFT-540 PD-1983 lFT-540 Out .of . Functional Te~t P~rf ormed Channel Calibration Out of Spec Calibration ADIATION MONITORlNG 1Rl4 PD-1985 Detector & Preamp failure Alarm Replaced Detector *~ 1

.. Failed. . . . . . . . . . . . . . . . . . . . . . . Preamp ADIATION MO?UTORING lR.18 PD-1988 Clean & Dry-out *\

. I .

. Sampler & Connector ADIATION MONITORiNG l~i3B PD-1989 Relay Contacts Spurious Alarm Fixed Relay Not Mak:l,ng

.Properly.. . .

ADIATION ~ONITORING 1Rl3C PD-1990 . Top & Bottom 11 0 11 ~ampler Leak:f.ng Replaced 11 0 11 Rings Rings Need Replacement

~IN STEAM GAUGES PD-1993 N/A N/A Install Temp G~uges to Test;: Relief Valves 1

. ~

\. * * -. . *

• INSTRUMENTATfJ:ON AND CONTROL CORRECTIVE MAINTENANCE I

LER OR OUTAGE MALFUNCTION EQUIPMENT WORK ORDER NO. NUMBER CAUSE RESULT CO~RECTIVE ~CTION I SERVICE WATER 12SW122 OD-2705 N/A 12SW122 Will Not Stroked Valve Sat.-

. ' - ' . .Open ....

CONTAINMENT PURGE 1VC3 OD-2708 Wiring Error Valve Indicates .Changed Valve Limit

• , *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. *

supply Flow to Meet SP(O) See WOl/PD1S02 & 150~

- . '. ' - . . . . . . . . ' . 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-

INSTRUMENTATION AND CONTROL CORRECTIVE MAINTENANCE * * * *

• LER OR OUTAGE MALFUNCTION EQUIPMENT WORK ORDER NO. NUMBER CAUSE *RESULT CORRECTIVE ~CTION

~IATION MONITORING SAMPLE OD-2847 Valve Limit No Close Indica.,.. Readjusted Valve VALVE lVCll Switch out I

of tion Limit Switch Adjustment ..

1CC215 OD-2903 Valve Limit Valve Does Not *Adj'usted I.imi.t switch Switch out.of Cycle in~ 10 sec . Stroked in< 10 sec Adjustment ,

Now as Indicated on

. . . . . .. . .. . . . . . . . . . . . . . . . . .Bezel .

NO. 11 NOZZLE SUPPORT VENT FAN OD-2917* Limit Switch Sequence Complete Installed Limit Switcf Couplings Missing Light Does Not Couplings & Springs Energize . and Adjusted Switch RADIATION MONITOR 1-RllA OD-2926 High Concentra~ Hi Rad.Alarm None Required tion of Welding Cannot Be Reset I Particulate in *

.. Sampler .Area. . . . . . . . ' .

c PANEL 241-1 *'

OD-2938 N/A S~lt Water in See WO#PD1577,1585~.

Panels & Ground 1607, & 1609 ..

PANEL 2l5*' "*:. *oD-2939 N/A Salt Water in See WO/IPD1597 Panels & Ground . . *'

12SW49 .. ..

.. OD-2964 Worn Ring Seal Valve Leaks Thru Replaced "Sea1 Ring &

" . .,., ., Restroked OVERHEAD ANNUNC~TOR POINT n.:..12 OD-2985*'* Blown Fuse Boron Inj. Tk. Replac.ed Samp Fuse on High Disch Press lPC-942

.Alarms lPI-403 OD-3002 Defective Signal Hot Leg Pressure Replaced 1PM403D Summa tor 1PM403D Loop II not

.. Indicating

. . . . . ..... . ' . . . .correctly . . .. . .

• *

• IN~UMENTATIOJ.9AND CONTROitCORRECTIV~INTENANC~ * *

• LER OR OUTAGE MALFUNCTION EQUIPMENT WORK ORDER NO. NUMBER CAUSE RESULT CORRECTIVE.ACTION 1CV172 OD-3004 Controller lFCllC lCVi72 Hunts .Tuned Controller was not Tuned to Dui'ing Auto lFCllO While in

. . . . . .**:;. .

. . . . . .. . . . . tl\e System .Op~ration . Service.

SI - COLD LEG INJECTION FLOW OD.,..3359 . Blown Fuse Indicator Failed Replace* Power

---

*-*- - - .. -. ~*----*-*'---~~"--**---- ... Dowri Scale . . . . . .Supply Fuse

-NOo-l--l-GHI-bL-ER.-- * - -- --*---* ** OD-3370 Vlv 11SW92 Limit Will Not Run Readjusteq 11SW92 Switch Out of Valve Limit Switch

• Adjustment 15swe23 OD-3372 :Defective Valve Valve Causes Replaced Valve

.Flow.Oscillations 1WL16 OD-3375

• Open* Limit Switcl V~lve Will Not Reset Opening

Out of Adjust- ... Stay Open Limit Switch

. . . . . . . . . . . . .ment . . . \. . . *' .. . . . . . .

NO. 15 FCU DRAIN FLOW ALARM OD-3383 Out of Calibra- Energized All the Readjusted Diff.

. . . . .. tion . rime. * *. . *: .Contro:ller YIC-110 OD-3389 Out of Calibra- Boric Acid Flow Recalibrated Loop tion Register Does Not

.... . Indicate ** *

• 11SW49 & 12SW49 LIMIT SWITCHES OD-3396 Valve Limit Continuous Alarm Readjusted Valve Switches Out of Limit Switches

. .'Adjustment . .. *.*

PR948A & PR948B OD-3476 Out of Calibra- *Recorders Do Not Recalibrated Recorders tion Agree with Each Other .. * * .* ........ .

.NO. 11 BORIC ACID TANK TEMP OD-3516 Temp Transmitter Boric Acid Tk Tem1 Recalibrated Temp INDICATOR Out of Calibra- Indicates 15~ Transmitter ECN tion Hi~her. Low Temp Required to Revise

...... :Alarm. :Energized . .Alarm.Buttons

• *

• IN~RUMENTATiof AND CONTRO~ CORRECTIV~MAINTENANc:P * *

• LER OR OUTAGE MALFUNCTION EQUIPMENT WORK ORDER NO. NUMBER CAUSE RESULT CORRECTIVE ACTION 1PR18

• OD-3521 Valve Limit Switcl Valve Position Removed Bonnet,Tighte~

Out of Adjustment Indication Does Diaphram Stem Locknut. 'I Due to Loose Vlv. Not Work Restroked & Set ~imit

.Components. Switches .

VITAL HEAT TRACING OD-3537 Pipe Insulation Recorder Temp Does Equipment Sat. Pipe to Missing at This Not Agree With be Insulated Later Time Local Temp Indica-

.tors NO. 11 NOZZLE SUP~ORT FAN OD-3538 Defective Limit No Sequence Repaired Limit LIMIT SWIT:H. . ..... :*: ... : : .*:* ... :S~iicih: ... complete . Light .... Switch NO. 12 STEAM GENERATOR OD-3553 Out of Calibra- Feedwater Flow Recalibrated Recorder tion Recorder Indicat~

,. . i#g

., *wrong Flow.

SOLID STATE PROTECTION SYSTEM OD-3568 No Power.Avail- IhitiJied IC SEC APB Initialed able to Test Sys. Actuation Circuit. Design When rrs602,TS604,

.Deficienci~ .. *'. &.tS~lO in:Test.: ..

1SS49 OD-3571 Valve Limit Val.Je Will Not Disassembled Valve to Switch Out of Stay Open. No Vlv. Tighten Locknut.

Adjustment Due to Position Indica-,. ': Stroked & Readjusted Loose Vlv Compon- tion Limit Switches

.......... ents ..... .

RADIATION MONITORING lRllA OD-3582 Check Source Indicates High Lubricated and

... : .. * .~olerioid ~iucik .Radiation Levels . . Recaiibrated Detector 12SW40 OD-3624 L6ose P~cikiiig:Nui .Air:te~ks ........ . Tightened Packing Nut SV541 & SV553 OD-3625 Worn Internals Air Leaks Replace Solenoid 'I Valve Internals RADIATION MONITORING CONTAIN. OD-3650 Defective Gas Pump Failed Replaced Gas Pump VENT APD 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 Calibra- '\Wrong Feedwater Recalibrated Loop TO NO. 14 STEAM GENERATOR . . . . . .. *tion. . . . . . . . Flow* Indication .. . .

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 .. '

NO. 11 ACCUMULATOR LEVEL INDIC. OD.,.3815 Out of* Calibra- Wrong L.~vel Recalibrated '*

. . . . . tion . . . . . . . ' .... .. ' .... . ... 1LT935A  !

-89".".

INSTRUMENTATION AND CONTROL CORRECTIVE MAINTENANCE * * *

• LER OR OUTAGE MALFUNCTION EQUIPMENT. WORK ORDER NO. NUMBER CAUSE. RESULT CORRECTIVE ACTION PRESSURIZER CHANNEL I OD-3816 Transmitter Was No Indication Open Transmitter Isolated Isolatio~ Valves NO~ 12 RHR LOCAL FLOW INDICATION OD-3817* Incorrect Flow 12RHR29 Opened at Reset Low Flow

_Setpoint 300gpm Instead of Set point

- -* ---------------~----

• - ... ,. ---y------- . . . , ,. ._. . . __ .500gpm ... . .

1---voLUME-CbNTROL-TANKLOW --- - OD-3818 Defective Low No Low Pressure Replaced Low ,

PRESSURE ALARM Pressure *com- Alarm Pressure Comparator*

• arator 1CV3~

OD-3820 *Wrong Level Valve Does Not None Required

' :Observed by Divert on VCT System Working Sat.

. . . . . . . . . :Ope!ator .High Level ..

1FT425 & 1FT426 OD-3827 *Defective *,No Flow Indica- Replace Transmitters

... Transmitters. .tions NO. 11 AUX BLDG EXHAUST FAN OD-3838 Per Design Discharge Dampers None. Damper Do Not Close When Controls Independant

. . Fan. is Stopped

• of .Fan Operation 12AF21 Valve Positioner Valve Leaks Thru Restroke Valve artd Out of Cali bra- Adjusted Positioner tion & Tension *spring 1MS132 OD-3846 ~

Rupture Diaphram Valve Will Not Replaced Diaphram Close NO. 14 S.G. FLOW CHANNEL 2 OD-3860 Out of Calibra- Indicates 20% Recalibrated Loop tion Flow With No Actual Flow 14AF21 OD-3864 Valve Stroke Out Valve Does Not Readjusted Positioner of Adjustment Provide Tight Spring & Stem

• .Shut'"'."off

-90....,

• *

• IN~RUMENTATIO,.AND CONTR~ CORRECTIV1"MAINTENANC~ * *

• LER OR OUTAGE MALFUNCTION EQUIPMENT. "WORK ORDER NO. NUMBER CAUSE. RESULT CORRECTIVE ACTION I

RADIATION MONITORING 1Rl3B OD-3867 See WOl/PD-:-1990 . No Alarm See WO//PD-l990 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 :cator Bulbs Indication Did Not Bezel Bulbs, Damper Energize After SI Operation Sat.

. ... . . . . ... Operation *- - -

lBBDC BKR. 1119 OD-3883 *No Apparent '* Breaker Tripped Checked Out Sat.

Problem Durine SEC PRESSURIZER LEVEL CONTROLLER OD-3893 Out of Calibra- Getting Letdown Recalibrated Recorder tiori Isolation & Checked Trip Point ROD POSITION - ROD BOTTOM 2C2 OD-3958 Out of Calibra- 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 I I Indicating Higher ..

Than Normal I

. I

! I i

I

~

INSTRUMFNTATION AND CONTROI COHRECTTVE MAINTENANCE J

.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 I 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 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 &

. . . . . . . . . .. . .. . .. *.Set. Screw .. Recalibrated I

I MAIN STEAM - 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. . . . . .. . . ... . . . . . . . ..

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

• .* . . . . . . . .. ..... . . . . .. . .'I~istabie*. . . . . . . .. . Aiar~ Not Working 11CA330 SU-467 Out of Adjust-ment Does Not Provide Tight Shut-off Restroke Valve &

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 Calibra..,. 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 LER OR OUTAGE MALFUNCTION WORK ORDER NO. NUMBER CAUSE RESULT CORRECTIVE ACTION EQUIPMENT LD-2725 SU-342 Alarm Switches Screen Trouble Recalibrated Alarm

• Change Calibra- Alarms at Wrong Switche~ & Insta!led tion Due to Lack Setpoint Locking Devi<;:es ..

, ~.-

of Locking Device ....

LD-2726 SU-343 Silt Buildup Indicates 2.2H20" Blew Down Bubbler Inside of .SWI$ All The Time Tubes,Recalibrated P1;Jmp Cells & In~tal!ed Alarm Switch Locking Deyice SV-833 & SV-569 SU-344 Defective SV's Bay 1 SWIS Prop~ Repaired Solenoid

.Damper Does Not Valvei; Operate Thru Full

.si~oke.. . ....

SV-563

• SU-345 Open Coil , Df1,mper 1SWV8 Does Replaced Coil 1

Ndt Close When #12 S:W" Veitt.Fan Stops.

I LD-4729 SU-346 Alarm Switches Scree~ Trouble Recalibrated Alarm Change Calibratio1 Alarnis at Wrong Switches & Installed Due to Lack of Setp~int Locking Devices

.Locking Devices SV-.562. SID'-347 Open Coil Damper 1SWV7 Does Replace Coil Not Close When #11 SW Vent.Fan.Stops 1SWV3 SU-348 Binding Diaphram Damper Does Not Lubricated Diaphram

.Operate &.Restroked Sat.

1WR80 SU-174 SV507 Restricting Opening Time Too None. Valve Will

.Exhaust .Air Long. . . . . .. Close.in 2 Sec,

• *

• IN~RUMENTArrot AND coNrRcf! coRREcrrvftMAINTENANC~ * **

• LER OR OUTAGE MALFUNCTION EQUIPMENT WORK ORDER NO. NUMBER CAUSE. RESULT CORRECTIVE ACTION 1PR17 SU-175 Valve Limit Switch Will Not Stay.: Readjusted Valve Limi1.

Out.of Adjustment .. Cl9sed . . .. Switch.

1CC215 SU-176 N/A Bent Limit Switch Tightened Limit,,.

Actuator Rod Switch Actuator Rod

& Readjusted Limit

.Switches 1WL98, 1WL12, 1WL17, 1WL13, SU-188 Wrong Type Do Not Close in Replaced .Solenoid 1WR80; .Solenoid .Vaive . *: :.c:.10 Sec *...... Valves TA-745C SU-229 Out of Calibrq- Low Output at .. * " Recalibrated t:ion .120'F.

TA-6416,6417, & 6418 SU-307 Wrong Thermowell Output Responds Thermowells

.Installation Too Slow to Chill- Relo*cated

• ,ed Water Tempera- .

. ture *Changes ....

1WL7 SU-310 Leaking Diaphram Air Leaks Around Replaced Diaphram Valve Operator

.Head.

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 CUMULATIVE 301.6 Reactor reserve shutdown hours 0.0

• Hours generator on-line 40.3 Unit reserve shutdown hours 0.0 Gross thermal energy generated (MWH) 48697

• Gross electrical energy generated (MWH) 3230 Net electrical energy generated (MWH) 0 Reactor service factor N/A

• Reactor availability factor N/A Unit service factor N/A Unit availability factor N/A

• Unit capacity factor (using MDC) N/A Unit capacity factor (using design MWe) N/A Unit forced outage rate N/A

• -100-

UNIT SHUTDOWNS AND POWER REDUCTIONS Method Of <2 >

Type Shutting Down Reportaple F: Forced Duration The Reactor Or Occurrence Date S: Scheduled (Hours) Reason(!) Reduci:ng Power Number Corrective Action~/Conunents 12/25/76 F 33.7 G 3 76-1 Feedwater Flow in Manua1~12 Steam ~enerator Low, Low Level Trip~

• 12/27/76 F 7.4 H 3 76-2 11 Steam Generator Feed Pump Trip on Low Suction Pressure-13 Steam Generator Low, Low Level Trip.

12/27/76 F 11.6 H 3 76-3 12 Steam Generator Feed Pump Trip on Low Suction Pressure-11 Steam Generator High Level Trip.

12/29/76 F 61.3 A 3 76-4 12 Steam Generator Feedwater Regulating Valve - 12 Steam G~nerator High Level Trip.

(1) Reason: (2) Method:

A - Equipment Failure (Explain) 1 - Manual B - Maintenance or Test 2 ~ Manual Scram.

C - Refueling 3 - Automatic Scram.

D Regulatory Restriction 4 Other (Explain)

E - Operator Training and License Examination F - Administrative G Operational Error (Explain)

H Other (Explain)

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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 Supervisory Personnel Engineering Personnel

. 0 0

0 0

0 0

6 23 0

0 3

32 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 Maintenance Personnel 0 0 0 221 0 269 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 Suspended Gross Gross Disso.lved Solids Boron Lithium Hydrogen Silica Activity Activity Tritium Iodine-131 pH Conductivity *Chlorides Fluoride Oxygen At 25°G (umhos/cm) (ppm) (ppm) (Crud) (ppm) (ppm) (cc/kg) . (ppm) 15~ Min. 7 Day (µci/!111) (µCi/ml)

(ppb) (Ppm) (µCi/ml) (µci/ml)

-2 -3 *-5 MAX. 6.80 12.0 0.149 0.014 93 6.9 1974 0.69 28.8 1.8 2.8xl0 1.3xl0-4 5.lxlO 2.0xlO

. -5 -4 4.8xl0-6

• AVG. 5.75 6,16 0.079 <0.011 15 6.9 1244 0.49 12.5 0.93 3.3xl0-3 . 2.3xl0 8. 7xlO *

-8 2.5xl0-7 MIN. 5.40 2.72 0.026 <0.011 '<2 6.9 665 0.36 7.0 .27 7.lxlO-6 l.3xl0 -6 5.5xl0

-104-