ML19320A854

Responds to NRC 800502 Request for Info Re Pressurizer Safety Valves.Includes Data Taken During 800226 Incident to Assist in Determining Flow Rates & Conditioners in RCV-8 Relief Train.Test Results Will Be Sent When Available

ML19320A854
Person / Time
Site:	Crystal River
Issue date:	06/25/1980
From:	Richard Bright FLORIDA POWER CORP.
To:	Reid R Office of Nuclear Reactor Regulation
References
TAC-12961, NUDOCS 8007030242
Download: ML19320A854 (175)

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-GL t q. y ,. ~y Florida Power C O M P O R A f to 8e June 25,1980 File Code: 3.B.5-a Mr. Robert W. Reid Chief Operating Reactors Branch #4 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Crystal River Unit No. 3 Docket No. 50-302 Operating License No. DPR-72 NRC letter dated May 2,1980 Requesting Information Concerning Pressurizer Safety Valves

Dear Mr. Reid:

In response to the subject letter requesting in fonnation concerning Pressurizer Relief Valves, Florida Power Corporation hereby submits the following:

1. :

Data taken during the incident on February 26, 1980 to assist in determining flow rates and conditions in the pressurizer relief train containing RCV-8.

2. : Additional information that was sent to Gilbert Associates, Inc. for thermal analysis of the relief piping.

The GAI report will be provided at a later date when it be-comes available. The pressurizer code safety relief valves, RCV-8 and 9, have been re-moved and replaced by two new valves of the same type. Both will even-tually be shipped to Wle Laboratories for disassembly and inspection in conjunction with EPRI, Dresser, and Babcock and Wilcox. Due to the present workload at Wle and the EPRI test schedule for other valves in this same study program, t' examination of RCV-8 and 9 will probably not occur until July,198h Therefore, there are no results currently available. These will be r ovided at a later date. THIS DOCUMENT CONTAINS 8 0 0'h 030#/k POOR QUAlffY PAGES General Office 3201 Thirty fourin street souin. P O Box 14042, St Petersburg. Flor da 33733 813-%6-5151

- Mr. Robert W. Reid Page Two June 17, 1980 We would appreciate receiving a copy of your completed study when it becomes available. Should you have any questions concerning this subject, please contact this office. Very truly yours, FLORIDA POWER-CORPORATION R. M. ~ Bright Acting Manager. ~ Nuclear Support Services Lobo (T02)D1 Attachments

STATE OF FLORIDA COUNTY OF PINELLAS R. M. Bri ght states that he is the Acting Manager, Nuclear Support Services Department of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief. A R. Mt Bt igt/t Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 25th day of June,1980. P Notary Public i Notary Public, State of Florida at Large, My Commission Expires: August 8, 1983 L

J s e TRANSIENT ASSESSMENT REPORT REACTOR TRIP AT CRYSTAL RIVER - 3 NUCLEAR STATION ON FEBRUARY 26, 1980 (PRELIMINARY) CAUTION: THIS IS A PRELIMINARY REPORT. IT IS BASE 0 ON INCOMPLETE DATA AS AVAILABLE TO US THROUGH MARCH 1, 1980. THE INFORMATION AND CONCLUSIONS HEREIN ARE PROVIDED SUBJECT TO FURTHER VERIFICATION. Prepared By Nuclear Power Generation Division The Babcock and Wilcox Company Lynchburg, Virginia March 2,1980 Report No. 07-80-02, Rev. 00 Prepared By: Reviewed By: Reviewed By: Reviewed By: Reviewed By:

1 TABLE OF CONTENTS Page I. EVENT SYNOPSIS 1 II. PERFORMANCE EVALUATION AND RECOMMENDATIONS 5 A. Expected Plant Performance and Deviations 1. Initiating Cause Assessment 5 2. Loss of Instrumentation Function 6 3. Opening of PORY and Spray Valve 13 4. Control System Actions Before Reactor Trip; 14 Reduction of Main Feedwater 5. Reactor Shutdown 15 6. Initiation of HPI 15 7. RC Pump Trip 15 8. Closure of PORY Isolation Valve 16 9. Control of HPI 16

10. Safety Valves Relief 18 11.

Steam Generator Cooling 18

12. Core Cooling 20 13.

Restoration of Pressurizer Pressure Control 21

14. Restart of Reactor Coolant System Pumps 22 15.

Release of Radiation to the Reactor Building 22

16. High Sodium in Primary System Water 26 B.

Safety Implications 28 C. Conclusions / Recommendations 29 III. EVENT DETAILS AND INPUT DATA 31 A. Initial Plant Conditions 31 B. Plots of Major Parameters 31 IV. COMPONENT TRANSIENT. ASSESSMENT 33 A. Reactor Vessel 33 B. Reactor Vessel Internals 33 C. Steam Generators 33 D. Pressurizer 34 E. Reactor Coolant Piping 34 F. Reactor Coolant Pumps 34 G. Control Rod Drive Mechanisms 35 H. Safety valves 35 I. Fuel 35 V. REFERENCES 37 i lfh^ A

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i GLOSSARY OF ABBREVIATIONS dp Differential pressure del ta p EFW Emergency Feedwater ESFAS Engineered Safeguards Features Actuation System FSAR Final Safety Analysis Report HPI High Pressure Injection ICS Integrated Control System Loop A, B Reactor Coolant Loop A; side with pressurizer connected to the reactor outlet piping.

Loop B is,ne opposite side. MFW Main Feedwater MT Main Turbine NNI Non-Nuclear Instrumentation OTSG Once Through Steam Generator PORY Power Operated Relief Valve RB Reactor Building RC Reactor Coolant RCS Recctor Coolant System RCV Reactor Coolant Valve RPS Reactor Protection System SEM Sequence of Events Monitor Tave Average Temperature of the Reactor's Inlet and Outlet Tenperatures Tc Reactor Inlet Temperature Tcold Th Reactor Outlet Temperature Thot x Power bus which supplies 120 VAC and plus and minus 24 VDC to NNI instrumentation and control systems y Power bus which supplies 120 VAC and plus and minus 24 VDC to NNI instrumentation l l ii

e I. EVENT SYNOPSIS On February 26, 1980, Crystal River-3, Nuclear Station experienced an automatic reactor shutdown. This synopsis of key events and parameters was obtained from the plant computer's post-trip review and plant alarm sumary, the sequence of events monitor, control room strip charts, and the shift supervisor's log, as well as the sequence of events prepared by the Florida Power Corporation (see Section III). Prior to the incident, the reactor was operating at approximately 100% FP with Integrated Control System (ICS) in automatic. No tests were in progress and minor maintenance was being performed in the Non-Nuclear Instrumentation (NNI) cabinet "Y." 14:23:20* A failure occurred resulting in interruption of one of the two (-25 sec)** 24 Volt DC power supply units for the plant's system. This supply (called the "X" supply) powers much of the plant's control instrumentation, transmitters and recorders. As a result of the failure, a number of erroneous alarms and indications were received in the Control Room. Erroneous signals were also supplied to the Integrated Control System (ICS) which controls the Reactor Power level, Main Turbine Steam flow, and Main Feedwater flow. Alarms recorded at this time indicated that the reactor inlet temperature was erroneously indicating approximately 5700F (instead of a normal 5550F) and that Reactor Coolant System (RCS) flow indication in one loop was erroneously indicating one-half normal flow. These erroneous signals caused the ICS to start reducing feedwater flow. Simultaneously, an erroneous indication of average RCS temperature caused the ICS to begin increasing reactor power. 14:23:21 The NNI "X" 24 volt power supply monitor tripped the 120 volt (-24 sec) AC breakers supplying power to the 24 volt power supply. The Power Operated Relief Valve (PORV) on the pressurizer opened and was held in the open position by the power supply failure The pressurizer spray valve was also opened slightly. Erroneous signals supplied to the ICS caused the feedwater to both Once Through Steam Generators (OTSG's) to be rapidly reduced, Steam Flow to the Main Turbine to be increased, and the reactor power to be increased. The combined effect of the feedwater to the OTSG being reduced and the reactor power being increased aised RCS pressure. 14:23:30 Main Feedwater (MF>') flow rate was minimum and RCS pressure (-15 sec) was increasing rapiCly.

• Eastern Standar1 Time
  • Times related to reactor trip Page 1

... ~.. ~ ~.. -.. Event Synopsis - Page 2 14:23:45 The reactor tripped on high RCS pressure at 2300 psig. No (0 sec) alarms were available on the annunciator printer because it 4 was not functional at this time. The Main Turbine (MT) was tripped at this same time by automatic circuit response. The RCS pressure peaked at approximately 2320 psig and started to decrease due to post trip cooling and the open PORY. 14:25:50 The Reactor Coolant Orain Tank level alamed high due to the (65 sec) accumulation of RCS coolant being released through the open PORY. 14:26:41 RCS pressure decreased to 1500 psig and the Emergency (176 sec) Safeguards System activated the High Pressure Injection (HPI) System which started twc additional HPI/ makeup pumps. The full flow of three pumns was now being injected to the RCS. 14:27:04-The four Reactor Coolant Pumps (RCP's) were turned off in 14:27:07 accordance with procedures. Some reactor building service (199-202 sec) penetrations were isolated manually by the operator in accord with procedures 14:28-14:32 The PORY and pressurizer spray line isolation valve were (255-495 sec) closed by the operator. This permitted RC pressure to rise as high pressure injection water flowed into the system (time approximate). 14:31:32 Reactor building pressure reached 2 psig. Reactor coolant was (467 sec) being released to the reactor building through the rupture disk on the Reactor Coolant Drain Tank. 14:31:49 OTSG A Rupture Matrix activated and tripped main feedwater (225 sec) pump 1A. OTSG A was dry at this time and OTSG B was nearly dry. 14:32:35 Steam Driven Emergency Feedwater (EFW) pump was manually (530 sec) started. 14:33:11 RCS p. -".re 2361 psig. (566 sec) 14:33 Motor-drive Emergency Feedwater (EFW) pump was manually (555 sec) started (time approximate). 14:33:15-RCS code safety relief valve opens (time approximate). 14:33:30 (510-525 sec) 14:34:33 Rettor building dome high radiation alarm. (648 sec) Page 2

Event Synopsis - Page 3 14:44:12 NNI "X" 24 VDC power supply re-energized. This provides (1227 sec) reliable indication of the primary and secondary parameters. 14:44:31 Reactor building pressure at 4 psig and the reactor building (1248 sec) isolated on automatic signal. 14:45 B&W notified of reactor building pressure and radiation (approx.) alarms. B&W established emergency communications and support to CR-3 control room from Lynchburg. 14:46:10 The reactor building isolation was bypassed to allow injection (1345 sec) flow to the RC pump seals, balance HPI flow, and restore essential component cooling water. 14:4B:24 Seal water and cooling water re-established to the Reactor (1479 sec) Coolant Pump seals. 14:51:57 The Steam Rupture Matrix on Once-Through Steam Generator (1692 sec) (OTSG) B activated because of low steam pressure and tripped MFW Pump 18. 14:52 HPI was throttled to approximately 250 gpm. (approx.) 14:53 Re-established letdown flow to reduce RCS pressure to aid in (approx.) reseating RCS code safety valve RCV-8. 14:56 Feedwater to OTSG A was re-established. (approx.) 14:57:09 Bypass OTSG-B rupture matrix to regain FW control (at approximately 65% operating range). 14:57:15 Re-establish RC pump seal return. 15:00:09 Water level was re-established in OTSG A. (2184 sec) 1 15:15 Verified that natural circulation cooldown had been (approx.) established on both OTSG's with approximately 230F reactor differential temperature. The Technical Support Center was manned. Page 3

t Event Synopsis - Page 4 15:17 A Class "B" accident was declared which evacuated (approx.) non-essential personnel from the site. 15:19 Commenced feeding OTSG B. (approx.) 15:26 Received a low level alarm from the Sodium Hydroxide tank. (approx.) 15:49 OTSG A at high level per procedure. (approx.) 15:50 Terminated HPI flow and established Makeup and Letdown control (approx.) of RCS pressure. At this time the RCS and pressurizer were

ompletely filled with liquid (" solid" system).

16:00 Connenced pressurizer heatup to establish a steam bubble. (approx.) 18:05 Established a steam bubble in the Pressurizer by increasing (approx.) letdown flow. 21:07 Started Reactor Coolant Pumps (RCP) 18 and 1D. RCS pressure (appro x. ) was approximately 2000 psig, Tave was was approximately 4200F and pressurizer level was 235". This returned the plant to a normal shutdown conditicn and terminated the abnormal transient. I e Page 4 --m.

1 II. PERFORMANCE EVALUATION AND RECOMMENDATIONS A. E,xpected Plant Performance and Deviations 1. Initiating Cause Assessment The distribution of essential AC electrical power at the Florida Power Corporation's Crystal River 3 nuclear plant is shown schematically in Figure II-1, adapted from the plant's Final Safety Analysis Report. The plant's principal control instrumentation, the "Non-Nuclear Instrumentation" is supplied by two sources, NNI-X, and NNI-Y. Instrumentation, transmitters, recorders, indicators, etc., is assigned to one of these two sources as discussed in Section II.A.2. The initiating event for this transient appears to have been a short circuit on the +24VDC buss in the NNI-X channel. The power supply monitor sensed this buss short and within 0.5 seconds tripped both 51 and 52. This automated function removed all DC power to the equipment served by the NNI-X supply. The Non-Nuclear Instrumentation (NNI) power distribution system for NNI-X channel is shown on Figure II-2. A similar power distribution system exists for NNI-Y and is shown on Figure II-3. The power distribution system provides + 24VDC as required for signal processing modules, output modules and relay Togics. 118 VAC power is provided for + 24 VDC power supplies, sensor power supplies, indicators, and electric to pneumatic converters. Two sources for AC power may be brought through shunt trip switches 51 and S2 on the auctioneer panel to the AC terminals of the + 24VDC power supplies. At the Crystal River 3 plant, NNI-X AC source 1 and 2 is supplied 120VAC by vital buss 3C, NNI-Y is supplied 120VAC by vital buss 3D. The 24VDC outputs of power supplies are brought through auctioneering diodes to form busses on the power supply auctioneer panel. The auctioneering diodes block the lowest of the two supply voltages, preventing a low or zero supply output fromloading down a buss. This arrangement results in an auctioneered +24VDC positive buss and an auctioneered -24VDC negative buss. The busses serve the + 24VDC loads in NNI-X. The 24VDC system is protected from high voltage supply output by overvoltage protection networks within the individual power supplies. If a power supply voltage exceeds an adjustable limit (approximately 27VDC), the overvoltage network forces the power supply output to zero volts. This will not affect the output to the NNI since the diode auctioneering circuit will allow the other power supply to continue to function. The 24VDC power distribution system is monitored by a power supply monitor module. The power supply monitor receives inputs from the redundant positive 24VDC power supplies (pins 1 and 2) and the redundant negative 24VDC power supplies (pins 19 and 20). These inputs are used to initiate an alarm relay contact to annunciate to the operator either a loss of one of the AC ll8VAC power sources or failure (low or no voltage) of either both positive and/or either or both negative 24VDC power supply. The alarms originate in comparator circuits that compare the power supply voltage to an adjustable setpoint voltage. Page 5

l ~ 1 The power supply monitor also monitors the +24VDC buss (pin 15) and the -24VDC buss (pin 18, pins 16 and 17 are common). If either the positive or negative boss voltage f alls below a setpoint (approximately 22 volts), the power supply monitor will initiate the shunt trip circuits on both switches Sl and S2. Switches Sl and 52 have an opening dropout time delay of approximately 0.5 seconds. Thus, if the buss voltage f alls and does not recover in 0.5 seconds, the AC power will be removed from all four 24VDC power supplies. The opening dropout time delay allow 2 the buss voltages to come up to normal when the AC power is restored. Switches S1 and S2 must be manually reset to restore power. Based on information received from the site within five hours of the transient an verified in discussions with FPC C&I technicians and B&W personnel at the site, the FPC technicians took proper and timely corrective actions. They verified that the power supply overvoltage breakers had not tripped and attempted to reset Si and S2. When they could not reset S1 and S2, they began trouble-shooting the circuit. This effort lead. the technicians to believe that the power supply monitor had failed so they removed the monitor from the circuit. They were then able to reset 51 and 52. The elapsed time from loss of 24VDC power to restoring 24VDC power to the NNI-X was approximately 21 minutes. Subsequent trouble-shooting and investigation by FPC and B&W personnel revealed that the power supply monitor was not defective. It is our opinion, not yet confirmed, that the initial short was caused by a f ault somewhere in the system and when the power supply monitor was removed, the short was burned out by the power supplies. Each power supply is capable of supplying approximately 15.5 amps and without the power supply monitor this current could burn through a shorted component. In summary, the NNI-X power supplies and power supply monitor all functioned as expected during a short circuit event. 2. Loss of Instrumentation Function This section identifies which displays, controls, annunciators, interlocks, and signals were valid and/or available to the operator during the time that 'the NNI "X" channel DC power supplies were tripped. Section 2.3 provides the detail results of an evaluation of these signals and contains the following tables: Table II-l identifies the valid signals to the computer, ICS, control room and hot shutdown panel. Table 11-2 identifies the valid operable alarm inputs to the control" room annunciator for the Reactor Coolant, Secondary Plant and Makeup and Purification Systems. Table II-3 addresses the digital interlock and control functions performed by the NNI for the Reactor Coolant and Makeup and Purfication Systems. 2.1 The NNI System does not provide any inputs to the safety systems. The 3 safety system process sensors are powered from their respective safety system channel. 2.2 Reactor Coolant System Pressure Indication L Page 6

t Valid RC narrow range (1700-2500 psig) pressure indication from Loop A and Loop B was available in the control room. The pressure information is displayed on recorders and is derived from the Reactor Protection System. Valid RC wide range (0-2500 psig) pressure indication for Loop A and Loop B was available in the Control Room. The pressure information is displayed on Indicators (Loop A is also recorded) and is derived from the Engineered Safety Features Actuation Systen. Valid RC wide range (0-2500 psig) pressure indication for Loop A was available at the Hot Shutdown Panel. The information is displayed on an indicator and is derived from the Engineered Safety Features Actuation System. Valid RC outlet temperature (520-6200F) indication for Loops A and B was available in the Control Room and at the Hot Shutdown Panel only if the sensors pwoered by the "Y" cabinet was selected. The information is displayed on indicators. Valid RC inlet temperature (520-6200F) indication for Loops A and B was available in the Control Room only if the sensors powered by the "Y" cabinet was selected. The information is displayed on indicators. Valid RC inlet temperature (50-6500F) indication for Loops A and B was available in the Control Room only if the sensors powered by the "Y" cabinet wwas selected. The information is displayed on indicators. Valid uncompensated pressurizer level was available in the Control Room from RCl-LT3 via the computer. Valid uncompensated pressurizer level was available at the hot shutdown panel from RCl-LTl and RCl-LT3 and is displayed on indicators. 2.3 Detail Results The loss of the "NNI-X" +24VDC power caused many instruments to give incorrect responses. This section identifies the affected instrumentation and alarms. This review is based upon the following: a. No loss of 120 VAC "x" power to and/or in the NNI "x" cabinets and peripheral components, b. Loss of +24 VDC and -24v de in the NNI-X cabinets due to tripping of breakers Sj and 52 as shown on Bailey drawing 080340420. c. No loss of 120 VAC, +24v0C, or -24VDC to or in the NNI "Y" cabinets. d. All instrument strings were operable prior to the power loss in "lb" above and were wired as shown on Bailey drawings listed in Section 2.0 below. Page 7 L.

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i I "Y" POWER F I GU. II-3 NNI-Y POWER [ 120V AC TERM. BLK s FUSE RC [ m PANEL $9 )St FUSE EU U PANEL ON +24V DC -24V DC CF BS POWER SUPPLY POWER SUPPLY FUSE RC PANEL SP

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t 21h SIGNAL -f-NOT USED MONITOR "b RC PRESSURE HIGHER THAN SETPOINT 23l ,,,,,,3,gg 27 "L" h TO PORY INTERLOCK CONTACTS OPEN WHEN RC PRES $URE -y 13 LESS THAN SETPOINT 28 NOT USED 29 ALL CONTACTS SHOWN IN SHELF STATE (NO POWER OR DE-ENERGlZED) SIGNAL MOMITOR CONFIGURATION 125V DC "H" "l* , _ 20 SIMPLIFIED PORY CONTROL CIRCUlT 7 - 20 FIGURE 11-4 K20 PORV j { SOLENOID Normal During Transient 1. when RC pressure exceeds high set point 1. due to losing +24VDC prior "H" contact closes to losing -24VDC, "H" contacts closed. 2. relay 20 energizes through "H" contacts 2. relay K20 energized 3. relay 20 latched through "L" contacts 3. K20 was latched through "L" and latch contacts of K20 contact since pressure was above low setpoint. 4. PORY opens by 120VDC being applied to 4. PORY opened through K20 PORY solonoid through K20 control control contacts contacts. 5. when pressure drops below high setpoint 5. lost -24VDC de-energizing "H" "H" relays de-energizes and H contacts relay and open "H" contact. open. "L" contacts remain closed since "L" relay already de-energized. 6. when pressure drops below low setpoint 6. PORY stays open "L" relay energized opening L contacts and de-energizes K20 which in turn denergizes the PORY solonoid to close the PORY. 7. when pressure returns to above the low setpoint the "L" relay de-energizes & thereby returning control circuit to normal operating conditon. Page 8 1 .l

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• H" TO PRESSURIZER SPRAY CONTROL VALVE INTERLOCK CONTACTS CLOSE WHEN PRESSURE 13 HIGHER THAN HJGH SETPolNT SIGNAL-l MoulTOR Rc PRES $URE 4 mil IIARROW RANGE 27

~J-2s L-TO PRESSURIZER SPRAY CONTROL VALVE INTERLOCK CONTACTS CLOSE WHEN PRESSURE is LOWER THAN LOW SETP0lNT 29 Pressurizer Spray Valve Figure II-5 4 All contacts shown in shelf state (no power or de-energized) Pressurizer Spray Valve is a motor controlled valve (MOV) Normal Operation During Transient 1. when RC pressure exceeds high setpoint, 1. d1e to losing +24VDC prior "H" contacts close and send open comand to losing -24VDC, "H" to MOV spray valve contacts closed. 2. when RC pressure returns to below high 2. open comand sent to MOV setpoint, "H" relay de-energizes - open spray valve. comand is removed. 3. when RC pressure goes below low 3. lost -24VDC, "H" relay setpoint, "L" contacts close and de-energizes, "H" contacts send close comand to MOV spray valve. open and open comand is removed. 4. when RC pressure goes above low 4. spray valve stays at position setpoint, "L" relay de-energizes and when comand was removed. control circuit returns to nonnal Approximately 13% open. operating state. 5. "L" contacts played no roll. Page 9

8.' ley Drawings 080340420 NNI-X Power Dist. Sheet 1 of 4 08034042D NNI-X ' Power Dist. Sheet 2 or 4 D8034042C NNI-Y Power Dist. Sheet 3 or 4 08034042D NNI-Y Power Dist. Sheet 4 of 4 08034033C R.C. Sys. Schematic Sheet 1 of 7 D8034033C R.C. Sys. Schematic Sheet 2 of 7 08034033E R.C. Sys. Schematic Sheet 3 of 7 08034033E R.C. SYS. Schematic Sheet 4 of 7 080340338 R.C. Sys. Schematic Sheet 5 of 7 00034033C R.C. Sys. Schematic Sheet 6 of 7 D80340330 R.C. Sys. Schematic Sheet 7 of 7 08034034C SP Sys. Schematic Sheet 1 of 4 08034034C SP Sys. Schematic Sheet 2 of 4 08034034D SP Sys. Schematic Sheet 3 of 4 D8034034C SP Sys. Schematic Sheet 4 of 4 08034035C CA Sys. Schematic D8034036C RB Spray Sys. Schematic 08034038C C.F. Sys. Schematic D8034037E DH Sys. Schematic 08034039D Makeup Sys. Schematic Sheet 1 of 5 080340390 Makeup sys. Schematic Sheet 2 of 5 08034039D Makeup sys. Schematic Sheet 3 of 5 080340390 Makeuo Sys. Schematic Sheet 4 of 5 D8034039D Makeup Sys. Schematic Sheet 5 of 5 08034040E Spent fuel Sys. Schematic D8034041C Condensate Flow Sys. Sheet 1 of 2 D8034041B Condensate Flow Sys. Sheet 2 of 2 Cabinet Module arrangement Sheets Rev B dated 12/10/71. Table II-l contains a tabulation of non-nuclear instrument parameters and provides the following information, assuming the failure of the "NNI-X" 124VDC power: a. Source of Power b. Validity of Signal to Computer c. Validity of Signal to Integrated Control System (ICS). Validity of Indication to the Control Room ')perator. e. Validity of Indication to the Hot Shutdown ?anel Operator'. Table II-2 contains a tabulation of non-nuclear instrumentation alarms for the reactor coolan't, secondary plant, makeup & purification systems and provid's the following information: I a. Source of Power b. Validity of signal for actuation of High Alarm on Control Room l Annunicator (assuming failure of the 124VDC NNI-X supply). Page 10 . ~

,~ O Validity of Signal for actuation of Low Alarm on Control Room c. Annunciator. Table II-3 contains a tabulation of non-nuclear instrumentation system control or interlock functions for the reactor coolant, secondary plant makeup and purification systems and provides the following information: a. Parameter b. Interlock or Control Function c. Source of Power d. Validity fo Signal for Actuation State of Interlock or Control function with no valid signal. e. The following definitions of table headings are provided to assist in understanding the information provided in table II-3. Definitions " Parameter": the process variable being monitored. " Interlock / control function": the function to be performed by contact actuation. " Cabinet power source": the source of power for the device listed which provides the contact action. " Valid signal available for implementation": The + 24VDC power and/or the Valid signal available for implementation - The + 24VDC power and/or the module (s) electrical signal representing the process variable being monitored does not exist or is in error. "Was interlock / control action implemented if no valid signal": The + 24VDC power was not available to energize signal monitor relays to change contact state to implement control action or interlock. The following is the status of the non-nuclear instrument system auto / manual controllers for the reactor coolant, and makeup & purification system in the event of NNI-X + 24 VDC power failure. Reactor coolant pump seal injection flow control - no valid signal. a. b. Reactor coolant makeup flow control - no valid signal, Pressurizer heater SCR control - no valid signal. c. d. letdown flow control - valid The following is a listing of NNI control room indications not addressed in Table 11-1. The signals to these indications are derived from various signal processing modules in the NNI. Total RC Flow Recorder - no valid signal a. b. Reactor Ccolant Loop A&B Tc Indicator - no valid signal Reactor T Indicator - no valid signal c. d. Reactor Th Recorder & Indicator - Signal valid only if loop A or B 1 Th selected by RC15-MS. Reactor Tave Recorder - No valid signal f. Reactor Tave Indicator - no valid signal e. Page 11 k

~ ' g. Loop A&B T Indicator - no valid signal h. Loop A&B Tave Indicator - no valid signal The following is a sunnary listing of NNI to ICS Signals taken from Table II-l. These signals were not valid to the ICS. a. RC Loop A Flow b. Controlling tave c. Total RC Flow d. Reactor Tc e. Steam generator A Startup Level f. Steam generator B Startup Level g. Steam generator A Feedwater Valve P h. Steam generator A Startup Feedwater Flow The following signals to the ICS would have been valid if the sensor signal select switch had been in the position identified in Table 11-1. The presumed status of key instruments listed below is discussed later in Section II.A.12. a. RC Loop B Flow b. Reactor Th c. Steam Generator A Pressure d. Steam Generator B Pressure e. Steam Generator B Feedwater Valve P f. Steam Generator A Operate Level g. Steam Generator B Operate Level h. Turbine Throttle Steam Pressure

i. Steam Generator B Startup Feedwater Flow j.

Steam Generator A Feedwater Temperature k. Steam Generator B Feedwater Temperatur 1. Steam Generator A Main Feedwater Flow m. Steam Generator B Main Feedwater Flow In most cases, instrumentation affected by the power loss will provide a mid-span (50% of range) indication on loss of +24VDC power. Page 12

h Table II-1 Signal Validity

• • • • Valid Signal Available To Cabinet Power Control Room Ect Shutdown Parameter Source Computer Operator Panel Oper.

ICS Pressurizer Level RC-LT1 X No No Yes-Indicator N.A. RC-LT2 X No No No N.A. RC-LT3 Y Yes No Yes-Indicator N.A. Pressurizer Temp RC2-TE1 X No No N.A. N.A. RC2-TE2 Y No

• Yes-Indicator N.A.

N.A.

• 0nly if. RC2-TE2 Selected RC Flow Loop A From NI,RPS N.A.

No N.A. No RCl4A-dPT 1 or 2

• Receive Flow Signal From NI/RPS NNI fiodules Dowered from NNI X Trans mitter NI/RPS Power RC Flow Loop B Y

N.A. No N.A.

• • Yas From NI/RPS
  • 0nly if RC48-TE4 Selected RCl48-dPT 1 or 2 RC Loop A Th RC4A-TE1 X

No No N.A. N.A. RC4A-TE4 Y. No

• Yes-Indicator
• Yes-Indicator
  • Yes
• 0nly if RC4A-TE4 Sele' te d c
  • 0nly if RC4A-TE4 Selecte d & RC15-MS Sel ected toLooplA RC Loop B Th RC4B-TEl X

No No N.A. No RC4B-TE4 Y

• Yes
  • Yes-Indicator **Yes-Indicator ***Yes
• If RC48-TE4 Not Selectec
  • 0nly if RC48-TE4 Selecte d
    • 0nly if RC4B-TE4 Selected and RC15-MS Selected to Loop B

RC Loop A Tc Narrow RCSA-TE1 X. No No N.A. No RCSA-TE3 Y Yes

• Yes-Indicator N.A.

No

• 0nly if RC5A-TE3 Selected

, Table II-1 i l (**** Assuming failure of the + 24 VDC NNI-X Power Supply)

i. ~ I L* Valid Signc1 Available To Cabinet Power Control Rocm F.ot Shutdo.n Parameter Sourco Computer Operator Panel Oper. ICS RC Loop B Tc Narror RC5B-TE1 X No No N.A. No RCSB-TE3 Y Yes

• Yes-Indicator N.A.

No

• 0nly if RC5B-TE3 Selected RC Loop A Tc Wide RC5A-TE2 X

No No N.A. N.A. RC5A-TE4 Y No

• Yes-Indicator N.A.

N.A.

• 0nly if RC5A-TE4 Selected RC Loop B Tc Wide RC5B-TE2 X

No No N.A. N.A. RC5B-TE4 Y

• Yes
  • Yes-Indicator N.A.

N.A.

• 0nly if RC5B-TE4 Not Selected
  • 0nly if RCSB-TE4 Selected RC Press Loop A Yes-Indicator Wide Range X

NNI N.A. Yes-Recorder Yes N.A. Signal from ESFAS RC3A-PT3 RC Press Loop B Wide Range Signal from ESFAS RC3B-PT3 X NNI N.A. Yes N.A. N.A. Table II-1 4 Page 2 e

( i Valid Signal Available To Cabinet Power Control Room Hot Shutdown Parast.er Source Computer Operator Panel Oper. ICS RC Pump #2 Seal Cavity Pressure RC10A-PT1 X N.A. No N.A. N.A. RC10A-PT2 X N.A. No N.A. N.A. RC10B-PT1 X N.A. No N.A. N.A. RC10B-PT2 X N.A. No N.A. N.A. RC Pump #3 Seal Cavity Pressure RC19A-PT1 X N.A. No N.A. N.A. RC19A-PT2 X N.A. No N.A. N.A. RC198-PTl X N.A. No N.A. N.A. RC198-PT2 X N.A. No N.A. N.A. Table II-1 Page 3

Valid Signal Available To Cabinet Power Control Room Hot Shutdown Parameter Source Computer Operator Panel Oper. ICS Start-up Stm. Gen. Loop A Level SPIA-LT4 X No No Yes No SPIA-LT5 Y No No H.A. No Start-up Stm. Gen. Loop B Level SPIB-LT4 Y

• Yes No Yes No SPIB-LT5 X
  • Yes No N.A.

No

• 0nly if SPIB-LT4 Not Se' ected
  • 0nly if SPIB-LT4 Selected Stm. Gen. Outlet i

Press. Loop A SP6A-PT1 X No No No No SP6A-PT2 Y Yes Yes-Recorder N.A.

• Yes
• 0nly if SP6A-PT2 Selected Stm. Gen. Outlet Press. Loop B SP6B-PT1 Y

Yes Yes-Recorder Yes

• Yes SP6B-PT2 X

No No No No

• 0nly if SP6B-PT1 Selectgd Stm. Gen. Level Full Range Loop A SP1A-LT1 X

No Yes N.A. N.A. Stm. Gen. Level Full Range Loop B SPIB-LT1 X No Yes N.A. N.A. Main Steam Temp. Loop A Sf4A-TE X No No N.A. N.A. M Table II-1 Page 4 R

~ _ _. Valid Signal Available To Cabinet Power Control Rocs P.ot Shutdown Parameter Source Computer Operator Panel Oper. ICS Main Steam Temp Loop B SP4B-TE Y Yes Yes-Indicator N.A. N.A. SGA FW VLv AP SP12A-dPT X N.A. N.A. .N.A. No SGB FW VLv aP SP12B-dPT Y N.A. N.A. N.A. Yes SGA Lower Down Comer Temp SP3A-TE1 X No No N.A. N.A. SP3A-TE2 Y No

• Yes-Indicator N.A.

N.A.

• 0nly if SP3A-TE2 Select <!d SGB Lower Down Comer Temp SP38-TE1 X

No No N.A. N.A. SP38-TE2 Y

• Yes
  • Yes-Indicator N.A.

N.A.

• 0nly if SP3B-TE2 Not Se'lected
  • 0nly if SP3B-TE2 Select <!d l

SGA Operate Level SPIA-LT2 X No No N.A. No SP1A-LT3 Y No Yes-Recorder N.A.

• Yes
• 0nly if SPIA-LT3 and SPlA-TE2 Selected M..

Table II-1 Page 5

Valid Signal Available To Cabinet Power Control Room liot Shutdown Parameter' Source Computer Operator Panel Oper. ICS SGB Operate Level SPIB-LT2 X No No N.A. No SPIB-LT3 Y

• Yes Yes-Recorder N.A.
  • Yes
• 0nly if SPIB-LT3 Not Sel ected
  • 0nly if SP18-LT3 and SPIR-TE2 Selected Turbine Throttle Steam Pressure (SGA SP10A-PT1 Y

Yes

• Yes-Recorder N.A.
• Yes (SGA SP10A-PT2 X

No No N.A. No (SGB SP108-PT1 Y Yes

• Yes-Recorder N.A.
• Yes (SGB) SP10B-PT2 X

No No N.A. No

• 0nly if this Transmitter Selected SGA FW Temp SP5A-TE1 X

Nu No N.A. No SP5A-TE2 Y No

• Yes-Indicator N.A.
• Yes
• 0nly if SP5A-TE2 Selected SGB FW Temp SP5B-TE1 X

No No N.A. No SP5B-TE2 Y

• Yes
  • Yes-Indicator N.A.
  • Yes
• 0nly if SP5B-TE2 Not Sel ected
  • 0nly if SP5B-TE2 Selected H

e l Table II-1 Page 6 L. ~ e.e=**=- -p* e *s = .e__ e*+"' ~..

p. 1 Valid Signal Available To Cabinet Power Control Room Ilot Shutdown Parameter Source Computer Operator Panc1 Oper. ICS SGA Startup FW Flow SP7A-dPT X No No N.A. No SGB Startup FW Flow SP78-dPT Y Yes

• Yes-Indicator N.A.
• Yes
• 0nly if 3P5B-TE2 Selecte<l SGA Main FW Flow SP8A-dPT1 X

No N.A. N.A. No SP8A-dPT2 Y No N.A. N.A.

• Yes
• 0nly if iPGA-deT2 and SPSA-TE2 Selected SGB Main FW Flow SP88-dPT1 X

No N.A. N.A. No SP8B-dPT2 Y

• Yes N.A.

N.A.

• • Yes
• 0nly if 3P8B-dPT2 Not Sei ected
  • 0nly if $P88-dPT2 and SP!;B-TE2 Selected H

Table II-1 Page 7 l

Valid Signal.Available To Cabinet Power Control Roc = Ilot Shutdown Para:neter Source Computer Operator Panel Oper. ICS RCP Total Seal Flor MU27-dPT X No No N.A. N.A. HPI Flow MU23-dPT1 X N.A. No N.A. N.A. MU23-dPT3 Y N.A. Yes 'N.A. N.A. MU23-dPT2 X N.A. No N.A. N.A. MU23-dPT4 Y N.A. Yes N.A. N.A. Letdown Flow MU4-dPT Y N.A. Yes N.A. N.A. MUS-TE X N.A. Yes N.A. N.A. Makeup Tank Level MU14-LT1 X No No N.A. N.A. MU14-LT2 Y No No N.A. N.A. MU Pump Pressure MU2-PT Y No Yes N.A. N.A. MU Tank Pressure MU17-PT X N.A. No N.A. N.A. MU Filter aP MU18-dPT Y N.A. Yes N.A. N.A. Makeup Flow MU24-dPT X N.A. No N.A. N.A. Table II-1 Page 8 m, ,. ;M - - = wze .MmMPe**P'****N""

o Valid Signal Available To Cabinet Power Control Roo= Hot Shutdown Parameter Source Computer Operator Panel Oper. ICS RC Pump Seal Flow MU7-dPT1 X N.A. No N.A. N.A. MU7-dPT3 X N.A. No N.A. N.A. MU7-dPT2 X N.A. No N.A. N.A. MU7-dPT4 X N.A. No N.A. N.A. RC Pump Seal Return Flow MU31-FT1 X No No N.A. N.A. MU31-FT2 X No No N.A. N.A. MU31 -FT3 X No No N.A. N.A. MU31-FT4 X No No N.A. N.A. Table II-; Page 9 ~ e

= =.. - - L- ~ < Valid Signal Available'To Cabinet Power Control Room Hot Shutdotm Parameter Source Computer Operator Panel Oper. ICS DH Removal Flow DH1-dPT1 X N.A. No N.A. N.A. DH1-dPT2 Y N.A. Yes-Indicator N.A. N.A. DH Injection Temp DH2-TE1 X No Yes-Indicator N.A. N.A. DH2-TE2 Y Yes Yes-Indicator N.A. N.A. DH Cooler Inlet Temp DH6-TE1 X N.A. Yes-Indicator N.A. N.A. DH6-TE2 Y H.A. Yes-Indicator N.A. N.A. i f Table 11-1 ( Page 10 l ~ f ..- n.

{ _.. - - q [* o. Valid Signal Available To Cabinet Power Control Rocc Hot Shutdown Parameter Source Computer Operator Panel Oper. ICS Core Flood Tank A Pressure CF1-PT1 X N.A. No N.A. N.A. CF1-PT2 Y N.A. Yes-Indicator N.A. N.A. Core Flood Tank B Pressure CF1-PT3 X N.A. No N.A. N.A. CF1-PT4 Y N.A. Yes-Indicator N.A. N \\. Core Flood Tank A Level CF2-LT1 X N.A. No N.A. N.A. CF2-LT2 Y Yes Yes-Indicator N.A. N.A. Core Flood Tank B Level CF2-LT3 X No No N.A. N.A. CF2-LT4 Y N.A. Yes-Indicator N.A. N.A. Table II-1 Page 11 4 e

Valid Signal Avcilable To Cabinet Power Control Roc = Hot Shutdoun Parameter Source Computer Operator Panel Oper. ICS RB Spray Flow -BSI-dPT1 X N.A. No N.A. N.A. BS1-dPT2 -Y N.A. Yes-Indicator N.A. N.A. Sodium Thio. Tank Level BS3-LT X N.A. No N.A. N.A. Sodium Hydroxide Tank Level BS5-LT X N.A. No N.A. N.A. Sodium Thio. Tank Temperature BS7-TE X N.A. Yes-Indicator N.A. N.A. Sodium Thio. Tank Pressure BS15-PT X N.A. flo N.A. N.A. Sodium Hydroxide Tank Temperature BS8-TE X N.A. Yes-Indicator N.A. fl. A. Sodium Hydroxide Tank Pressure BS14-PT X N.A. No N.A. N.A. ' Table II-1 Page 12 m

Valid Signal Available To Cabinet Power Control Roou Hot Shutdown Parameter' Source Computer Operator Panel Oper. ICS Boric Acid Tank #1 Temperature CAIO-TE X No N.A. Yes N.A. Boric Acid Tank #1 Level Call-LT X No N.A. No N.A. Boric Acid Pump PIA & PIB Discharge Pressure CA14-PT X N.A. No No N.A. Boric Acid Tank #2 Temperature CA12-TE X No N.A. Yes-Indicator N.A. Boric Acid Tank #2 Level CA13-LT X No N.A. No N.A. Table II-1 Page 13

Valid Signal Available To Cabinet Power Control Roo:s Hot Shutdown Parameter Source Corputer Operator Panel Oper. ICS S. F. Storage Pool "A" Level SF1-LT1 Y N.A. Yes-Indicator N.A. N.A. S. F. Storage Pool "B" Level SF1-LT2 Y H.A. Yes-Indicator N.A. N.A. i Table II-1 Page 14

=, \\ Valid Signal Available To Cabinet Power Control Room Hot Shutdown Parameter Sourca Computer Operator Panel Oper. ICS CD Deaerator Level CD61-Lt Y Yes Yes-Recorder N.A. N.A. CD Total Cond. Flow CD15-FT Y N.A. Yes-Recorder N.A. N.A 1 Table II-1 Page 15 I I +

Valid Signal Available For Actuation of. Cabinet Pawer ~ ' Parameter Source Hi Alarm Lo Alarm urizer x Lu. 1 (RCl-LR/LS2) No No Pr ssurizer x Lcval (RCl-LS1) No No Loop A RC Flow x (RC14A-FS) N.A. No Lt.np B RC Flow x (RC14B-FS) N.A. No Total RC Flow x (RC13FR/FS) N.A. No Loop A/B ATC x (RC8-dTS) No No Reactor TH x (RC4-TR/TS)

• yes N.A.
• 0nly if Loop A or B TH Selected by RC 15-MS Loop A RC Pressure x

wide range (RC3A-PR2/ PS ) N.A. Yes RC Pressure Vs. x Core Flood Valve (RC3A-PS3 ) No No Position Alarm essure x . Press Inj. (RC3A-PS6) No N.A. Not by Passed RC Pressure x Low Press Inj. (RC3A-PS S) No h.A. Not by Passed RC Pump #2 Seal x Cavity Pressure (RC10A-PSI) No N.A. (All 4 Pumps) (RC10A-PS 2) (RC10B-PS I) (RC10B-PS 2) RC Pump #3 Seal x Cavity Pressure (RC19A-PS 1) No N.A. (All 4 Pumps) (RC19A-PS2) (RC19B-PSI) (RC19B-PS2) SGA Startup level x (SP1A-LS 2) N.A. No SGA Startup level x (SPIB-LS2) N.A. No SGA Operate Level x (SP1A LR/LSI)

• Yes N.A.
• Only if SP1A-LT3 and SP3A-TE2 is selected.

SGB Operate Level x (SPIB-LR/LSI )

• Yes N.A.
• only if SP18-LT3 and SP3B-TE2 is selected.

T h H-2

~ Valid Signal Available For Actuation of s - Cabinet Power ee ter Source Hi Alarm Lo Alarm Total RC Pump Seal Inject. x Flew (MU27-FS) No No High Pressure Injection Flow x RC Loop A (MU23-FS2) No No Y (MU23-FS4) Yes Yes High Pressure Injection Flow x RC Loop B (MU23-FS1) No No Y (MU23-FS3) Yes Yes Lot down Temp x (MUS-TS) No N.A. Makeup Tank Level x (MU14 LR/LSI) No No Makeup Tank Press x (MU17-PS) No No RC Makeup Flow x (MU24-FS) No No Jmp Seal Injection Flow x w.i 4 pumps) (MU7-FS1) No No x (MU7-FS2) No No x (MU7-FS3) No No x (MU7-FS4) No No RC Pump Seal Return Flow x (all 4 pumps) (MU31-FS1) No N.A. x (MU31-FS2) No N.A. x (MU31-FS3) No N.A. x (MU31-FS4) No N.A. Turbine Throttle x Pressure (SP10-PR/ PSI)

• Yes
• Yes
• 0nly if SP10A-P T1 or SP108-PT1 is selected Table II-2 Page 2

Cabinet (alid Signal i s " Interlock / Control Power Available for 3 ti n n ed Parametc; Function Source Implementation If No Valid Signal l !l,Pr:ssurizer De Energize Pressurizer x Level Heaters on Low Level (RCl-LSI) No No Loop A RC Flow Transfer Controlling Tave x To Loop B on Low Loop A (RC14A-FS) N6 No Flow Loop B RC Flow Transfer Controlling Tave x 8 To Loop A on low loop B (RC14B-FS) No No -l F1ow RC Loop A Tc Prevent Start of 4th RC x (wide range) Pump when Tc less than (RC5A-TS) No No Temp. Set Point I RC Lcop B Tc Prevent Start of 4th RC x Pump when Tc Less than (RCSB-TS) No No Low Temp. Setpoint .i RC Pressure Open & Close Pressurizer x Electro Matic Relief (RC3-PS8) No No RC Pressure Open/Close Pressurizer x Spray Valve (RC3-PS3) No No RC Pressure On/Off Pressurizer x Henter Bank #3 (RC3-PS6) No No RC Pressure On/0ff Pressurizer x 'I Ileater Bank f4 (RC3-PS7) No No ~I RC Press... Decay Heat Valve (DH-V1) x Prevent opening when (RC3A-PS3) No No aC Dressure High i RC Pressure

11.. RC Pressure Interloc (

x

To'ustomerSprayValve (RC3A-P57)

No iio l .i71, RCV-53F l Letdown Temp hoseMU-V3onHigh x .i (MUS-TS) No No I Makeup Tank Terminate Feed Bleed x On Low MU Tank Level. (Mul4-LS2) No No j I Table II-3 i

6-Cabinet /alid Signal Was Interlock /Contr Interlock / Control Power Available For Action Implemented Parameter Function Source Implementa tion If No Valid Signal I l? RC Pump Seal Close RC Pump Seal x i Inj:ction Flow Return Valve on Low (MU7-FSI) No No' k (all 4 pumps) Seal Injection flow j and x i Prevent Start of (MU7-FS2) No No RC Pump with low Seal Inject. Flow (MU7-FS3) No No x l (MU7-FS4) No No t I 1 't 4 s e i i l + l Table II-3

) 3. Opening of PORV and Pressurizer Spray Line Valve As described in Section II.A.1 above, the NNI x + 24VDC power bus was lost, due probably to a short circuit, which resulted in an immediate loss of the +24VDC power. Approximately 0.5 seconds later, the -24VDC power was removed by the power monitor. This sequence of losing power has the potential of causing the signal monitors to energize all "High" signal relays. The consequences of this action at the Crystal River Unit 3 Nuclear Unit would be that the NNI would send an open command to the PORV (see Figure II-4) and, until power is restored, would not be able to send a close command. The NNI would also send an open command to the Pressurizer spray valve (see Figure II-5) for the period of tine from the loss of the +24VDC to the loss of -24VDC (approximately 0.5 seconds). A close command would not be sent until power is restored. In order to verify that the signal monitors used in the NNI would behave as described, two tests were conducted, one by Florida Power Corp. and one by Bailey Control Company. The model signal converter tested by FPC, (identical to the one in the FPC NNI) was an earlier version than the one tested by BCC0 but the results were similar. In both tests, the signal monitor was powered by + and - 24VDC and the output state was monitored. The +24VDC power was removed, then restored, then the -24VDC was removed and then reconnected. The results of these tests were: a. FPC (using earlier version of signal monitor) - when +24VDC was removed, "H" relay energized. b. BCC0 - when the -24VDC was removed, the "H" relay energized. The results of these tests reveal that it is possible for the NNI to issue a false command or alarm signal if the + and - 24VDC power supplies are lost in a set sequence ("+" first on older models of signal converters and " " first on newer models). 9 i I l Page 13

k-4.0 Control System Actions Before Reactor Trip 4.1 ICS Signal Status The interruption of the "NNI - X" power supply caused several NSS process signals to fail which are inputs to the ICS. The signals important to the ICS performance are: RCS Hot Leg Temperature (T ot) H Steam Generator Startup Levels RCS Average Temperature from RCS hot and cold leg temperatures Steam Generator Operate Range Levels Feedwater Control Valve Delta Pressure Steam Generator Outlet Pressure (A&B) (TAVERAGE) - Calculated Total RC Flow - calculated from individual loop measurements The failure mode of all the signals listed above is to mid range. The failed signal reading and its relation to setpoint is as follows: Setpoint or Failed Signal Normal Value Value THCT 600 570 TCOLD 556 570 TAVG 578 570 Total RC Flow 100% 50% Loop A RC Flow 100% 50% Loop B RC Flow 100% 50% Turbine Header Pressure 885 psig 900 psig SG Startup Level 25 inches

• 125 inches SG Operate Range Level 50%**-

50% MFW Control Valve Differential Pressure 50 psi 50 psi Steam Generator Outlet Pressure 1000 psi 600 psig

• Low load or post trip level setpoint, RC pumps on Page 14 t

.. ~ -

• • Post-trip Level Setpont with RC pumps off In the period before and after the reactor trip (up until NNI "X" power was restored), some, or all of the fiNI signals listed above, reached the failed value.

The preliminary data assessment indicated the following: Signal Loop A Loop B TH0T Failed OK TCOLD Failed Failed TAVERAGE

---

Failed----------

Total RC Flow Failed OK7 Loop RC Flow Failed OK? Turbine Header Pressure

---

Probable Failure-----

Steam Generator Outlet Pressure Faiied OK SG Startup Level Failed Failed? SG Operate Level Failed OK MFW Control Valve P Failed OK 5. Reactor Shutdown The ICS actions, based on invalid input signals, in the pre-trip period (10 to 25 seconds) initiated (a) a rapid recuction in feedwater flow to the A generator, (b) a reduction in feedwater to the B generator, (c) an opening of the turbine valves and (d) rod withdrawal to bring TAVERAGE toward setpoint. These actions caused an increase in the actual RCS TAVERAGE, and the RC system pressure, although the PORV was open, which led to a high pressure reactor trip at about 2300 psig some 10 to 25 seconds after the NNI "X" pressure response is indicated on the wide range control room recorder chart, Figure III-1, which is constructed from the Plant Computer Data, and the Signal Event Monitor (SEM) refers. 6. High Pressure Injection Initiat on Following reactor trip, the relief of steam through the open PORV caused RC Pressure to f all reapidly as shown in Figure III-1. The Energency Safeguards Features Actuation System (ESFAS) initiated high pressure injection automatically as designed, when the RC pressure fell to approximately 1500 psig. 7. RC Pump Trip B&W instructions to the utilities specify that the reactor coolant pumps (RCP's) shall be tripped immediately after initiation of ESFAS by low reactor coolant system (RCS) pressure. Low RCS pressure alarms were received at 14:24:43, alerting the operators that RCS pressure was decreasing. The low pressure ESFAS initiation alarm was annunciated at 14:26:41. Two RCP's were tripped manually at 14:27:04, and the final two were tripped at 14:27:07. This was excellent response by the Page 15

4 operator. 8. Closure of PORV Isolation Valve B&W Small Break Operating Guidelines specify that, when the symptoms of a small break occur, the following valves shall be clos.ed. o Letdown Isolation Valve o PORV Block Valve o Spray Block and Control Valve These actions are specified to isolate a small break, if the break is downstream of (PORV block or letdown isolation valves) or between (spray block and control valves) the specified valves. The operators had received a low RCS pressure alarm at 14:24:43, following the high pressure trip. A low pressure ESFAS actuation signal was received at 14:26:48, indicating RCS pressure of 1500 psi. This pressure decrease indicated the possibility of a small break. Letdown had been isolated by the low pressure ESFAS actuation. The operator then manually closed the PORV block valve and the spray block valve per the Small Break instructions. The spray valve was closed when the power supply failed, and was still closed at this time. 9. Control of High Pressure Injection A The High Pressure Injection (HPI) system was actuated automatically on the low pressure ESFAS signal. Three HPI pumps functioned, providing a flow rate of about 1000 gallons per minute. Pump suction was from the Borated Water Storage Tank (BWST). The HPI water was injected through the normal safety injection nozzles, in the four cold legs between the reactor coolant system pump discharge and the reactor vessel inlet. Flow was therefore from the BWST through the ESFAS suction valves, then through three HPI pumps, and through ESFAS valves to the injection nozzles. Initially, the operator chose not to throttle HPI flow. This decision was correct, and in accordance with B&W's Small Break Operating Guidelines. Pressurizer level indication at the operator's panel had been invalidated by the power supply failure. Valid core temperatures were available only from the outlet thermocouple readout. The operator could not immediately determine the validity of reactor coolant pressure signals available to him. The Tsat meter reading may have been erroneous because of invalid instrument input. The operator therefore opted for HPI cooling to assure the core was properly cooled. After regaining NNI power (about 20 minutes after initial power loss) the operator could assess plant conditions. They were as follows: HPI cooling in effect, and RCS filled with water (pressurizer level o off-scale high, RCS pressure oscillating at about 2400 psi, subcooling margin greater than 1000F). Page 16 .s

Natural circulation in B OTSG (delta T of about 300F across this steam o generator, steam pressure consistent with outlet cold leg temperature, steam generator secondary water level about 50% on the operate range). HPI injection was then throttled to about 250 gpm. This is consistent with instructions allowing throttling when pressurizer level is high and subcooling margin is greatee than 500F. Natural circulation was then established in the A steam generator by raising the secondary water level and observing the proper delta T across the generator. Core temperatures were now controlled by the steam generators. The control room pressure trace shows RCS pressure oscillating between 2250 and 2400 psi. This indicated a pressure code safety valve was cycling as HPI was adding water. Since temperature control no longer depended on HPI, HPI was throttled to determine if the safety valve would reseat. By balancing HPI flow with letdown flow, it was determined that the valve had reset. Some point HPI flow rates were read by the operators during HPI injection, but no continuous recording of HPI flow vs. time is available. Based on BWST levels before and after the incident, about 50,000 gallons of HPI water was injected. About 46,000 gallons were injected through the PORV and code safety valve to the RC drain tank and thence to the containment building basement. The remaining 4,000 gallons filled the pressurizer steam space, and was discharged to a reactor coolant bleed tank when the pressurizer bubble was established. 3 Page 17 __2. :.~ ~.

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10. PRESSURIZER RELIEF VALVES Only one of the two safety valves (RCV-8) was actuated based on evaluation of discharge pipe temperature readings. The actuation pressure was approximately 2400 psig. The normal set pressure is 2500 psig.

The downward drift In set pressure was probably due to the seat leakage experienced by this valve prior to lifting. Seat leakage causes the thermal expansion of the valve internals. This expansion increases the areas exposed to the escaping steam as the valve nears its set pressure. The increased areas require lower steam pressures to generate the forces necessary to overcome the closing force of the spring. During the two hours that the safety valve appeared to be open, it passed saturated steam, two-phase flow and water. The pressure and temperatures seen by the valve are recorded in Section III. The valve appears to have reseated at approximately 2300 psi or less than a 5% blowdown below the initial opening. Except for the low opening pressure of 2400 psi vs. the 2500 psi setpoint, the safety valve appeared to perform as expected. The PORV was opened at the beginning of the incident as described in Section II.A.3. After approximately 5 minutes, the PORV isolation valve was manually closed. During the time the PORV was open, it is our opinion that the PORV passed only saturated steam, based on event simulation. The pressure range experienced by the valve can be seen in Section III. The PORV appears to have performed as expected.

11. Steam Generator Cooling (Reactor Trip until RC Flow Restored)

Upon reactor trip, the ICS performs the following normal functions: (a) Reduces feedwater flow to that value required to maintain 25" level on steam generator startup range instrumentation (50% on operate range if no RC pumps are operating). (b) Transfers turbine bypass setpoint from 885 psig to about 1000 psig for steam generator pressure coltrol. (c) Transfers steam generctor pressure control signal from turbine header pressure to steam generator outlet pressure. As a result of the input signal failures, this preliminary evaluation indicates: (1) The selected startup range level indications for both steam generators were f ailed to mid-position, indicating a level of about 125 inches in both generators. Since the setpoint is 25 inches, feedwater was definitely not added to the A gene ator and may not have been added to the B generator. When the reactor coolant pumps were tripped at about 14:27:00 (3-1/2 minutes into the event), the ICS transferred the steam j generator level setpoint from 25 inches on the startup range to SD' -- the operate range. This transfer provided a valid level signal an the B steam generator, which also had a valid main feedwater control valve delta P signal. The B steam generator startep feedwater valve opened, Page 18

L ~, feed pump speed increased, and feedwater was introduced at about 1400 gpm to the B generator through the main feedwater nozzles. This action is believed (from incore temperature data) to have established natural circulation cooling in the "B" loop. Auxiliary feedwater flow to the B steam geneator was manually initiated and controlled by the operator at about 14:33:00 (10 minutes). The B steam generator level was increased to about 92% on the cperate range, and then manually controlled to 50% on the operate range instrument. The A steam generator most likely had an invalid operate range level signal (50% setpoint, 50% indicated), so that no feedwater demand was created. The A-0TSG rupture matrix was actuated at about 14:31:49. There is no indication of feedwater to the A generator until 14:56:43 (33 minutes into the event). (2) Short-term post trip steam generator cooling control appears, frca this preliminary assessment, to have been valid in the B steam generator (e.g., control at about 1000 psig setpoint--indicating a valid pressure measurement), and invalid in the A steam generator (e.g., loss of pressure such that the rupture matrix was activated leading to isolation from the main feedwater). While there is no available feedwater flow indication, the main and auxiliary feedwater flow to each generator may be inferred from steam gener ator operate range level response as shown in Figure III-3. The automatic actuation of the auxiliary feedwater flow was presented by the mid-range f ailure of the steam generator startup range level signals. A valid low level signal is required from both steam generators to actuate the auxiliary feedwater system, or loss of control oil pressure on each main feed pump. Since these were invalid startup level signals and at least one main feed pump operating, no AFW , initiation signals were available. The operator actuated AFW to the B steam generator at about 14:32:35 (8 minutes 30 seconds after trip), although the main feedwater was supplying feedwater through the startup valve at this time. After AFW initiation steam generator flow control and pressure control were manual. After AFW initiation steam pressure began to decrease in the B steam generator, and reached the rupture matrix setpoint at about 14:52:00, which isolated the B steam generator and initiated trip of the 8 main feed pump. Feedwater flow to the A steam generator was reestablished by AFW at abcut 15:00:00, and natural circulation cooling was obtained in both loops. At about 15:19, AFW flow both steam generators were manually increased .to achieve 95% on the operate range level. This level was maintained until RC Pump restart at 21:07. Page 19

s.

12. Core Cooling Before and at the beginning of the transient, the core was cooled by forced convection provided by the four reactor coolant pumps. This mode of cooling continued for about the first two hundred seconds after reactor trip. At this time, high pressure injection was initiated and all four reactor coolant pumps were tripped.

The heat transfer mode from the fuel was thermal convection to the RCS inventory. The heat was being removed from RCS by venting of steam and water through the pressurizer relief system, with the HPI system replacing lost water. A limited amount of OTSG cooling was also available, as described in Section II.A.11. Although core outlet temperature data during the first ten minutes of the transient are incomplete, the highest core outlet temperature recorded in the data is 6000F. The minimum subcooling appears to have been reached at approximately three minutes after reactor trip. From this point forward, subcooling margin increased as shown in Figure III-4. Heat transfer to the RCS fluid from the core, primarily in the thermal convection mode, appears to have continued throughout the transient. In these circumstances no significant fuel cladding failures are expected. For approximately seven hours, decay heat was removed from the core by thermal convection natural circulation in the subcooled mode. At the end of this period, forced convection cooling was resumed by the restart of two reactor coolant pumps. It appears that the core was always well covered by water, and no indication of superheated conditions has been found in the data. The evidence from measured radiation levels in the containment building in the reactor coolant system is consistent with the conclusion that no new fuel cladding failures occurred in this transient. This evidence is as follows: 1. The radiation monitor on the letdown line, RM-L1 (which is recorded on RM-R5) showed a continuously decreasing activity level following reactor trip. Figure III-5 shows the decreasing activity levels recorded on RM-RS. The letddown monitor has a three-minute delay line to allow for the decay of nitrogen-16 so that the monitor will be more sensitive to the activity of other nuclides. If any significant number of fuel rods (approximately 10 to 20) had their clad breached by this transient, RM-L1 would not have shown a steady decrease in the coolant activity level. 2. The radionuclide concentrations in the containment atmosphere can be accounted for based on the activity expected to be released from those fuel rods that were leaking fission product activity into the reactor coolant prior to tN reactor transient. This point is discussed in greater detail in Section II.A.15. 3. The dose rates measured by the radiation monitors in containment are in the range that would be expected based on the release of activity from feel rods that were leaking prior to the reactor transient. If any significant amount of fuel cladding failed due the reactor transient, the dose rates in the containment would have been much higher. Section II.A.15 presents the technical basis for this conclusion. Page 20

~ -l s These data do not preclude that a small number of fuel rods (10 to 20) may have developed cladding leaks during this reactor transient since a small activity release would have been indis+1nguishable from other activity release mechanisms which follow a normal shutdown transeints or could have been obscured by calculational and measurement uncertainties. Later testing will be required to confirm this. We conclude that effective core cooling continued throughout this transient. 13. Restoration of Pressurizer Pressure Control After high pressure injection was terminated, pressure control was ac.%ie: red by balancing letdown and makeup. RCS temperature was being controlled via natural circulation and steam generator pressure control. Natural circulation was verified by measuring a delta T of about 290F across the cora, cold leg temperatures within 50F of steam generator saturation temperatures, and constant core outlet temperatures. The plant was stable, with aoout 1400F subcooling. A review of makeup and letdown flow rates rhowed that the pressurizer code safeties had reseated. A RCS coolant sample was taken and analyzed for radioisotopes, Fission product isotopes indicated no fuel pins had been ruptured during the transient. This was further verified by the letdown line radiation monitor readings. Further, the condenser air ejector radiation monitor verified that there was no abnormal primary-to-secondary leakage. Since there was no unusual coolant activity, the obvious decision to take the plant to cold shutdown on the decay heat system was made. Several methods of achieving cold shutdown were available, as follows: o Solid plant cooldown via natural circulstion or forced flow o Reestablish normal pressurizer control, then cooldown by either natural circulation or forced flow. The joint decision between the B&W Emergency Response Team and Florida Power Corporation was to reestablish normal pressurizer pressure control, then establish forced flow, and then go to cold shutdown and decay heat via the normal cooldown procedure. Once normal pressurizer pressure control and forced flow was established, the operators would be able to revert to normal operations. Pressurizer water temperature was about 5350F when this decision was made. A steam bubble could be established by heating the pressurizer water to about 6100F, corresponding to a saturation pressure of 2000 psi. The pressurizer heaters were activated to accomplish this. Since the Florida Power Company operators had performed a similar sequence during simulator training at B&W, no difficulties were anticipated, or encountered. Pressurizer water temperature increased about 400F per hour with all heaters activated. When water temperature reached about 6200F, letdown flow was increased (to a bleed storage tank, to man:tain proper makeup tank level control) and a steam bubble was formed. There were no significant pressure or temperature swings during bubb':c formation. Page 21

~ t High letdown was continued until the pressurizer level was about 210 inches. 14. Restart or' Reactor Coolant System Pumps RC Pump seal data had been retrieved hourly and reviewed by B&W pump experts since about two hours after transient initiation. All pumps were capable of restart. Normal procedures specify one pump per steam generator loop for cooldown. The B pump was selected in loop 1, to maximize pressurizer spray flow capability, if required and, therefore, pressure control capability. The D pump was chosen for startup in loop 2. There was a delta T of about 25*F across the core, before RC pump restart. After pump start, this delta T would go to about 1-2*F, so bulk average temperature would decrease upon pump start. A run was made on the B&W simulator to mockup pump start. this showed a sharp upward spike of about 50 psi on RCS pressure indication due to a sudden flow increase at the RCS pressure taps. The actual system pressure would not spike. A pressure decrease of about 150 psi, and a presurizer level decrease of about 20 inches, was shown due to bulk average temperature decrease. Neither cond' tion was detrimental to the plant, but the expected response was discus 'ed thoroughly with the Florida Shift Technical Advisor so that the operato. would recognize such changes as normal. Immediately before planned pump start, low oil level alarms were received on the upper oil pots on RC pump B&D motors. The B&W pump expert evaluated these alarms at thermal contractions of the oil volume, and not detrimental to pump restart. This was discussed with Florid Power Corporation, and the alarms were bypassed. The operators were instructed to closely monitor the motor upper thrust bearing temperatures, and trip the pump if this temperature exceeded 185'F. RC pump B was started first, without incident. The pressurizer level only decreased five inches, and little pressure change occurred. The delta T decreased to abot 2*F, as expected. Cold leg temperatures, core outlet temperatures, system pressure, and pressurizer level were all normal. Tne D pump was then started without incident. Upper thrust bearing temperatures stayed below 130*F, and oil level alarms cleared. The plant was now in normal cooldown configuration.

15. RELEASE OF RADIATION INTO THE REACTOR BUILDING Priar to the transient, the reactor was operating with reactor coolant activities corresponding to between 3.7 and 5.8 percent of the design coolant activities, as shown in Table II.A.15-1.

This coolant activity level would correspond approximately to 17 + 3 leaking fuel rods. As can be seen from Table II.A.15-2, the radionuclide concentrations measured in reactor coolant samples following the reactor transient show that all the iodine and cesium nuclides exhibited increased activity which is characteristic of the fission product spiking phenomena which occurs when operating with leaking fuel. The spike factors (after correcting for decay but without correcting for dilution) appear to be between 5 and 6 for the iodine and cesium nuclides. l Page 22 r w

TABLE II.A.15-1 COMPARISON OF REACTOR COOLANT ACTIVITIES PRIOR TO TRANSIENT WITH DESIGN BASIS ACTIVITY IN F5AR Activity Measured FSAR Design in Reactor Coolant Fraction of Basis Activity (1) Before Transient (2) Design Basis Nuclide ( C1/ml) ( C1/ml) Activity in Coolant I-131 3.17 0.184 0.058 I-133 3.75 0.174 0.046 I-135 1.92 0.072 0.037 XE-133 250.00 9.200 0.037 Average = 0.045(3) (1) FSAR Table 11-2 for 1% defective fuel (368 leaking fuel rods) based on hot coolant density. Multiplying by ( c/ h) = (62.2/46.5) = 1.34 (2) Based on reactor coolsot samples taken on February 26, 1980, at 00:10 (liquid) and 10:15 (stripped gas) corrected to hot coolant density by multiplying by ( h/ c) = (46.5/62.2) = 0.748. (3) Equivalent to 17 + 3 leaking fuel rods. I Page 23

i)~ s. Based on about 50,000 gallons being pumped from the BWST into the reactor coolant system, the dilution f actor is 1.89 (or 53% of the activity remaining in system) after appropriately correcting for density differer.ces and assuming a well-mixed reactor coolant loop, which seems to be a reasonable assumption during natural circulation with HPI flow. Thus, after adjusting for dilution, the spike factors become 9.5 to 11.5 which is a realistic range. If it is assumed that the water added to the reactor coolant system in the first 90 minutes following the reactor trip are divided such that 72% is discharged into the reactor building and 28% is discharged into the bleed holdup tanks, the measured activity in a containment atmosphere agrees with the activity release associated with the reactor coolant discharge and with the pressurizer steam space discharge (see Table II.A.15-3). Despite the good agreement shown on Table II.A.15-3, one might choose to disregard the concept of fission product spiking and claim that the activity increase shown in Table II.A.15-2 is due to the failure of addition fuel rods. This equivalent effect could be produced by creating small leaks in 10 to 20 fuel rods that were previously intact. Since there are 36,816 fuel rods in the core, 10 to 20 rods represents 0.03 to 0.06 percent of the total. Figure II.A.15-1 shows the dose rates measured by the radiation monitors in the reactor building. Calculations were made to see if the release of reactor coolant into the containment would give a similar repsonse. Based on releasing the coolant activity into the reactor building atmosphere and assuming that the atmosphare was well-mixed, the dose rate would be between 1.5 and 3.0 R/hr in any unsnielded area; however, since the calculation neglected many short half-life nuclides, it might have been possible to have a slightly higher dose rate for a short time. The 60 R/hr reading shown on the dome monitor (RM-G19) can best be explained by assuming that the activity was not well-mixed with the entire building atmosphere for the first several hours. This explanation is further supported by the great disparity between the four radiation monitors in the reactor building. The monitors that read the highest were generally located at higher elevations in the building and on exterior walls which induced convection downdrafts that swept the activity to the monitor. Apparently, the steam and hot gases rose rapidly to the dome and tended to accumulate there until the steam release was terminated. The reactor bu'ilding isclation was apparently effective in containing essentially all the radioactivity within the building, thus there were no significant amount of activity detected in the environment. i i. h, Page 24

e.. TABLE II.A.15-2 RADIONUCLIDE CONCENTRATIONS IN REACTOR COOLANT SAMPLES Radionuclide Concentration in Ci/m1* Date Time XE-133 I-131 I-133 I-135 CS-134 CS-136 CS-137 02/26/80 '00:10 0.240 0.233 0.096 0.018 10:15 12.3 14:25** -- 0.454 0.4 29 0.180 0.045 0.007 21:35 0.664 0.5438 0.158 0.058 0.013 02/27/80 00:58' 1.190 0.884 0.215 0.089 06:15 0.924 0.574 0.100 0.085 0.039 08:55 0.833 0.506 0.073 0.104 0.101 12:55 0.818 0.437 0.077 0.036 0.083 17:55 0.949 0.416 0.031 0.094 0.035 0.088 21:10 0.736 0.288 0.016 0.071 0.024 0.066 02/28/80 08:15 0.575 0.160 0.004 0.068 0.022 0.067

• Based on coolant density at room temperature.
  • Actual sample result is marked:

" Sample time 2/26/80 14:15" but also states "RCS cold letdown for Rx trip" which implies sometime after trip at 14:24 and the sample counting time at 14:30. 'O. Page 25 - - n- -

TABLE II.A.15-3 GASEOUS ACTIVITY IN THE REACTOR BUILDING Released (5) (1) Release with with per Total Conc. in RB Curies in Conc. In Coolant 5 team Release Nuclide ( c/ml) RB Atmos.(2) Coolant (3) (Ci) (4) TETT (Ci> Xe-133 2.94x10 1582 12.3 1075 503 1578 Xe-135 7.0lx10 377 2.86 250 117 367 Kr-88 1.80x10 97 0.648 57 27 84 I-131 1.17x10 0.063 0.55 68 (6) 68 (1) Based on containment gas sample taken 2/26/80 at 21:55 (except I-131 comes from RM-A6 channel 2/27/80 at 04:05) and decay corrected back to the time of trip. (2) Assumes a reactor building free volume of 1.9 x 106 ft, 3 (3) Based on reactor coolant sample taken 2/26/80 at 10:15 and stripped of gas (except iodine activity which was estimated from Table II.A.15-2). (4) Based on 32,868 gallos of cold coolant in RB and 12,782 gallons of cold coolant in Bleed Holdup Tanks. (5) Based on a Henry's Law constant of 8.5 x 104 psia per mole fraction. (6) Corresponds to a partition factor of about 1080.

16. Sodium Contamination of RCS Water When the incident occurred the decay heat system actuated and recirculated from the discharge of the decay heat coolant back two suction side of the pumps since the reactor coolant system pressure was higher than the dead head pressure of the pump. When the reactor building pressure increased the remove valve on the outlet of the sodium hydroxide storage tank actuated and connected the tank to the suction side of the decay heat pump.

As the decay heat pumps continued to operate in the recirculation mode, the level in the sodium hydroxide tank decreased from about 33 feet to 31 feet 2 inches which is equivalent to about 760 gallons of solution containing about 20 weight percent sodium hydroxide. Thus, the decay heat system became contaniaated with high concentrations of sodium hydroxide. The reactor coolant did not become contaminated with the sodium hydroxide while the reactor coolant system pressure was higher than the dead head'.hressure of the decay heat pumps as evidence by the f act that analysis of an RCS sample taken at 05:15 on February 27, 1980, indicated the sodium level was only 1.8 ppm. Before the RCS was placed in cold shutdown with the decay heat system operating, the decay heat system was recirculated to the borated water storage tank (BWST) in an effort to reduce the sodium levels. The sodium levels in the BWST's increased up to approximately 60 ppm. After the decay Page 26

. _. ~... s. heat system was connected to the RCS for cold shutdown cooling, sodium in a sample of the decay heat loop indicated that the sodium level was about 45 ppm which also indicated that water in the reactor vessel and other parts of the RCS were contaminated with the sodium at approximately this level. Sodium in the BWST is being reduced by processing the water through a spent fuel demineralizer. The decay heat and RCS water is also being processed through a demineralizer disposal system to reduce sodium. As of March 1, the sodium was in the range of 10 to 20 parts per million in the reactor coolant system. l l I page 27

B. Safety Implications The Loss of Electric power is an analyzed design basis event for the CR-3 FSAR. The following criteria for reactor protection are required for this event: a) Fuel damage will not occur from an excessive power-to-flow rate, b) Reactor coolant system pressure wil not exceed code pressure limits. c) The resultant doses are within 10CFR100 limits. The February 26, 1980, transient involved a partial loss-of-electrical power. The applicable protection criteria appear to have been met throughout the event. The sequence of events following the power supply failure in the NNI "X" cabinet is similar in nature to a loss of feedwater type transient whose consequences have been bounded for the FSAR analysis by the design basis event of a Feedwater Line Break. The reactor protection criteria for the Feedwater Line Break are: a) The core shall remain intact for effective core cooling. b) The reactor coolant system pressure shall not exceed code pressure limits of 110% of 2500 psig; i.e., 2750 psig. The major difference between the February 26, 1980, event and the bounding Feedwater Line Break event analyzed for the FSAR are itemized below. 1. The main feedwater values were closed over a 25-30 second time interval rather than the conservative FSAR assumption of an instantaneous rupture of the main feedwater header at the steam generator inlet nozzles. 2. The combination of the opening of the PORV, the ICS demand for 103% full power and feedwater runbacks caused the reactor trip on high pressure to occur at 10-25 seconds into the event rather than at 11.8 seconds for the FSAR event. 3. The opened PORV allowed a rapid depressurization to 1500 psi such that the ESFAS was actuated and two HPI pumps were started. The PORY and spray block valves were closed about 5 minutes into the event and the RCS code safety valves actuated about 13 minutes into the event. This was much slower than 22.3 seconds for the FSAR events. 4. The operator ic'tiated emergency feedwater at approximately 9 minutes into.the event rather than the 15 minutes which was demonstrated for the FSAR as an acceptable time for operator action to prevent core or reactor coolant boundary damage. 5. Main feedwater was supplied "B" 0TSG at about 4 minutes (approximately 1400 gpm) rather than being totally lost as analyzed in the FSAR. 6. The maintenance of full HPI flow' for 32 minutes provided a significantly greater heat removal capacity than assumed in the FSAR where only relief I Page 28 l

.~_ through the safety valves of the expanding RCS system water is considered. For both vients, core coverage was maintained, no fuel damage occurred and the reactor coolant system pressure remained within code allowable limits. The safety evaluation criteria were met. Although apparently initiated by a single fault, this transient involved a series of multiple, propagating abnormalities through the interaction of the various sytstems which are affected directly or indirectly by the interruption of the "NNI-X" power source. These interactions led to: (a) Loss of some instrumentation and annunciator indications to the plant operator. Presentation of some confusing and invalid information. (b) PresentWon of some invalid plant signals to the Integrated Control System, which acted upon them to increase reactor power, decrease feedwater flow and increase steam flow. (c) The pressurizer PORY was opened and latched at a system pressure below its setpoint. (d) Automatic initiation of emergency feedwater did not occur, despite reduction of main feedwater. The maintenance of plant conditions within the safet, criteria required the action of automatic safeguards (reactor trip, high presure injection, reactor building isolation), safeguards features (safety relief valve), and/or operator action (start emergency feedwater) in response to items (b), (c), and (d). Item (a) reduced the operator's ability to respond. C. Conclusions and Recommendations The conclusions and recomendations are preliminary and are subject to change. 1. Conclusions (a) The PORY was opened by an electrical upset on the NNI 24 VDC "X" buss. This upset also partially opened the pressurizer spray valve. (b) The following loss of the NNI 24 VDC "X" buss caused failure of input signals to the ICS, the computer, alarms, and control room indications. (c) The ICS, with available input information, acted in a predictable manner. (d) The Safety Systems actuated as required. (e) There was no known radiation released outside the reactor building. (f) The reactor core remained covered, and for the greater part of the event subcooling margin was greater than 500F. A momentary minimum subcooled margin of about 20F occurred. (g) The operators took the correct actions, in the safe direction. (h) Auxiliary feedwater was not initiated automatically. Page 29 {

s (i) Feedwater was lost to the "A" steam generator for about 30 minutes. Operators followed procedures in re-establishing flow and level to the "A" steam generator. (j) There is no indication of increased fuel failure. (k) Pressurizer safety valve RC-V8 opened at about 2400 psig, reseated at about 2300 psig, and was subjected to water flow of about 700 gpm. (1) RC System cooldown after RC-V8 reseated and two RC pumps were restarted was a normal operation. (m) Incident review would have been more accurate and timely with improved data logging and transmission facilities. 2. Short Term Recommendations (a) Complete review of transient effects on RCS components, including fuel, and determine suitability for restart. See Section IV for detailed recommendations. (b) Determine cause of the power fault which interrupted "NNI-X" +24 volt DC power supplies and take appropriate corrective action on a basic cause of the fault. (c) Review PORY circuitry to assure that credible power failures do not cause the PORY to open when it is not required to open. (d) Review power supply independence between PORY and PORY isolation block valve to assure that any single failure which would affect PORY does not eliminate the possibility of PORY isolation block action. (e) Review emergency feedwater automatic initiation system and modify to assure that no single power supply failure can cause main feedwater reduction and simultaneously inhibit automatic initiation of the emergency feedwater. A system review should be performed and modifications considered to assure automatic initiation of emergency feedwater in any case in which main feedwater is reduced by power supply failure in the control instrumentation or control circuitry. (f) Review availability of vital signals to the control room operator in the event of oower supply failures such as this one and provide for best arrangement of vital signal availability to the operator. (g) Review guidance and training provided to operator for managing the transient when confronted with loss of control room instrumentation which might accompany credible power supply failures and revise as appropriate in light of this transient. i Page 30

L ~ III. EVENT DETAILS AND INPUT DATA A. Initial Plant Conditions The following table of data summarizes the initial plant conditions. Time of Reactor Trip Approximately 14:23 February 26, 1980 Reactor Power 98.6 Full Power RCS Temperature (Tave) 5780F RCS Pressure 2157 psig Pressurizer Level 202 inches Number of RC Pumps Operating 4 Steam Pressure Loop A - 911 psig Loop B - 909 psig Number of Main Feedwater Pumps Operating 2 Tests in Progress None ICS Mode Automatic B. Plots of Major Parameters Several of the recorded parameters were selected for plotting to show major trends. These plots are shown in the following pages and are listed below: Figure III-1 Reactor Coolant System Pressure (-2 to 16 minutes) Figure III-2 Reactor Coolant System Pressure (-4 to 72 minutes) Figure III-3 Feedwater Flow ( e to 72 minutes) Page 31 _....m_ - - ~.

Figure III-4 Core Outlet Temperature and Tsat (-4 to 72 minutes) Figure III-5 Letdown Monitor Readings on February 26, 1980 Figure III-6 Radiation Monitor Readings in Containment on February 26, 1980 Figure III-7 HPI Flow During CR-III Incident Figure III-8 Steam Generator Pressure (-4 to 72 minutes) Figure III-9 Reactor Power from NI-5 (-360 to 840 seconds) Figure III-10 Pressurizer Level Indication (-360 to 840 seconds) Figure III-11 Reactor Cooalnt Flow (-350 to 840 seconds) Figure III-12 Feedwater Flow (-360 to 840 seconds) Figure III-13 Feedwater Pumo Speed (-360 to 840 seconds) Figure III-14 Feedwater Pump Discharge Pressure (-360 to 840 seconds) Figure III-15 Stecm Generator Pressure (-360 to 840 seconds) Figure III-16 Main Steam Pressure (-360 to 840 seconds) Figure III-17 Dearator Feed Tank Level (-360 to 840 seconds) Figure III-18 Reactor Building Pressure (-360 to 840 seconds) Figure 111-19 Reactor Coolant Pressure (-2 to 42 hours) Figure III-20 Incore Thermocouple (Maximum) (-2 to 42 hours) Figure III-21 Reactor Coolant Cold Leg Temperatures (-2 to 42 hours) Figure III-22 Pressurizer Tenperature (-2 to 42 hours) Figure III-23 Pressurizer Level Indication (-2 to 42 hours) 3 Figure 111-24 Steam Generator Levels (-2 to 42 hours) Figure III-25 Steam Generator Pressure (-2 to 42 hours) Page 32

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( IV. COMPONENT TRANSIENT ASSESSMENT A preliminary evaluation has been conducted for major RCS components which were subjected to this transient. These evaluations focused on the component structural integrity and their acceptability for continued operation. Additional structural fatigue analyses would be necessary in order to determine the overall effects of this transient on the 40-year design life of the plant. A. Reactor Yessel The characteristic of this transient most affecting reactor vessel structural integrity was the rapid drop in reactor coolant inlet temperature which developed high thermal stresses in the inlet nozzle and shell areas. These will only affect the fatigue life of the vessel and do not affect the short term safe operation of the plant. A fatigue analysis would be necessary in order to determine the impact of this transient on the 40-year design life of the reactor vessel. Brittle fracture is not a concern as a result of this transient since the minimum inlet downcomer coolant temperature achieved was 2500F. Fracture mechanics analysis has demonstrated that crack initiation of flaws up to and including the standard postulated flaw size did not take place and the existing pressure temperature limitations curves are still valid. B. Reactor Vessel Internals The Reactor Yessel Internals were not adversely affected by this transient. Excessive thermal stresses were not experienced and positive clamping force was maintained between the reactor vessel and internals. C. Steam Generators The maximum steam generator tube-to-shell differential temperature experienced was conservatively estimated to be 1380F. This is less than the 1860F temperature differential which has previously been analyzed for the Rancho Seco rapid cooldown event of March 20, 1978. The resulting axial tube loads are bounded by this previous analysis and, therefore, are acceptable. The stresses developed in the shell-to-tubesheet and lower head-to-tubesheet regions are also bounded by the previous analysis of the Rancho Seco event. These stresses were within code allowables and the effect on usage factor is negligible. The effect of the temperature change on the support skirt-to-lower head attachment is bounded by conditions already analyzed in the Crystal River-3 stress report. Prior to the February 26, 1980, incident, a primary-to-secondary leak of approximately 0.4 gpm existed at CR-3. This leakage is thought to be caused by tube-to-tubesheet weld damage in the B-steam generator resulting from the burnable poison rod assembly which separated from the fuel assembly in March, 1978. If an increased leakage rate is detected upon the plant's return to operation, it is more likely indicative of the general condition of the previously damaged tube-to-tubesheet welds rather than specifically related to the recent incident. I Page 33 i

t A i The structural integrity of the steam generators has not been adversely affected, and the steam generators are acceptable for resuming operation. Since the lower portion of the steam generator support skirt was potentially immersed in a pool of reactor coolant, it is recommended that the lower portion of the steam generator support skirts and anchor bolts be visually inspected during the next refueling outage and any corrosive residue removed. D. Pressurizer The pressure and temperature transient within the pressurizer, spray line and surge line were not severe enough to adversely affect the continued short term operation of the pressurizer. This qualitative assessment is based on a comparison of this transient to design transients prescribed in the CR-3 functional specification. The e"fect on the fatigue life of the pressurizer must be quantitatively assessed. The pressurizer heaters (upper bundle and half the middle bundle) may have been subjected to saturated steam conditions while energized. This can lead to accelerated failure of heater elements, deterioration of the heater sheath to diaphram weld, deterioration of the heater bundle diaphram seal welds and possible stressing of the heater sheath due to axial growth of the heater element. An evaluation has been conducted for each of these areas of concern. It was concluded that the diaphram to sheath weld was not adversely affected and the heater sheath was not subjected to excessive stresses as a result of heater growth. The heater bundles should be inspected for seal leakage and heater elements electrically checked for continuity pricr to their return tc operating service. A fatigue analysis should be performed to demonstrate that the 40-year design life was not adversely impacted by this transient. Loadings in excess of the original design loads may have been induced on the pressurizer relief nozzles during relief valve operation. The relief valve loadings which occured during this transient should be determined and the effect on the pressurizer relief valve nozzles assessed. (See Section IV.H). E. Reactor Coolant Piping RC piping analyses existed for the rapid depressurization transient in the Florida Power Functional Spec and for the rapid depressurization transient considered in the Rancho Seco Stress Report. These analyses were either representative or conservative for all areas of the RC piping except the A-loop cold leg. Analyses of the A-loop cold leg pipe and HPI nozzle were performed and resulted in acceptable stresses and usage factors. It is concluded that this transient event had no significant effect on reactor coolant piping and the RC piping is suitable for continued operation. F. Reactor Coolant Pumps The evaluation of the effect of this transient on Reactor Coolant Pumps included a review cf the pump environment during the transient and a review i of the performance parameters. The significant environmental conditions Page 34

F' y.. considered were system pressure, temperature, service water temperature and reactor building humidity, temperature and pressure. The pump performance parameters reviewed were pump mechanical performance, seal leakage rate and seal staging pressures. There is no indication the Reactor Coolant Pumps sustained any damage during this transient which would affect-their performance. M1owing a check on proper reservoir oil level, the pumps should be returned to service using normal startup procedures. G. Control Rod Drive Mechanism (CRDM's) + This transient had no impact on the ability of the CRDM's to perform a safety function (trip or maintain integrity of RCS pressure boundary). The maximum RCS pressure experienced and loss of component cooling water did not adversely affect the operation of the CRDM's. The high humidity in the Reactor Building may have, however, degraded stator insulation resistance. The majority of past CRDM failures have been attributed to moisture. All CRDM's should be checked for proper insulation resistance prior to their return to service.and, if necessary, dried out to achieve acceptable readings. H. Pressurizer Relief Yalve and Relief System 4 The pressure, temperature, and flow conditions experienced by the power operated relief valve (PORV) were not outside of its design parameters with the exception of any two-phase flow which the valve experienced. To the best of our knowledge, the PORY valve performed as expected and should not have been substantially affected by the transient conditions. It is not known, hcwever, if the valve did indeed close when it was de-energized. 1 Although the pressurizer code safety valve (s) lifted on steam, it experienced water flow for a considerable length of time. The relief of water through the code safety valve is not a normal condition and may have had some detrimental effect on the valve internals. Reaction forces imposed by the valve on the pressurizer nozzle due to the flow conditions (i.e., water versus steam) should not have been any greater then the normal design loads. However, the several hour duration of flow through the discharge piping may have resulted in excessive expansion of the piping and imposed loadings on the valve and pressurizer nozzle in excess of that considered in the original design. Although the conditions experienced by the PORY and code safety valves should not have substantially affected their structural integrity, or their ability to perform their intended relief function the following actions are recomended prior to their return to operating service: 1. Perform a visual inspection of the pressurizer relief system (i.e., PORY,-both code safety valves, and the discharge piping). Inspection of the discharge piping system including hangers should be perfonued to ensure that no gross distortions have occurred. 2. Confirm by calculation that the axial loads and moments imposed on the valves and pressurizer as a result of the extended period of discharge to the quench tanks are no greater than those considered in the original design evaluation. Page 35 l ~

( ~ e 3. Di sassembly, inspection, and refurbishment (as re'uired) of the PORY and code safety valves. I. Fuel The conditions experienced by the fuel should not have failed any sound fuel rods. The activity seen is consistent with the predicted 15 to 20 leaking rods present prior to the incident. No fuel technical specifications limits were violated. The pressure-temperature envelop did exceed the B&W recomended " operating limit" curve to ensure fuel compression. However, we. estimate that the fuel actually remained in compression during the pressure reduction phase. A detailed evaluation would be necessary to confirm this preliminary assessment. t Page 36

e -- .e e ,,,c Y..~ REFERENCES 1. Crystal River-3 Model 855 Computer Alarm Log - February 26, 1980 2. Crystal River-3 Sequer.ce of Events Monitor - February 26, 1980 3. Control Room Charts - February 26, 1980 Page 37

. a. :... 6 i ATTACHMEN' 2 DATA FORWARDED TO GAI FOR RELIEF VALVE ANALYSIS

1... _.

l g INTEROFFICE CORRESPONDENCE Crystal River Nuclear Plant CR 3 (triltt) (maltCast) sesitCT: Crystal River Unit 3 Data Requested by Gilbert for Relief Valve Analysis TS: Mr. F. J. Tomazic SAft: March 24, 1980 Gilbert Associates, Inc. 3-B-5a In an informal correspondence from P. L. Bunker to J. C. Colby, a request for information concerning the transient of February 26, 1980, was placed to assist in making a thermal-hydraulic analysis on the pressurizer relief lines. This information is attached. Please note that the information enclosed is based on the format and times specified by Gilbert. However, it should be recognized that the sequence of events, times and some data analyzed by B & W does not entirely agree with the data taken from the FPC report. A copy of both reports is attached for your information. On the data sheets attached, the information is identified as from which report it originated. Should there be any questions or a need for additional information, please contact me. O T. C. Lu'tkahaus Technical Services Superintendent TCL/jl xc: T. C. Lutkehaus G. L. Boldt M. W. Culver Attachments. C 908 205 ($) a

TABLE 1 - COMPARISON OF PZR. LEVEL CURVES ( NO. SOURCE BRIEF DESCR. (including Data source) PROBLEMS ASSOCIATED WITH THE CURVE 1. FPC report Curve with PZR. height (in inches) Not properly graduated to allow (calculated and PER. scale reading vs. time. easy, accurate reading. The from pressure calculations were based on actua data) pressure readings but also on an assumed PORV leak rate. The ac-curacy of the curve depends on the accuracy of the assumption. 2. FPC report PZR. level vs time 14:00-22:00 This is simply a copy of curve No. 3 (below) on an expanded scale. 3. FPC report PZR. level recorder strip chart The recorder failed when the pow was lost and when power was restored, the pzr. was already solid. 4. B & W post Fig. III-10 PZR. level indication Shows PZR. level flatten out as trip review (360 to 840 seconds from the if it had gone solid at approx. trip); 14:30, 3 minutes before current estimates of solid conditions. k This, in itself, is not neces-sarily a problem, it could show pzr. really went solid at 14:30. However, it levels off ac 200", about the same as initial con-ditions. It shows a normal operating level when it should show solid. The problem with th: curve is probably invalid temper-ature compensation during the incident when some instrumentatic was lost. 5. B&W Report Fig. III - 23 PZR. level indication The curve does not start until 3-1/2 hours after the trip. l l ( -1a )

..-u--.... l TABLE 2 - SOURCE OF SUPPLIED DATA AND THE REASON FOR SELECTING THAT SOURCE TIME DATA POINT , SOURCE REASON 14:23:21 A) ' RCS Hot leg press. R&W/FPC initial Conditions Same Data

1. RCS Hot leg Temp.

FPC-initial conditions BEE-Fig. III-4 Same Data B) 1. PZR. level B&W/FPC initial conditions Same data

2. PZR. press.

B&W/FPC initial conditions Same data

3. PZR. temp. (steam)

B&W/FPC initial conditions Same data C) 1. RC Drain Tank level FPC - operators logbook No other data available.

2. RC Drain Tank press FPC No other data available.

3. RC Drain Tank temp.

FPC No other data available. D) 4" Tail pipe temp. FPC computer summasies-No other data available. 14:25:50 A) 1. RC Drain Tank level FPC annunciator logs No other data available.

2. RC Drain Tank press FPC No other data available.

3. RC Drain Tank Temp.

FPC No other data available. B)1.PkR. level FPC The only curves available this time span were curves 1 & 4 (from Table 1). Curv. 1 indicates a gauge readin of 100" while curve 4 indi-cates 174". Curve 4 is a temperature compensated curve with questionable temperature compensation (due to multiple instrumen failures). Curve 1 has a more reasonable shape when the other data is consideri and is based on fairly rel: able pressure data. There-fore Curve 1 was selected.

2. PZR. press.

B&W; Fig. III-l Largest scale pressure cur-

3. PZR. temp.

[ B&W; Fig. III-4 only source for this time / span. 14:33:30 A) 1. RCS Hot leg press. B&W; Fig. III-l Largest scale pressure cur-

2. RCS Hot leg temp.

B&W; Fig. III-4 only source for this time span B) 1. PZR. level FPC Curve 4 (table 1) only re-gisters 200"; it should be solid. Use Curve 1. ( i

I TABLE 2 - SOURCE OF SUPPLIED DATA AND THE REASON FOR SELECTINC THAT SOURCE TIME DATA POINT SOURCE REASON 14:33:30 B) 2. PZR. press. B&W; Fig. III-l largest scale pressure (continued) curve

3. PZR. temp.

B&W; Fig. III-4 only source for this time span. C) 1. RC Drain Tk-level FPC drawings only source

2. RCDT press.

Post trip review only source

3. RCDT Temp.

Computer alarm only source D) Tailpipe temp. Computer alarm only source VALVE DATA A) PORV (RCV-10)

1. Flow Rate FPC drawings only source

2. Min. flow area FPC drawings only source

3. Drawing N/A N/A 4.

2-phase testing NONE no tes*.ing found

5. Valve opening RC Hydrotest only source time i

B) RCV-8 1. Flow rate FPC drawings only source 2. Min. flow area FPC drawings only source 3. Drawing N/A N/A 4. Valve Opening time NONE no data found f (

( 1) 14:23:21 [-14 sec. from reactor trip] before PORV opens. This was only one second into the incident therefore the change in FW and Rx demand at 14:23:20 (B&W report) has had insufficient time to affect core thermal characteristics and plant initial conditions can be assumed. A. RCS HOT LEG 1. Pressure 2157 psig 2. T 600*F from incore T/C 26 H B. PRESSURIZER 1. level 202 inches 2. pressure 2157 psig - from RCS pressure; no direct pzr. pressure data available. 3*. temperature (n am) - assume saturated steam for initial conditions -+ Tsat = 647'F. Also, PZR. temp. was 648.5*F at 08:40:40 on 2/26/80l C. RC DRAIN TANK. 1. level 7.7 feet - from operators M gbook (1150 a.m.) 2. pressure O to 2 psig - assuming normal operating conditions 3. temp. 100*F - assuming normal operating conditions. D. 4" TisIL PIPE TEMPERATURE & LOCATION OF THERMOCOUPLES One temperature element on each line (see attached drawing, P-304-651, for locations). VENDOR MANUFACTURER MODEL NUMBER COMPUTER POINT B&W RC-17-TE1 RCV-10 Thermo Electric 2A2121A R 205 B&W RC-17-TE2 'RCV-9 Thermo Electric 2A2121A R 206 B&W RC-17-TE3 RCV-8 Thermo Electric 2A2121A R 207 at 12:43:12 on 2/26/80 R207 = 199.6*F assume this as initial conditions at 05:38:18 R205 = 203.3* F assume this as initial conditions s ( l

L

0 I 2) 14:25:50 [135 sec. after trip] before PORV closed A. RC DRAIN TANK - no numerical data available 1. level - alarmed high at this time therefore the level should have been approx.11'10" (high level alarm setpoint) 2. pressure-the PORV was closed about this time. The first indication of the rupture of the RCDT rupture disc was not for another 1-1/2 min., but t.c disc must have ruptured before the PORV was closed since this was the only significant input to the tank at this time. Therefore the pressure was probably about 110 psig (disc rupture pressure) or less. 3. temperature - the worst case temperature would be the temperature of the saturated steam in the PZR., 608'F. B. PZR. 1. level 100" 2. pressure 1645 psig; this is RCS pressure - pzr. pressure should be approximately this pressure or slightly less. 3. temperature 608' F. (RCS Tsat); pzr. was assumed to not be solid yet (assumed to have gone solid around 14:33) therefore there should be steam in the pzr. at Tsat. 3) 14:33:30 [595 sec. after trip] before RCV-8 (code safety) opened. k A. RCS HOT LEG 1. pressure 2395 psig 2. temperature 560*F B. PZR 1. level-pegged high - indication over 320" - FPC curve reads 480 to 490 inches actual - pzr. solid. 2. pressure - approx. 2395 - same as RCS since the code safety has not opened 3. temperature - approx. 560*F - indications show the pzr solid at this point no steam. The pzr. heaters have high pressure cutoffs below this pressure and so should not be contributing any heat. Therefore pzr. temperature should be the same as RC hot leg temperature. C. RC DRAIN TANK 1. level - unknown - worst case would be up to the RCDT rupture disc - approximately 16-1/2 feet from the bottom head. 2. pressure - unknown - after rupture disc blew and before the code safety opened it may have dropped to near RB pressure 22 14.96 psia from post trip review. 3. temperature - unknown - worst case wnuld probably be the temperature of th PORV tail pipe recorded at 14:31:54 (after the PORV had closed). If the tail pipe had cooled to this temperature, the RCDT, which was relieving steam to the RB and may have had cooling water, should have cooled to thi;.emperature or lower - 348.6. W "-9 W e M

. a..;. m.v. e I 14:33:30 (continued) D. 4" TAIL PIPE TEMPERATURE & T/C LOCATION RC-17-TE1 (RCV-10) out temp (to RC Drain Tank) = 348.6 RC-17-TE2 (RCV-9) out temp (to RC Drain l'ank) = 146.3 RC-17-TE3 (RCV-8) out temp (to RC Drain Tank) - 233.4 These computer points printed out at approximately 14:32 and is the only tail pipe temp. data recorded during the incident. 4) VALVE DATA PORY (RCV-10) a) Flow rate @ rated conditions 100,000 lb/hr b) Min Flow area - unavailable, bu': can probably be calculated from drawing dimensions. 4 c) drawing - not included; our copy here is toolight to reproduce. See Gilbert drawing #4203-77-262-0 d) Any two phase testing done. None was found recorded after searching through Hot. Functional Testing and Purchase Request records and correspondence. Valve books listed no 2 phase tests. If information on 2 phase testing is uncovered, it will be - forwarded. At the present, it appears there wss no 2 phase (- testing. 3) Valve opening time - specified opening time <1 sec. No actual test. data found. VALVE DATA CODE SAFETY- (RCV-8) t a) Flow rate @ rated conditions 317,973 lbs/hr at 90% rating b) Min flow area 2.545 sq. in, c) drawing (attached) - Gilbert drawing No. 4203-77-263-0 d) valve opening time - no data uncovered; probably comparable to PORY opening time. 5) TRANSIENT DATA (attached) b . I a

--~ ",, ^ ^- r o - ;"~', Rev. 5 Page i a ('. SEQUENCE (AS OF 2300 3/1/80) 26 February Transient CR-3 EVElfr SYNOPSIS At 14:23 on February 26, 1980 Crystal River -3 Nuclear Station experienced a reactor trip from approximately 100% full power. A synopsis of key events and parameters was obtained from the plant computer's post-trip review and plant alarm summary, the sequence of events monitor, control room strip charts, and the Shift Supervisor's log. The reactonness operating at approximately 100 % full power with incegrated Control System (ICS) in automatic. No tests were in progress and minor =ain-tenance was being performed in the Non-Nuclear Instru=entation (N TI) cabinet "Y". Time Evtnt Cause/Co ents 14:23:00

• The following is a smry of plant conditions prior to the trip nux 98.6%

RC Pressure 2157 psig i PZR level 202 inches W tank level 71 inches "A" 599'F. "B" 600*F. "A" 557'F. T "B" 556 *F. RE now "A" 73 I 106 lbs/hr RC now "B" 73 I 106 lbs/hr Latdown nov 48 gym OTSG "A" Iv1 (OP) 67: OTSG "B" 1v1 (OP) 65" OISG "A" FRLV 242 inches OTSG "B" FRLV 254 inches OTSG "A" Pressure 911 psig OTSG "B" pressure 909 psig Main Steam Pressure 894 psig m in Stamm Temp. 589*F. Condenser Vacuum 1.76 Generated W 834 DFI level 12.7 ft. Feed.n'ow "A" 5 I 100 lbs/hr Feed now "B" 5 I 10 lbs/hr Feed. Pressure "A" 970 psig Feed Pressure "B" 968 psig 14:23:21 +24 Volt Bus Failure (NNI i power loss'"I" supply) the positive 24 VDC bus shorted dragging the bus voltage down to a y ..m.... . _ ~ gm. s _.. - 3.. - u ma_. ns, e. w ....w.

p e Rev. 5 Page 2 (G s Time Event Ceuse/Comnents low voltage trip condition. There is a built-in % to h second delay at which time all power supplies will trip. There was no trip indication on negative (-) voltage. This event was missed by the l annunciator. Following the NNI power : failure, much of the control room l indication was lost. Of the I.nstrum- -entation that remained operable transient conditions made their indic-cation qlestienable to the operators. ' i 4 14:23:21 PORV and Spray Open When the positive 24 VDC supply was lost due te the sequence discussed ab<! the signal monitors in NNI changed st. causing PORV/ Spray valves to open. The ; POK7 cirecitry is designed :o seal in upon actuation and did so. The result: loss of the negative 24 VDC halted spray valve =otor operator and preven: PORY seal in from clearing en icw t pressure. It is postulated that the Pt' opened fully and the spray valve strol for approxinately h second. The 40% of indication on spray valve did not actuate, therefore, the spray valve d: not exceed 40% open. 14:23:21 Reduction in Feedwater As a result of the "I" power supply fcilure many primary plant control signals responded erreneously. Teold failed to 570*? (nornal indication was 557*7) producing several spurious ala: Tave failed to 570*7 (decreased). The resultant Tave error modified the reac demand such that control rods were withdrawn < yto increse Tave and reacte power. The power increase was terninat at 103% by the ICS and a " Reactor Dena High Limit" alarm was received. Thot failed to g70*F (low) and RC flow fail to 40 I 10 lbs/hr in each loop (low). Both these failures created a BTU alar! i and limit on feedwater which reduced feedwater flow to both OTSG's to essentially zero. Turbine Header Press failed to 900.psig (high) which caused. .)- the turbine valves to open slightly to

e Rev. 5 Page 3 ( s Time Event Cause/Cemments regulate header pressure thus increasing generated megswatts. These combined failure resulted in a loss of heat sink to the reac initiating sn excessively high RC pressure condition. 14:23:35 Reactor Trip / Turbine Rx trip caused by high RCS pressure at 230C Trip Turbine was '.; ripped by the reactor. 14:24:02 Hi Pressure Inj. This was a computer printout and indicates Req. (Flag) <50* subcooling.* See attached graph of RC Pressure / Temp. vs. Time. This graph is base on Post Trip data and actual incere ther: couple data. From the reactor trip point (1 to 14:33, core exit temperature data was obtained by extrapolstion and calculated da This is eupported by.two alar = data points plotted at 18' and 21* of subecoling during this period from the computer. It is i= port to note that lowest level of subcooling was 8*7 for a very short period of ti=e.

• NOTE: This computer program was initiated a result of the IMI incident.

14:24:02 Loss of Both Suspect condensate pump tripped due to high Condensate Pumps DTT level. This is verified by ???? printed by computer, indicati:ig the level instrumen was over ranged as well as a low flow indication in the gland steam condenser as indicated by computer. 14:25:50 PORY Isolated At this time a high RC Drain Tank level'als was received. This was resultant from the PCRV remaining open and was positive indies that the PORV was open. At this time, the operator closed the PORV block valve due to l RCS pressure decreasing and high RCDT level 14:26:41 HPI Auto Initiation EPI initiated automatically due to low RCS 3 pressure of 1500 psig. The low pressure ~ condition was resultant from the PORV re=ai: full open while the plant was tripped. Full HPI was initiated with 3 pumps resulting in 5 approximately 1100 gym flow to the RCS. At this time, all remaining non. essential R.B. isolation valves s, I i es m e me ,~ easesse-G--- age. e see e e e e *

.*.:,..n

~

3-

-"P O O

• Rev.5 Page 4

( Time Event Cause/ Comments were closed per TMI Lessons L'earne'd Guidelin 14:26:54 RC Pumps Shutdown Operator turned RC pumps off as required by the applicable emergency procedure and B & 5 small break guidelines. 14:27:20 RB Pressure Increasing This is first indication that RCDT rupture disc had Yuptured, RB pr m ure increase dat was obtained from Post Trip Review and Strip Chr indication. 14:31:32 RB Pressure High This* alarm was initiated by 2 psig in RB. 1 is attributed to steam release from RCDT. C safeties had not opened at this time based t; tail pipe temperatures recorded at 14:32:03 (Computer). 14:31:49 OSTG "A" Rupture Matriz This occurred due to <600 psig in OTSG "A. Actuation The low pressure was caused by OTSG "A" boil ' dry which was resultant from the BTU 11=1: a 'm failed OTSG 1evel transmitter. This resulte in the closure of all feedwater and steam bl valves which service OTSG "A". 14:31:59 Main Feedwater Pump 1A Caused by suction valve shutting due to Tripped matrix actuation in previous step. 14:32+14:41 ES A/B Bypass Manually bypassed and HPI balanced between : 4 nozzles (Total flow approximately 1100 gp= -small break operati=g guidelines). 14:32:35 Started Steam Driven Started by operator to ensure feedwater was Emargency Feedwater Pump available to feed OTSG's. 14:33 Core Exit Temp. Verified The core exit incore ther= occupies indicated the highest core outlet temperature value va 560*F. RCS pressure was 2353 psig atthis ti- 'therefore, the subcooling margin at this ti=. was 100*F. Minimum subcooling margin for thi ~ l entire transient was 8 F. ~ s x i 14:33+14:44 Started Motor Driven Emer-Same discussion as " Started Steam Driven E=e-gency Feedwater Pump gency Feedwater Pump." 14:33:30 RC Pressure High (2395 psig) At this point, pressurizer is solid and code safety lifts (RCV-8). This is the highest RCS pressure as recorded on Post Trip Review. Agarentipn RC7-8 lif ted _ ear 1R dun m rrrn

Rev. 5 Page 5 ( h Time Event Cause/ Comments leakage prior to the transient and RC7-9 dic not lift. 14:34:23 RB Dona Hi Rad Level RMG-19 alarmed at this point. Highest leve' indicated during course of incident was -SC(e R/hr. High radiation levels in R3 caused b: releast of non-condensable gases in the pre: urizer and coolant. 14:35:33 Attempted NNI Repower With-This resulted in spikes observed du de-e=er-out Success gized strip charts. 14:36:50 Computer overload caused by overload of buffer. Resulting in no further computer data until buffer catch-up with printout. 14:38:15 FWV-34 Closed This valve was closed to prevent overfeedin; OTSG "B" b,eyond 1002' indicated Operating pz 14:44:12 NNI Power Restored Success-NNI was restored by removing the X-UNI Peve: ( fully Supply Monitor Module. This allowed the breakers to be reclosed. At this ti=e, it t observed that the "A" OTSG was dry, the pre: urizar was solid (Indicated off scale high) RC outlet temperature indicated 556*F (Loop & B average), and RC average temperature int cated 532*F (Loop A & 3). The highest core thermocouple te=perature at this time was 5: RSC pressure was 2400 psig (saturation te=p this pressure is 662*F.). This data verific natural circulation was in ororress and the plant subcooling margin was 131*7. (based at core exit thermocouples). 14:44:31 RB Isolation and Cooling Actuation At this time, RB pressure increased to 4 ps: and initiated RB Isolation. The operator verified all i= mediate actions occurred pro; for HPI, LPI, and R3 Isolation and Cooling. increasing R3 pressure was resultant from _Rf passing HPI at this time. 14:46:10 Bypassed HPI, LPI and RB These "ES" systems were bypassed at this ti: Isolation and Cooling to again balance HPI flow and restore cooli: water to essential auxiliary equipnent (i.e. j RCP's, letdown coolers, CRDM's etc.). I l = t L -. _ _, _ ~.. -.

5 e

Rev. 5 Page 6 (~ s. Time Event Cause/Consnents 14:51:57 Rupture Matrix Actuation on The actuation was resultant from a det-OTSG-B radation of CTSG-B pressure. Cold emer-gency feed was being injected into the CTSC at this tima. This matrix actuation isolat all feedvater. and steam block valves to et B-0TSG and tripped the "B" main FW pump. Bc Emergency PW pumps were already in operatic at this time. B-CTSG 1evel at this time va 70% (Operation Range). 14:52 BPI Throttled and RCS At this time, the maximum core exit ther=o-Pressure Reduced to 2300 couple temperature was 515*7, RCS pressure psig was 2390 psig. Therefore, the subcooling 1 margin was 147'7. Natural circulation was in effect as verified previously. All con-ditions had been satisfied to throttle EPI. Therefore, flow was throttled down to appro imately 250 gpm to reduce RCS pressure to 2300 psig in order to attempt to reduce the flow rate through RC7-8 and into the RB. 14:53 ReestablishedLe$down At this time, the operator was atta=pting to establish RCS pressure control via nor=a. RC makeup and latdown. 14 :56 Opened W Pump Recire. This was done to assure the W pumps would Valves have =4n4 am flow at all times to prevent possible pump damage. 14:56:43 Bypassed the A-0TSG Rupture Feedwater was slowly admitte: Matrix and Reestaolished - to the A-0TSG which was dry up to this poin: Feed to the A-0TSG Feedwater was admitted through the Auxiliar-FW header via the EW bypass valves. The feedrate was very slow in order to minimire thermal shock to the STSG and resultant dept surization of the RCS. RCS pressure control was very unstable at this time. 6 6 l .= -. =

.c Rev. 5 Page 7 ( ) Time Event Cause/ Comments 1N:57:09

• Bypassed the B-0TSG This was done,to regain W control of the Rupture Matriz B-0TSG. Level was still high in this OTSG 1

(approximately 65% Operating Range). Therefo: feed was not necessary at this time. Be Mair Steam Isolation valves were open in preparation for bypass valve operatien (when necessary). 14:57:15 Established RC Pump This was.done in preparation for a RC? start Seal Escurn (when tiecessaz7) and to minimize punp seal degradation. 15:00:09 Reestablished Level This verified feedwater was being admitted et In A-CISG the OTSG and made it available for core cooling via natural circulation. Feed to thi: generator was continued with the intent of proceeding to 95% on the operating Range. 15:00:09 77*.7 Subcooled "A" Loop This value was based upon "A" RCS loop parameters at this ti=e. The "A" leep was being cooled down at this ti=e by the A-0TSG b_ fill and the operator was attenpting to equalize loop tenperatures. .i 15:15 23*F Delta-T/ Manned the ~At this time, loop temperatures were nearing Technical Support Center equalization. This delta-T was calculated from loop A & B T 's and core exit thermo-e couples. 15:17 Declared Class "B" Emergency This was done based on the fact there was a ~ ~ loss of coolant through RC7-8 in the containment and HPI had been initiated. All non-essen,[1al Cit # 1 eersonnel were directed ~ . to irvacuate 'and-c'entact off-site agencies ~b ~gan. Survey ~ tee:d was's4ne to' Auxiliary 3uil 15:19 Opened Emergency W Block h this point the A-0TSG 1evel was increasing to B-0TSG and the decision was made to commence filling the B-0TSG simultaneously. The intent was to go 95% on both CTSG's without exceeding RCS cooldown limits (10097/br) while maintaining RCS pressure centrol. ~ i i. ( ) 1 J l l ?

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~ Rev.5 Page 3 ( s. Time Event Cause/ Comments 15:26 Lo Level Alarm in Sodium This was recultant from the tank supply val Hydroxide Tank opening when the 4 psig R3 isolation and cc ing signal actuated. The sodium hydroxide released to both LPI trains. - Sodium Hydrds: was admitted to the RCS via. EPI from.the 3'4: (Approx 1'=ately 2. ppm injected into the RCS.: 15:50 TerminatedhPI At this time, all conditions had been satis fled (per smtl1 break operating guidelines) to terminate HPI. RCS pressure control had been established using nor=al makeup an letdown. HPI was terniniated and essential all releases to the RB vere discontinued. 16:00 Commenced Pressurizar At this time, RCS pressure and te=perature Heatup were well under control. Natural circulati was functioning as designed (approx 1=ately delta-T). RCS ta=perature was being maints at approx 1=ately 450*. RCS pressure was ap imately 2300 psig. The decision was nade a S this point to co==ence pressurizer heatup i / preparation to re-establish a steam space i che pressurizer. 16:07 Survey Team Report The Emergency Survey Team reported no radia survey results taken offsite vare above bac ground. 16:08 :04 Shutdown Steam Drive Emergency FW Pump The motor driven E=ergency W pu=p was runn. therefore, the steam driven pu=p was not ne. The plant remained in this condition for ap: roximately 2 hours, while heating up the pr l urizer to sacuration temperature for 1800 p: 1 16:15 Press Release Media was notified of plant c' 1 18:05 Established Steam Space Pressurizar At this point, pressurizer temperature was approximately 620*F. Pressurizer level was brought back on scale by increasing letdown. i. From this point pressurizer level was reduce to normal operating level and normal pressur was established via pressure heaters. 18:30 Terminated Class B Emergency State and Feder'l Agencies notified. a l

_m g - ~ Rev 5 Page 9 (.. Time Event Cause/ Comments ~ 21:07 Forced Flow Initiated The decision was made to re-establish force < in RCS flow cooling in the RCS at this time. B&W and NRC were consulted. RCP-13 and ID were started. At this point,,RCS parameters vert stabilized and maintained at RC pressure-20i peig, RCS temperature-420'F. Pressurizar level-235 inches. The plant was considered a normal configuration. O e e b 9 4 e } t l i y i

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INOPERABLE INSTRLHENTS ~ TAG NO. DESCRIPTION LOCATION MU-14-LT 1 MU Tank Level Control Board MU-14-LT2 CA-10-TT Boric Acid Temp. All CA-ll 4T Level All CA-13-LT All CA-14-PT ". Pump Discharge All BS-1-dpt 1 RB Spray Flow Control Board BS-3-LT Thiosulphate Tank Level Control Board BS-5-LT Tank Level Control Board BS-15-PT Thios. Tank Pressure Control BS-14-PT Hydroxide Tank Pressure Control Board CF-Z-LT 1 CF Tank Level Board CF-2-LT 3 CF Tank Level Control ( CF-1-PT-1 CF Tank Pressure CF-1-PT 3 CF D.H. 1-dpt 1 DH Flow DH 2 TT 1 Dh Ins. Te=p Computer MU-27 dpt RC pump seal flow All MU-23-dptl HPI flow Contrl Board MU-23-dpez MU-2-PT MU pump discharge pressure computer MU-17-PT MU tank pressure Control Board MU-24-dpt RC Makeup flow Control MU-31-ft 1 control bleed off Computer MU-31-ft 2 Control bleed off l MU-31-ft 3 2fU-31-ft 4 l

INOPERABLE INSTRUMINTS TAC NO. DESCRIPTION LOCATION MU-7-dpt 1 RC Pump Seal Flow Control Board MU-7-dpc 3 MU-7-dpt 4 MU-7-dpt 2 " 7 SP-7A-dpt Sbartup W Flow All SP-8A-dpt 1 hin W flow All -SP-8B dpt-1 hin W Flow All SP-8A-dpt,zr hin W flow Computer SP-5A-TTI W Temp. All SP-5B-TTI W Temp. All SP-5A-TT W Temp. Computer SP-6A-PT 1 OTSG Pressure All l SP-6B-PT 2 All SP-10 A PT 2 Turbine Inlet Pressure All SP-10B-PT 3 2 All SP-3A-TTI OTSG Downcomer Te=p. All SP-3B-TTI All SP-3A-TT2 Computer SP-4A-TT hinsteam Temp. All SP-1A-LT 4 OTSG Startup Level All SP-1A-LT 4 All SP-1A-LT 5 All l SP-13-LT 4 Control Board SP-13-LT-5 Y All 1 l' G -- ; - -~ ~ ~ ~ ... -. - ~. - - - - - - - -

\\ a ,s INOPERABLE INSTRL'MENTS TAG NO. DESCRIPTION LOCATION .JP-1A-LT 2 OTSG Operate Range Level All l SP-13-LT 2 All SP-1A-LT 3 All SP-1A-LT 1 Full Computer SP-15-LT 1 Full Computer RC-10A-PT 1 RC Pump Cavity Seal Pressure conteol Board RC-10A-PT 2 RC Pump Cavity Control Board RC-10B-PT 1 RC-10B-PT 2 RC-19A-PT 1 RC-19A-PT 2 RC-193-PT I RC-19B-PT 2 (. AC-SA-TTI T Narrow Range All C RC-5B-TT2 All RC-SA-TT2 Wide Range All RC-5B-TT2 RC-5A-TT4 Co=puter RC-4A-TT 1 T Temp. All h RC-4B-TTl All RC-4A-TT 4 Computer RC-14B-FT RC Flow Control Board RC-1-LT 1 Press. Level All RC-1-LT 2 RC-1-LT 3 Control Board i All

• 1C-2-TT J, RC-2-TT 2 All

.=_ OPERABLE INSTRUMENTS TAG NO. DESCRIPTION LOCATION SF-1-LT 1 Spent Fuel Level Control Board FF-1-LT 2 CD-15-FT Condensate Flow CD-61-LT Dearator Level CA-12-TT Boric Acid Temp. Waste Disposal Panel BS-1-dpt 2 RB Spray Flow Control Board BS-7-TT Thics. Tank Temp. Control Board CF-2-LT 2 CF Tank Level All CF-2-LT 4 CF Control Board CF-1-PT 2 Pressures CF-1-PT 4 DH-2-TT2 DH Ins. Te=p. All' DH-6 TT 2 DH Cooler Inlet Temp. Control Board t DE-1-dpt 2 DE Flow DH-2-TT 1 DH Ins. Temp. DE-6-TTI DH Cooler Inlet Te=p. MU-23-dpt 3 HPI flow MU-23-dpt 4 MU-4-dpt Letdown Flow All MU-5-TT Temp. Control Board MU-2-PT MU Pump Discharge Pressure ( MU-18-dpt MU filterf.P i l SP-7B-dpt Startup FW flow Computer l l SP-6B-PT 1 OTSG Pressure All' l l SP-6A PT 2 Computer l SP-10A-PT 1 Turbine Inlet Pressure Computer SP-10B-PT 2 3, 4* -r

w.-.. OPERABLE INSTRUMENTS TAG NO. JESCRIPTION LOCATION SP-4B-TT Mainsteam Temp. Compueer SP-1A-LT 1 OTSG Full range level Control Room SP-15-LT 1 OTSG RC-3A-PT 3 Safeguards Wide Range Press. RC-3B-PT 3 RC-5A-TT3 T Narrow Computer e RC-5B-TT3 RC-1-LT 3 Pressurizer level RC-131 PT Low Range RC Pressure All SP-1B-LT 4 OTSG startup level Computer SP-13-LT 3 Oper. Level Control Roo ( i l l ( 1 g s .~n. --e. n -r

OPERABLE / INOPERABLE ~ 'o .,i* DEPENDING ON SWITCH POSITION POS. TAG NO. DESCRIPTION STATUS LOCATION SP-7B-dpt Startup W flow Bad Control Baard N.S SP-8A-dpt 2 Main FW flow Bad Control Board N.S. SF-8B-dpt 2 Main W flow Bad Control Baord-N.S SP-5A-TT 2 Feedwater Temp. Bad Control Board N.S. SP-5B-TT2 Bad N.S SP-6A-PT 2 OTSC Outlet Press. Bad N.S. SP-10A-PT 1 Turbine Inlet Press. Bad N.S SP-10B-PT 1 Turbine Inlet Press. Bad N.S. SP-3A-TT 2 Downcomer Temp. Bad N.S. SP-3B-TT 2 Bad All N.S. SP-1B-LT 4 Startup level Good Computer SEL SP-13-LT 5 Bad SEL SP-1B-LT 3 OTSG Level Operate rnge Good Control Roo= k N.S. SP-1A-LT 3 Bad N.S. RC-SA-TT 3 T Narrow Bad c N.S. RC-5B-TI 3 T Barrow Bad e SEL RC-5A-TT 4 T vide Good Control Room c SEL RC-5B-TT 4 T Wide Good All c N.S. RC-4A-TT 4 "A" T Bad Control Room h N.S. RC-4B-TT 4 "B" T BAD All h i SP-1B-LT 3 Oper. Level Bad Computer Tavg Ind. Bad -i A TC Bad SP-4A-TT Main Steam Temp. Bad Control Room

• * * ~ ~ ~
• ~ ~ ~ - "

~~ ... r- - '~~.C"~-.

• . -.:.~.

a a. ',*/

• RDIOTE SHUTDOWN INSTRUMENTATION
• l*o TAG DESCRIPTION STATUS _

RC-4A-TTl "A" T I perable h RC-45-TT1 "B" Th Inoperable ^ SP-1A-LT 4 Startup level Inoperable SP-13-LT 4 Startup level Operable SP-6A-PT 1 OTSG Outlet Press. Inoperable SP-6B-PT 1 Operable DH-2-TT 1 D.H. Inj. temp Inoperable DH-2-TT 2 D.H. Operable MU-14-LT L MU Tank Level Inoperable MU-14-Lt 2 MU Tank Level Inoperable ( mne.. m, de eg a+ 0 s m +=6

• • • • Nh=

~ t-J1 .* t P. MW i - E aimoe 4 aos **** rete ara uerru._. n

• e..

a. e-f N141012 592 1212 s PERS ACC MATCH NOT FULL CLSD i

N141015 043 1*13

• PERS ACC HATCH INTKL ENGAGED A141018 849 1*13 PERS ACC HATCH INTKL ENGAGED A141023 706 1212 PERS ACC HATCH NOT FULL CLSD i3 weatnam too ta
• a cree ara uavau sn* rm.

c. cn 3.

N141049 0*2 1213

• PERE ACC HATCH INTKL ENGAGED 1

A141331 305 080e SS COMPR TRIP 7 N, start *** noon a ce rnwee vote N141439 900 1541

• DG RM 3A AHF 3B AUTO STRT

_.J. N141439 927 1539 s DG RM 3A AHF 3A AUTO STRT 4 A.A* ode Adi S194

• U Pe TL f f fLF U?e ri m, nM i

N142C54 063 0128

• CW PP 3B LUBE WTR FLO LOW j.'

A142054 162 0129 CW PP 3B LUBE WTR FLD LOW C N1490'A 90c otap e FM PD Th ftfpr UTR rf n i nu ( b l p(f ) Ji ~ n142300 969 1328 RC_Dstrr rn0P ASB DIFF TEMP HI **~~~ N /

L A14'320 9S2 0946 C3D 3B'LVL LOWl'~

i 3 4 4???^ se. taa* -o i r-nnten True u, 11 A14:320 980 0944 SG 3A LVL LO A -:a. 2*. A142320 989 1119 it" FT.mHBACK IN EFFECT p )

r *%e t a a a t a. nem tasa ecret rire-erwatte etr utu ero_in neru li A142321 024 1125 UNIT NASTER IN TRACKING

- - ~ " * ., g' 4442321 027 1126 SG A ON BTU LIM 4e 9:4riat eS- *tae e er em r* e nne een e-er vrup w-2 A142321 086 1112 RX DEMAND LIMITED HI .)jf f ~T-E A14*321 100 1143 + 24 V NNI-X BUS FAIL ~ ~~ ~. kW.4g t, o r,ieasa. 4r sta? A a s t' wwt-v out cifre ratt E A142321 142 1955 T SAT 41 LOW SATURATION MARGIN E A142321 24E 1373 RC PZR LVL LOW ) 3 c..a, a4- .ste e - enva. re n e au 2 A142321 545 1756 A.E. GAS DECAY TNK AREA RAD LVL HT ~ A142436 894 0261 HD RHTR C WTR LVL HI ( ) A.4*av- .,e e.eet ma?T to nram A142442 36" 1015 LOW R2 PRESS TRIF SUB ASSY D' g A142443 403 0987 LCW RC PRESS TRIF SUB ASSY B (

• )

q v . 3aefe ea .au .e" na reree +n e

e..e seev

} E A142444 549 0973 LOW RC PRESS TRIP SUB ASSY A E N142448 622 0261

• HD RHTR C WTR LVL HI J

r 3.sasso ae, naon u* u-e we ven inu 1== N142501 266 0191 m INV 3C AC CUT UNDR VOLT N142514 361 1119

• RC FLO RUNBACK IN EFFECT

) m ...aear re-rane um u-o...... v a.. E N142526 323 0274

• HD HTR 2B LVL LCW E

A142526 544 0197 FIRE SYS TRBL y n rema-a* vne nao-un ute en ..n u-f A142520 0*2 0274 HD HTR 2E LVL LOW i

1. d42520 462 0288 DUMP VLV NOT CLSD HDV-56 m

...a -- -~...., . on.e.-ee -n e e..e .eev w-d A142535 260 0974 TEMP / PRESS TRIP SUB ASSY A ( 2 A14253 -3aae,6 065 092S TEMP /PRESSTRIPSUBASSYB} J n

• -nt nao, e un uve -e e u.

u, 1 /.142537 541 1000 TEMP / PRESS TRIP SUB ASSY C f .N142538 142 0197

• FIRE SYS TRBL vi

..,fa.r-fe-,ene, m e r e.... u, JC N142550 041 0274

• HD HTR 2h LVL LOW 28.,

A142550 724 1592 RC DR TNK LVL HI si-e,3*-e, -se ne,a un ure an. u. iau E U142627-6es 0303

• DEAR HI HI LVL DUMP CONT VLV HDV-83 2

A140633 345 0323 DR POT LVL HI (EXTR TO HTR 3) u_ .,rna,e vaa ss:e. un un su re n i.a u. C A14.* 641 906 0938.._.CHt1;..PM1500 PSI TRIP BI/ST TRIP ' l 9'o'51 ES ACT A TRBC ~ ~~ ~ vaa.23'O ?" 41*2o41 ) Nt4?A44 ato a ce are a reo, A*42644 800 1230 ES ACT A TRBL N142644 865 1230

• ES A2T A TREL

(- A140644 *02 1230 FS ACT A TRM

s O

b

f,, +. e i t i a ~~ so? ?n?T ! nopf Nn ern PtnN/ ? 4?T e O A142444 A142646 623 1020 LOADING SEO BLOCN : ACT A N142648 043'1230

• ES ACT A TRBL A142648 066 1230 ES ACT A TRBL N142e4G 328 1230
• ES ACT A TRPL t

A14p(49 TP' t?'o rc 4?T A TRM A.J.4. 244E._. 4J O939_ QHNQC-1 IZ2Q,P$ L, TRIP

• ? "?

TRIE.. ( 4 i A143648 469 0921 ES ACT A HP INJ ON D 7 A142i.4H._4B3 no*t re e. " T o we Tuf tw 1 4140648 507 1074 MU HP,IN)_F40 B-2 LOW A142744 882 1672 THROT PRESS LIM 1 914av44 9ne tA a, Tsear reree e eu 1 A142745 640 1672 THROT FRESS LIM 1 N142745 661 1672

• THROT PRESS LIM

.I e A14?'4A A46 1A79 TwPn? Prect i TM h N142746 687 1672

• THROT FRESS LIM N142747 003 0052
• GS EXHSTR PRESS HI

"? A34a o,an. ,u e. m + eeeee. ?- h N142747 OO2 1672

• THROT PRESS LIM e

A142747 964 1672 THROT PRF3S LIM n ute?747 ora 1Ava e turn? cerce evu i A142743 406 167 THROT PRESS LIM N140748 642 1672

• THROT PRESS LIM 3

l op A14994o 9po 9-ae pp 3?e e w et e ? yr tar- ? He e n' pra ?

• l) di A142749 329 1672 THROT PRESS LIM i;

N142749 342 1672

• THROT PRESS LIM p

AIA?Q4* 491 1A7" TMP97 PRret f TM h N142845 447 1672

• THROT PRESS LIM r

4142345 040 1672 THROT FRESS LIM 1 1 37 ueraose o4, 4-- , Tuenv erree e ?- l' il A14:347 903 1472 THROT FRESS LIM N142947 944 1672

• THROT PRESS LIM A142948 4**

t/7? TwRnv eReet ! TM N140948 460 1670

• THROT FRESS LIM E

A142848 882 1672 THROT FRESS LIM l1 K wtm?oap oaa

• Awa e Tucn? peree e *>

F A142949 3S6 1672 THROT FRESS LIM E N142949 425 1672

• THROT PRESS LIM 3

?? Nt4?n49 4oo o?97

• c'Rr CYR TR r!

s A142850 007 1672 THROT FRESS LIM 37 N142850 000 1672

• THROT FRESS LIM s

N?4re?S 74? 07ee v PP c tie n e evH Be'r' o'e r!n tnu F A14294 926 1672 THROT PRESS LIM 7 N142942 941 1672

• THROT F RESS LIM 3

F A142o47 54? 1A75 TH30T PREse LTM N142943 582 167

• THROT PRES LIM

+ A142944 267 1672 THROT PRESS LIM 8 7 w!42044 See 14?? + TuecT P4ree '_ ? = f A142944 663 1672 THROT FRESS LIM N142944 888 1672

• THROT PRESS LIN

~ 7 A142945 527 1672 THROT press LTM

• E N142945 542 1672
• THROT PRESS LIM F

A142946 488 1672 THROT PRESS LIM l 7 N142944 509 1672

• THeOT PKr99 L!M I

N142946 840 0261

• HD RHTR C WTR LVL H1 II A142947 106 1672 THROT FRESS LIM I*

N142947 1*7 1672

• THROT PRESS LIM E

A14294S 345 1672 THROT FRESS LIN B A143049 205 1308 RC FP 3A MTR TOF dis LVt. LOW U st43 toe sev 3,to er ce vs. 3T vena e e e. 9-A143120 308 0941 SUR ROD HOLD E A143120 307 1235 ROD DRIVE OUT INHIBIT ' J-s '"3 r- {' N147t?? ?oA oo?1 m re Ar? A He TMt ny M 1,1.. ,ba.A t4143102 925 1021

• LOADING SEO PLOCK 3 ACT A

-\\ / r4143122 929 1020

• LOADING SEO PLOCK ACT A

' !" #'^# N143122 *43 1022

• LOADtNG sEo N och 4 ar? A 3

1.i

f et - hI i I ~ w . w,.attae tea sn=n

• mn we tu, r, n z.a uv

-A143131 801 0929 ES ACT A NOT BYP A143132 240 0067 RB PRESS AT 2 PSIG A143133 720 1048 MU HP INJ FLO A-2 HI []~ N143141 083 0923

• ES ACT B HP INJ ON N147141 Aae inAo a Mo we tw a rtn a a we l'

4143141 723 1048 MU HP INJ FLO A-2 HI 1 H143141 924 1023

• LOADING SEQ BLOCK 2 ACT 3 7

o w143 tat eae tea-w inantun een nrnm-5 met m i 1 N143141 923 1026

• LOADING SED BLOCK 4 ACT B 1

N143227 721 1914

• COMPUTER ALARM e'

wistaan 79. .nao, wrr we tu, r,n r..e u-JL' A143228 409 1070 MU HP INJ FLO B-2 HI JW .A143228 587 1025 LOADING SED BLOCK 3 ACT B et atataae eat inat 'snantwn een nrner t art a 28 N143226 962 1070

• ML' HP INJ FLO B-2 HI 9

COMPUTER ALARM it A143,231 629 1, n*14 n 414 95v gav ,nantwn een etnar a arv a u A143233 200 1026 LOADING SED BLOCK 4 ACT B Gf

• bn, Aw T 3,5[

A143235 323 1521 CHEM ADD PP EFP-3 AUTO OP , a5 Nidta7M 7At 1-94 2 FurM ann PO rrp-1 TOTP .N143244 682 1365

• RC PRESS LOW di N143244 484 1366
• RC FLO 00P A LOW to A14354v, Ma,?am Ase emet CTaTu cab, Ut ut E

N143255 384 0280

• HD HTR 3B LVL LOW

(___,g, ~ 21 A143256 485 1364 RC PRESS HI g) at ' A142340 Soo iA7t - F-W Pnu? he PuR raf t E A143351 445 1672 THROT PRESS LIM E H143416 20s 0941

• TURB BYP ISOL VLV-(MSV-53) NOT FULL OPEN 24 y,454.e na.

no,- , v e, ave, e n. ..r. , e._.. - a s unt r... neen El N143438 100 02S5

• DUMP VLV NOT CLSD HDV-55 l

(- 3 N143442 706 1785

• RB DOME RAD LVL LOW / FAIL

,3 '3 wi47445 ?S? 1794 e no nnMr man tut 97 N143442 725 1784

• PRIM CLNG LETDOWN RAD LVL HI

( [) It A143443 626 1785 RB DONE RAD LVL LOW / FAIL ,L v avev445 maa. wee revu e, un tr?nnuu can ior ut j 2 A143443 645 1764 RB DONE RAD LVL HI 2 E. 4143522 401 0945 SG 3B LVL HI 3 A145-97 744 1Tia en Pp tha MTe ?Ne ntf ftn 1 6,, 2L A143533 887 1367 RC FLO LOOP B LOW f J! N143533 920 1144 * .24 V NNI-X BUS FAIL 4 g [,w.r. 3 g.4,-,v eae. tac,. mm ey we,_v eue e,.ee re -. -s E N143534 042 1363

• RC PRESS WIDE RANGE LOW-LOW 2t A143534 186 1128 SG A DN LOW LVL LIM

--.f. se ataveta,ma 42 _ am u wu _v ne,e e s t. i A143534 223 1146 - 24 V NNI-X PWR SUPP FAIL f. A143'34 289 1363 RC PRESS WIDE RANGE LOW-LOW a n.?,e,. .en a- , en er e, -m e v. , e.. 2! N143534 505 1120 *- SG A ON LOW LVL LIM I 21 N143558 684 02.77

• HD HTR 34 LVL LOW es' atava,A non 6 v

euer no e i., enu 2L .A143457 727 0297 HD HTR SB LVL HI 2L N143657 725 0287

• HD HTR 5B LVL HI es a,ste-e oa-eaca un uve ce it..

u, C N143459 843 0287

• HD HTR 5B LVL HI

.E A143703 122 0287, e HD HTR 5B LVL HI su wiattat ,4-eae un uve -n e or ut E A143703 58* 0287 HD HTR 5B LVL HI [ N143703 584 Ca87

• HD HTR SB LVL H1 m

c..itao, ca. 3me-un uve -e.... ut - 2L N143703 829 0287 s'HD HTR 5B LVL HI 4143703 844 0287 HD HTR 5B LVL HI' 7 wi a t?e.1 eso esas e un ute en eut ut A1437C3 903 0287 HD HTR 5B LVL HI N143703 926 0287

• HD HTR 5B LVL HI~

A143704 007 0287 HD.HTR SR.IVI WT. 1 y L l' .h g et i-j.- . - ~, -r

t fJ I 8 N14?704 Oeo 0?o? e HD WTP EP LVL H! N143754 248 1593

• RC DR TNN LVL LOW A143756 246 1593 RC DR TNK LVL LOW N142754 286 1593
• RC DR TNK LVL LOW A143756 '84 1593 RC DR TNK LVL LOW

( H14T?f_3 T47 ?-97 e RF DP TNV t Ut t nu N143805 681 0287

• HD HTR 5B LVL HI 1.

4143805 700 0287 HD HTR 5B LVL HI w?4,qne vn aany a un ute en,", ut f.g }y. , p g ?.' i N143812 461 1600

• TG BRG OIL LIFT PRESS LOW t

f 1134 ISOL VLV LOOP B FWV-34 CLSD-EF RED i % -** % '"^ ( A143S15 480, nano, nowo -f m j s e u.sva.e .n o,o unv n en uno -e i l^ J.' A143819 625 1593 RC DR TNK LVL LOW 1 N143952 564 03:3

• DR POT LVL, or,EXTR TO HTR 3)

HI ( e-at4 Sono taA na?? wn ute sa nu 21 N143901 403 0277

• ND HTR 3A LVL LOW 11 A143903 680 0 77 HD HTR 3A LVL LOW etavon-eno n --

r wD wTe it t ut t nu 11 A143908 208 0277 HD HTR 3A LVL LOW J,g N143910 160 0*77

• HD HTR 3A LVL LOW

' ~, Ataso7? 7A-naae nowo oru une eten unu..at E N143937 764 0079

• DUMP VLV NOT CLSD HDV-123 CL A143o48 120 1783 INCORE INST RMVL AREA RAD LVL LOW / FAIL e

at44 nan do aa,e w"we e. o unt c. ee ua"..aw 21 N144040 767 O*79

• DUMP VLV NOT CLSD HDV-123 EE A144116 300 0079 DUMP VLV NOT CLSD HDV-123 U

N14411A 740 OS7o ? D!'we Ut U NET Et CD MnQ-1?7 E A144121 686 CSSS SS COMPR TRIP E N144101 S03 0282

• SS COMPR TRIP

=> A i.3 4 ; rv.ra ^~as Domo y,v unT r, e r, wDv_,as E N144153 600 0279

• DUMP VLV NOT CLSD HDV-123 A144003 961 0279 DUMP VLV NOT CLSD HDV-123

.) N144*02 oso 0*7o m DUMo VLU NOT Pt 4D HDU **' A144 10 500 1699 AHU AHF-1C CNDST HI _n A144023 881 0279 DUMP VLV NOT CLSD HDV-123 23 91 455o eco e?vo e D"wo et U nna rten wDU '*7 ~--"' " EL' A144:34 341 0o43 SG 3A LVL HI E A144 34 341 1065 MU TNK LVL LOW T u A144234 244 t?aa Rc P?P t ut wt E A144034 368 10o4 MU TNK LVL HI E A14434 367 1369 RC CUTLET TEMP HI a A!44234 rea ??do row e4 ?' Nvi-v ren E N144034 687 1140

• FAN FAIL NNI-X CAB E

N14434 700 1064

• MU TNK LVL HI-w N144234 705 134o
• Rr cutt rT Trwe Mi f

N14434 721 1045

• MU TNN LVL LOW

,144034 7 5 C943

• SG 3A LVL HI c

N!Aamia aae evaa e er e?P t ut ut f. A144:55 548 1625 TURB CNDSR VAC LOW TRIP i A144:55 542 1626 TURB THRUST PRG FAIL TRIP 4 N144722 925 0297

• HD HTR EB LUL HT g

N144341 004 0083

• DUMP VLV NOT CLSr HDV-56

) N144357 963 1632

• SPD REF MNTR 1

AI44400 04? OOP4 FND9P eMPt FYTP PP 7D tMU PRCCe TP?O C N144411 986 1147 * + 24 V NNI-X PWR SUPP FAIL j s N144412 103 1148 * - 24 V NNI-X PWR SUPP FAIL s' N14441a 242 1144 s - ?4 U NN?-Y OtM FAff ) ii A144410 261 lied - 24 V NNI-X BUS FAIL f. N144412 308 1143 * + 24 V NNI-X BUS RAIL g u. v e w w!saat? 7*? ??44 e-a4 e NNT-v otte cAf t Ib" ' ',, J, N UII ~ 6 H A144412 341 1148 - 24 V NNI-X PWR SUPP FAIL e-u N144412 349 1148 * - 24 V NNI-X PWR SUPP FAIL (, [ A1444?T NA3 0977 HD HTP 7A 1 U1 l Oft N144418 76 0277

• HD HTR 3A LVL LOW A144416 825 1367 RC FLO LOOP B LOW A14a419 120 112C SG A ON LOW LUt iTM

g

.~ r 9 9 e

t i i I b .a a a44me.ns swx e en veren urne eaune. mn_t en A1444:1 500 0932 ES ACT B RB ISOL ON -- A144431 509 0230 LOW PRESS INJ FLO B LOW N144500 668 1946

• NS DIFF FLO TO LETDOWN COOLER 3A A144537 16 1018 HI KB PRESS TRIP SUB ASSY D c.23ee? Ane.eeT er no *ur ? 99

.eu A144555 984 1782 INCORE INST RMVL AREA RAD LVL HI 8 A144600 784 0277 HD HTR 3A LVL LOW 3 P!14 4._ ; 8 AAA SOTT e rt AFT a pm ? c n? Fu JL N144610 680 0029

• LOW FRESS INJ FLO A LOW 2.

H144610 681 09 2

• ES ACT A LF INJ DN a

414AA99 @do TOTn 9 NC Mfer rf n TM @*e-Ta* J2 A144612 967 1850 NS DIFF FLO TO RCP-3A2 J, N144612 965 1850

• NS DIFF FLO TO RCP-3A2 9

M144A** e46 6977 3 WB NTP TA f Ut.nu 5 A144e:1 004 0277 HD HTR 3A LVL LOW n A144o40 206 0511 SMPL RM EX4 DUCT AIR FLO LOW

c. 4 o t e,,ca ne,*

, ewer ew eyn nner eve er n e n,, 2 A144040 244 0511 SMPL RM EXH DUCT AIR FLO LOW 3 N144640 OS3 0511

• SMFL RM EXH DUCT AIR FLO LOW

.~) is n?44e4e Tec est. ewer nM evy nitry are r!n inu 2 N144o40 342 0511

• SMFL RM EXH DUCT AIR FLO LOW 2

A144640 349 0511 SMPL RM EXH DUCT AIR FLO LOW s 914444n 2e+ ost? e emes ew ryp mr v ate et n t nt. a 2 N144730 100 0 77

• HD HTR 3A LVL LOW 2E A144742 064 0*77 HD HTR 3A LVL LOW

[) 7b N14A'44 7PQ 0970 s EMNt Re-T teoo pct TRTO 97/C7 Te?P E N14474* S61 0938

• CHNL RC-2 1500 PSI TRIP BI/ST TRIP E

N144749 905 09:1

• ES ACT A HP INJ ON u

.;.4 ea 44n not-, ewe er_. ,eaa eev Teve t+rer Teve N144752 484 09:3

• ES ACT B HP INJ ON A144758 561 1852 NS DIFF FLO TO RCP-3B2

_) n144 5e 3ea 14r?

• tc pp 7pa Crat t MTP atNn uTR Ft n t nu iL N14,750 567 0277
• HD H*R 3A LVL LOW gg N144*00 044 1400
• RC PP 3A2 SEAL & MTR CLNG WTR FLO LOW i

n e.maone aso ea*T ue wTr we e ut i nu g it N144819 305 1852

• NS DIFF FLO TO RCP-3B2 E

N144824 926 1421

• RC PP 3B1 SEAL & NTR CLNG WTR FLO LOW n

2342,a. cae ,a.e e er er va,

era, t wve erun uro ern,en 2L N145059 000 0*77

• HD HTR 3A LVL LOW N145111 344 1318
• RC PP 3B1 AT 2ERO SPD w

t., ..a es. 3,ec ce en-ce, e ' e. E N145118 503 088S

• SS COMPR TRIP E

A14514: 666 1070 MU HP INJ FLO B-2 HI O .w w.eetas as, .n-a . wo ue tu, e, n z_a ut i A145145 SOS 1070 MU HP INJ FLO B-2 HI E r414514e 8*3 1070

• MU HP INJ FLO B-2 HI o

f..-..e nor .a-a ... ue...,

e. a e_-

u-d N145148 585 1070

• MU HP INJ FLO B-2 HI f.

A145149 147 1070 MU HP INJ FLO B-2 HI C) d atae.no een sna* me we t u, ri a r_+ u* r. 1 A145157 268 1506 FW-SYS ACT B TRIP IP 'N*** 4' ~~" fi N145217 905 1067

• MU HP INJ FLO A-I HI a

...rea.. in, .w,e e= tu.ev enaa e*

• • ee -rwe u+

C A145 19 863 0295 DUMP VLV NOT CLSD HDU-55 f. N145000 408 1087

• RC PP 3B-2 SEAL FLO LOW s) r n.aeavn neo,naa
• er ec va_,

eear er n, nu E A14230 284 1084 RC PP 3A-1 SEAL FLO LOW il N14:231 141 1084

• RC PP 3A-1 SEAL FLO LOW u

r*~ e ar.. net se se ,3., ee. e, n. av E N145300 009 1084

• RC PP 3A-1 SEAL FLO LOW A145300 229 108*

MU1P PREFLTR DIFF PRESS HI s P .!?4-inn Tot ino*. mete oerette vtre weree ut A145300 484 1084 RC PP 3A-1 SEAL FLO LOW A145300 6*7 1082 MU1P PREFLTR DIFF PRESS HI (. d14!300 669 10R'

• MHAP PcFA Tm nTrr rergm wr 1

e i mv., - -

• e _,

.f.. 4 U~ I t ' f f i r a FE pp 55' I'Nrit rt n 75u "~ Nta3700 PS? t bb's ~-- f A145300 921 1084 RC PP 3A-1 SEAL FLO LOW N145301 65 1084

• RC PP 3A-1 SEAL FLO LOW N145302 560 1070
• MU HP INJ FLO B-2 HI A145312 681 1632 LP TURB #1 EXH STM TEMP HI A;4r?!? iSi toca pa PP 1 A -1 erv rt n t nu A145325 849 1087 RC PP 3B-2 SEAL FLO LOW FLD LOW

{} 1 N145326 284 1087

• RC PP 3B-2 SEAL, A14-va4 /An taa?

re ec in

• era ren eno A

N145327 403 1087

• RC PP 3B-2 SEAL FLO LOW JL A145421 891 1087 RC PP 3B-2 SEAL FLO LOW f'

s N145459 Mna too? e ec po in

• era, ren enu N145432 426 1084
• RC PP 3A-1 eEAL FLO LOW j
• 1 N145434 142 1080
• RC PP SEAL TOTAL FLO LOW 7

o pia--t3 an4 t7en a er enTai rin inu A145550 128 1471 FW PP 3B TURB TRIP IL A145550 265 1706 TURB.EMERG.FW PUMP FAILED TO START u z.,---n aca 96* vnow. rueen. eu co=e miten erseera il A145603 127 1765 A.B. NEAP PERS ACC HATCH RAD LVL LOW / FAIL I 21 A145603 122 1773 A.B. DECON PIT AREA RAD LVL LOW / FAIL 4.sexa4 aa-tara wrt Tue e o, ur la A145622 647 1587 A.B. SUMP PPS TRBL f. M145o42 968 1593

• RC DR TNN LVL LOW is ei4544v 44

.-^* ru eve are a ove waT preev N145643 665 1504

• NORM SHUTDOWN FW SYS ACT A NOT BYP m

At4-705 4Pe toAa wit TNy peree we i., 97 Nu 'h* - 5 N145643 669 1503

• FW SYS ACT A TRIP -

E N145700 745 1505

• NORM SHUTDOWN FW SYS ACT B NOT BYP E

A145709 749 1507 FW SYS ACT B PYP NOT-RESET w n,J no 45 .re. , ru eve erv e reve A145711 369 1077 RC PP 3B-1 CON / BLEEDOFF HI N145711 681 1036 8 MUV-253 NOT FULL OPEN 1 A14rT12 -94 to?+ Mov-Ss? NnT rt et t neew il N145?14 529 1077 a RC PP 3B-1 CONT BLEEDOFF HI g N145715 403 1036 8 MUV-253 NOT FULL OF EN ) 3 Ass-tv r#e taas fu Pe TA 7tien re ewart ere ut ED A145750 123 1076 RC PP 3A-2 CONT BLEED 0FF HI E N145750 089 1076

• RC PP 3A
• CONT PLEEDOFF HI

), v Ai457-S rR* 1674 RE PD 7A 9 PnNT DfCrBOrr MT 31 A145753 4SS 1126 SG A DN BTU LIM E N145753 649 1076

• RC PP 3A-2 CONT BLEEDOFF HI a

nier Tr 44? to4a, wt* Tum eeree wt A145643 145 1080 RC PP SEAL TOTAL FLO LOW I g'; E A145850 667 1479 FW PP 3B TURB MISSING SPD SIG ) N Nia-O^? 04? 1090

• RE PP erAl TOTA? rtn LOU 1

A145*25 523 0196 GROUND DETECTED g N145941 900 1064 s MU TNK LUL HI 4 4:4re4+ !?ie re eo ?9? AT ?rRn een i N145948 662 1318

• RC PP 3B1 AT ZERO SPD O

A1459 5 123 0984 PWR/IMBAL/FLO BI/ST TRIP SUB ASSY B as TOOOO5? 000 OooS SYCTrM TrmT L N150000 021 0000

• SYSTEM TEST g

4150000 091 1787 PRIM CLNG LETDOWN RAD LVL LOW / FAIL a misSooo eae ??to er rp in, av Tren een 21 N150009 381 0912

• SG 3A LVL LOW / LOW E

N150010 266 1126

• SG A DN BTU LIN n

N150026 !?? tre?

• A.P.

nimP rpm TR9t E N150037 541 131C

• RC PP 3B1 AT ZERO SPD li 4150037 845 1313 RC PP 3B1 AT ZERO SPD s

u-utrno?e raa ??te e Fr er vpt AT venn eer E A150040 009 131S RC FP 3B1 AT ZERO SPD m A150042 284 1126 SG A ON BTU LIM s 3" Nisco42 Ter t3to

• PE PP ?Pt 47 77Rn een A*50v43 361 1318 RC PP 3B1 AT ZERO SPD

(" N150043 540 1319 r RC PP 3D1 AT ZERO SPD t A150646 641 1312 RC PP 3P1 AT 2ERO SPD s .g a 1 ,a

t F l! ' yf.- f I I sac tvte e re er vne a- -ren e c c. Niroo44 8 A150050 003 1316 RC PP 331 AT ZERO SPD A150050 5"5 1342 RC PRESS HI-NARROW RANGE A1 0050 545 1361 RC PRESS LOW NARROW RANCE S N150052 642 1362

• RC PRESS HI-NARROW RANGE a:500!M 654 tvt-te peree wi-natenu enwne N1500*J S26 1362
• RC PRESS HI-NARROW RANCE 3

1 A1501"6 980 1415 TOP BNDL 6 BKR OPEN i N150it' ooo tate r Tnp wNnt A pen norN 1 A15015' 008 1415 TOP BNDL 6 BKR OPEN 1 N150157 007 1415

• TOP BNDL 6 BKR OPEN e

A150157 o?? 14?? Tnr DNm A pre neru 3 N150157 023 1415

• TOP BNDL 6 BKR OPEN

) Jg 4150157 042 1415 TOP BNDL 6 BKR OPEN e wirote? 040 *415 r Tne owm A pen norw 2c A153157 049 1415 TCP BNDL 6 BKR OPEN li_ N150157 067 1415

• TOP BN"'

6 DKR OPEN ir al-cir 04- ,4t-vne 999 4 pre nerv il N150157 OB4 1415

• TOP bdDL 6 BKR OPEN l

m 22 A150157 082 1415 TCP BNDL 6 BKR OPEN l 1s _ wirote? tat

• 4*e e Tne num A mee neru le Al"0157 109 1415 TOP BNDL 6 BKR OPEN 3

N150157 107 1415

• TOP BNDL 6 BNR OPEN

s Ni-^rre ces

!4,= e Tno pum 4 own nerv 11 4150259 982 1415 TOP BNDL 6 BNR OPEN E N150300 000 1415

• TCP BNDL 6 BKR OPEN l -

2 Airc200 com 1415 Tnp FNm A *KR nPew t E N150300 007 1415

• TOP BNDL 6 BKR OPEN E

A150300 025 1415 TOP BNDL 6 BKR OPEN n ut-evnn n, ,4.- , -ne one, e eve rery EL A150300 042 1415 TCP BNDL 6 BKR OPEN N150300 040 1415

• TOP BNDL 6 BKR OPEN

.2 At-a on 64o 14?- Tne owm A pre noen = N150300 067 1415

• TOP $NDL 6 BAR OPEN n

A150300 068 1415 TOP BNDL 6 BNR OPEN i n ut-avon sea to.- , rep enm e eye neen i s'i A150300 105 1415 TOP BNDL 6 BKR OPEN E N150300 103 1415

• TOP BNDL 4 BKR OPEN J

r a -svoo taa 14.- vne num 4 ore neru E A150404 407 1415 TOP BNDL 6 BNR OPEN E N150404 40* 1415

• TOP BNDL 6 BKR OPEN s

4.-^4r3 eaa io.- rec e u n. 4 ter nere E N150404 422 1415

• TOP BNDL 6 BKR OPEN E

A150404 441 1415 TCP BNDL 4 BKR OPEN 'l o u.-aans aae va.e. vne unnt A o re neeu I di A150404 447 1415 TOP BNDL 6 BKR OPEN il N150404 466 1415

• TOP BNDL 6 BKR OPEN a

pi. e n e.

v.._. n. a sv. n e e..

d N150404 483 1415

• TOP BNDL 6 BNR OPEN O

A150404 481 1415 TOP BNDL 6 BKR OPEN 4 wi-maaa zoo ,e.e e vne s un, e eve neeu i 1 A150404 508 1415 TOP BNDL 6 BKR OPEN d N150404 506 1415

• TOP BNDL 6 BKR OPEN 4

at-nano ---.... vne o n e. 2 eve nee,, N150404 523 1415

• TOP BNDL 6 BKR OPEN ff A150508 841 1415 TOP BNDL 4 BKR OPEN l

si uten-ae man to - e vne nunt x ove nern E A15050E S48 1415 TOP BNDL 6 BAR OFEN 13. N150503 866 1415

• TOP BNDL 6 BNR OPEN u

grea-no one ...e vne n u n. A me mere H N150508 883 1415

• TOP BNDL 6 BKR OPEN A150508 904 1415 TOP BNDL 6 BKR OPEN E

MifneoA 90T ta9e 2 np nunt A pre nern A150500 e21 1415 TOP BNDL 6 BAR OPEN N150508 90e 1415

• TOP BNDL 6 BKR OPEN A150503 9*8 1415 TOP.BNDL 4 PNR nPFN 9

4 ?

.f. = \\ e-y-

• l

. I i s pyr cohu ~ N1-0506 #4+ 1415

• TOP DNet g A150506 945 1415 TOP BNDL 6 BKR OPEN N150508 963 1415
• TOP BNDL 6 BKR OPEN A150508 961 1415 TOP BNDL 6 BKR OPEN N150508 980 1415
• TOP BNDL 6 BKR OPEN Nir0 dis 100 OSo? s uD uTo 49 t ut ! nu i

A150631 142 1318 RC PP 331 AT ZERO SPD J. A150634 646 0375 SG CLNG FANS DUCT AIR FLO LOW ri-osyn 144 1N p a er pp to, av Tron epn 1 A.'.50706 721 0292 HD HTR 68 LVL LOW JL A150729 922 0185 WASTE EVAP TNK LVL EXTRA HI e A1-0736 34 f no? runer evne vnv ive tnu J. A150810 403 131B RC PP 3B1 AT ZERO SPD gg s, N150847 004 0196

• GROUND DETECTED 8

ti Aj50D4? 195 n*g4 ntnttun nrTertrn 't r:150547 467 0196

• GROUND DETECTED E

N150847 52e 1318

• RC PP 3B1 AT ZERO SPD

/ 7 A3emos-a nc... os nent 9m e,errr-ro u N150647 927 0196

• GROUND DE1ECTED

~3 3[ A150848 101 0196 GROUND DETECTED s w?rno49 4?4 otoA e centrun nrTra?cn i it A150848 565 0196' GROUND DETECTED 11 N150848 840 0196

• GROUND DETECTED 2

e atr%e-. 704 +s,o e-ee 73 a- -ren cea 3 N151032 089 1318

• RC PP 3B1 AT ZERO SPD ft A151045 486 1318 RC PP 3B1 AT ZERO SPD si ner?cre ooo *stm e oc re so, av veen een 3i A151105 047 1960 LOOSE PARTS MNTR El A15:106 700 1318 RC PP 3B1 AT ZERO SPD u

r. eg*~e e~4 .ean, ence pse,e un-e 3[ N151132 124 0195

• WASTE EVAD TNN LVL EXTRA HI e

I N151200 647 1318

• RC PP 3B1 AT ZERO SPD A15120i ??o 12tp Re et 791 at vecn ten M151252 980 1076 RC PP 3A-2, CONT BLEEDOFF HI 21 N151253 501 1076
• RC PP 3A-2 CONT PLEIDOFF HI n

nir,S-~ Tre tAoo e Apu awe *r ente, u' Eg A151313 507 1661 SPD CHAN MNTR 3 [L N151318 544 1661

• SPD CHAN MNTR p

41ri319 946 1A41 ePh EMAN MNTR 21 N15*319 906 1661

• SPD CHAN MNTR 3

N151320 220 1316

• RC PP 3B1 AT ZERO SPD s

A15:7?? ip*

• 44 een Euau rute O

N151321 321 1661

• SPD CHAN MNTK fi A151322 501 16o1 SPD CHAN MNTR Nif1??? LF7 ?AA? 3 90D EuAN MNTR dt A151323 684 16el SPD CHAN MNTR g

N151324 204 1661

• SPD CHAN MNTR o

A1!!!24 Sov ?A4+ con Spaw wuTe j[ N151324 329 1661

• SPD CHAN MNTR 21 A151325 141 1661 SPD CHAN NNTR N151325 AB3 1661
• SPS EHAN MNTR gt A151325 782 1661 SPD CHAN MNTR.
• [

A151426 407 1483 FW PP 3B TURB ECC HI d A151436 Oot 1341 LOW DNDf _ 15 %KP norN g; N151436 925 1341

• LOW BNDL 12 BKR OPEN li N151500 421 1834
• NS B00ST PP 3B (SWP-23) AUTO STRT J"

A151500 587 1934 N9 DOOCT PP NP feUP-SD) AUTO MTCT li 9151500 627 1834 s NS B00ST PP 3B (SW.*-2B) AUTO STRT 11 N151502 580 1318

• RC PP 3B1 AT 2ERO SPD A!????* sea via, enu ovni sa ove noen 1[

N151515 382 1341

• LOW BNDL 12 BKR OPEN tt A151515 401 1341 LOW BNDL 12 BKR OPEN F

ni?i-te 4no 154, e e nu ownt te are neru A151515 408 1341 LOW BNDL 12 BAR OPEN N151515 4*6 1341

• LOW BNDL 12 BKR OPEN A1'1515 424 1341 LOW BNnL 22 RKR norN A

b ?

?.

.4 6 d: o-I l i ute... 4., ,,a. ,, m, u n. ,a .,e -eev 8 A151515 441 1341 LOW BNDL 10 BKR OPEN N151515 460 1341

• LOW BNDL 12 BKR OPEN A151515 468 1341 LOW BNDL 12 BnR OPEN

--._j N151515 4o6 1341

• LOW BNDL 12 BKR OPEN g

e. tano 64* 74 e nu mun. ,a n er. arru 1 N151609 044 1341

• LOW BNDL 12 PKR OPEN 3

8 A151609 082 1341 LOW BNDL 12 BNR OPEN n.-,ano ne,

Sta, e e nu o uw.

• • era aeru 8

A151609 009 1341 LOW BNDL 12 BKR OPEN s 1 N151609 107 1341

• LOW BNDLP12 BKR OPEN A

14no tne ima, , nu o ura,- eve neru 1 N151609 124 1341

• LOW BNDL 12 BKR OFEN 3

1 A1516C9 123 1341 LOW BNDL 12 BNR OPEN e Histaoe tat 1141, t nu rum sa wre norn 1 A151609 140 1341 LOW BNDL 12 BKR OPEN o N151609 148 1341

• LOW BNDL 12 PKR OPEN air..no 44
• ta, e nu mun'

,a ove reen

i N151609 165 1341

• LOW PNDL 12 PKR OPEN O

3 A151609 183 1341 LOW BNDL 1,2 PKR OPEN n 4151400 iPt 174? e (nu ownt a tre reen h N151716 200 107S

• RC PP 3B-2 CONT BLEEDOFF HI 2

A151716 629 1078 RC PP 3B-2 CONT BLEEDOFF HI is Airt 17 6co oto. nent,wn neverTen 3 N151718 16* 0196

• GROUND DCTECTED Ii A151721 980 1848 NS DIFF FLO TO CRDM v

u!!!744 7ai 1679 a ca oc 79-? erwT terenner wt El A151744 SSd 1749 CONT RM RAD LVL LOW / FAIL (( N151744 904 1749 ~ 7M RAD LVL LOW / FAIL u ctr. 44 on? tvi . e a e... i no rra *. E N151744 921 17 .chT RM RAD LVL LCW/ FAIL ( A151744 929 1749 CONT RM RAD LVL LOW / FAIL s N,r*7sa oas 74o e nnwT ew can t o' t nu eran A151744 946 1749 CONT RM RAD LVL LOW / FAIL 2 N151744 944 1749

• CONT RM RAD LVL LOW / FAIL r

see. aa oes .,ao ano, ew p a r.. t.. e ne en e. E N151744 ?61 1749

• CONT RM RAD LVL LOW / FAIL

'O i A151744 969 1749 CONT RN RAD LVL LOW / FAIL 1 r n e.742 ooo evao, enur ew can, u, e nu re a t, E A151744 966 1749 CONT RN RAL LVL LOW / FAIL 11 N151745 005 1749

• CONT RM RAD LVL LOW / FAIL 3

......, nn,. _. e em.-

r.. esa,...

.n...r... I' C. N15190: 921 1078

• RC PP 3P-2 CONT PLEEDOFF HI A151006 803 1078 RC PP 3B-2 CONT BLEEDCFF HI n

u.eteaa e;e .,vm , vem en o i nno e run_s# e.en_re er i N1519*4 149 1078

• RC PP 3B-2 CONT BLEEDOFF HI E

A151924 942 1079 RC PP 3B-2 CONT BLEEDOFF HI a .....o,, ...e e-ee ,e. -e-, ,e. d N151943 302 1078

• RC PP 3P-2 CONT BLEEDOFF HI i

A151943 423 1,078 RC PP 3B-2 CONT PLEEDOFF HI e a.e.ney .e ,a er ec we,, a, ,e n een i A15:005 641 0888 SS COMPR TRIP S N152005 664 0888

• SS COMPR TRIP w

u.-aa.* a-, .e,o e-en we_a ~ ~. - r..ce-eee u. S A152013 029 107S RC PP 3P-2 CONT BLEEDOFF HI N152017 487 1078

• RC PP 3P-2 CONT BLEED 0FF HI be o

ateanto.an ,e*o en oc in a nnur weeenner uv E N15:033 740 107S & RC PP 3B-2 CONT BLEEDOFF HI 13. A152039 *29 1078 RC FP 3B-2 CON 1 BLEED 0FF HI a ..-aa , neo ,6-o . en ce te. a em.- ..eeware u, il A152056 320 1078 RC PP 3P-2 CONT BLEED 0FF HI n N152102 380 1078

• RC PP 3B-2 CONT BLEEDOFF HI f_

e:teatna *ma in*o en ec ,t_a anu-ne rennre ut N152113 82o 1078 a RC PP 3B-2 CONT BLEEDOFF HI A152114 304 1078 RC PP 3B-2 CONT BLEEDOFF HI (', ut*211o 24* to7A

• RC PP ME-? cnNT m renner wt k:

s

t e

j' I

..s. 'e ateSite ego to?e re er vs.* raw? mecrenrr w? i t!1521~2 925 1078

• RC PP 38-0 CONT BLEED 0FF HI N15*123 106 0318
• Fu TURB LO PURIFR OVRFLO CHMBR LVL LOW A152123 544 1078 RC PP 39-2 CONT BLEEDOFF HI N1521*8 204 1914
• COMPUTER ALARM I.

A!eriSO aat. eta amuroter atAew j. N152128 267 1914

• COMPUTER ALARM 1

415:129 121 1914 COMPUTER ALARM l s NieStie 7ao to?p r PP pe in a Pnut ofFrener ut JL A152139 0o4 1078 RC PP 3B-2 CONT BLEEDOFF H! JL N1521*9 448 1078

• RC PP 33-2 CONT BLEEDOFF HI e

At-**on 4aw into ce ec ww_a enu, or renner ut JO N152203 464 1076 s RC PP 33-2 CONT BLEED 0FF HI l' JL N1522*6 727 1078 s RC PP 33-2 CONT BLEED 0FF HI e n?-aa97 ene sove er et vs.* enut averaner ut le f 415:231 167 1078

• RC PP 3B-2 CONT BLEEDOFF HI RC PP 3B-2 CONT BLEEDOFF HI it A15:03,1 782 10,78 e

...a-a4;. ,e oa e. ,c. av,een ere 11 N15"245 82: 1078 s RC PP 3D-2 CONT BLEEDOFF HI RC PP 33-2 CONT BLEED 0FF HI !) 11 A15:246 041 ,1078 eta e er to tn.* anu, nerrnnrr ut is n?--ado 67 28 A15:250 289 1078 RC PP 39-2 CONT BLEED 0FF HI ) il N15205,2 926 1078

• RC PP 3D-2 CONT BLEED 0FF HI e

..--ae

• • o

.nse ea co in_a ennt nirenner u+ [i N15'*59 406 1078

• RC PP 33-2 CONT BLEEDOFF HI 3

21 415:300 424 1078 RC PP 33-2 CONT BLEEDOFF HI n N1fr304 7o4 to7m e me er in a enwT nerrnnre ut t il A15:306 109 1078 RC PP 3b-2 CONT BLEED 0FF HI l E N15:308 56* 1078

• RC FP 3,B-2 CONT BLEEDOFF HI, C

u neva,4, see n-e e va yo s.a een, o,erraer u I E A152344 205 1078 RC PP 3B-2 CONT BLEED 0FF HI l E A152345 4:1 0 88 DUMP VLV NOT CLSD HDV-56 g 2 N!52247 P95 1679 a KE Pe 39 9 *NNT Pirfjyrr H? 2L A15:34; 743 0:S7 HD HTR 5B LVL HI { I: N152412 905 0 s7 HD HTR 5B LVL HI y e??24!? #*4 n?95 HM HTe *P t Ut u? l, j rj N152412 943 0287

• HD HTR 5B LVL HI g

N15:414 347 1507

• FW SYS ACT B B7} NOT RESET g

p Nit?4ST 9*n OSMO P DUMP Ute NNT c' <n wDU

• A i

31 A1525:4 0*2 1623 TURB ZERO SFD n N15:5*8 203 1623

• TURB ZERO SPD s

N!*2&os 14? oro? e ur 970 49 t et inu E A15263e 1"7 0054 SODIUM HYDROXIDE TNK LVL LOW g A152652 *:7 1836 NS SURGE TNK LVL LOW p 4152*1? 964 0159 EU PP 19 tutr UTR Ft n t 69 A15 756 345 1:30 EE ACT A TRBL g A15:P.?4 Col 0838 ES COMPR TRIP er N:!2taa 164 ocoe, ee cruem TR+e g[ N1528 S 763 1318

• RC PF 3B1 AT ZERO SFD A152906 667 143*

AIR PWR Fe4IL ON FWV-39 as N15290a ses 143r

• ATR puR rart 09 ruv-To j

gt A152911 205 C292 HD HTR 6F LVL LOW g N152913 627 1342

• RC PRESS HI-NARROW RANGE J

4 A?5203o 767 t?fr Rc Peres w?.Narenu caNne 25 A152932 904 1:31 ES ACT B TRPL ar A15*943 290 1090 RC PP SEAL TOTAL FLO LOW CJ U NiS29?? 945 toso y ec PP eral TcTat rtotnu E A1:3444 229,1940 LOCSE PARTS MNTR ga N153519 6S( 1860

• LOOSE PARTS MNTR s

an. anvero -ee avao ce e.iene e t ic e awo te taur _acs, e. + c E A153529 588 0378 RB PURGE SUPP AdV 3A (AHF-6A) TRIP m N153531 460 0378

• RB PURGE SUPP AHV 3A (AHF-6A) TRIP U

E Nie???t 4A-os79 m en p.icnr ntire auu in taur-Ass retr A153633 584 1960 LOOSE PARTS MNTR N153644 143 1960

• LODSE PARTS MNTR

(, ruff *29 T06 1"72 s RC PP AC.0IL LIFT PP 331 AUTO STRT. a .i -wee.mq ma eene men, g.-ymeo. < - * -e>w., s es-my ++ ws. -

f

t ;

s ll 3 e i i I .n...... .,s,.3. 47 .e f N153a47 g;; g960

• LODSE PARTS MNTK l

A153947 586 1960 LOOSE PARTS MNTR N154021 962 1960

• LOOSE PARTS MNTR 7

y a154141 705 1960 LOOSE PARTS MNTR t ei?4*51 a4'.o4n v enner capte mute y, N154306 104 1306

• RC PP 3A2 AT ZERO SPD 2;

A154318 448 1960 LOOSE PARTS MNTR i nie474a mAA to4n e eener carve wuve 1 A154349 400 1960 LOOSE PARTS MNTR l. N154401 2*6 1960

• LOOSE PARTS MNTR s'

a?'446a ana soen e nner eac ve quer .lj N1'4400 402 1960

• LOOSE PARTS MNTR e

A154409 021 1960 LOCSE PARTS MNTR 91-44S4 oxa voAS a 'n8CF DacTC wMTc

e A154424 780 1960 LOOSE PARTS MNTR I

f IL N1544*9 344 1960

• LOCSE PARTS MNTR u

r.raag, na.een taner ear's wwve A154434 567 1832 NS P00ST PP 3A (SWP-2A) AUTO STRT 1: A154435 724 1848 'NS DIFF FLO TO CRDN C) is vi?4474 Toe ?nva a we mnaet ro 7a tero mas antn eve? il t!154436 640 ?960

• LOOSE PARTS MNTR t

N15'437 269 1830

• NS SUCST PP FLO i

is ai 44?e

• • 4 toen ennee car'e Mwvn 11 N154447 408 1960
• LOOSE PARTS MNTR E

(.154447 9S8 1960 LOCSE FARTS MNTR ) l ir Ai?4?on ere 3*oi ce no twr, oi, nu El N154503 "03 1960

• LOOSE PARTS MNTR E.

A154505 549 1960 LOCSE PARTS MNTA a u.-aeme 4ae.een, eener eerve w w v e. N154526 364 1960

• LOOSE PARTS MNTR k.

4154527 **7 1960 LOCSE PARTS MNTR 'I a Nirasse or4 togo e 'occr eARTs =NTR i u A154535 737 1960 LOOSE PARTS MNTE l n N154544 567 1960

• LOOSE PARTS MNTR y

s.eaede .e. ,o.n ,nace u.anse wuve E. A154547 389 180S TURP RM SUMP LVL HI l EL N154615 843 1960

• LOOSE PARTS MNTR J

I n ni 44,- we- ,,4n inn-r caete mure 1 tl:54617 9SE 1960

• LOOSE PARTS MNTR N154603 545 1625
• TURB CNDSR VAC LOW TRIP u

... essa, -a, 4-a , vnre .. c r..... .n.. eer_,c,e E A154632 442 1960 LCOSE PARTS MNTR ij N154640 196 1960

• LOCSE PARTS MNTR w

n -m?., nea.eae e v,.c o ew enue ier ut di A154733 20s 1593 RO DR TNK LVL LOW it A154303 3*3 1078 R* PP 3B-2 C,ONT MLEEDOFF HI l e a e.. -e --wee.- e 18 N154803 929 0888

• SS COMPR TRIP I,

fi N154905 043 1073

• RC PP 3B
• CONT PLEEDOFF HI, J

s-a.-monA ca-, nan er ce s%_= cau, e ernere u 1 N154807 109 1078

• RC PP 3P-2 CONT PLEEDOFF HI A1540,30 700 1940..O,DSE PARTS MNTR L

....,o a <-, ,c,. e-e,r-e w...- d N154851 841 1593

• RC DR TNK LVL LOW l,,

O A154900 542 1593 RC DR TNK LVL LOW so s,-4eae saa ,n,e er er sn_a reur e.rror.re ut E N15de31 146 1078

• KC PP 3B-2 CONT PLEEDOFF HI E

A154935,145 0.e 3 SC 3A L,VL,. HI 94 u v.ee.,, se , en or n..,..... E C155151 564 1593 RC DR TNK LVL LOW N155213 429 1593

• R0 DR TNh LVL LOW m

w F at-eava *Aa vn-e er eo ve_a raur overmeer ut N1'5:39 929 1360

• RC PRESS HI-NARROW RANGE N15524: 847 1073
• RC PP 33-2 CONT ELEEDOFF HI 11:5:43 e4A 124' RC PRrts w'-wscequ newnr 3I J

_w

n f Ii ' P, i e. s i C ..m..,.......,_,. e 415'?44 0a0 ?^79 Fe FP Tt." emN, Of errenrr W7 f A1:5245 141 1593 RC DR TNN LVL LOW 8 N15524& 661 1078 ? RC PP 3P-2 CONT PLEEDOFF HI A1:5249 367 1078 RC PP 3B-2 CONT BLEED 0FF HI as L N1,:525,1 829 1C78,

• RC PP 3B-2 CONT PLEEDOFF.HI

( 4, cae -e= 3n3 ma en vw_a emn, eternnre w' i N155253 842 1078

• RC PP 3B-2 CONT BLEEDOFF HI 8;

A155254 563 1078 RC PP 3P-2 CONT PLEEDOFF HI N,*-a-o aan sn*r e ca op 7p_* enu? orrrnnrr wt JL A15:259 965 1078 RC FP 3B-2 CONT PLEEDOFF HI J. N155320 680 1078

• RC FP,3P-2 CONT BLEED 0FF HI e

gt-wwn, wo. ,nse ne ve sn enas noresner ur l) JJ N155324 187 1078

• RC PP 3P-2 CONT BLEEDOFF HI JL A15:324 968 1078 RC PP 3B-2 CONT BLEED 0FF HI e'

Attra*A 6po tOAS fnner PacTC MMTP 3 N15"503 629 1078

• RC PF 3B-2 CONT BLEEDOFF HI N1:5520 542 1960
• LOOSE PARTS MNTR y

n Lt***4, Oaw <nss wrr Tuv s u* us 15 A155620 704 0888 SS COMPR TRIP 12 N155420 746 0888

• SC COMPR TRIP l

in AirrA*4 144 nea-en is s ur wr A1:5811 460 1076 FC PF 1A-2 CONT BLEED 0FF HI iL N1:5813 320 1076

• RC FF 3A-2 CONT PLEEDOFF HI a....

e-4 er ce va.* anv' o.rrnmer u? 2 N155823 989 1076

• RC PP 3A-2 CONT BLEED 0FF HI l

El A15:952 982 1960 LOOSE PARTS MNTR 70000-3 ooo oenn cycTrw Trmt 3L N1$0000 007 0000

• SYSTEM TEST El N160005 747 182'
• ENERG NS CCC FF 3B OSWP-1B) AUTO STRT 2n

....nnan ~se .ese e emmer essve u.,- e El N1o0202 925 1064

• MU TNK LVL HI 2L A160212 949 0196 GROUND DETECTED Nf60??? sa' ov't e tn c.yn raye nnrT a,e re n e nm.

N16034 44e 0196

• OROUND DETECTED E

A160343 46,5 0196 GROUND DETECTED uj.*v4, 44 n.e4, nr.n,.nn erTre+er v su Alc0356 605 1960 LOCSE PARTS MNTR I -J h N160446 349 19/0

• LOCSE PARTS MNTA u

Nigneen tat twee e pp naar par, t ut t nt'f ra te 21 N16045S 105 1784

• RP DOME RAD LVL HI 11 N160503 405 1783
• INCORE INST RMVL AREA RAD LVL LOW / FAIL 3

.....-=, in- .,e- , e veae r ..e, e..., ene, e 3 r,.... u, Z'; A160503 623 17S2 .(CORE INST RMVL AREA RAD LVL HI A140503 427 1783 INCORE INST RMVL AREA RAD LVL LCW/ FAIL v w.._amma -as .sms, enen.rar-e ru enwe ra,, rn *n e ar* 2 t.16 0804 526 1707

• TURB. EMERG. FW PUMP AUTC STARTED C.

AlcOSO4 606 0100 EMERG FEED FF TURB STM SUFP NOT READY ar n,- .,.. e-crece wr..,3 renu e3nne 25 41e1000 024 13o2 RC PRESS HI-NARROW RANGE 2" 4161039 462 1960 LOCSE FARTS MNTR -/ as 4'310r? 447 6&o4 FNnRT C Tn2 THA 9 ut MT 2L

• 161122 065 1960
• LOOSE PARTS NNTR g

N161154 147 0158

• CNDNST DEMIN PNL TRPL d

414t5?' 'n? 667o enter ce 'n vnr* Mre en"e"n nre N161340 564 0089

• CNDST PP 3B NORM MAG COUPLING OFF M

H141544 SB0 183e

• NS SURGE TNK LVL LOW Il A161 tar one te74 we evenr Tuv rur inu 11 N16154o 746 1836
• NS SURGE TNN LVL LOW di A161452 784 1434 FW PF 3A TURB 2ERO SPD-TURN GEAR NOT ACT u

,..:..., ene,,,.. en re -. ,..-v -,.,-e.. --.e .. - - ??. il A161709 3 5 1434 FW FP 3A TURP ZERO SPD-TURN GEAR NOT ACT "5 A161724 748 17d' CONT RM RAD LVL, LOW / FAIL 3 utAttas 727 s ta c, emuy em ea r: eo e nurra tr A161724 765 1749 CONT RM RAD LVL LOW / FAIL N14}724 764 1749

• CONT RM RAD LVL LOW / FAIL A161704 782 1740 cant RM RAraJ Ns 8 6u/FA IJ..

3 i 9 3 i S l

.t y-e i. i i 4;,u,:r; =e= .= =.= -

• [

A161724 789 1749 CONT RM, RAD LVL LOW / FAIL N161724 807 1749

• CONT RM RAD LVL LOW / FAIL A161724 806 1749 CONT RM RAD LVL LOW / FAIL

[]. N,161724 824 1749

• CONT RM RAD LVL LOW / FAIL t

4 4t? 4 eaa asao enut em pan ew e au reate e N161724 841 1749

• CONT RM RAD LVL LOW / FAIL 3

J. A161724 849 1749 CONT RM RAD LVL LOW / FAIL s 5 pisa,?9A mam *?lo e "nue DM eAD f Lff f nt.1/r A f f J. Ale 1724 869 1749 CONT RM RAD LVL LOW / FAIL j. N161724 887 1749

• CONT RM RAD LVL LCW/ FAIL e

n 4,oea eat .a1 e e-a nu t vi e i tw 22 A162138 725 0158 CNDNST DEMIN PNL TRPL 3 w l. Ale 2429 709 1304 RC PP 3A2 AT ZERO SPD e peraevv *et stea a en ceree ut-uspenu raune E P:16:550 769 1344

• RC PRESS HI s, 3 Alo0601 4*3 1079 RC PP SEAL TOTAL FLO HI n

visaan. eew sn,e e pe ce era, vnva, n n w+ 's A16"605 449 1079 RC PP SEAL TOTAL FLO HI 3 , la N162606 745 1079

• RC PP SEAL TOTAL FLO HI

's 41!?aca 940 to?* Rc pc tra? ?ntu et n ut 2L A162617 004 1860 LOOSE PARTS MNTR n A1626*a '41 0277 HD HTR 3A LVL LOW

• • T Atergre ar-r,coe et enwee veve a

N162628 040 0888

• SS COMPR TRIP 3

N16*640 584 1940

• LCOSE PARTS MNTR

) '" II utart-? eSt to?e e er Pp m es' TnTat n n ut '. E t.142658 300 1079 RC PP SEAL TOTAL FLO HI E N162659 020 1079

• RC PP SEAL TOTAL FLO HI

.2. ?as-e saa t*,o na ee cree ?mts,

e. n w e

jl NJ42700 041 1079

• KO PP SEAL TOTAL FLO HI g

A162700 066 1079 RC PP SEAL TOTAL FLD HI J rnea?nt end to?o e r re era. *nvat et n we A162701 C*1 1079 RC PP SEAL TOTAL FLO HI 21 4102702 e25 1079 s RC FP SEAL TOTAL FLO HI n 4.r-- 24, ,r-e na ee ra. v a... r, a w, IL N162703 280 1079

• KC PP SEAL TOTAL FLO HI 3

E A162703 623 1079 RC PP SEAL TOTAL FLO HI J -m u.sa,-- sae, r.

• o.

e-er ee#. vn-i.

c. n u,

s hL A16~704 982 1079 RC PP SEAL T6TAL FLD HI ~ ll N1~6270" 26* 1079

• RC PP SEAL TOTAL FLO HI n

..:--*r ..~ e-e e-e~ -e_. ~ ~,.. en o_- ' E. A162716 28' 0277 HD HTR 3A LVL LOW 11 N1629*1 609 0e*77

• HD HTR 3A LVL LOW n

a Ameae eco in , m er n,e-e mure 21 N1o2E39 864 1960

• LOOSE PARTS MNTR fi A16"943 227 C*77 HD HTR 3A LVL LOW d

o w--. - e. -,,.,,-,. un,.. -.,,..... A N162254 443 1079

• RC PP SEAL TUTAL FLO HI l e3 2

A162859 668 027,7 HD HTR 3A LVL, LOW e ...,-ee naa ny, up uvn,,. i_ i - ,y. 2 N16290* 226 1780 & RB NEAR PERS ACC HATCH RAD LVL HI f N16200* 243 1781

• RB NEAR PERS ACC HATCH RAD LVL LOW / FAIL n

-...... ----.--..-,........~ -... f AII3955 537 5780 RBNEARPbkhACbHATCNRAD(VLHE ~] m .E A1,62919 769 1079 RC PP SEAL TOTAL FLO HI I 1 . m u 4ao. sae ,a*. e-ee e e n. -n mi

c.,

u-E A142926 849 1079 RC PP SEAL TOTAL FLO HI E N162.'c S 400 1079 RC PP SEAL. TOTA',.m..- 2 FLO HI m -,e -e ..--- n O A162f3E 349 0*:5 GS PRESS HI/ LOW A162945 049 0277 HD HTR 3A LVL LOW ... E visaoas eat aa*? e un ute SA e t re e no Als:145 o09 13o4 RC PRESS HI A~c2215 2C3 124* RC PRESS HI-NAPROW RANGE N163217 4e2 008: a ntlMP UI V NOT,f?! AL NhU-MM 3 ?.; f A .*.e* is .es e > an nem N es .e gsu. 9 4 eb. m ..ra

g e I; ,l*' V .---r.....

====* **** **=** - *= 4-N163321 448 130s

• RC PD 3A2 AT TrRO SPP 1

r A163321 446 1306 RC PP 342 AT ZERO SPD N163321 465 1306

• RC PP 3A2 AT ZERO SPD A163407 703 1960 LOOSE PARTS NNTR I

N163423 307 0158

• CNDNST DEMIN PNL TRBL k

Nf63479 4?a ?#A0 t fMOer DAPTC M MTR f1 4143433 423 1306 RC PP 3A2 AT ZERO SPD lj N143433 447 1306

• RC PP 3A2 AT ZERO SPD

'3 Es N1A7442 'An in91 e fEan?wn Crn RfnFP T AFT A J; N163442 564 1022

• LOADING SEO BLOCK 4 ACT A 2.

N163442 568 1020

• LOADING SED PLOCK 2 ACT A le*

N1Avd49 MAe 191n 2 rC AFT A TDRf

• 18 N163452 601 1231
• ES ACT B TRBL

{ () iel N163452 641 1025

• LDADING SED PLOCK 3 ACT B il N143455 A45 in*A e fnantwn trn atnew A art a 21 N163452 649 1023
• LOADING SEO DLOCK 2 ACT B 3

4143458 309 1023 LOADING SED BLOCK 2 ACT B ,g nr n1A?4rp ygo somt t tnAntwn trn menev a se+ n _ g A163503 200 1023.-LOADING SED BLOCK 2 ACT B a* N163503 228 1023

• LOADING SED BLOCK 2 ACT B

-s 9 AtA7 n? ont in,t rnantum een nince a arv = l 21 N163508 025 10*3

• LOADING SEO BLOCK 2 ACT B

I A163513 085 1023 LOADING SED BLOCK 2 ACT B sja

,a,, .. n,#..., ee, ..a-- , -, e g' A163647 581 02S5 DUMP VLV NOT CLSD HDV-55 N1636*8 129 1541

• DG RM 3A AHF 3B AUTO STRT L'
• ri vtAve-m ta* ve7o e nn ow 7a awr TA air?n ever

'E A163715 061 1306 RC PP 3A2 AT ZERO SPD E N163715 10,9 1306

• RC PP 3A2 AT ZERO SPC 3.

s. 4v,aa

• e

.oao ti ee eu

e..w e s i.e ut 2%

N163742 643 0*85

• DUMP ULV NOT CLSD HDV-55 U^

A163759 905 1306 RC PP 3A2 AT ZERO SPD N163759 944 130A

• PE Po 3AS AT Pren een i

A163801 241 1306 RC PP 3A* AT ZERO SPD ag N163801 260 1306

• RC PP 3A2 AT ZERO SPD or A143901 345 1304 PE SP TAS A? vren een

!g N163301 382 1306

• RC PP 3A2 AT ZERO SPD

, Et A163804 943 1306 RC PP 3A2 AT ZERO.SPD p N143264 94A 176A r Rc PP taa ar ?ren con ., h A163805 562 1306 RC PP 3A2 AT ZERO SPD ,E N16390: 560 1306

• RC PP 3A2 AT ZERO SPD A 4veae ca.

76A er oo 7a* a? vren con .E N1o3805 942 1306

• RC PP 3A2 AT ZERO SPD 3

A163806 347 1306 RC PP 3A2 AT ZERO SPD %J 2= N143904 34-1364 t er oP 3AS AT eren epn I A163827 666 1306 RC PP 3A2 AT ZERO SPD . Dj N163327 706 1306

• RC PP 3A2 AT ZERO SPD

.l da Areveng 4av 7oA er oc taa ar 7ren een N163908 980 1.306

• RC PP 3A2 AT ZERO SPD i

A163909 005 1306 RC PP 3A2 AT ZERO SPD p N1d3909 644 130a t Rc PP 345 at 7ren spn A163911 383 1306 RC PP 3A2 AT 2ERO SPD N163911 482 1306

• RC PP 3A2 AT ZERO SPD w

2 4163924 107 178A PP PP 1A9 AT ?ren Cpn i S N163924 126 1306

• RC PP 3A2 AT ZERO SPD A163927 241 1306 RC PP 3A2 AT ZERO SPD su N!a3927 34? 130a
• Rc PP 3A? AT ?rpn RPn RE A163036 569 1306 RC PP 3A2 AT ZERO SPD R$

N163936 603 1306

• RC PP 3A2 AT ZERO SPD l

w A163937 LS3 1306 RC Pp MA9 AT ?rDD eon u N163937 728 1304

• RC PP 3A2 AT ZERO SPD 4

52 A163943 727 1306 RC PP 3A2 AT ZERO SPD Le g"

• E Nia3943 744 1McA t er PP 1A9 at 77Rn CPn l

i A164030 044 1306 RC PP 3A2 AT ZERO SPD N164030 084 1306

• RC PP 3A2 AT 2ERO SPD

.ALA.iD33 D4.3.1306..RC.2P NA' AT 2ERO.SPD s .e ..i }ii $,\\ \\ U 9+ ,z_ __ -- r - - --*

,.t p' - i l' l '. 1 i l ~,,,e,., n,4.,. ,.. e, or ,a, m. .re, een I~ N164111 900 13w2

• RC PRESS HI-NARROW RANGE g

A164155 244 0158 CNDNST DEMIN PNL TRBL M164201 448 0158

• CNDNST DEMIN PNL TRSL m

[] a164300 148 1207 EMERG LG 3A ANY SW NOT IN AUTO POS t Aif4732 7?e

• • a-rwrzn nq ta t r o,

,i_ A164330 469 1306 RC PP 3A2 AT ZERO SPD ) .. JL N164111 103 1306

• RC PP 3A2 AT ZERO SPD Alg42??

et +7nA Rc pp 7aa at 7een een 2. N164335 323 1306

• RC PP 3A2 AT ZERO SFD T J.

A164335 346 1306 RC PP 3AO AT ZERO SPD e Nie4754 mat s'ng a ec or tan a? 7ren een i l,) fj A164359 702 1306 RC PP 3A2 AT ZERO SPD j; N164359 7*2 1306

• RC PP 3A2 AT ZERO SPD e'

Ate 442-746 *nn4 er pp vaa av Tron een N164435 7E2 1306

• RC FF 3A2 AT ZERO SPD.

iL N104407 686 0096

• CNDST STOR TNK LVL HId u

tie:-aa tee.een inner cecyc move u Nio4510 500 1960

• LOOSE PARTS MNTR

, }} A164511 120 1960 LOOSE PARTS MNTR C) u N14451* 904 todo e taner eneTm wNTe 21 Alo4535 So6 1362 RC PRESS HI-NARROW RANGE 21 Ale 4656 to: 0688 SS COM*R TRIP 8 Higa4ee *ee ecco e ce E m u r.e ? par 11 Alo4311 943 1306 RC PP 3A2 AT.ERO SPD

• f.

N164211 942 1206

• RC PP 3A2 AT ZERO SPD

) O aiemoaa $46 sinA ra re 7aa af ?ren een 3i 44ed*2Z 365 1306

• RC PF 3A2 AT ZERO SPD 11 Alo4930 711 130o RC FF 3A2 AT ZERO SP-D

.} u ..<4oyo ?.n ven4, ca c.e vna a+ *ren een 11 A164931 089 1306 RC FF 3A2 AT ZERO SPD g 3 N164731 185 1306

• RC PP 3A2 AT ZERO SPD Aigao?? ese tina re ce saa av 'ern men E.

N1o4931 548 1306

• RC FF 3A: AT ZERO SPD n

A164042 064 1306 RC FP 3A2 AT ZERO SPD x. w.,.eaa a,. ,-n( . ce ce ese a-Seen een EL N164950 368 0285

• DUMP VLV NOT CLSD HDV-55

() E N165047 723 1205

• ENERG D3 3A TRPL v

N.eema, vn-. met. ruren nn

• A ruv eu unt vu an-m eme 1

A165051 865 1306 RC FP 3A2 AT ZERO SPD ll N145051 909 1306

• RC FF 3A: AT ZF' 1 SPD I

a see*~ ~en .,ms r~ ee,.-., -en er IL N16505" 240 1304

• RC PP 3A2 AT ZERO SPD E

N165112 406 1713

• RP PURGE DUCT RAD LVL LOW / FAIL CJ n

utieten ann,va

• en r ne -r m-,

enn e u, ur S N16:138 468 1716 s A.P. 3 F-H AREA EXH DUCT RAD LVL LOW /Fe d" .N.13 : ....5 308 1362

• RC FRESS HI.-NARROW RANGE 23 a

d h165355 086 1306 Rb PP 3A2 AT ZERO SPD '~ ,4 N165355 165 1306

• RC PP 3A2 AT ZERO SPD

= j e et,-an- -g4.s r.7 'jy; ;7;,rg y enue em fi N165405 328 1749

• CONT RM RAD LVL LOW / FAIL

..f A165405 347 1749 CONT RM RAD LVL LOW / FAIL i r.,y. ..e . -,... ~,.... =,-.g C A16:405 364 1749 CONT RN RAD LVL LOW / FAIL . fs N165405 362 1749

• CONT RM RAD LVL LOW / FAIL se atee.n.,en

...e ran-nu e. .~.,r... 6 N165405 389 1749

• CbNT RM RAD [V[ [bW/FAi[

. E A165405 307 1749 CONT RN RAD LVL LOW / FAIL u -re-s, .~s, v-n- 7,e.; di A165405 404 1749 CONT RM RAD LVL LOW / FAIL N165405 422 1749

• CONT RM RAD LVL LOW / FAIL J

f& ateeane a*. , ?a o caut eu can, ut, mo re. y e_ N165405 429 1749

• CONT RM RAD LVL LOW / FAIL A165405 447 1749 CONT RM RAD LVL LOW / FAIL

( N165405 44A 1749 z cnNT RM RAD 1888 I OW / rett 9 M i. .8 i y

b* a 'k-.;- e p y ~ .f:,1 I 13!33!32 VATR N791 [0RE THERMAL POWER (MW) 2440'. ~~~' ~~ l "" ~~~ 13 J5 J3 VATR r.791 CCRE THERMAL FOwER (Mwa 2440. 13:37:30 VATR N791 CORE THERMAL POWER (MW) 2440. 13:39:31 VATR N791 CORE THERMAL POWER (MW) 2445. 13:41:32 VATR N791 CORE THERMAL POWER (MW) 2445. "k 13:43:3: VATR N791 CORE THERMAL POWER (MW) 2445. $b-( G; 13:45:09 ENDA M710 BORON CONCENTRATION (PPM) 305. / "E 13:45:20 CONT A042 DEMINERALIZER STSTEM ALRM s 13:44:09 CONT A04: DEMINERALIZER SYSTEM CA --h)fSO'4g 15 13:45:32 VATR N791 CORE THERMAL PCWER (MW) 2447. / _ 10' 13:46 09 CONT A042 DEMINERALIIER SYSTEM ALRN 13 13:44:31 CONT A042 DEMINERALIZER SYSTEM CK ire 13:4e:40 CONT A04: CEMINERALIZER SYSTEM ALEM UU 13:44:42 CONT A042 DEMINERALIZER SYSTEM OK 7I 13:47:32 VATR N791 CCRE THERMAL POWER (MW) 2447. 4 13:49:30 VATR N791 CORE THERMAL POWER (MW) 2447. IE 13:50:07 CONT A04: CEMINERALIZER SYSTEM ALRN IE 13 5: 32 UATR N791 CCRE* THERMAL POWER 'MW) 2444 tr 13:53:31 UATR N791 CORE THERMAL POWER (MW) 2444. 3 GROUP 6 im 13!54:53 3 02/2o/80 1 71 7E ANALOG ASSIGNMENT

SUMMARY

P 14 FLUX IMBALANCE (CH NI-5) (%) ATR 1 -10.000/ .000 IU N657 80D 7-1 NO.54 LCC. 8-F POSITTCN ATR 2 .00/ .00 D T310 LUBE CIL COOLER GIL CUTLET TEMP ATR 3 110.00/ 20.00 35 X304 RC PUMP A: MTR LOWRGUIOE BRG TMP ATR 4 130.00/ .09 i; j m 13:55:30 VATR N791 CORE THERNAL PCLER (MW) 2444. jE GRCUP 6 3' 13:56:00 ji C /06/80 ,i 2: y ANALCO AS3IGNMENT

SUMMARY

) l'J n. P 14 FLUX IMBALANCE (CH NI-5) (%) ATR 1 -10.000/ .000 IE N657 RCD 7-1 NO.54 LOC.'9-B POSITICN ATR S .00/ .00 u. T310 LUBE CIL COCLER OIL CUTLET TEMP ATR 3 110.00/ 20.00 jj 1304 RC PUMP A: MTR LCWRGUIDE BRG TMP ATR 4 130.00/ .00 t m 13:56:30 DATA T310 LUBE OIL COOLER CIL QUTLET TEMP 583.1 jj 13:57:05 DATA T310 LUBE DIL CCCLER DIL QUTLET TEMP 583 1 r* 13:57!31 VATR N791 ESRE THERMAL POWER (MM) S441. ja 13:59:30 VATR N791 CORE THERMAL PCWER (MW) 2441. gij 14:01:31 VATR N791 CCRE THERMAL POWER (MW) 0441. .a taro?;yt vaTe N70 crer Tuf R=at ecure ewu) Sa4A. i! 14:05:31 VATR N791 00RE THERMAL POWER (MW) 2444.

14:07:31 VATR N791 CORE THERMAL POWER (NW) 2444.

• 14:09 ?1 VATR N791 CORE THERMAL POWER (MW)

S446. t 14:11:30 VATR N791 CORE THERMAL POWER (MW) 2446. gg 14:12:34 DATA T310 LUBE DIL COOLER OIL CUTLET TEMP 583 3

== 14f13:32 VATR N791 CORE THERMAL POWER (MW) 5444. g3 14:14:44 CONT E043 EMERGENCT GENERATCR A RUNNING NO am 14:15:32 VATR N791 CORE THERMAL POWER (MW) 2442. v! 14:17:31 UATR N701 CORE THERMAL POWER (MW) S44S. sf 14:19:30 VATR N791 COAE THERMAL POWER (MW) 2440. 14:01:31 UATC N?'1 CORE TWESMAL ECWEt (MW) 2437 4-pi.::::2, LOC $70' 9'f4M GEN NUT' r' ?A ete": si? !! 14:23:34 VATR N791 CORE THERNAL POWER (MW) 2437. w 14:23:30 BAD S337

• STEAM GEN A INLET FW (NARROW)DP

-???*. E 14!23:30 DAD S349

• ETEAM GEN 9 TNLET FM (NARROW)PP 959*.

14:23:32 LOW P201 CORE FLOOD TANK B LEVEL (FT) 7.04 14:03:33 LOW T:07 1A MAIN STEAM TO TURB TEMP 375.4 ( , 14:03:38 LOW,S298 STEAM GEN A,LCWER DOWNCOMER TEM.P, 300.5, a 4 ~ .' h .N I.i 't .m _.. ~ _ ~.....

5 t,,.

• ~

~ ~ p p ~. j -100.0 ' ~ ' ~ ~ ~ ~' '14 :03:4" LOW X:00 BORIC ' ACID STORAG'E TANK'A TEMP 4 44 .A. 4... .-.A.., Y. Y 14:23:42 HICH $240 DEAERATOR LEVEL (FT) 13.68 14:23:42 LOW X203 BORIC ACID STORAGE TANN B TEMP 100.0 14:23:44 CONT A130 CRD SYSTEM PROGRAMMER LAMP FAULT YES 14:23:45 CONT E045 500 KV GENERATOR BREAKER 1661 OPEN ~} 7##

1. V bi 14:23:45 CONT E046 500 AV GENERATCR BREAKER 166 OPEN \\

)) 14: 14:23:45 CONT E101 EXCITER FIELD BREAKER OPEN U .o 23:45 CONT P032 REACTOR PROT. CHANNEL A TRIP ALRM o 14:23:45 CONT P033 REACTOR PROT. CHANNEL B TRIP ALRM )) 14:23:45 CONT P034 REACTOR PROT. CHANNEL C TRIP ALRM in 14:23!45 CONT P035 REACTCR

• ROT. CHANNEL D TRIP ALRM gj 14:23:45 CONT P054 CRD ON MANUAL YES gg 14:23:45 CONT P055 CRD ON AUTOMATIC NO o 14:05*33 UATR N701 CORE THERMAL POWER (MW) 2437.

os 14:03:45 CONT F057 CRD TRIP CONFIAMED T E S==== i ># ' '# TC 14:23:45 CCNT P059 CRD ASSYMETRIC RCD ALRM Ti 14:23:45 CONT P060 CRD SAPETY RODS WITHDRAWN NO ,s 144;J445 GGN. e0*; TLA31NE ON IC5 CONTROL NO T; 14:23:45 CONT T046 AUTO STCP TRIP 7" 14:03:45 CONT 7049 TURBINE ON GOV VALVE CONTROL NO w 44;; oil; JATA A20s AC FRESS (wl EJ (LOOP A) 1600. TK 14:03:45 CONT T052 GOVERNOR VALVE NO 1 CLOSED YES 7" 14:23:45 CONT 70f3 GOVERNOR VALUE NO 2 CPEN NC in 14123:45 CONT T054 GOVERNOR VALVE NO 2 CLOSED YES 3s 14:23:45 CONT 7055 GOVERNCR VALVE NO 3 OPEN NO IU 14:03:45 CONT 7058 GOVERNCR VALVE NO 4 CLOSED YES =r 144 3 45 CONT 70e0 TMA0TTLE VALVE NO 1 CLOSED YES E 14:23:45 CONT 7061 THROTTLE VALVE NO :.0 PEN NO I" 14:03:45 CONT 706 THROTTLE VALVE NO CLCSED YES l w 14;;314L caN. 4003 innGTTLE VALVE NQ 3 CF EN NG

• i 5"

14:23:45 CONT T064 THROTTLE VALVE NO 3 CLOSED YES 3R 14:23:45 CCNT T065 THROTTLE VALVE NO 4 OPEN NO y w... 4 4a ..ai iwoo .nn .iis vewv. nu 4 LLoans TE6 -l. j" 14: 14:23:45 CONT 7067 INTERCEPTOR VALVE NO 1 0?CN NO 23!45 CONT 7068 INTERCEPTOR VALVE NO 1 CLOSED YES su 143.iial Vasa N7V1 GGnc IMERMAL PG=EA sns) 2437. l'

14

03

45 CONT T069 INTERCEPTOR VALVE NO OPEN NO E 14:23:45 CONT 7070 INTERCEPTOR VALVE NO CLOSED YES y

w 14;23:45 CCNT TQ71 INTERCEPTOR VALVE NO 3 OPEN NO s 5 14:23:45 CCNT 707: INTERCEPTOR VALVE NO 3 CLOSED YES 3" 14:23:45 CONT T073 INTERCEPTOR VALVE NO 4 CPEN NO 7 14323;45 CUNT TQ74 INTEACEPTOR VALVE NO 4 CLOSED YE5 ,3 14:23:45 CONT T075 REHEAT STOP VALVE NO 1 OPEN NO 33 14:03:45 CONT 7076 REHEAT STOP VALVE NO 1 CLOS D YES m 14;;3:45 CONT TG77 AEnEAT 5TCP VALVE NO 2 CF EN NO

14

23

45 CONT 7078 REHEAT STOP VALVE NO CLOSED YES l3 14:03:45 CONT T079 REHEAT STOP VALVE NO 3 OPEN NO a A4;.aa4L Gahr iaa0 kammai dicF VALVE NG J GLG5EL YE5

% 14:23:45 CONT 7081 REHEAT STOP VALVE NO 4 OPEN NO lI 14:23:45 CONT 7082 REHEAT STCP VALVE NO 4 CLOSED YES wm 14423:45 CONT T005 GENERATOR LOAD CONTRCL OFF q }3 14:23:45 CONT 7099 SPEED REFRENCE CHANNEL OFF .a 14:23:45 PAD S731 NEATER 3B DRAIN FLOW

• • t.*

d 14:23:46 CONT 7029 STEAM LINE A2 DRAIN CPEN 3" 14:23:46 CONT T030 STEAM LINE B1 DRTIN QPEN i IU 14:09:34 UATR N791 CCRE THERMAL PCWrR (MW) 2437. e 14:23:46 BAD S379 sREHEATER C MP DRAIN DP -?.??' U 14:23:46 CONT TOOS STEAM LINE Al DRAIN CPEN E 14:02:46 CONT 7031 STEAM LINE B DRAIN OPEN m 14:23:47 BAD 5879 REHEATER C HP DRAIN FLOW -???.? ' I; 14:23:47 FLAG X182 RC PUMP A1 SUCTION TEMP (R214) BAD E 14:23:47 FLAG X183 RC PUMP A2 SUCTION TEMP (R 15) BAD i43;3147 FLAG X184 AC FuMP B1 SUCTION TEMP (R le) BAD 14:23:47 FLAG X185 RC PUMP B SUCTION TEMP (R217) BAD 14:23:47 CONT T101 STEAM CHEST CROSSOVER DRAIN CPEN ( 1 i) 1 i ..A t 1

s. g :- -e M 1 p. ["" 14:03:48 'CCNT' P043 ' START-OP RATE BiP5SS FROM"CE'Of5'~ NO ~ ' ' ~ ~ ~ ~ ~~ ~ f 14 ;3:45 GGNT F043 START-UP AATE BfPAS'o FROM CH NI6 NO l 14:23:48 CONT P044 START-UP RATE BYPASS FROM CH NI7 NO 14:23:48 CONT 8045 START-UP RATE BYPASS FRCM CH NIS NO ()', 14:23:48 CONT 7033 GOVERNOR VALV 2 AFTER SEAT DRAIN CPEN h,_,L4: 03!49 CCNT A003 RENEATE3 9 CSLD REHT LINE DRAIN ODEN 2; 14:23:48 CONT A004 REHEATEF C CCLD RENT LINE DRAIN CPEN tj 14:23:49 CONT 703: GOVERNOR VALV 1 AFTER SEAT DRAIN CPEN n 14:03:49 CONT 7034 GOVERNOR VALV 3 AFTER SEAT PRAIN OPEN L.; 14:23:49 CONT 7035 GOVERNOR VALV 4 AFTER SEAT DRAIN OPEN oi 14:23:49 CONT T100 HP TURBINE DRAIN CPEN Cl 14:31:23 DATA R203 PRESSUR(2ER TEMP 350.0 'y 14:23:49 CCNT A035 GLAND STEAM CDSR COND FLCW LCW 91 14:31:33 DATA R204 PRESSURIZER CUTLET TEMP 390.7 Ti 14:31:30 VATR N791 CCRE THERMAL POWER (FW) 2437. = 14:31:43 DATA R204 PRESSURIZER QUTLET TEMP 391.0 Is 14:23:50 CONT A005 REHEATER D CCLD REHT LINE DRAIN OPEN 3 !4:31!!4 DATA. R205 PRESS RELIEF VLV RCV-10 CUT *Ew' 3 4 9. 4 4 ---- m 14:23:50 CONT 7002 LP TURB B GOV END STM SEAL PRESS LOW ' I~ 14:32:03 DATA R206 PRESS RELIEF VALV RCV-9 CUT TEMP 146.3*G-- E 14:32!09 UAT4 R207 PRFE9 RELTEr VALU DEV-9 00? Tew* ???.4ar-- 4 14:23:51 BAD R70: RC OUTLET A PRESS (NARROW) 2189. 3 14:23:52 CCNT 700 LP TURB B GCV END STM SEAL PRESS CK is 14:23!52 CONT 7003 LP TURP A GrN END STM SEAL RRESS LOW m 14:23:53 CONT A00 REHEATER A COLD REHT LINE DRAIN OPEN ( E 14:23:55 HIGH R701 RC TOTAL CUTLET FLOW (MLB/HR) 149.3 IU 14:23:55 CCNT 7000 LP TURB B 000 END STM SEAL PRESS LCW a 14:23:55 CONT T000 LP TURB B GOV END STM SEAL PRESS CN ./ E 14:03:5o HIGH R860 RC TOTAL FLCW (RP CH A) (MLB/HR) 149.4 3! 14f23:56 HIGH #963 RC TCTAL FLOW (RP CH D) (wLP/W2) 156.3 I a 14:23:56 HIGH RS64 RC LOCP A FLOW (RP CH A)(MLB/HR) 74.59

• (

E 14:23:56 HIGd R848 RC LOOP A FLOW (RP CH C)(MLB/HR) 74.59 E y 14!23:56 MfGH Re70 Rc tecP A FLSU (RP EH DifML9/wR) 7?.to g 14:23:56 HIGH R871 RC LOOP B FLOW (RP CH D)(MLB/HR) 75.0

j. g 14:23:56 HIGH R87 RC LOCP A FLOW (TEMP COMPeMLB/HR) 74.60 w 14:33:37 UATe N'91 ccof THE?wAL ecWre fMW) 5437

?- l' I EU 14:03:56 LOW R22: RC QUTLET A PRESS (NARRCW) 2047. g 14:23:56 LCW R234 RC LOOP A FLCW (CH A) (MLB/HR) 69.72 m 14f?3!!a LSU RS3E Rc LOOP 9 FLOW (EH A) fwl#/NR) A9.40 g 14:03:56 HIGH S308 STEAM GEN DUTLET 1B PRESS 1011. 3 g 14:23:56 CONT 700 LP TURB B GOV END STM SEAL PRESS LOW w 14!?3:57 NCRM S 31 SWEATER 3B DRAIN DP 25.13 p 14:23:58 CCNT T002 LP TURB B GCV END STM SEAL PRESS CK E 14:23:59 CCNT 7002 LP TURB B GOV END STM SEAL PRESS LOW E 14:03:59 LOW S313

• STEAM GEN B INLET FW (WfDE) SP 5.

g 14:24:00 BAD S346 sRHTR A TO FWPT B DP -???.? g 14:04:01 NORM 5731 NEATER 3B DRAIN FLOW 174.5 as 14rra:01

yet, esso,eruratre e we ppaty ne 4,3en g 14:24:01 BAD Sa46 REHEATER A TO FWPT B FLCW

-???.? g 14:24:00 NORM S879 REHEATER C HP DRAIN FLCW 131'.8 4 as 14!24!0? DAD PSOA STARTUP RATE ffNTrR RAiMEDEM Nf3 5 14:24:02 BAD P207 STARTUP RATE (INTER RANGE)CH NI4 -TT.TT ,g 14:24:03 HIGH T 28 1A MAIN STEAM TO TURB PRESS 984. ps 14 t?4 f t ! MfDH T2So SA MATN ETrAM 70 TUR9 TEMP soo.o g 14:24:03 HIGH T232 1B NAIN STEAM TO TURB PRESE 1009,. . as 14:35:34 UATR N791 CCRE THERMAL POWER (NW) 2437.- ' IU 14:24:05 MIGH A018 HOTWELL LEVEL (TN) 3.997

• • 14:24:06 LOW R:23 RC QUTLET A PRESS (NARRCW) 1988.

j{ 14:24:06 LOW R2:4 RC DUTLET B PRESS (NARROW) ! *P.6.

• 14:24:04 LCW R225 RC OUTLET p PRESS (NARROW) to90.

g 14:24:07 LOW R230 RC TOTAL FLOW (CH A1 (MLB/HR) 138.4T as 148 4:07 LOW R 31 RC TOTAL FLOW (CH B) (MLB/HR) 138.4 s 36 14:24:07 LOW RO3? RC TETAL FLEW fEH E) (ML9/HR) 13A.4 14:24:07 LOW R 33 RC TOTAL FLOW (CH D) (MLB/HR) 140.0 14:24:07 LOW R234 RC LCCP A FLOW (CH B) (MLB/HR) 69.4 14:24:07 LOW R:37 RC LOOP B FLOW (CH B) (MLB/HR) 68.38 ( ~~ y 31 h ..?

• j
• )

g. lj I. ( l: i 14:24:07 LOW R239 RC LOOP A FLOW'(CN C) ~ (SLB/NR) 69.36'

• ~~

I 14aa4;e7 sse n;Ji RG Lgsr o PLs (Gn 6J (MLb/nR) od.92 14:24:07 LOW R240 RC LOOP A FLOW (CH D) (MLB/HR) 69.98 14:24:07 LOW R241 RC LOOP 3 FLOW (CH D) (MLB/HR) 69.88 t 14:24:10 LOW R718 RC LOOP A FLOW (MLB/HR) 69.8 14:24:12 FLAG X108 HIGH PRESSURE INJECTION REQUIRED YES aff 6. 14;;4;12 3AD 3;JQ sDEAERAiGN INLET b COND DP -???.? ! 10 14:24:12 BAD S240 DEAERATOR LEVEL (FT) -??.?? 5' 14:24:16 BAD S730 DEAERATOR INLET B COND FLOW -9'*9 gj 145J7330 VATR N791 CORE THERMAL F0WER (MW) 2437. .s 14:24:17 FLAG X173 POWER RANGE CHANNEL 1 ERROR YES J t Isi 14:24:17 FLAG X174 POWER RANGE CHANNEL 2 ERRCR YE9 14:24:17 FLAG X175 POWER RANGE CHANNEL 3 ERROR YES ( 7 14:24:17 FLAG X174 POWER RANGE CHANNEL 4 ERROR YES E 14:24:19 HICH T233 2B MAIN STEAM TO TURB TEMP 599.4 as 14:04300 BAD A21a MOTWELL LEVEL (IN) '.?'? 73 14:24:25 CONT T083 TURNING GEAR CIL PUMP DN AUTC NO r %i 14:24:25 CONT T109 SEAL CIL BACKUP PL'MP DN AUTC NO am 14:24:05 NORM A701 RC TOTAL CUTLET FLOW (MLB/HR) 142.8 / $" 14:24:25 CONT T006 GLAND STEAM CDSR VACUUM LOW Ti 14:24:25 CONT 7015 TURNING GEAR DIL PUMP DN 44, 14&24&;o n0RM Rheo RC TOTAL 760w (RF Cn AJ (MLB/MR) 142.7 ~ [" 14 :24:26 NORM RS63 RC TOTAL FLOW (RP CH D) (MLB/HR) 144.4 w 14:24:26 NORM R864 RC LOOP A FLOW (RP CH A)(MLP/HR) 72.45 na 1432442o NORM R8ea RC LOOF A FLOW (RP CH C)(ML3/NR) 71.54 35 14:24:26 NORM R870 RC LOOP A FLOW (RP CH D)(MLB/HR) 72.18 IU 14:24:26 NORM R871 RC LOOP B FLOW (RP CH D)(MLP/NR) 72.07 a 1432412e NORM A87 RC LOOP A FLOW (TEMF CONF MLB/NR) 71.e4 .( EE 14:24:26 LOW R208 RC PRESS (WIDE) (LOOP A) 1881. EE 14:24:27 CONT T108 SEAL CIL PACKUP PUMP RUN l n 14439:36 VATR N791 CORE THERMAL PC' ER (MW) 2437. w .( E3 14:24:27 NORM S230 sDEAERATOR INLET B COND DP .4 E 14:24:28 HIGH S240 DEAERATOR LEVEL' (FT) 13.99 l s, a=;;*&;e bas 525o anEA TER sb LRAIN LF -???.? l( j" 14:24:30 BAD S354

• REHEATER A DRAIN DP

-?.??? 14:24:31 NORM 5730 DEAERATOR INLET B COND FLOW 234. y A4. 44aa eAe e/so MLA.cn so s AAla r L6. -Y???. pj l( 14:24:32 BAD S854 REHTATER A DRAIN FLOW -???.? 5s 14:24:33 NORM P206 STxRTUP RATE (IN'ER RANGE)CH NI3 .73 = ,i w 143;4&dJ NORM F207 5TARTUP RATE (INTER RANGE)CH NI4 - .71 ( ;; 14:24:33 HIGH T:31 13 MAIN STEAM TO TURB TEMP 600.4 3D 14:24:35 HIGH R200 PRESSURIZER LEVEL Li(IN)(UNCOMP) 160.0 g 143;4&JL HIGH R201 FRESSURIZER LEVEL L FIN)(UNCOMP) 160 0 14:24:36 LOW R209 RC PRESS (WIDE) (LOOP A) 1855. 4 mm 53 14:24:36 LOW R210 RC PRESS (WIDE) (LOOP B) 1856. wm 14:24:39 LGm 5093 STEAM GENERATOR B LEVEL (STARTLP) 16.9 Is 14:24:45 NORM S354

• REHEATER A DRAIN DP 6.054 Ii 14:24:47 NORM S854 REHEATER A DRAIN FLOW 173.4 am 144;4347 FLAG X162 RC PUNP Al SLCTIGN TEMP (R214J GGOD

, " 14:24:47 FLAG X184 RC PUMP B1 SUCTION TEMP (R216) GOOD l3 14:41:34 VATR N791 CORE THERMAL POWER (MW) 2437. wm 144;444/ PLAu X4ds NG F UNF B2 5UGTION TEMF (R217) GOOD ( p"s"14:24:51 NORM R7:2 RC OUTLET A PRES 9 (UTRROW) 1832. . 14:24:sn man e749 Sternn?ce L-; ; ,g -79.?? gg 14:25:07 BAD A722 RC OUTLET A FRESS (NARROW) 1785. m 14:25:17 FLAG X182 RC PUMP A1 SUCTION TEMP (R214) BAD ( 31_ 14: 25:17 FLAG X184 RC PUMP B1 SUCTION TEMP (R216) PAD u 14825:17 FLAG A185 RC FOMP 22 SUCTICN TEMF (R217) BAD IC 14:25:21 NORM R7:2 RC QUTLET A PRESS (NARROW) 1755. EE 14:25:29 WIGH S240 DEAERATOR LEVEL (FT) 13.'9 as 14:05:34 LOW T251 STEAM SEAL HEADER FRESS 92.9 .~ 52 14:25:34 BAD R223 RC QUTLET A PRESS (NARROW) -????. Fi 14:25:34 BAD R224 RC OUTLET B PRESS (NARROW) 999t. 14:05:36 6AD A7:2 RC QUTLET A FRESS (NARROW) 1716. 14:25:37 BAD R:25 RC CUTLET B PRESS (NARROW) -????. 14:25:41 BAD R:22 RC QUTLET A PRESS (NARROW) ='???. f( .l 't*i!! H e it n

F Zi t s h-ri y-a \\, I ( 14:05:43 NORM S258

• MEATER 5B DRAIN DP 61.7 ~

~ ~ ~ ~~~ '" ~~" ~ ~~ ~ ( 444 Lieo NG6M a7Ls nEAiEA Lb shAAN F60w 1085. "I l 14:05:47 BAD $386

• HEATER 4A DRAIN DP

-???.? I 14:25:47 BAD S886 HEATER 6A DRAIN FLOW '*??. "l! 14:25:52 NORM R72 RC CUTLTT A PRESS (NARROW) 0 '~l 14:43:37 VATR N791 CORE TwERMAL POWER (MW) 54?7. 'e 14:,25:58 NORM S240 DEAERATOR LEVEL (FT) 12 17 7" 14:25:58 BAD S258

• HEATER 53 DRAIN DP

-???.? 'T II 14:26:01 BAD 5758 WEATER 5B SRAIN FLCW j; 14:26:01' SAD S370 sREHEATER B COMB DRAIN DP -?.??? e jg 14:26:02 BAD S870 REHEATER B COMB DRAIN FLOW -???.? g

e' 14:06:05 MIDM R202 PRESSURIZER LEVEL L3(IN)(UNCOMP) 164.0 N 14:26 09 BAD T312 HP TURB BEARING NO 1 VIBR (MILS)

-7?.?? 7" 14:26:14 NCRM T312 HP TURB 314 RING NO 1 VIBR (MILS) .00 ") 3' 14!:6:16 NORM $770 sREHEATER B COMB DRAIN DP .077 ~ m 14:;6:17 NGAM F470 REHEATER B COMB DRAIN FLOW 50.8 7" 14:26:25 LOW R/01 RC TOTAL QUTLET FLOW (MLB/HR 140.7 Ti 14:26:06 LCW R860 RC TOTAL FLOW (RP CH A) (MLB/NR) 140.5 in 14:26: e LCW R861 RC TOTAL FLOW (RP CH B) (MLB/HR) 140.7 72 14:26:26 LOW R862 RC TOTAL FLOW (RP CH C) (MLB/HR) 140.7 II 14:06*26 LOW R967 RC LOOP 9 FLCu (RP CH 9)(ML9/wR) 40.97 8 it 14:26:06 LOW R869 RC LOCP B FLCW (RP CH C)(MLB/HR) 70.01 it 14:26:26 LCW R873 RC LOOP B FLOWCTEMP COMP,MLS/HR) 70.48 l '* 14!06:29 NORM S258

• HEATER 59 ScaTN Pp 1.9 it 14:26:31 NORM $758 HEATER 5B DRAIN FLCW 186.

g 14:45:34 VATR N791 CORE THERMAL PCWER (MW) 2437. ) 2r 14:26:31 CCNT 7004 LP TUR9 A COV END STM TEAL PDEET LOW ft 14:26:40 LOW R770 RC SUBC0 CLING (CEG F) 18. t a 14:26:44 BAD 5:58

• HEATER 5B DRAIN DP,

'??.? } IE 14:06:46 pad S759 WEATER 59 DRAIN rtCW ,+++. n 14:26:4o BAD S370

• REHEATER B COMB CRAIN DP

-?.??? l "; 14:26:47 BAD 5870 REHEATER B COMB DRAIN FLOW -???.? E 14:06:53 CONT PC50 MAKE UP PUMP A - RUN G E" ( E 14:26:53 CONT PC50 MAAE UP FUMP C RUN- --

• PL g 14:;6:53 CCNT X063 DECAY HEAT PUMP A RUN w 14:06:53 CON' YO64 DECAv wtAT 00ao 9 enN FJ 14:26:57 CONT XO6 ENER NUCLEAR SVC SEA WATR PUMP B RUN n; 14:26:58 CONT E044 EMERGENCY GENERATOR B RUNNING YES

) 2 14t?AtM9 PENT Fo41 FurRNr4EY OFNFRATOR A R?!NN'NN VFR 3g 14:27:01 NCRM S370

• REHEATER B COMB DRAIN DP

.140 2m 14:07:02 BAD S379

• REHEATER C HP DRAIN DP

-?.??? )

• 14*T7:00 NCRM $870 REHEATER R COM9 DRAIN FLOW 71.0 in 14:27:02 BAD S879 REHEATER C HP CRAsN FLOW

-???.? E 14:27:04 CONT XQ11 RC PUMP Al STOP b4 'U2 E.14:07:04 CONT x044 RC PUM* B2 STEP eties

m 14

47:34 VATR N791 CORE THERMAL POWER (MW) 2437.

gu 14:27:06 CONT 7001 LP TURB B OEN END STM SEAL PRESS - LOW

• F 14:27:06 CONT YO21 RC PUMP At SPEEP LOW

! 14:27:00 CONT XO54 RC PUMP B: SPEED LOW = 14:07:07 CONT X022 RC PUMP B1 STOP .6 14:27!07 CONT YO33 RC PUMP A? MTED =t 14:27:07 CONT XQ32 RC PUMP A2 SPEED LOW 35 14:27:07 CONT X043 RC PUM? B1 SPEED LOW ) me 14:27!10 CONT Pos3 MAKE UP PUMD E EOntTNG WATR FLOW OK $ 14:27 10 LOW T246 EH FLUID TEMP 109.2 23 14:27:25 LOW R702 RC LOCP A BEST EST FLOW (MLB/HR) 69.48 .i 1" 14:27:25 LCW R703 RC LOCP 8 BEST EST FLCW (MLB/WR) 69.38 E 14:07:06 LOW R863 RC TOTAL FLOW (RP CH D) (MLB/HR) 134 4 18 14:27:26 LOW RS64 RC LOOP A FLOW (RP CH A)(MLB/HR) 47.88 ) h 14:07:26 LOW R865 RO LOOP 3 FLOW (RP CH A)(ML3/WR) 47.55 su 14:27:26 LOW R866 RC LOOP A FLOW (RP CH B)(NLB/HR) 69 12 l "s 14:27:26 LOW Rd68 RC LOOP 4 FLOW (RP CH C)(MLB/HR) 67.29 3 T' 14:27!26 LOW R870 RC LCCP A rLOW (Rp CH 3)tML9/NR) 67.25 14:27:26 LOW RS71 RC LCOP S FLOW (RP CH D)(MLB/HR) 68.69 14:27:2a LOW RG72 RC LOOP 4 FLOW (TEMP COMPeMLB/hR) 69.10 s 14:49:32 VATR N791 CORE THERMAL POWER (MW)., ._,,,2,4 3,7,. (

.e 4

j 4 m e-engusma e m m

• • =e
  • -*P***

e e

p, p yL ~ t' ' a l M J-I i 14:07:33 NORM TOOS 1A"MA N STEAM TO TURB PRESS '9 0 8'. ~ ~~~~~~ ~ "" ~ ~ ~ ~ " " _, ~ ~ ' ~ f 146.ies, wvhi Aaam wne srsiun snautNGL FAULT fE3 l 14:27:37 CONT E03: 120VAC REG INST BUS 3B(VBDP-2) DEAD 14:27:38 CONT XO:9 RC MOTOR B1 LOWER OIL POT LVL LO YES 14:49:59 DATA R205 PRESS RELIEF VLV RCV-10 QUT TEMP 280.4 -- 14:50:04 DATA R206 PRESS RELIEF VALV RCV-9 OUT TEMP 154.8 4 V 14:27;J5 GQNT A1 5 CAD SY5 TEM SEGUENCE FAULT NO _h* "U 14:50:14 DATA R207 PRESS RELIEF VALV RCV-8 CUT TEMP 356. f ~* 14:27:39 CONT E032 120VAC REG INST BUS 3B(UBDP-2) ENRG ".7 T4;ae...

• As se<o sAgesArtn b cant LAaIN DP

-?.??? "I 14:27:47 BAD S870 REHEATER B COMB DRAIN FLOW -???.? ) 10 14:27:52 CONT 7006 GLAND STEAM CDSR VACUUM OK in 14:27:54 MIGH T315 LP TURB BEARING NO 4 VIBR (MILS) 7.11 g @ 14:27:54 CONT XO40 RC MOTOR A2 LOWER OIL POT LVL LO YES ) u 14:27:56 CONT 7006 GLAND STEAM CDSR VACUUM. LOW to 14:08:09 NCkn SO93 STEAN GENEAATCA B LEVEL (b7ARTUP) 29.0 7" 14:08:13 CCNT 7006 GLAND STEAM CDSR VACUUM OK ) Ti 14:08:16 NORM S379 sREHEATER C HP DRAIN DP .045 u, 14:28:17 NORN 5879 REnEATER C HP DRAIN FLOW 13.9 7; 14:28:17 FLAG X18: RC PUMP Al SUCTION TEMP (R214) GOOD ) 7" 14:28:17 FLAG X184 RC PUMP Bt SUCTION TEMP (ROl6) GOCD s 14:51:3e VATR N791 CORE THERMAL POWER (nW) 2437. 7" 14:29:17 FLAG X185 RC PUMP B: SUCTION TEMP (R217) GCOD ) "i 14:28:44 NORM T315 LP TURB BEARING NO 4 VI3R (MILS) 6.40 n, 4444a&4i r6AU Aans AG PUNF bi 5LGiisN TEnP (A217) BAD ( se 14:28:48 CONT X040 RC MOTOR A2 LOWER CIL POT LVL LO NO ) IU 14:29:03 LCW T:28 1A MAIN STEAM TO TURB PRESS 834. n 1*;;f&id NGAn T229 2A MAIN STEAM TO TURB TEnP 588.o E 14:29:29 CCNT 7005 HP TURB STEAM SEAL PRESS LOW ) E 14:09:09 MfGH S329 DEAERATOR (9 SIDE) TEMP 310.1 l n 14:29&40 NOAM S370 sREHEATEA B CCMB DRAIN LP .087 .( "E 14:29:46 NCRM SS70 REHEATER B CCMB DRAIN FLOW 56.1 } 3R 14:29:54 CCNT X009 RC MOTOR B1 LOWER CIL POT LVL LO NO (' y 3 4;s0401 bAL 5370 anEnsaiEn b Cone DAAIN CF -?.??? g "" 14:30:02 BAD S870 REHEATER B CCMB DRAIN FLOW -???.? 14:30:31 BAD N230 FLUX 8-F LEVEL 7 (NANDAMPS) -????. t 3, sy 44;av;46 usAn aaev aAcNtaica e cena LAAaN LF .oa; {r ;p 14:30:47 NORM S870 REHEATER B COMB DRAIN FLCW 156.8 ) I 5" 14:30:52 BAD $964 STEAM GEN A UPPER DOWNCOMER TEMP 559.7 3 44; avis

• wami Ageo nu nuiLA A2 ureEA GAL Foi L46 60 fE5 s.

E 14:31:04 BAD N556 FLUX 7-R LEVEL 7 (NANDAMPS) -?*r?. 3; 14:53:34 VATR N791 CCRE THERMAL POWER (M6) 2437. 4*.as;;v Nonn ne<v nc suscsst2No (ces e )

21. --

3 14:31:25 CONT P058 CRD WITHDRAWN INHIBIT AwAM as E 14:31:32 BAD P204 STARTUP RATE (SOURC RANGE)CH NIX -.** .m 14:31&30 BAL F205 STAATUP RATE (SOURC AAriGE)C% NIO -??.?T i In 14:31:46 BAD N38 FLUX 13-F LEVEL 7 (NANDAMPS) -????. I "a 14:31:47 BAD N390 FLUX 10-F LEVEL 7 (NANCAMPS) am 14:31:59 CONT AO 9 FWP A SUCTICN VALVE CPEN NO i " 14:32:01 BAD N534 FLUX 5-0 LEVEL 7 (NAN 0 AMPS) -????. ' ) [E 14:3:!O2 NORM P204 STARTUP RATE (SOURC RANGE)CH NI1 1.59 wm 14:3230; NOAn F205 STARTUP RATE (SouRC RANGE)CH NIO 1.54 }} 14:32:06 BAD NSS: FLUX 12-0 LEVEL 7 (NANDAMPS) -????. ) .a 14:32:09 BAD N604 FLUX 14-D LEVEL 7 (NANCAMPS) -????. g3 14&J2307 GUNT F058 CAD WITHLRAWN IhMIBIT CN un 14:32:11 NORM S308 STEAM GEN OUTLET 1B PRESS 944. ""~ IU 14:32:13 BAD $261 FUPT A FIRST STAGE PRESS -?".' ~6 n 14&32:16 BAD T;;8 1A NAIN STEAn TO TURB FRESS -???'. II 14:3 :18 LOW 7:29 2A MAIN STEAM TO TURB TEMP $64.7 j II 14:55:39 VATR N791 CORE THERMAL POWER (MW) 0437. us 14:32:26 LOW R 22 RC QUTLET A PRESS (NARROW) 1700. Il 14:32:31 BAD S370 sRENEATER B COMB DRAIN DP -?.??? ) 1R 14:32:30 BAD S870 REHEATER B COMB DRAIN FLOW 14:30:36 LOW R223 RC OUTLET A PRESS (NARROW) 1869. 14:32:34 LOW R:24 RC OUTLET B PRESS (NARROW) 1873. s 14:32:36 BAD R7 RC QUTLET A PRESS (NARROW) 1869. ).. th h l I i p ?i 'I f s. - =.. t d tr-e'

~ tf = l1 ' L*t ? b* I: I 14:32:36 LOW R225 RC OUTLET B PRESS (NARROW) 1559. ~~' ~~ ~~~~~~~ "~~ [ 14sJs341 640 N324 FLUX 9-M LEVEL 7 (NANGAnF5) -?'??. 3 i 14:32:41 NORM R200 RC PRESS (WIDE) (LCOP Al 1941. i 14:32 43 FLAG X108 HIGH PRESSURE INJECTION REQUIRED NO "T 14:32:44 BAD N381 FLUX 13-F LEVEL e (NANCAMPS) -???'. '"i 14:54:59 DATA R*08 RC PRESS (WIDE) (LOOP At 2323. % 14:32:47 NORM M390 FLUX 12-F LEVEL 7 (NANCAMPS) 9. ll 14:32:48 BAD N398 FLUX 11-0 LEVEL 7 (NAN 0 AMPS) -????. 3 10 14:32:48 NORM 7031 13 MAIN STEAM 70 TURS TEMP M90.* 2; 14:32:48 NORM T232 13 MAIN STEAN TO TUR3 PRESS 927. i

• A '? _

l ) J; -14:57f'*.VATR N791 CORE _'wrcMAL 80Wre '" s' 14:32:56 NORM R222 RC OUTLET A PRESS (NARROW) S170. I J! 14:33:01 NORM $370

• REHEATER 3 COMS DRAIN DP

.276 ' 3 14:33:01 NORM S570 REHEATER S COMB DRAIN FLOW 99.8 3 e-14:33:05 HIGH R209 RC PRESS (WIDE) (LCCP A) 2293. >* 14:33 05 HIGH R210 RC PRESS (WIDE) (LCOP 3) 2301. I~ 14:33:06 HIGH R223 RC OUTLET A PRESS (NARROW) 2 86. 77 14:33:06 HIGH R**4 RC OUTLET 3 PRESS (NARROW)

• 29*.

m 14:33:0e CONT 403e RC MOTOR 41 HP OIL PP DISCH PRES HIGH "j 14:33:04 HIGH R225 RC QUTLET 3 PRESS (NARROW) 2303. ) 1r 14:33:11 WIGH R*08 RC PRESS (WI2E) (LOOP A) 23!a. as 14:33 11 HIGH R :: RC CUTLET A PRESS (NARROW) 0361. ij 14:33:18 NORM T233 33 MAIN STEAM TO TURS TEMP 590.0 ) 's 14:33:34 BAD N262 FLUY 4-G LEVEL 7 (NAN 0 AMPS) 1! 14:33:37 BAD N286 FLUX 5-K LEVEL 7 (NANDAMPS) -????. It 14:33:44 NORM S3:8 DEAERATCR (3 SIDE) TEMP 308.7 ) 20 14:33:46 NCRM N381 FLUX 13-F LEVEL a (NANOAMPS) 9.

E 14*33:47 BAD N390 FLUX 12-F LEVEL 7 (NAN 0 AMPS)

-????. 2 14:33:47 FLAG X182 RC PUMP Al SUCTION TEMP 4R214) BAD II 14:59:34 VATc N701 O2RE TwER=AL pcWER (=W) 543*. l 2 14:33:47 FLAG X183 RC PUMP A: SUCTICN TEMP (R215) GCCD ( -. jj 14:33:47 FLAG X194 RC PUMP B1 SUCTION TEMP (R216) BAD ) O' 14:33:51 NORM R722 RC CUTLET A PRESS (NARROW) 2325. g z. 14:33 54 BAL Nee 2 FLUX 5-D LEVEL 7 (NANDAMPS) -???'. jj 14:33:56 LOW S308 STEAM QEN QUTLET in PRESS 9:0. j p 14:34:03 LCW T232 13 MAIN STEAM TO TURB PRESS 910. g gj 14:34:17 FLAG X160 RP SOURCE RANGE NIX AUTO ALRM g( g 14:34:17 FLAG X191 RP SOURCE RANGE NI2 AUTO ALRM 3 w 14:34:17 FLAN Ytq3 Rc PUMP AS cimT?nN Tr=* (R***$ =An 2C 14:34;** NORM S964 STEAM GEN A UPPER DOWNCOMER TEMP 557.7 3 14:34:31 BAD N229 FLUX 9-F LEVEL 6 (NAN 0 AMPS) -????. w 14:34:34 NORM N2s2 rLUY A-G LEVFL 7 (NANDAMD9) ?O. E 14:34:40 BAD S 30 sDEAERATOR INLET 3 COND DP -???.'s J Jo 14:34:43 BAD N350 FLUX 11-K LEVEL 7 (NANCAMPS) -????. p 14:34*45 BAD E730 DEAERATCR INLET R ESND FLSW 2 14:34:57 NORM $230 *DEAERATOR INLET 3 CCND DP .1 au 14:35:01 NORM S730 DEAERATOR INLET 3 COND FLOW 1**. 3 14:35:01 BAD S370 aREWE4TER 9 COM9 DRAIN 08 g! 14:35:00 BAD SS70 REHEATER 3 CCMS DRAIN FLOW -???.? i am 15:01:34 VATR N791 CORE THERMAL POWER (MW) 2437. 33 14:35:02 BAD N542 FLUX a-0 LEVEL 7 (NAN 0 AMPS) ~~**. th 14:35:03 BAD M550 FLUX 4-P LEVEL 7 (NANCAM*0) ' '? ?. gg 14:35:08 BAD N598 FLUX 13-L LEuEL 7 n NANCAMPS) -????. y W8 14!35fSR EONT YO49 RF MOTOR 99 UPPER MT8 PMT f Ut fn vrC !$ 14:35:31 CONT X034 RC MOTOR 31 HP OIL PP DISCH PRES CK 38 14:35:33 BAD N244 FLUX 7-F LEVEL 7 (NANDAMPS) -????. ,y JH 14:35!2E BAD NS70 FluY S=G LEVEL 7 (MANDAMPS) fB 14:35:36 CCNT XO36 RC MOTOR 31 HP OIL PP DISCH PRES HIGH

• 14:35:37 CCNT X034 RC MOTOR 31 HP OIL PP DISCH PRES OK l

3E 14:35:30 CONT YO3a RC MOTOR 91 Ho ffL PD DTSCH OEES WYGH ja 14:35:39 CONT XQ3e RC MOTOR 31 HP OIL PP DISCH PRES ON l to 14:35:41 CONT XQ34 RC MOTOR 31 HP OIL PP DISCH PRES HIGH ,) l El 14:35:42 CON _T YO34' RC MOTOR 91 WP OTL ## DISCH P#ES DK 4:35:43 CC:t f XO3e RC MOTOR B1 HP OIL PP DISCH PRES HIGH 14:35:44 CONT X036 RC MOTOR 31 HP OIL PP DISCH PRES OK 14:35:44 NORM S370

• REHEATER 3 COMB DRAIN DP

.141 ( i.- .J u 9.J 9n. m ~- .m. A o. m e.,m e. ._ m. -o + '5

g. E o s g i I ...--..~;. I 14:35:46 NCRM 9870 REHEATER S COMB DRAIN" FLOW 70.2 ~ ~ ' ~ ~ ~ 44.asisw LJe A;10 Fwe A sFasa (nFM) Be. ~~ 14:35:53 CONT XO36 RC MOTOR 81 HP OIL PP DISCH PRES H I " 15:03:37 UATR N791 CORE THERMAL POWER (MW) 2437. 14:35:53 BAD N454 FLUX 6-C LEVEL 7 (NANDAMPS) -????. 14:35:55 CONT X036 RC MOTOR B1 WP OIL PP DISCH PRES Ok 4 14:35:57 CONT XO36 RC MOTOR B1 HP OIL PP DISCH PRES HIGH ) UU 14:35:58 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES OK 00 14:36:01 BAD NS 6 FLUX 4-N LEVEL 7 (NANCAMPS) .c 14:36&O1 CONT XQ36 RC MOTOR B1 MP OIL PP DISCH PRES HIGH i ~l 14:36 02 CONT X036 RC MOTOR 81 HP OIL PP DISCH PRES OK Il 14:34 03 CONT XO36 RC MOTOR 91 kP OIL PP DISCH PRES HIGH in 14:3o:04 CCNT XO3e RC MOTCR.. MP OIL PP DISCH PRES DA ) "y 14:3620e CONT XO36 RC MOTCR B1 HP OIL Fi DISCH PRES HIGH t u 14:36:07 CONT YO36 RC MOTOR St HP OIL 'P DISCH PRES OK 14430413 CCNT XO36 RC MOTOR 81 MP OIL PP DISCH FRES MIGH ) 77, 14:34:15 CONT X034 RC MOTOR B1 HP CIL PP DISCH PRES CK Ti 14:36:18 CONT XO36 RC MOTOR B1 HP OIL pp DISCH PRES WTGH am 14:36:19 CONT XQ36 RC MOTCR B1 HP OIL PP DISCH PRES. On ) / T 14:36:20 CCNT X036 RC MOTCR B1 HP OIL PP DISCH PRES HIGH 73 14:36:01 CONT YO36 RC MOTOR B1 HP OIL PP DISCH PRES OK

• 14:3e:22 CCNT XO3e RC MCTCR B1 HP OIL PP DISCH PRES HIGH

) IT 14:36:03 CCNT XQ36 RC MOTOR B1 HP OIL PP DISCH PRES OK IE 15:C5:36 UATR' N791 CORE THERNAL POWER (MW) 0437. ,m 14;Jo;;o CCNT XO3e RC MOTCR B1 MP CIL PP DISCH PRES HIGH ) ( 3; 14:36:26 CONT XO24 RC MOTOR 31 HP OIL PP DISCH PRES CN IU 14:36:27 CONT X036 RC MOTOR B1 HP CIL PP DISCH PRES HIGH n idaJoi;s JuNi XOJo RG MOTCR B1 nP OIL PP DISCn FRES CA 1 ) ( is 14:36:29 BAD N206 FLUX 8-H LEVEL 7 (NANCAMPS) -????. II 14:36:30 BAD N002 FLUX 9-0 LEVEL 7 (NaNOAMPS) l zu 14:3015; BAe N23e Flux 9-E LEVEL 7 (NANCAMPS) -???T. } ./ 5; 14:36:33 NCRM N246 FLUX 7-F LEVEL 7 (NAN 0 AMPS) 9. j E 14:36:34 BAD h:6: FLUX 6-0 LEVEL' 7 (NANCAMPS) a 14aJo:Jo BAL R215 AC PUMF A2 SUCTION TEMP (NARROW) -???.? ) f j"t 14:36:37 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES HIGH y 14:36:30 BAD S:93 STEAM GENERATOR B LEVEL (STARTUP) "?. ? ps 14&J6sJV GUNT XOJo RG MOTGR B1 nP OIL PP DISCH PRES ON } "E 14:36:41 BAD N334 FLUX 10-H LEVEL 7 (NANCAMPS) -????. E 14:36:42 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES HIGH w i4;5o&43 NGAM N350 FLUX 11-h 6 EVE 6 7 (NANOANF S) 9. ,: Ji 14:36:43 CONT X034 RC MOTO9 B1 HP OIL PP DISCH PRES OK ED 14:34:44 SAD N358 FLUX 12-K LEVEL 7 (NANCAMPS) -???'. I 2n 4.a. 40 mas nJei reux ad-r Law c 6 (NaNuanro) - r rr y. 3; 15:07:34 VATR N791 CORE THERMAL POWER (MW) 2437. 3; 14:36:46 CONT XO36 RC MOTCR B1 HP OIL PP DISCH PRES HIGH a 144Jo447 FLAG A1SJ RG FUMP A2 SUCTION TEMP (R215) GCCL IE 14:36:47 CONT XO36 RC MOTOR 31 HP OIL PP DISCH PRES CA i 23 14:36:49 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES HIGH I An 14:36:51 tCT.T~~A03e RC MOTOR B1 HP OIL PP D1bCH PRES OK I ) d 14:36:53 NCRM N454 FLUX 6-C LEVEL 7 (NANDAMPS) 9. ' ps 14:36:55 HIGH R706 STEAM OEN A RC TEMP DIFF 79.5 au 14:3e:55 BAD N470 FLUX 4-E LEVEL 7 (NANGAMPS) -????. ) < G3 14:34:55 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES HIGH s 14:36:57 BAD N496 FLUX 2-G LEVEL 7 (NAN 0 AMPS) m 14:36:57 CCNT XO36 RC MOTOR 31 MP OIL PP DISCH PRES DA ) 13 14:37:02 BAD N541 FLUX 6-0 LEVEL 6 (NANCAMPS) -????. I4 14:37:02 NORM N542 FLUX 6-0 LEVEL 7 (NANCAMPS) 10. sa ;444/iGJ Gani AOJo RC MOTOR B1 MP GIL PP DISCM PRES HIGH ') is 14:37:04 CONT XO36 RC MOTOR 81 HP OIL PP DISCH PRES OK E: 14:37:05 BAD N574 FLUX 10-0 LEVEL 7 (NANDAMPS) n 14:37:05 CCNT X036 RC MOTOR B1 wP OIL PP DISCH PRES HIGH J ~3 14:37:06 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES OK i E4 14:37!06 9AD P71: LOG N (LOG (AMPS)) -10.67 f-15:09:33 VATR N791 CORE THERMAL POWER (MW) 2437. 14:37:07 CONT XO34 RC MOTOR B1 HP OIL PP DISCH PRES HIGH 14:37 08 CONT XO34 RC MOTOR B1 HP OIL PP DISCH PRES OK ,s, 4

• 1 6

4 '. H i i k fl 14:37!09 CONT X036 #C MOTOR P1 HP OfL ** DISCH PRES WIGH ~~ ~~ ~~ 14:37:09 CCNT XO3e RC MOTOR 61 HP OIL PP DISCH PRES OK 1 14:37:10 CONT X036 RC MOTOR 91 HP OIL PP DISCH PRES HIGH 14:37:11 CONT XO36 RC MOTCR B1 HP OIL PP DISCH PRES OK [] 14:37:11 HIGH S21 HEATER 1B INLET COND TEMP 130.5 t 14:37:10 CONT X036 RC MOTOR 91 HP OIL PP DISCH DRES HIGH 61 14:37:13 LCNT XO3e RC MOTGR B1 HP OIL PP DISCH FRES OK 1* 14:37:14 CONT XO36 RC MOTOR 91 HP OIL PP DISCH PRES HIGH T 51 14:37:15 CCNT X034 RC MOTOR 81 HP OIL PP DISOH PRES CK . 14:37:17 FLAG X17: HEAT /CCOL RATE EXCESSIVE YES II 14:37:24 CONT X036 RC MOTOR 91 HP OIL PP DISCH PRES HIGH ) 51 14:37:25 HIGH R713 HEATINC RATE (DEG r/WR) ?91.9 7 14:37:25 CONT X036 RC MOTCR B1 HP OIL PP DISCH PRES OK 14:37:27 BAD G210 EXCITER BEARING NO 9 VIBR (MILS) -??.?? ) 'o 14:37:31 CCNT X036 RC MOTOR 91 HP OfL P* DIECH PRES Mfcu

• 14:37:30 NCRM N38 FLUX 9-E LEVEL 7 (NANCAMPS) 10.

70 14:37:32 CONT XC36 RC MOTOR B1 HP OIL PP DISCH PRES OK 3 If 14:37:35 CCNT X036 RC MOTOR B1 HP OIL po DISCH PRES H!GH ni 15:11:37 VATR N791 C0hE THERMAL POWER (MW) 2437. I 14:37:36 CCNT XO36 RC MOTCR B1 HP OIL PP DISCH PRES CK Is 15:11:44 8A1 $32: REHEATER A HOT REHEAT PRESS N. 15: 11:44 HIGH X 40 CRD -H DISCHARGE WATER TEMP 160 1 ~[ 15:11:46 NCRM N389 FLUX 10-F LEVEL 6 (NANCAMPS) 9. ) " si 15:11:49 CCNT X036 RC MOTCR B1 WP OTL PP DISCH PRES H!GW 4* 15:11:50 CONT XQ36 RC MOTCR B1 HP OIL PP DISCH PRES CK 55 15:11:52 BAD N446 FLUX 7-B LEVEL 7 (NAN 0 AMPS) -????. ) 2" 15:12:03 DATA RS74 PRES 5URIZER AVE COMP LEVEL ffN) 753.9 3E 25:11:50 BAL N45: FLUX 6-C LEVEL 5 (NANCAMPS) -????. ' 2E 15:11:53 NORN N461 FLUX 5-D LEVEL 6 (NAN 0 AMPS) 10. 3 > ?r!!!!?? wee = N4-o e' uv 3 e Erve' ? cNANea=ce) o_ = l EE 15:11:57 BAD N502 FLUX 2-L LEVEL 7 (NANCAMPS) -?T??.

• 15:12:00 CONT X036 RC MOTCR B1 HP OIL PP DISCH PRES HIGH 20

( g 15:12!01 BAD N540 FLOY a-O LEVEC ? (NANOAFF91 15:10:00 CONT XO36 RC MOTOR B1 HP OIL PP DISCH PRES OK i EE.

• g-g 15:10:05 BAD N580 FLUX 12-0 LEVEL 5 (NAN 0 AMPS)

-????.

• 15:12:0A CCN? XO36 RC "0 TOR P1 WP OIL ** DISCH PRT9 WYGW j{ 15:12:04 NORM N590 FLUX 14-M LF. VEL 7 (NANCAMPS) 8.

f su 15:12:07 CCNT XO36 RC MOTOR B1 HP CIL PP DISCH PRES CK ) p t!!!?:10 CON' 7036 RC MOTOR 91 HP OTL ** D?eEM Perm W?nu E 15:13:33 VATR N791 CCRE THERMAL POWER (MW) 2437. 8 3g 15:13:39 ATRA R874 PRESSURIZER AVE COMP LEVEL (IN) ATR 01 350.00/ 50.00 3 > 15tt2:13 cSNT v024 RC MOTOR Pt Ho STL ** SYSEH eere nk TJ 15:12:15 HIGH. X:67 CRD 13M DISCHARGE WATER TEMP 160.2 3g 15:12:15 CONT XO36 RC MOTOR B1 HP OIL PP DISCH PRES HIGH w ) 2* if????ta ESN? YSTA RF WO?DR 91 HP N?t 00 D?eEH PRet EV f 15:14:05 ATRA R874 PRESSURIZER AVE CCMP LEVEL (IN) ATR 01 300.C0/ 50.00 fj 15:12:17 CONT X036 RC MOTCR B1 HP OIL PP DISCH PRES HIGH ) a t? tis!!s cSNT ve76 ec =0700 pi we ??t ep ??ec9 eRei et ! 15:12:21 CONT XO36 RC MOTCR B1 HP OIL PP DISCH PRES HIGH

• 15:12:22 CONT X036 RC MOTCR B1 HP OIL PP DISCH PRES OK di 15:14:31 ATRA R207 PRESS RELIEF VALV RCV-G OUT TEMP ATR OS 300.00/ 100.00 um 15:12:24 CONT XO34 RC MOTCR B1 HP OIL PP DISCH PRES HIGH

( E3 15:12:27 CONT X036 RC MOTOR B1 HP CIL PP DISCH PRES OK as 15:12:2g BAD N504 Fluy e-H trVrt 7 (NANSAMPsi bj 15:12:31 BAD N 36 FLUX 9-E LEVEL 5 (NAN 0 AMPS) -????. 3 em 15:12132 BAD N254 FLUX 7-E LEVEL 7 (NANDAMPS) -????. J 3H 15'12!37 9AD NTOS rf UY 7-M trUrt 7 (NANDAMDM) !! 15:12:40 CONT X036. RC MOTOR B1 HP OIL PP DISCH PRES HIGH { ) g! 15:12:40 NORM N333 PLUX 10-M LEVEL 6 (NAN 0 AMPS) 10. -I > !!!!Stai CENT X036 Rc woTOP pt wo 9?? ** a?ccM pere cx m 15:12:42 NORM N350 FLUX 11-K LEVEL 7 (NANCAMPS) 9. 33 15:15:37 VATR N791 CORE THERMAL POWER (MW) 2437. ) 3R 15:12:44 CONT YO36 RC MOTOR B1 HP OIL Pp DISCH PREE HIGH 15:12:44 NORM N3eo FLUX 13-H LEVEL 7 (NAN 0 AMPS) 8. 15:12:45 CONT X036 RC MOTOR 81 HP OIL PP DISCH PRES OK 15:12:45 BAD NISO FLUX 13-F LEVEL 5 (NANCAMPS) -????. 4 H O ~ h ff "C- -___.m__@ P f

. _.. _ _.~ 3 g. G' S

f. '

o "i j' i V. ,.i I 15:12:47 CONT X036 RC* MOTOR B1 HP OIL PP'DISCH PRES HIGH ~~ r assa.s*, wwa. Avse ng neign el er al6 er slain chE5 GN 15:12:52 NORM N444 FLUX 7-B LEVEL 7 (NANCAMPS) 10. 15:12:52 NORM N452 FLUX 4-C LEVEL 5 (NANDAMPS) 10. I 15:12:53 BAD N461 FLUX 5-D LEVEL 6 (NANCAMPS) -??". ( 15:12:54 CONT X036 RC MOTOR B1 HP OIL P* DISCH FPES HIGH in 15:12:55 CONT A03o RC MOTOR 81 HP OIL PP DISCH PRES CK

• I 15:12:54 CONT X034 RC MOTOR 81 HP OIL PP DISCH PRES HIGH li 15:12:56 CONT XO36 RC MOTOR B1 HP OIL P' DISCH PRES OK o 15:12:59 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES HIGH

} ][ 15:13:00 CCNT X036 RC MOTOR B1 HP OIL PP DISCH PRES OK n. 15:13:01 NORM N540 FLUX 6-0 LEVEL 5 (NANOAMPS) 10. 8 '76 15:13:01 NORM N541 FLUX e-0 LEVEL e (NAN 0 AMPS) 10. ) 30 15:13:05 NORM N580 FLUX 12-0 LEVEL 5 (NANDAMPS) t 10. 7*. 15:13:09 CCNT X036 RC MOTOR 91 HP OIL PP DISCH PRES HIGH a, AL;14&ld 6;Ni AGso AG norGA b1 MP OIL FP DISCM FRES On ) 7" 15:17:37 VATR N791 CORE THERMAL POWER (MW) 2437. Ti 15:13:11 CCNT X036 RC MOTOR B1 HP OIL PP DISCH PRES HIGW tr 15:13:13 CCNT A036 RC MOTOR St HP OIL PP DISCH PRES CK } 7" 15:13:14 CONT XO36 RC MOTOR B1 HP OIL PP DISCH PRES HIGH 73 15:13:15 CONT X036 RC MOTOR 91 HP OIL PP DISCH PRES Ok n 15:13:15 HIGM X70 CAD 12N DISCHARDE WATER TEMP 160 1 ~~ 15:13:18 CONT XO36 RC MOTOR B1 HP 0*L PP DISCH PRES HIGH Ti 15:13:19 CON

• X036 RC MOTOR 91 HP OIL PP DISCH PRES CK om 15:13:22 CONT x03e RC MOTCR 31 NP OIL PP DISCH PRES HIGH EE 15:13:23 CONT XO36 RC MOTCR 81 HP OIL P' DISCH PRES OK IE 15!!3:29 NCRM N214 FLUX 9-H LEVEL 7 (NANCAMPS) 10.

m 15.3:50 cant A034 AC n0 TOR B1 nP OIL PF DISCM AhES HIGM ) IE 15:13:31 CONT XO34 RC NDTOR B1 HP OIL [P DISCH FRES OK II 15:13:31 NCRM N234 FLUX 9-E LEVEL 5 (NANCAMPS) 9. is.ia.aa eAs N.Ja rowx y s Lcvs. 7 (NANGAnes) -????. !s 15:13:32 BAD N244 FLUX 7-F LEVEL 7 (NANOAMPS) -????. ) 55ER 15:13:32 BAD N252 FLUX 7-E LEVEL' 5 (NANCAMPS) -????. y is.l.;a. mwnn N.L* FuwA / s LEvsu 7 (NANGAnrsa 7. fm}" 15:13:33 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES HIGH I \\ 15:13:34 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES CN y se 15:19:34 VATA N791 CGAE THEanAL POWER (nwa 2437. I' is 15:13:3S CCNT X034 RC MOTCR B1 HP OIL PP DISCH PRES HIGH I 3 15:13:40 CONT XO36 RC MOTCR B1 HP OIL PP DISCH PRES CK w 15:13:41 CONT A03e RC NOTOR 61 MP OIL PP DISCH PRES HIGN is 15:13:41 BAD N342 FLUX 11-L LEVEL 7 (NANCAMPS) -????. EU 15:13:42 HIGW X221 CRD 10D DISCHARGE WATER TEMP 160.7 2n isalJ4A; CTL N3so Flux 11-6 LEVLc / (NANGAnFS) -7?7?. 3 3; 15:13:43 CCNT XW36 RC MOTOR B1 HP OIL PP DISCH PRES OK 3I 15:13:43 HIGH X229 CRD 2-F DISCHARGE WATER TEMP 160.0 e LLia444s BAD NJ;7 Fuux 12-n LEVEL e (NANCAnPS) -????. 3 15:13:44 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES HIGH 3 15:13:44 PAD N364 FLUX 13-H LEVEL 7 (NANDAMPS) e 15:1J:45 CONT x036 RC MCTOR B1 NP OIL PP DISCH PRES OK I 15:13:45 NORM N300 FLUX 13-F LEVEL 5 (NANCAMPS) 9. ) lE 15:13:46 CONT XO36 RC MOTOR B1 HP OIL PP DISCH PRES HICH m 15:13:46 3AD N389 FLUX 12-F LEVEL 6 (NANCAMPS) -?T??. i 15:13:47 CONT X036 RC MOTOR 31 HP OIL PP DISCH PRES , 0K 15:13:40 NORM N414 FLUX 10-D LEVEL 7 (NAN 0 AMPS) A 15:13:51 CONT XO36 RC COTOR 81 HP OIL PP DISCH PRES HIOW I EN 15:13:50 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES CK IU 15:21:32 UATR N791 CCRE THERMAL PCUER (NU) 0437. n 15:13:53 CONT x036 AC MOTCk B1 MP OIL PP DISCH PRES HIGH IT 15:13:53 CONT XO36 RC MOTOR 31 HP OIL PP DISCH PRES OK J II 15:13:54 SAD N469 FLUX 4-E LEVEL 6 (NANDAMPS) -t. in 15:13:55 &# D N478 FLUX 3-F LEVEL 7 (NANCAMPS) -????. lJ 33 15:13:56 BAD N494 FLUX 1-H LEVEL 7 (NANCAMPS) -????. M 15:13:57 CONT x036 RC MOTOR B1 HP CIL Pa DISCH PRES HIGH 15&l3:57 CONT x036 RC MOTOR B1 HP OIL PP DISCH PRES ON 15:14:00 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES HIGH 15:14:00

BAD, N533 FLUX 5-0 LEVEL 6 (NANCAMPS)

-????. .r ilo 0 y.

---

=

y

i y

FI e f, I: .i :. 1 14:01 CCNT X034 RC "0TCR P1 HP CIL'PP DISCH core cv ~" ~ '~~ ,3 15 14:ut BAD N541 FLUX e-O LEVEL o (NANCAMPS) -?'?'. { 15:14:06 CONT X036 RC MOTCR B1 HP OIL PP DISCH PRES HIGH ,,f 15:14:06 BAD N590 FLUX 14-M LEVEL 7 (NANDAMDS) -??'?. '3 _j 15:14:07 CONT X036 RC MOTCR B1 HP OIL PP DISCH PRES CA [*

• 14_:07 CCNT YO3e RC MOTOR P! WP OIL ** DIECW reEe WISw il 15:14:08 NORM N604 FLUX 14-D LEVEL 7 (NANCAMPS) 9.

71 15:14:09 CONT XO36 RC MOTOR B1 HP OIL PP DISCH PRES CK ll 15:14:19 CCNT XO36 RC MOTCR B1 HP OIL AP UISCH PRES HIGH e-15: 14:00 CONI X036 RC MOTCR B1 HP CIL FP DISCH PRES CK l l' 15:14:03 CONT XO36 RC MOTCR B1 HP LIL PP DISCH PRES HIGH i I" 15:23:36 VATR N791 CORE THERMAL POWER (MU) 2437. I 2j 15:14:24 CONT XO36 RC MGTCR B1 HP OIL PP DISCH PRES CK Jg 15:14:28 BAD N205 FLUX 8-H LEVEL 6 (NANCAMPS) -????. .) o 15:14:30 CONT XO36 RC wCTcR ?! HP O!L op Siscw ePrr Hi H 15:14:30 CONT X036 RC MOTCR B1 HP OIL PP DISCH PRES CA E'o 15:14:31 BAD NO3a FLUX 9-E LEVEL 5 (NANDAMPS) '??*. 3 15:14:31 NCRm N;3g rLUX 9-E LEVEL 7 (Na" CAM *S) 9 s 15*14:31 BAD N241 FLUX 7-F LEVEL 2 (NANOAMPS) -??'T. l ) I'I 15:14:32 CONT X034 RC MOTOR B1 HP OIL PP DISCH PRES HIGH E 15:14:30 pad N 45 FLUX 7

• LEVEL 6 (NANDAa*S) 16 15:14:32 NCRM N244 FLUX 7-F LEVEL 7 (NANCAMPS) 9.

IT 15:14:32 NORM N252 FLUX 7-E LEVEL 5 (NANCAMPS) 10. } 7 15:14:32 BAD N:54 rLuX 7-E LEVEL 7 (nan 0aMos) a* 15:14:33 CCNT XQ34 RC MOTCR 31 HP OIL PP DISCH FRES CK IE 15:14:34 CONT XO34 RC MOTCR B1 HP OIL PP DISCH PRES HIGH ) I~ 15:14:35 CONT XO36 RC MOTCR B1 HP OIL Pp DISCH DeEE CK n 15:14:35 NORM N78 FLUX 5-M LEVEL 7 (NANCAMPS) 9. E 15:14:39 NCRM N317 FLUX 9-N LEVEL 6 (NAN 0 AMPS) 9. E !*:14:Jo Neen N324 etuv ta = LTV L fNaN0s-es) O. h 15:14:41. NORM N34 FLUX 11-L LEVEL 7 (NANCAMPS) 9. 3~ 15:25:32 VATR N791 CCRE THERMAL PCWER (MU) 2437. I k E 15:14:43 CCNT X036 RC *0 TOR P1 up OTL PD SIeEH DDEI HIOw f 2 15:14:44 CCNT XC36 RC MCTCR B1 hF OIL PF DISCH PRES CA e 3 15:14:44 BAD N373 FLUX 13-G LEVEL 4 (NANCAMPS) -????. ) ] p 15:14:4A NORM N3go rLUX 12-r LEVEL 6 (NAN 0A**9) 9. g L 15:14:46 NCRM N390 FLUX 12-F LEVEL 7 (NANCAMPS) 9. g-15:14:47 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES HIGH ) ~ p 15:14:49 BAD N414 FLUX 10-0 LEVEL 7 (NaNcaMos) w. > 15:14:49 CONT XQ36 RC MOTCR 31 HP OIL PP DI3CH PRES CK L E 1*:14*53 NORM N461 FLUX 5-D LEVEL 6 (NANCAMPS) 9. I E 1*:14:*4 NCR" N404 FLUX 1-4 LEVEL 7 (NAN 0 amps) 9. n 15:14:57

• NORM N50 FLUX

-L LEVEL 7 (NANCAMPS) 9. E 15:15:00 CCNT X034 RC MOTCR B1 HP OIL PP DISCH PRES HIGH ) E it:is:Oc Neem Ner+ rLuv 4-N t eur'_ 7 tNaNeaMee) to. g 15:15:00 NORM N5:3 FLUX 5-0 LEVEL 6 (NANCAMPS) 10. g 15:15:01 CCNT X036 RC MOTCR B1 HP OIL PP DISCH PRES CK a ?*!? ?a? yne = N*a. ce ev 4-n i ruri 4 < N a n a n = e.e. .a f 1*:15:02 PAD N549 FLUX 6-P LEVEL 6 (NANCAMPS) -??'?. = 15:15:04 CCNT XO34 RC M37CR 81 HP OIL PP DISCH PRES HIGH n* 15:15:C5 CONT X026 RC MOTOR B1 HP O?L #P D?eEH #REE 0% = 15:1*:08 CONT XC36 RC MOTOR 81 HP OIL PP DISCH PRES HIGH g3 15:27:35 VATR N791 CORE THERMAL POWER (MU) 2437. ) .a 15:15:M9 bad N606 FLUX 14-D LEVEL 7 (NANDAMP9) a 15:15:09 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES CK IE 15:15:11 CONT X036 RC MOToi! B1 HP OIL PP DISCH PRES HIGH -) IU 15:15:10 CCNT X036 RC MOTCR B1 HP OIL PP DISCH PRES UK n 5:15::: CCNT Xo3o RC MOTCR B1 HP OIL PP DISCH PRES HIGH 3 ;15:15:23 CONT XC36 RC MOTCR B1 HP OIL PP DISCH PRES CK l h !!!!E:55 ccN' vo'A oc =nToe ** ue c9 ee S?eru eee; w+nu 3 15:15:07 CONT XO34 RC MCTCR B1 HP OIL PP DISCH PRES CA l# 3 15:15:29 NORM N205 FLUX 8-H LEVEL 6 (NANCAMPS) 10. Fi 15:15:31 NORM N234 FLUX O-E LEVEL 5 (NANDA*PS) J. 15:15:31 NORM N241 FLUX 7-F LEVEL 2 (NANOAMPS) 5. 15:15:31 NCRM N244 FLUX 7-F LEVEL 5 (NANCAMPS) S. 15:15:32 NCRM N24t FLUX 7-F,, LEVEL 6 (NANCAMPS: 10.,, / h =y a 1 h

• {.

~

<.i g 0i n. I tl P. l:? i t b. 15:!$130 BAD N246 FLUX 7-F LEVEL 7 (NANDAMPS)...... ='. r Aseas... maw N.Le FL.A < s L6v6. o $Nmh6Anede -????. 15:15:34 BAD T312 HP TURB BEARINO N0 1 VIBR (MILS) -??.?' 15:15::A CCNT XO36 RC MOTOR B1 HP OIL PP DISCH PRES HICH 15:15:35 CONT XC3e RC MOTOR 31 HP OIL PP DISCH PRES CA 15:15:30 BAD N317 FLUX 9-N LEVEL 6 (NANCAMPS) I Of 13:15&43 NORn N358 FLUX 12-n LEVEL 7 (NAN 0 AMPS) 9. ~1 15:29:37 VATR N791 CORE THERMAL POWER (MH) 2437. Il 15:15:43 NORM T312 HP TURB BEARING NO 1 UIBR (MILS) .02 ',g 15:15:44 NIGH A;61 CRD 14L DISCHAh0E WATER TEMP 163.6 pg 15:15:44 NORN N366 FLUX 13-H LEVEL 7 (NAN 0 AMPS) 9. .st 15:15:44 NORM N373 FLUX 13-G LEVEL 6 (NANOA=PS) 10. Jj 15:15:46 BAD N389 FLUX 12-F LEVEL & (NAH0 AMPS) -????. Lei 15:15:46 BAD N390 FLUX 12-F LEVEL 7 (NANCAMPS) -????. } al 15:15:48 CCNT Xo36 RC MOTCR B1 HP OIL PP DISCH PRES HIGH

• 15: 45;46 BAD T312 MP Tuhb BEAAING NO 1 VIBR (NILS)

-??.?? IE 15:15:49 CONT XO3e RC MOTOR 81 HP OIL PP DISCH PRES OK ) II 15:15:50 SAD N430 FLUX 9-C LEVEL 7 (NAN 0 AMPS) im A&&lL.LJ GLNi XQ3o RG nGTGA S1 MP OIL PP DISCn PRES MIGH T3 15:15:53 BAD N461 FLUX 5-D LEVEL & (NANCAMPS) -????. 3 II 15:15:54 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES CK 15:15.55 OJni AC3e RC n0TGR 81 NP OIL FF DISCH PRES HIGH IE 15:15:55 CCNT X036 RC MOTCR B1 HP OIL PP DISCH PRES CK IE 15:15:59 BAD N510 FLUX 3-L LEVEL 7 (NANDAFPS)

• 154;535* CONT XO3e RC MOTCR Si MP OIL PP DISCH FRES HIGH f 3E 15:14:00 BAD N532 FLUX 5-0 LEVEL 5 (NANOAMPS)

-????. j j IU 15:16:00 CCNT X036 RC NOTCR B1 HP OIL PP DISCH PRES OK I n.?:31:35 vata N791 CCRE THERMAL PCWEA (Mw) 2437. is 15:16:01 CONT M036 RC MOTCR B1 HP OIL PP DISCH PRES HIGH ) E 15:16:01 BAD N541 FLUX 6-0 LEVEL 6 (NANDAMPS) j n 1s;;o;G; NGAn n549 FLuA o -F LEVEL o (NANCAnPSJ 10. ~~ 15:16:03 CONT X036 RC MOTCR B1 HP OIL PP DISCH PRES CK } j is 15:16:C3 NCRM N558 FLUX 7-R LEVEL 7 (NANCAMPS) 9. .e..a.. eev .ai. we owne osan;NU nO 4 VIbn sn465) -f?.?? .l 3,j* 15:14:04 NCRM N574 FLUX 10-0 LEVEL 7 (NANCAMPS) 9. 3 15:32:13 ATRA R222 RC OUTLET A PRESS (NARRCW) ATR 03 2000.0/ 500.0 30 issio&GL LUNT AGa6 nG MaiGN bl NF 016 FP DI5CH PRES HIGN Ep 15:16!05 BAD N581 FLUX 12-0 LEVEL 6 (NANCAMPS) -????. f EE 15:16:06 CONT X036 RC MOTOR 31 HP OIL PP DISCH PRES OK w 15alo 00 NCAM N590 FLUX 14-M LEVEL 7 (NANCAMPS) 4 .8i is 15:16:07 BAD N597 FLUX 13-L LEVEL 6 (NAN 0 AMPS) -????. 30 15:16:13 CCNT X036 RC MOTOR 81 HP OIL PP DISCH PRES HIGH sn 1341o314 Hism X;40 GRD 1;L DI5 CHARGE nATER TEMP 160 5 i 5$ 15:16:14 CCNT XO36 RC MOTOR B1 HP OIL PP DISCH PRES CK 33 15:16:15 HIGH X271 CRD 10N DISCHARGE WATER TEMP 160.2 e AL.ao&ts ;;NT Av3e RC nGTGA B1 NP GIL FP DI5CH FRE5 MIGn 73 15:16:16 CCNT XQ36 RC MOTOR B1 HP OIL PP DISCH PRES CA II 15*16:13 CONT X034 RC MOTOR B1 HP OIL PP DISCH PRES HIGH o is.eaeas wain N/vA Lens intnnet emeha (nn)

447.

15:14:18 CCNT X034 RC MOTOR 81 HP OIL PP DISCH PRES CK

) lm 15:16:25 CONT X036 RC MOTOR $1 HP OIL PP DISCH PRES HIGH ww LL;1042a GGNT K034 AC MOTOR B1 NP OIL PP DISCH PRES CK lR 15:14:28 CONT X034 RC MOTOR S1 HP OIL PP DISCH PRES HIGH y se 15 16!29 BAD N214 FLUX 9-H LEVEL 7 (NAN 0 AMPS) 33 15:16:28 CONT XO36 RC MOTOR 81 HP OIL PP DISCH PRES OK m 15:16:31 BAD N238 FLUX 9-E LEVEL 7 (NANDAMPS) -????. j IU 15:14:32 NORM N246 FLUX 7-F LEVEL 7 (NANDAMPS) 9. 2 15:16:3; NORM N253 FLUA 7-E LEVEL e (NANCAMPS) 7. II 15:16:32 CCNT X036 RC MOTOR B1 HP OIL PP DISCH PRES HIGH I: 15:16:03 PAD N261 FLUX 6-G LEVEL 6 (NANCAMPS) to 15:16:33 CONT x036 RC MOTOR 81 HP CIL PP DISCH PRES OK E 15:16:3+ HIGH P253 RC PUMP B2 BLEEDCFF FLOW (CPM) 1.266 j E 15:16:36 NORM N2S5 FLUX 5-K LEVEL 4 (NANDAMPS) 10. 4L;16;Ja aO6n NJAG FLUA 8-N LE' E6 7 (NAN 0 AMPS) 8. v 15:1o:44 H I GH, X254 CRD 4-L DISCHARCE WATER TEMP 160 0 y 15:16:44 BAD N346 ~~-- - FLUX 13-H LEVEL 7 (NANDANPS) -????. (~ 1-9 Il

• s

6~ 3 d*J Fa ,s Mi i' e l. ( h ll I'~ 15:16:45 HIGH x2$9 CRD 6-N DISCHARGE WATER tem

• 160 0

~ ~~~ ~ ~~~* ~3 IL31oids DAP NJa0 FLWX 13-F 6 EVE. 5 (NANCAnFS) -??. 15:35:33 VATR N791 CORE THERMAL POWER (MW) 2437. I 3 15:16:48 NORM N414 FLUX 10-D LEVEL 7 (NANCAMPS) 8. g] 15:16:50 NORM N430 FLUX 9-C LEVEL 7 (NANDAMPS) 10. t 15:16:53 NORM N4el PLux 5-D LEVEL 6 (NANCAme?) 10. [L 15:16:53 NORM T315 LP TURB BEARING NO 4 VIBR (MILS) .00 2; 15:16:54 NORN M469 FLUX 4-E LEVEL 6 (NAN 0 AMPS) 9. v 15:14:55 COMT x036 RC MOTCR B1 HP OIL ** DISCH reES HIGW 1 .; 15:16:55 NORM N478 FLUX 3-F LEVEL 7 (NAN 0 AMPS) 9. Jg 15:14:57 CONT X034 RC MOTOR 81 HP OIL FP DISCH PRES OK 'ei 15:16:57 9AD N50: FLUX 2-L LEVEL 7 (NANOAM*S) I 10. ) .rt 15:16:58 NORM N510 FLUX 3-L LEVEL 7 (NANCAMPS) = ' G3 15:16:58 BAD T315 LP TURD BEARING NO 4 VIBR (MILS) -??.'? G* 15:17:00 CONT YO36 RC MOTOR B1 HP OIL *P DISCH PRES HIGH I am 15:17:00 BAD N526 FLUX 4-N LEVEL 7 (NANCAMPS) -????. l ) IU 15:17:00 NORM N53: FLUX 5-0 LEVEL 5 (NAN 0 AMPS) 7. II 15:17t02 CONT YO3e RC =0T02 91 we OTL ** DISCH *eES OT 12 15:17:03 BAD N558 FLUX 7-R LEVEL 7 (NANCAMPS) -????. 3 15:17:04 BAD N574 FLUX 10-0 LEVEL 7 (NANCAMPS) -????. j 's 15!!7?Of NORM NEE 1 Ft MY ??-O f FUEL A (NANDAMOSS 9. I It 15:17:07 NORM N597 FLUX 13-L LEVEL 6 (NANCAMPS) 10. l ) 13 15:17:09 CONT X034 RC NOTOR 81 HP OIL PP DISCH PRES HIGH n s+ 15!37:36 VATE N?91 CDCE TWERMAL COWER (mV) S437. I ) 1* 15:17:10 CONT XO3e RC MOTOR 81 MP OIL PP DISCH PRES CK Ig 15:17:14 CONT XO36 RC MOTOR 81 HP OIL PP DISCH PRES HIGH su 15:17:14 CONT XO36 RC MOTOR B1 HP OIL Pp DISCH PRES cK 3r 15:17:2e CCNT X036 RC MOTOR 81 HP CIL FP DISCH PRES HIGH n 15:17:27 CCNT XC36 RC MOTOR B1 HP OIL FP DISCH PRES CA 3 I* 15:17!:9 CONT YO36 RC *0 TOR B1 WP OIL ep DIgcw Perg utgu 3E 15:17::S NORM N214 FLUX 9-H LEVEL 7 (NAN 0 AMPS 3 10. 3aj 15:17:29 CONT X036 RC MOTOR B1 HP CIL PP DISCH PRES OK L g !!:17:3? CONT XO36 Re METER 91 HP o?L pp S!EEH Pore w?Nw E 15:17:33 CONT XC36 RC MOTOR B1 HP OIL PP DISCH PRES ON r k j, zt 15:17:36 CONT XO34 RC MOTOR B1 HP OIL PP DISCH PRES HICH l p it!!7:2? SSNT YS3+ Rc =c?re et Ho c?' em Staru eeee cv g EU 15:17:43 NCRM X209 CRD 2-F DISCHARGE WATER TEMP 156.8 i ) g' g 15:17:43 NORM X:36 CRD 3-0 DI3 CHARGE WATER TEMP 156.8 F 15!!7!42 PAD N359 FLUY ?S-T tEUrt 7 (NANNAMes) =****. I Jg 15:17:44 NCRM X256 CRD 4-L DISCHARGE WATER TEMP 153 4 j 2 8 a 15:17:44 NORM X 60 CRD 12L DISCHARGE WATER TEMP 156.5 l E !!!!7:44 BAD N373 FLUX 13-G LEVEL 6 (NANCA"p?) 1 zn 15:17:45 NCRM XO64 CRD 7-M DISCHARGE WATER TEMP 157.3 l ( j~ 15:39:31 VATR N791 CORE THERMAL POWER (MW) 2437. f 7" 15:17:45 NORM X269 CRD 6-N DISCHARSE WATER TEMP 150.9 gg 15:17:45 NORM X71 CRD 10N DISOHARGE WATOR TEMP 152 1 d 15:17:45 NORM X275 CRD 9-0 DIS

• MARGE WATER TEMP 156 6 e !!!?*?45 NECM Y?'O E: P ?SP D?t!HAR9E WA'?R Tr=*

???.4 9. 'l g! 15:17:4e NCRM N389 FLUX 12-P LEVEL 4 (NANCAPPS) g 15:17:47 CONT X036 RC MOTOR 81 HP OIL PP DISCH PRES HIGH d 15:17:47 PAD N396 FLUX 11-G LEVEL 5 (NANSAMPS) S***. t 15:17:48 BAD N414 FLUX 10-D LEVEL 7 (NAN 0 AMPS) -?*??. D s d3 15:17:49 CONT XO36 RC MOTOR B1 HP OIL PP DISCH PRES OR de 15:17!!0 CONT X038 RE adTCR 91 Hp dTL eP DTEEH PRrM H!SW ha 15:17:51 CONT X036 RC MOTOR 81 HP OIL PP DISCH PRES CK 5) am 15:17:52 CONT X036 RC MOTOR 81 HP OIL PP DISCH PRES HIGH s m 15:17:52 CONT XO36 RC MOTOR B1 HP OIL PP DISCH PRES CK u 15:17:54 NORM N470 FLUX 4-E LEVEL 7 (NANCAMPS) 9. ") E 15:17:59 BAD N518 FLUX 3-M LEVEL 7 (NAN 0 AMPS) -??*?. I~ 15:18:01 CONT XO36 RC MOTOR B1 Wp OIL Pp DT90W PeEE W'9w J }m 15:18:02 CONT X034 RC MOTCA 31 HP OIL PP DISCH PRES ON l w 15:18:00 BAD N549 FLUX 6-P LEVEL 4 (NANCAMPS) -*???. l 8 IN 15:19:03 CONT Y026 RC MOTER B1 WP OTL P* S?qcH peee utnu 15:18:04 CONT XO3e RC MOTOR B1 HP OIL PP DISCH PRES ON 15:41:34 VATR N791 CORE THERMAL POWER (MW) 2437. 15:18:10 CONT X036 RC. MOTOR B1 H.P OIL PP DISCH PRES HICH (' 1 7' t u.

• S

f: ~ q( s b ( GPCUP e f .s;44444 02/26/80 1 ANALOG ASSIGNMENT

SUMMARY

l A A4/4 VhLeaun44sn avl Lune 6EVEL GIN) A iA 1 J00 00/ 50.00 7 T R207 PRE 3S RELIEF VALV RCV-8 CUT TEMP ATR 2 300.00/ 100.00 l' RO:0 RC CUTLET A PRESS (NARROW) ATR 3 2000.0/ 500.0 .; 4304 AG FUMP A2 MTR LOWRGUIDE BAG TMP ATR 4 130.00/ .00 ) l si 15:18:11 CONT X036 RC MOTOR 91 NP OIL PP DISCH PRES OK ~~ 15:18:12 NORM X 11 CRD 6-8 DISCHARGE. WATER TEMP 123.7 ) .JJ si 15:18:12 NORM X12 CRD 8-B DISCHARGE WATER TEMP 1?0.8 Il 15:18:12 NORM X213 CRD 109 DISCHARGE WATEP TEMP 119,6 w 15:16112 NCRM A14 CRD 5-C DISCNARGE WATER TEMP 118.6 TT 15:18:12 NORM X15 CRD 7-C DISCHARGE WATER TEMP 126.0 U 15:19:12 NORM X214 CRD 9-C DISCHARGE WATER TEMP 119.0 m 15:13:12 NGAn x;17 CRD 11C DISCMARGE WATER TEMP 149.0 T; 15:18:12 NORM X:18 CRD 4-D DISCHARGE WATER TEMP 116.2 Ti 15:15:12 NORM X:19 CRD 6-D DISCHARGE WATER TEMP 111.6 s is.a.;i. Nenn x..o enL e-a ai5cnanGE.ATER TEne 116 0 8 7 15:18:12 NORM X:21 CRD 10D DISCHARGE WATER TEMP 116.3 15:18:13 NORM X22 CRD 1 D DISCHARGE WATER TEMP 105.9 n. iL444&s; wain N791 GGRE THERMAL PGWEA (MW) 2437. E 15:18:13 NORM X 23 CRD 3-E DISCHARGE WATER TEMP 115.6 .) IU 15:18:13 NORM X:24 CRD 5-E DISCHARGE WATER TEMP 116.8 ra 15:1s;13 NCAn 4:25 CRD 7-E DISCHARGE.ATER TEMP 123.2 E 15:18:13 NORM X:26 CRD 9-E DISCHARGE WATER TEMP 116.8 II 15:18:13 NORM X:07 CRD 11E DISCHARGE '4ATER TEMP 138.7 n. 15;44&Oe LATA A674 FRE55URAZER AVE CONF LEVEL (INJ J 3.o "" 15:18:13' NORM X :S CRD 13E DISCHARGE WATER TEMP 122.7 ) Fi 15:18:13 NCRM X:31 CRD 6-F DISCHARGE WATER TEMP 119.8 LJ isilos.a menn A;4. Gna n-F L;56nARsE WATEA TEnF 13o.0 NCRM X:33 CRD 10F DISCHARGE WATER TEMP 118.5 ) ff" 15:18:13 15:18:13 NORM X:34 CRD 1:F DISCHARGE WATER TEMP 117.8 m As.4 asea nunn Aaas wnu A4e aAsseanus wa.sn isnr 124.4 ) -~ 15:18:13 NORM X37 CRD 5-0 DISCHARGE WATER TEhP 113.6 3 5 15:18:13 NORM X:38 CRD 7-0 DIOCHARGE WATER TEMP 115.3 w 6L;ios.a NUnn x;4Y GAL W-G L15 CHARGE 6ATER TEnP 110.7 E 15:18:13 NORM X40 CRD 11G DISCHARGE WATER TEMP 117.8 33 15*18:13 NCRM X241 CRD 13G DISCHARGE WATER TEMP 109.9 m AL;1d;14-nGAM x;42 GAL 2-n DI5 CHARGE WATER TEMP 113.6 ? E 15:18:14 NORF X:43 CRD A-H DISCHARGE WATER TEMF 118.8 E 15:18:14 NORM Y244 CRD 6-H DISCHARGE WATER TEMP 115.1 mr 15:18:44 NGAn X45 CAL 8-n DISCHAnGE WATER TEMP 1 1.9 7, 15:45:36 VATP. N791 CORE 'HERMAL POWER (MW) 2437. I J II 15:45:42 ATRA R200 PRESSURI ER LEVEL L1(IN)(UNCCMP) ATR 01 300.00/ 50.00 m iL&id;14 NOAn X24o GRL 1GH DISCHAAGE WATER TEMP 119.7 2* 15:1S:14 NORM X:47 CRD 1 H DISCHARGE WATER TEMP 118.8 ) IE 15:18:14 NCRM X:48 CRD 14H DISCHARGE WATER TEMP 119.5 . As46sa14 Nunn x24f GAL J-n DI5GnAnGE WATER TEMP 112.5 gj 15:18:14 NORM X250 CRD 5-K DISCHARGE WATER TEMP 115.1 ) wo 15:46:15 ATRA R200 PRESSilRITER LEVEL Li(IN)(UNCOMP) ATR 01 200.00/ 100.00 en 15318:14 NORM X251 CRD 7-A DISCHARGE WATER TEMP 115.3 Ii 15:18:14 NORM X252 CRD 9-K DISCHARGE WATER TEMP 117.0 ) I0 15:18:14 NCRM X253 CRD 11K DISCHARGE WATER TEMP 119.4 n 15&lS;14 NORM A54 CRL 13N D1SCHARGE WATER TEMP 116 0 E 15:1S:14 NORM X255 CRD 2-L DISCHARGE WATER TEMP 119.0 ) E 15:19:14 NORM X257 CRD 6-L' DISCHARGE WATEt TEMP 114.0 su 15:18:14 NORM X258 CRD 8-L DISCHARGE WATER TEMP 115.1 ) I3 15:18:14 NORM X259 CRD 10L DISCHARGE WATER TEMP 117.8 e E 15:47:05 VATR RO:n RC PUMPS A SUCTION TEMP (UTDE) 439.4 15&id:14 NORM A 61 CRD 14L DISCHARGE WATER TEMP 117.4 15:18:15 NORM X26 CRD 3-M DISCHARGE WATER TEMP 100 8 / 15:18:15 NORM, X263,,CRD,5-M DISCHARGE WATER TEMP _,122 2 ( 1-4 b:! ii e44

g. i F. e .*i.' I.g i 6 = t> ((. t ( ~

• ~ ~

f'*" 15:18:15 'NCRM X265 CRD 9-M DISCHARGE WATER TEND ' tiI.3'~~ assioil; NGAM A;6e CRL lin LI5CnAAGE WATER TEMr 115 8 ') r I 15:18:15 NORM X267 CRD 13M DISCHARGE WATER TEMP 113.8 15:18:15 NORM X268 CRD 4-N'DISCHARCE WATER TEMP 122.0 l [] 15:18:15 NORM X270 CRD 8-N DISCHARGE WATER TEMP 114 2 t 15:t8:15 N0mm X272 CRn tr4 91SCNaRcE WATER -E tre.t Q; 15:46:02 VATR R220 RC PUMPS A SUCTION TEMP (WIDE) 438.7 lj 15:18:15 60RM X273 CRD 5-0 DISCHARCE UATER TEMP 126 3 v 15:11:15 NCRM v274 cRD 7-0 DISC 9ARGE WATEo TE=* ?i7.a 2,' 15:18:15 NORM X276 CRD 110 DISCHARCE WATER TEMP 121.1 2, 15:19:15 NORM X277 CRD 4-P DISCHARGE WATER TEMP 138.2 l ) o' 15:19:15 NORM X278 CRD 8-* DISCHARGE WATEe TEM * !?4.5 9. Ug 15:18:31 NORM N233 FLUX 9-E LEVEL 7 (NANCAMPS) gy 15:18:32 BAD N246 FLUX 7-F LEVEL 7 (NANCAMPS) -????. 3 n 15:18:32 NORM N254 FLUX 7-E LEVEL 7 (NANCAMPS) 7. as &5:18:30 BAD N235 FLUX 5-N LEVEL 6 (NANCAMPS) -????. II 15:49:01 VATR R220 RC PUMPS A SUCTION TEMP (UIOE) 437.5 If 15: 18:37 NCRM N302 FLUX 7-M LEVEL 7 (NANCAMPS) 9 in 15:18:38 BAD N310 FLUX 8-N LEVEL 7 (NANDAMPS) -????. II 15:18:43 CONT XQ36 RC MOTOR 31 HP OIL PP DISCH PRES HICH Ti 15!!8:43 NCRM N357 FLUT iS-K LEVEL a (NANDAMDT) 20. 21 15:18:44 CONT XO36 RC MOTOR B1 HP OIL PP DISCH Pr.ES OK 7. ' ;; 15:18:44 NORM N306 FLUX 13-H LEVEL 7 (NANOAMPS) g ) < s-15:1S!44 NORM N373 FLUT 13-0 LEVEL 4 (WANOAMPS) 9. 3 15:13:4e BAD N389 FLUX 12-F LEVEL 6 (NANDAMPS) -????. q 15:10:47 NORM N396 FLUX 11-0 LEVEL 5 (NANCAMPS) 10. ) in 15:49:59 UATR R220 RC PUMPS A SUCTION TEMP (WIDE) 436.1 n 15:18:47 BAD N397 FLUX 11-0 LEVEL 6 (NANCAMPS) -??. Ii 15:18:48 NORM N414 FLUX 10-D LEVEL 7 (NAN 0 AMPS) 10. E :5:19:54 BAD N4?O FLUX 4-E LEVEL 7 (NANCAMPS) I

s.

15:18:55 6AD N478 FLUX 3-F LEVEL 7 (NANCAMPS) -????. I j[ 15:18:57 NORM N502 FLUX 2-L LEVEL 7 (NANCAMPS) 10. ) ( 31 15:18!59 NCR,4 N518 FLUX 3-M LEVEL 7 (NANDAMPS) 9. 3 15:19:00 BAD N533 FLUX 5-0 LEVEL 6 (NANCAMPS) '?'?. j j' 15:19:01 NORM N541 FLUX 6-0 LEVEL 6 (NANOAMPS) 10. ) x 15:10:o4 NcRM N5?4 ELOY 16-0 LEVEL 7 (NANDAMDE) ????. O. EU 15:19:05 BAD N580 FLUX 12-0 LEVEL 5 (NANCAMPS) g/ 15:51:03 VATR R220 RC PUMPS A SUCTION TEMP (WICE) 434.9 g gg ) w tritoto? ESNT re3A Re Metne 21 NP n't no n?cru PRec N?nu I & 15:19:08 CONT XO36 RC MOTOR B1 HP OIL PP DISCH PRES CK 8 3 15:19:28 NORM N206 FLUX 8-H LEVEL 7 (NAN 0 AMPS) 10. g > 15:19*29 9AD N214 FLUX O-H LEVEL 7 (NANCAMPS$ 3 15:19:32 BAD N254 FLUX 7-E LEVEL 7 (NANDAMPS) -*??'. g 15:19:33 NORM N261 FLUX 6-G LEVEL 6 (NANCAMPS) 10. -) w 15:19:36 NCAM N2S5 FLUX 5-K LEVE1. 4 (NAN 0 AMPS) 10. 3 15:19:40 BAD N334 FLUX 10-M LEVEL 7 (NANCAMPS) -?'?'. y, 15:19:41 SAD N342 FLUX 11-L LEVEL 7 (NANCAMPS) -????. e 15:52!01 UATR R220 RC PU"P9 A SUCT!SN TEMS cu??rs 417.9 it 15:19:42 NORM N350 FLUX 11-K LEVEL 7 (NANDAMPS) 9. 3: 15:19:43 BAD N357 FLUX 12-K LEVEL 6 (NANOAMPS) -????. j d 15!19!44 PAD N344 Ft 11Y 13-N L EUrt 7 fNANnAMPM) 2 15:19:45 NORr: N380 FLUX 13-F LEVEL.5 (NANDAMPS) 9. g 15:19:45 NORM N381 FLUX 13-F LEVEL 6 (NANCAMPS) 9. ) s as 15!19f4a NORM N2R9 Ft IfY 19-F f Furl A (NANNAMoC) 9. !! 15:19:47 NORM N377 FLUX 11-0 LEVEL 4 (NANCAMPS) 9. gm 15:19:54 BAD N469 FLUX A-E LEVEL 6 (NANCAMPS) -????. j v' 15!19:55 NCRM M479 FLOY 3-F L EVEL 7 (NANOAMPS) 10. 12 15:52:59 VATR R220 RC PUMPS A SUCTION TEMP (WIDE) 433.0 !! 15:20:00 SAD N532 FLUX F-0 LEVEL 5 (NANCAMPS) -?'??. y

• 15:20 00 NOR" N!33 FLUV 5-0 LEVEL 6 (NANOAmos) 9.

lJ p 15:20:01 BAD N541 FLUX 6-0 LEVEL 6 (NAN 0 AMPS) -????. I~ 15:20:02 NORM N549 TLUX 6-P LEVEL 6 (NANCAMPS) 9. E 15!20:04 3AD N574 FLUX 10-0 LEVEL 7 (NANDANPs) I 8. 15:20:05 NORM N580 FLUX 12-0 LEVEL 5 (NANCAMPS) 15:20:06 BAD R226 RC QUTLET A TEMP (NARROU) -???.? 15:20:06 BAD R227 RC QUTLET A TEMP (NARROU) _ -???.? a. ? 1 -8 .h 4,. e e -mm

1 h. f,L ,*4 q i-r V n-l ( I 35!00:18 LOW.. X333 NUCLEAR..-.SVC CLN3 WTR TNK (VL(FT) 7.79 133;G324 NOAn A7Co 5TEAN GEN A AC FEMP DIFF -354 0 15:54:04 VATR R20 RC PUMPS A SUCTION TEMP (WIDE) 432 2 15:20:24 CONT X036 RC MOTCR 81 HP OIL PP DISCH PRES HICH 15:20:25 CONT X036 RC MOTCR 81 HP OIL PP DISCH PRES CK l 15:20:27 CONT X036 RC MOTOR 91 HP OIL PP D!SCH FRES HIGH h 15:203:8 CONT K036 RC MOTCk 81 MP OIL PP DISCH PRES ON 1C 15:20:29 BAD N206 FLUX S-H LEVEL 7 (NANDAMPS) -????. ) 31 15:20:09 NORM N214 FLUX 9-H LEVEL 7 (NANCAMPS) 9. en '5&;0;;a 60NT AQ34 AC NOTCR B1 MP OIL PP DISCH FRES HION IU 15:20:29 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES ON ) 00 15:20:31 BAD N238 FLUX 9-E LEVEL 7 (NANCAMPS) jy 15:55804 UATR R2:0 RC PUMPS A SUCTICN TEMP (WIDE) 431 0 is 15:20:32 NCRM N 54 FLUX 7-E LEVEL 7 (NANCAMPS) 8. ) N 15:20:33 9AD N261 FL UX 6-0 LEVEL 6 (NANOAmes) "* 15:00:37 BAD N30; FLUX 7-M LEVEL 7 (NANOANPS) -?"'. 7; 15:00:41 NORM N34: FLUX 11-L LEVEL 7 (NANCAMPS) 9. ) 75 15:20:42 PAD N350 FLUX 11-K LEVEL 7 (NAN 0 AMPS) in 1580Ct#3 NCRM N357 FLUX 12-N LEVEL 6 (NAN 0 AMPS) 10. Tl 15:20:44 NORM N366 FLUX 13-H LEVEL 7 (NANCAMPS) 9. } 75 15:20:45 SAD N380 FLUX 13-F LEVEL 5 (NANCAMDS) 96 1542045 BAD N3a1 FLUX 13-F LEVEL 6 (NANOAnFS) -?'?'. TF 15:56:00 VATR R220 RC PUMPS A SUCTICN TEMP (UIDE) 409.7 I IE 15:00:48 5AD N414 FLUX 10-D LEVEL 7 (NANCAMPS)

ia As&a9&;G SAL N430 FLUX 9-G LivEL 7 (NANDAMP5)

-????. l r is 15:20 :: NORM N454 FLUX 6-C LEVEL 7 (NAN 0 AMPS) 9. I EU 15 20:54 NCRM N469 FLUX 4-E LEVEL 6 (NAN 0 AMPS) 9. s 15420:55 SAD N47S FLUX 3-F LEVEL 7 (NANOAnFS) -??". ,' is 15:00:53 BAD N510 FLUX 3-L LEVEL 7 (NANDAMPS) -*?". II 15:01:00 NCRM N530 FLUX 5-0 LEVEL 5 (NANCA*PS) 8. I a 15:21:05 6AD N5a1 FLUX 12-0 LEVES 6 (NANOAMPS) -????. I' EU 15:01:19 CCNT X036 RC MOTOR B1 HP CIL PP DISCH PRES HIGH E 15:57:01 VATR R220 RC PUMPS A SUCTICN TEMP (UIDE) 409.2 -) I = 1:a;1;;w Gabi Auso AC NOTUA b1 nF 016 eF DinGM EnEn CN A, lf }" 15:01:06 BAD R21: RC CUTLET A TEMP (NARROU) -???.' 15:21::S CONT X036 RC MOTCR B1 F? DIL PP DISCH PRES HIGH I I asisa;;a NGAM N;0o ewex e-n LL7E6 7 (N ANG AnF 5) 10. l piis 15:21:09 CONT XO36 RC MOTOR B1 HP OIL PP DISCH PRES CK I j 59 15:57:31 ATRA R207 PRESS RELIEF VALU RCV-8 CUT TEMP ATR 02 200.00/ 100.00 3. .s..;;a.

• As N_44 ewwX 7-r LEvEu s tNANcanes)

-r r r?. a is 15:01:32 BAD N245 FLUX 7-F LEVEL 6 (NANDANPS) -????. 3D 15:21:30 BAD N:54 FLUX 7-E LEVEL 7 (NANCAMPS) -??. sn asi iiae NUAn N46a rLux 6-0 wEVEL 4 (NANGAn?S) 10. "; 15:58:00 VATR R:20 RC PUMPS A SUCTION TEMP (WIDE) 429 3 in 15.21:36 NORM R712 RC CUTLET TEMP (NARRCU) .0 6s 15:01:31 NCRM N302 FLUX 7-M LEVEL 7 tNANDAnPSs 10. 73 15:21:38 NORM N310 FLUX 8-N LEVEL 7 (NANCAMPS) 10. 73 15:01:43 BAD N357 FLUX *12-N LEVEL 6 (NANOAMFS) In 15:21:4e BAD N369 FLUX 12-F LEVEL 6 (NANCAnPS)

• ????.

( II 15:01:50 NORM N4:0 FLUX 9-C LEVEL 7 (NAN 0 AMPS) 9. = E 15:21:54 BAD N469 FLUX 4-E LEVEL 4 (NANCAMPS) t. sm 15:5634o DATA R207 PRESS AELIEF VALV RCV-8 CUT TEMP 241.5 ( {j 15:21:54 NORM N470 FLUX 4-E LEVEL 7 (NANDAMPS) 9. =m 15:21:56 PORM N486 FLUX 2-0 LEVEL 7 dNAN0 AMPS) 9. 13&LFAG2 VATR R220 RC PUMPS A SUCTION TfnP (WIDE) 429 1 15:21:57 CONT X036 RC MOTOR 81 HP OIL PP DISCH PRES HICH .' IU 15:01:57 CONT X036 RC NOTOR B1 HP OIL PP DISCH PRES OK ) sa 15&21:56 NURN N51J FLUX 3-6 LEVEL 7 (NANDAnFS) 9. IE 15::::10 CCNT X034 RC MOTOR 91 HP OIL PP DISCH PRES HIGH I 15:00:11 CONT X036 RC *C?OR 91 WP OIL P* DISCW 8RES Ch / sm 15:20:23 CCNT X034 RC MOTCR 81 HP OIL FP DISCH PRES HICH 12 15::::24 CONT XO36 RC MOTCR B1 HP OIL PP DISCH PRES CR P 15:22:08 BAD N206 FLUX 0-4 LEVEL 7 (NANCAMPS) 15:22:J1 NORM N238 FLUX 9-E LEVEL 7 (NANDAMPS) 8. 15::: 31 NORM N244 FLUX 7-F LEVEL 5 (NAN 0 AMPS) 9. 16:00:03 VATR R220 RC PUNPS A SUCTICN TEMP (UIDE) 48.4 J 4,. e = 1

) p. e

• k*
• g.)

i..

l. l ( ' " ' 10. ) .4. 15::::3: NCsa N:45 rCux '7-r LEVEL 6"(NANcAmesf

• • ~

~~ f aLia;;;; bas N;La Fwax 7-E wivs. 5 (NAmuAerbs -????. l 15:22:30 NORM N054 FLUX 7-E LEVEL 7 (NANCAMPS) 7. 15::::37 BAD N30 FLUX 7-M LEVEL 7 (NAN 0 AMPS) -??. I [] 15:22:38 BAD N310 FLUX 8-N LEVEL 7 (NAN 0 AMPS) -M'? j 15::::40 NORM N334 rLUX 10-M LEVEL 7 (NAN 0AMES) 9 i 2U" 15:22:43 NCRM N358 FLUX 12-N LEVEL 7 (NANCAMPS) 9. ! 3 l' 15:22:44 BAD N366 FLUX 13-H LEVEL 7 (NANDAMPS) -????. ll 1* 02:44 BAD N373 FLUY 13-G LEVEL 6 (NANCAMP9) j; 16:01:04 VATR R2 0 RC PUMPS A SUCTION TEMP (WIDE) 48.3 ) 2; 15:22:44 CCNT X03o RC MOTCR 31 HP OIL FP DISCH PRES HICH

si 15 :::45 CONT x036 RC MOTOR 91 wp OfL PP DISCH **EE CK 9.

~) i 15:22:46 NORM N389 FLUX 12-F LEVEL 6 (NAN 0 AMPS) d ' dj 15:22:48 CONT X036 RC MOTCR 81 HP OIL PP DISCH PRES HIGH 'n 15:22:49 CCNT r036 RC MOTCR B1 HP OIL P8 DISCH PRES CK = 15::: 50 SAD N454 FLUX 6-C LEVEL 7 (NANGAMPS) -????. ) II: 15:22:54 NCRM N469 FLUX 4-E LEVEL 6 (NANDAMPS) 8. I~ 15::::54 PAD N470 FLUX 4-E LEVEL 7 (NANDAMP5) is lo:01:55 DATA A 05 PRESS RELIEF VLV RCV-10 CUT TEMP 200.0 l } T~ 16:00:00 VATR R:20 RC, PUMPS A SUCTICN TEMP (WIDE) 428.7 ~~ 16:02:05 DATA R 06 PRTSS RELIEF VALV RCV-9 CUT TEMP 150.2

• ~~ 16:02:10 DATA R207 PRISS RELIEF VALV RCV-8 CUT TEMP 239.8

'+ 15:22:55 NORM N478 FL'JX 3-7 LEVEL 7 (NANCAMPS) 10. I 15!:::56 PAD N49e FUJX O-G LEVEL 7 fNANCA**?) ig 15:03:04 NORM N574 FLJX 10-0 LEVEL 7 (NAN 0 AMPS) 9. ) g 15:23:05 NCRM N581 FLUX 12-0 LEVEL 6 (NANCAMPS) 8. 2" 15:03!06 CONT X036 RC MOTOR P1 NP OIL ** DISCH *Res HIGw EE 15:03:00 BAD N590 FLUX 14-M LEVEL 7 (NAN 0 AMPS) -?'?'. ) 2r 15:23:07 CCNT XO36 RC MOTCR B1 HP OIL FP DISCH PRES CN 52 15:03:09 CONT 4036 RC *CTOR 91 WP OTL ** DTSCW PRE 9 WTGw 3 16:03:02 VATR R 20 RC PUNPS A SUCTION TEMP (WIOE) 49.5 7 3D 15:23:08 CCNT X036 RC MOTOR B1 HP OIL PP DISCH PRES CK 2E 15:03:10 CONT X036 KC MCTOR P1 WP OfL ** DISCH PRES WIGH a 15: 3:13 CONT XO3e RC MOTOR B1 HP OIL PP DISCH PRES CN ( ~{ 15:23:18 CCNT %C36 RC MOTCR B1 HP OIL FP DISCH FRES HIGH w :*:23t!* CONT Y036 CC NOTSR Pt we OIL em DT?ru PR 9 c= g 13 15:03:28 BAD N:14 F LV;; 9-H LEVEL 7 (NANCAMPS) ????. } ni 1*:23:31 BAD NO38 FLUX 9-E LEVEL 7 (NAN 0 AMPS) -????. p irres!s' unaw N'** n uv 7-r t eur? - enaNcAwoci .n. I 2 15:03:38 NORM N310 FLUX S-N LEVEL 7 (NANCAMPS) 8. ) is 16:04:01 VATR R20 RC PUMPS A SUCTION TEMP (WIDE) 430.1 av !!!??!ao enn N222 etur to a t rurt 4 (NANOA=ost 25 15:23:43 NCRM N357 FL'JX 12-K LEVEL 6 (NANDAMPS) 9. 3 3 15:23:43 BAD N358 FLUX 12-K LEVEL 7 (NANDAMPS) -????. P !?!S3!44 DAD N309 Fluy iS-r t rvrt 4 (NAySAmoq) 2 15:23:49 CCNT XO36 RC MOTOR 91 HP OIL PP DISCH FRES MIGH ) gj 15:03:50 CONT X036 RC MOTCR 81 HP OIL PP DISCH PRES OK u 15:03153 0997 x036 cc *CTOR 91 WD OTL Po S!?cu ptT9 WISw it 15:03:53 NORM N46: FLUX 5-D LEVEL 7 (NAN 0 AMPS) 9. 33 15:23:54 CCNT X036 RC MOTCR B1 HP.0IL PP DISCH PRES OK i

== 16!05:00 VATR R200 RC pumps A SUCTION TEMo tuttr) 471.? t 15:23:55 BAD N479 FLUX 3-F LIVEL 7 (NANCAMPS) -????. fl) gg 15:23:57 CCNT XO36 RC MOTOR B1 HP OIL PP DISCH PRES HIGH s as 1*;S?!*7 DAB N?o? rL ifY ?-t t rue! 7 (NANNA= pet g5 15:2~:58 CONT XO36 RC MOTOR B1 HP OIL PP DISCH PRES OK

)

28 15:2400 NORM N526 FLUX 4-N LEVEL 7 (NANDANPS) 8. W 1*!?4:00 CCNT YO3a RC MDTQR 91 No STL Pe D?sCM PReM HTDM 15 15:24:01 BAD N540 FLUX 6-0 LEVEL 5 (NANCAMPS) -??'?. / 38 15:24:01 CCNT XO3e RC MOTCR B1 HP OIL PP DISCH PRES CK h 15!!4:01 NCem N!at FLOV 6-0 LEVEL 6 (NANSAmo@5 10. $a 16:06:00 VATR R:20 RC PUMPS A SUCTION TEMP (WIOE) 430 6 I~ 15:24:03 CONT X036 RC MOTCR 81 HP OIL PP DISCH PRES HIGH j M 15:04:04 CONT XO36 RC MOTCR 91 HP OTL P* SISCN PRES ON 15:24:04 NCRM P 53 RC PUMP B BLEEDOFF FLGW (GPM) 1.003 15*24:04 BAD N574 FLUX 10-0 LEVEL 7 (NANCAMPS) -????. 15:24:06 CONT,,XO36 RC M,0 TOR.B1 hP OIL PP DISCH FRES, HIGH d .? l M 1 3 J, tc

c i g. o;.. i l'l T I / J' ( - _. ~ ' ". ~ ~ ~ ' " ' ~ ~ ' ^ ' ~ " 15:24:06 NORM' N590 ~FL'UX 14-M ' LEVEL 7~ (N'ANOA'ME )' ~~~' - S ? is. 4;v, v.N. A..o nL nw.wn ei ne uL er ai6sn esE5 ch 15:24:14 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES HIGH 15:24:14 CONT x03o RC MOTOR B1 HP OIL PP DISCH PRES DA 1 16:06:59 VATR R::0 RC PuMF3 A SUCTION TEMP (WIDE) 433.1 l 15:24:25 CONT 2036 RC MOTOR B1 HP O!L PP DISCH SRE3 HIGW 6 15:04:26 CONT x03e RC MOTCR B1 nP OIL PP DISCM PRES DA l' 15:24:28 NORM N214 FLUX 9-H LEVEL 7 (NAN 0 AMPS) 9. l' 15:24:31 BAD N244 FLUX 7-F LEVEL 5 (NANCAMPS) -??. ,o 15;;4432 CGNT A03o RC MOTOR 61 NF CIL FP DISCM FRE5 HIGH l' 15:24:30 NORM N40 FLUX 7-F LEVEL 7 (NANCAMPS) 9. 10 15:24:32 BAD N054 FLUX 7-E LEVEL 7 (NANCAMPS) -?. u 13&;4333 CONT XO36 RC MOTCR b1 MP OIL PP DISCH PRES OK a 15:14:37 NORM N302 FLUX 7-M LEVEL 7 (NAN 0 AMPS) 8. '.e 15:24:38 CCAT X036 RC MOTOR B1 HP CIL PP DISCH PRES WION w lo;0a&O3 VAIR h;20 AC PunFS A SUCTICN TEMP (WILE) 432.3 7; 15:24:38 CONT E036 RC MOTOR 81 HP OIL PP DISCH PRES OK II 15:04:39 NCRM N317 FLUX 9-N LEVEL 6 (NAN 0AMos) 10. in 15124340 NORM N333 FLUX 10-M LEVEL 4 (NANOAMFS) 10. I; 15:24:40 SAD N334 FLUX 10-M LEVEL 7 (NAN 0 AMPS) -????. ) TU 15

• 4:43 3AD N357 FLUX 12-k LEVEL 6 (NANCAMPS)

-?*9?. 4 15:04:44 NonM N373 FLJA 13-G LEVEL 6 tNANGAMFS) e. IE 15:24:45 NORM N380 FLUX 13-F LEVEL 5 (NAN 0 AMPS) 9. Is 15:04:46 NCRM N399 FLUX 12-F LEVEL 6 (NANDAMPS) 9.

i. 1;;;4:47 BAD N39o Flux 11-0 LEVEL 5 LNANOAnFS)

-????. 53 14:09*00 VATR R:20 RC PUNPS A SUCTION TEMP (WIDE) 431.0 ') EU 15:04:48 NORM N414 FLUX 10-D LEVEL 7 (NANDAMPS) 10. e is;. ;si ..N. A.ao he nu.wn al nF GiL rF LihGn rhE5 niQn ]; 15:24:52 CCNT XC36 RC MOTOR B1 HP OIL PP DISCH PRES ON i: 15:24:52 LAD N446 FLUX 7-B LEVEL 7 (NANDAMPS) -????. si i;;.4;LJ bau N4o; rLwA L-D wEvEu 7 LNANGAnPS) -????. E 15:24:54 BAD N469 FLUX 4-E LEVEL 6 (NANCAMPS) -?'??. ) 3 3R 15:24:57 NORM H502 FLUX 2-L LEVEL 7 (NANDAMFS) 9. 3 z. Aa;.;;49 eAb NL;a. lea 4 i. LEws. / LNANLAnr5) -??'?. gj 15:25:00 BAD N533 FLUX 5-0 LEVEL 4 (NAN 0 AMPS) '*??. ( 16:10:01 VATR R20 RC PUMPS A SUCTION TEMP (WICE) 429.8 y si. iL;;;;al NymM NL40 FLs4 o-Q LEVEL L (NANGANFS) f. "E 15:25:01 BAD N541 FLUX 4-0 LEVEL 6 (NANCAMPS) -????. ) IF 15:05:03 NORM N553 FLUX 7-R LEVEL 7 (NANCAMPS) 9. w 1;;;L;11 GUNT Auss AC n0TGA B1 MP O!L rF DI5CH PAE5 nIan }" 15:25*11 CONT XO36 RC MOTCR B1 HP OIL PP DISCH PRES CK 3" 13:25:12 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES HIGH 2n es..e.aa ..N4 Awao nL nu.wn ma ne ses er aidcn Fhca wh 1; 15:25:27 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES HIGH i; 15::::24. CNT XC36 RC MOTOR B1 HP OIL PP DISCH PRES OK e aosiiacy VAFA h;20 AG F unF 5 A 5LCTICN TinF (.ILEJ 429.4 Z 15:25 8 CCNT T010 ROTOR ABOVE ZERO SPEED NO lI 15:05:29 CONT 70 4 TURNING GEAR MOTOR ON a 15:25:29 CCNT TO:5 TURNING GEAR ENGAGED YE5 I' 15::::32 CCNT 7010 ROTOR ABOVE ZERO SPEED YES 1 l3 15:05:33 CONT 70 5 TURNING GEAR ENGA0ED NO m 15:25:33 NCRM N062 FLUX 6-G LEVEL 7 (NANDAMFS3 9 37 15:25:33 CONT 7025 TURNING GEAR ENGAGCD YES s 15:25:34 CONT X036 RC MOTOR B1 HP OIL PP DISCH PRES HIGH wm 15:25:34 CONT X036 RC MOTOR 61 HP OIL PP DISCH PRES CA 13 16:11:59 VATR ROOO RG PUMPS A SUCTION TEMP (WIDE) 429.4 ) Il 15:25:37 BAD N302 FLUX 7-M LEVEL 7 (NANCAMPS) "?'. ni iL;;L;Ja SAL N310 FLUA d-N LEVEL 7 ( N Ate 0 AMF S ) -????. IE 15:25:40 LAD N333 FLUX 10-M LEVEL 6 (NAN 0 AMPS) -????. ) U 15::::40 NORM N350 FLUX 11-N LEVEL 7 (NANCAMPS) p 15:25443 NCRM N357 FLUX 12-K LEVEL 4 (NANCAMPS) 10. 9 .) Is 15::: 44 NORM N366 FLUX 13-H LEVEL 7 (NAN 0 AMPS) F 15:05:45 BAD N330 FLUY 13-F LEVEL 5 (NAN 0 AMPS) 15325147 CONT XO36 RC n0 TOR D1 MP OIL PP DISCH PRES HICH 15:25:47 NOPM N396 FLUX 11-0 LEVEL 5 (NAN 0 AMPS) 8. 16:12:58 VATR R 20 RC PUMPS A SUCTION TEMP (WIDE) 429.7 ( .a J .s na

e = ). d' .4 n.j - ep l. pi ~~~ 15:25:48 PAD N414 FLUX 10'~D LEVEL 7 (NANOAa*SE E'445~~~~"" ~~ 15:25:49 CONT AG36 RC MOTOR b1 MP QIL PP DISCd FRES Oh 15:23::: CONT X036 RC MOTOR 81 HP OIL PP DISCH PRES HICH 15 :::$2 NORM N446 FLUX 7-B LEVEL 7 (NANCAMPS) 7. []l 15:25:53 CONT XQ36 RC MOTOR 31 HP OIL PP DISCH PRES SK 14:13:30 DATA R20 PAESS RELIEF VLV RCV-10 OUT TEMP 216.3 T: 16:13:3o LATA R206 PRESS RELIEF VALV RCV-9 OUT TEMP 1"6 0 I 15:25:54 NORM N449 FLUX 4-E LEVEL 4 (NAN 0 AMPS) 9. i ll 14:13:47 DATA R207 PRESS RELIEF VALV RCV-8 CUT TEMP 231.0 l 3 1 15:05 :: NCRd N478 FLUX 3-F LEVEL 7 (NANCAMPS) 9. .n 16:13:58 VATR R2:0 RC PUMPS A SUCTION TEMP (WIDE) 430.0 00 15:25:54 CCNT XC36 RC MOTOR 91 WP OfL DP Sf5CH PRET WIGN ) 'M 15 :: 57 CCNT XO36 RC MOTCR 81 HP OIL PP DISCH PRES CK Foi 15:25:57 BAD N 02 FLUX 2-L LEVEL 7 (NANCAMPS) -????. II 1 !!6:01 NCRM N542 FLUX 6-0 LEVEL 7 (NANCAMPS) 10, ) It 15:Co 00 SAD N549 FLUX 6-7 LEVEL 6 (NANCAMPS) -?'??. ig 15:06:03 BAD N58 FLUX 7-R LEVEL 7 (NANCAMPS) -????. ) 4 15:26:04 NORM N574 FLUX 10-0 LEVEL 7 (NAN 0 AMPS) i 13 15:06:10 CCNT XO36 RC MOTOR 81 HP OIL PP DISCH PRES HIGH

• • 15:26:11 CCNT X036 RC MOTCR 31 HP OIL PP DISCH PRES OK IE 15!26:19 CCNT YO36 RC MOTOR B1 WP OIL ** DISCH PRES WIGH 3

J o. lo:15 G3 VATR R 00 RC PUMPS A SUCTION TEMP (WIDE) 430.9 ' IE 15:26:20 CONT' X036 RC MOTCR B1 HP OIL PP DISCH PRES ON IE 15:06:22 CONT X036 RC MOTOR Pt WP OIL ** DISCH PRE 9 HIGW 13 15:26:03 CONT X036 RC MOTCR B1 HP OIL PP DISCH PRES CK a 15:26:27 CONT X036 RC MOTOR 81 HP OIL PP DISCH PRES HICH IU 15:06:~9 CCNT XO36 RC MOTCR 91 wp OIL DD 3?E04 DREE SK ) 3E 13:0e:28 SAD N214 FLUX 9-M LEVEL 7 (NANOAMPS) -???*. 35 15:26:09 NORM N2:2 FLUX 9-0 LEVEL 7 (WAN0 AMPS) 9. 2* 15 :t:31 CONT YO36 cc *0TCR 91 wp 0!L pe S!!CW reE9 w! w I f [g 13:26:31 BAD N36 FLUX 9-E LEVEL (NANCAMPS) -????. 39 16:16:02 VATR R:20 RC PUMPS A SUCTION TEMP (WI E) 430.2 ( 8' 15:26:31 NCRM N239 FLUX 9-E LEVEL 7 (NANCAMPS) 10. ?; 15:06:31 NORM N 44 FLUX 7-F LEVEL (NANCAMPS) 9. g: 15:06:31 CONT XQ3e RC NOTCR B1 HP OIL PP DISCH PRES OK w 15:26:32 NCRM N254 FLUX 7-E LEVEL 7 (NaNCA=es) q. gg 15:26:33 BAD N 6: FLUX 6-0 LEVEL 7 (NANCAMPS) -????. j m

• 126:40 NCRM N333 FLUX 10-M LEVEL 4 (NANCAMPS) 10.

EE 15:26:42 9AD N350 FLOY it-K LEVEL 7 (NANCAM*9) \\ ) 2t 15:26:44 BAD N366 FLUX 13-H LEVEL 7 (NANCAMPS) -????. { gg 15:26:47 BAD N396 FLUX 11-0 LEVEL (NANCAMPS) -????. l 3 16:!7:01 UATR R220 RC eUMPs A MUETTEN Tr=P fu? Set 477.7 ? Z" 15:26:50 CCNT XO36 RC MOTOR B1 HP OIL PP DISCH PRES HICH st 15:26:50 CONT X036 RC MOTCR B1 HP OIL PP DISCH PRES CK w i!!?a!?? NcR= N4E4 eLUX A-E LEUF!. 7 fNANDAM89) 9 d! 15:26:53 CONT XO36 RC MOTOR B1 HP OIL PP DISCH PRES HIGH g 15:26:54 CONT X036 RC MOTOR B1 HP CIL PP DISCH PRES OK

• a 15:26:54 NcRM N470 rLUX 4 r Levei 7 (NaNEA=ces o.

2 15:26:55 CCNT X036 RC MOTOR B1 HE LIL PP DISCH PRES HIGH 15 :e::: BAD N478 FLUX 3-F LEVEL 7 (NANDAMPS) -????. += s 15:26:55 0CNT Yo36 RC MOTCR B1 NP OIL Pp DISCH prEE CK J gg 16:17:59 VATR R20 RC PUMPS A SL'CTION TEMP (WIDE) 435.1 6 gg 15:26:57 NORM N 02 FLUX 2-L LEVEL 7 (NANCAMPS) 9. as 15:27:00 NCRM N533 FLUX 5-0 LEVEL a (NANOAMPM) 9. ) 15:27:01 CONT XO36 RC MOTOR B1 HP OIL PP DISCH PRES HICH , 23 15:27 01 BAD N 42 FLUX 6-0 LEVEL 7 (NANDAMPS) -????. SI 15:27:02 CCNT X036 RC MOTER 91 He oft ** STEEW FREM Ok 28 15:27:02 NORM N49 FLUX 6-P LEVEL 4 (NANDAMPS) 10. !! 1 327:03 NORM N:58 FLUX 7-R LEVEL 7 (NANCAMPS) 9. M !!!?7:04 C2NT YO3A ec *070e 91 Ho S ?! pp D?eEM Pees w'Sw 28 15:27:05 CCNT XO36 RC MOTCR 81 HP 0IL PP DISCH PRES CK w 15:27:06 CONT X036 RC MOTOR 31 HP OIL PP DISCH PRES HIGH E 16:19:03 UATR R220 RC cumpg A gue?;eg ygwo gyrpr3 433,g J 15:07:06 BAD N590 FLUX 14-M LEVEL 7 (NANCAMPS) -?'?*. 15:27:07 CONT Xo36 RC MOTOR 31 HP OIL PP DISCH PRES OK 15:27 07 NORM N98 FLUX 13-L LEVEL 7 (NANCAMPS) 9. 1 \\

• f u

q 9 e ---n ,e

j-

s....

ll e d.; e. i i f' L l! l { (' ' ~ ~ ~ ~ ~~~~ 15:27:12 CONT."X034 RC' MOTOR '91 HP OIL'PP DISCH PRES ~ ~~ HIGH aaa.<+aa .wn. Avae M6 nw in sa nr wAL Pr wamLa PAE3 GA 'l 15:27:22 CONT X034 RC MOTOR 31 HP OIL PP DISCH PRES HIGH 1 15:27:23 CONT X034 RC MOTOR 31 HP OIL PP DISCH PRES OK 15:27:29 NORM N 14' FLUX 9-H LEVEL 7 (NAMOAMPS) 10. 1 :27:29 CONT x034 RC MOTOR 31 HP O!L P* DISCH PRES HIGH oi

20:00 VATR R220 RC PUMPS A SUCTION TEMP (WIDE) 435 1 III 15:27:29 BAD N222 FLUX 9-0 LEVEL 7 (NAN 0 AMPS)

-????. 10 15:27:30 CONT X034 RC MOTOR 31 HP OIL PP DISCM PRES OK l 7. c 15:27:31 NORM m23. FLUX 9-E LEVEL 5 (MANDAMPS) [U 15:27:31 340 N38 FLUX 9-E LEVEL 7 (HANDAMPS) -T7??. 5:27:30 SAD N254 FLUX 7-E LEVEL 7 (NANCAMPS) 16:27:30 NORM N310 FLUX S-M LEVEL 7 (NAMOAMPS) 10. 15:27:39 CONT X034 RC MOTOR 31 HP OIL PP DISCH PRES HIGH ' 'se 15:27:40 CONT N034 RC MOTOR St HP OIL P* DISCH PRES CK 4 153;7340 6AL N333 FLUX 10-M LEVEL e (NANCAMPS) -??'?. "; 14:20:59 VATR R2:0 RC PUMPS A SUCTION TEMP (WIDE) 434.0 G 15:27:40 NORM N334 FLUX 10-M LEVEL 7 (NANCAMPS) S. tg 153;7341 BAD M341 FLUX 11-L LEVEL 4 (MANCAMPS) -????. in 15:07:45 NORM N300 FLUX 13-F LEVEL 5 (NAN 0 AMPS) 10. -j 7. I II 15:27:47 NORM N396 FLUX 11-0 LEVEL 5 (NANCAMPS) w 158 7351 CONT A03e RC MOTOR 31 MP OIL PP DISCM PRES HION "E 15:07:50 CONT X034 RC MOTOR 31 HP OIL PP DISCH PRES CK II 15:27:52 340 N454 FLUX 4-C LEVEL 7 (NANCAMPS) In 154;7334 BAL N470 FLUX 4-E LEVEL 7 (NANCAMFS) -????. f Ei'15:27:57 CONT X034 RC MOTOR 31 HP OIL PP DISCH PRES HIGH ]) in 15:27:59 CONT X036 RC MOTOR 91 NP OIL PP DISCH PRES OK am 16 ;;303 VATA A220 AC pumps A SUCTION TEMP (WIDE) 434 1 jj 15:23:00 NORM NS 6 FLUX 4-N LEVEL 7-(NANCAMPS) 10. ) w 15:09:00 CONT X034 RC MOTOR P1 HP OIL PP DISCH PRES HICH f

D 15

29:01 MORM. ML49 Flux e-D LEVE. 5 (NANGAMF 5)

-TTTT. 3, ase.diwa sas N541 FLUX e-O LEVEL & (NAN 0 AMPS) 10. (~$ 3R 15 9:00 CONT X034 RC MOTOR 31 HP OIL PP DISCH PRES OK ( si AL4 43wd eas. NLLS FwuA 7-A bEVE. 7 (NANOAMP5) -????. jj 15:08:04 BAD N574 FLUX 10-0 LEVEL 7 (NANDAMPS) -????. ) y 15:29104 -NORM N590 FLUX 14-M LEVEL 7 (NANCAMPS) S. 453;53G6 GUNT A903 NG P'JMF Al 2ND 5EAL CAVITY PRE 55 GA 3 gij 14:23:0 VATR.2220 RC PUMPS A SUCTION TEMP (WIDE) 434.e () ggzu 15:28:07' CONT K034 RC MOTOR 31 MP OIL PP DISCH PRES HIGH w &53;8307 bAL M5ft FLUX 13-6 LEVEL 7 (NANDAMES) -????. jj 15:29:08 CONT X034 RC MOTOR 31 HP OIL PP DISCH PRES CK ) i a> 15:08:09 CONT 'X034.RC MOTOR 31 MP OIL PP DISCH PRES HICH in L;e.u;Ao wana modo nu nu un al Mr UIL 77 DIscM rnEs ch 33 15:29:17 CONT X03e 'RC MOTOR 31 HP OIL PP DISCH PRES HIGH 3 15 151 S:19 CONT X034 RC MOTOR 31 HP OIL PP DISCH PRES OK ase.o... eeN; 464e As noiwh sa Me g4L F P DIscM F8Es nism

" 15

:S:25 CONT X03e RC MOTOR 31 HP OIL PP DISCH PRES OK 23 14:24:01 VATR R220 RC PUMPS A SUCTION TEMP (UIDE) 434.4 em Asa.usaa Mbkn N24s Flux y-E LEVEL 7 (NANQAMPL) 9.

2" 15:29:32 NORM N54 FLUX 7-E LEVEL 7 (NAN 0 AMPS) S. 3

E 15

25:33 NCRM N262 FLUX 4-0 LEVEL 7 (NAN 0 AMPS) 9.

am 154:S 33 CONT X034 RC MOTOR 31 MP OIL PP DISCM FRES MIGH 3R 15:29:34 CONT X034 RC MOTOR 31 HP OIL PP DISCH PRES OK t CE 15:29:35 BAD N279 FLUX 5-H LEVEL 7 (NAN 0 AMPS) 'e 15:29:37 NORM N302 FLUX 7-M LEVEL 7 (NAN 0 AMPS) 9. w jj 15:28:38 BAD M310 FLUX S-N LEVEL 7 (NANCAMPS) -????. - et 15:28:40 CONT X034 RC MOTOR 31 HP OIL PP DISCH PRES HIGH sa 144;4:59 VAIK R 20 RC PUMP 5 A SUCTION TEMP (WIDE) 4J4.7 si 16:25:03 DATA R205 PRESS RELIEF VLV RCV-10 OUT TEMP 208.1 l . 33 14:05:00 DATA R:04 PRESS RELIEF VALV RCV-9 007 TEMP 153 3 w 14.;3314 DATA A208 RC PRESS (WIDE) (LQQP A) 2:43. [ )- g" 14:23:19 DATA R207 PRESS RELIEF VALV RCV-8 OUT TEMP 212 5 i

)

m 15:29:40 NORM N333 FLUX 10-M LEVEL e (NANCAMPS) 4. 15:;9:40 6AD N304 FLUX 10-M LEVEL 7 (NAN 0 AMPS) -????. 15:28:41 CONT X034 RC MOTOR 31 HP CIL PP DISCH PRES OK 15:29:41 NORM N341 FLUX 11-L, LEVEL e (NAN 0 AMPS). 9. i' (, ll a n!- e n A l Y* l. i V

h. r< 1 e t. t s (. 25:09:43 CONT XC36 kC MOTOR 91 Wp'OEL'PD SteCW DC's "WISW ~~" ~^ c..-__... " ~ " '.3 15:28:43 NORM N3:6 FLUX 12-n LEVEL 7 (NANCAMPS) 9. f' 16:26:01 VATR R 20 RC PUMPS A SUCTICN TEMP (WIDE) 434.7 15:29:44 CONT XO3e RC MOTCR 31 HP OIL PP DISCH PRES CK [] 15:28:45 CCNT XQ36 RC MOTCR 81 HP OIL PP DISCN PRES HIGH 15:08:45 BAD N390 FLUX.31-r LEVEL 5 tNaNcAMPs, t 2j 15:28:44 CONT XO3e RC MOTOR 91 HP OIL PP DISCH PRES CK !3 ju 15:*8:44 BAD N389, FLUX 12-F LEVEL e (NANDAMPS) -????. n 15:08:47 CONT X034 RC MOTCR 91 NP OIL PP DISCW PRES WIGH 3, 15:26:48 CONT K034 RC MOTOR 31 MP OIL PP DISCH PRES CK ) gt 15:08::: CONT X003 RC PUMP A1 2ND SEAL CAVITY PRESS HIGH in 15:*9:52 NORM N454 FLUX 6-C LEVEL 7 (NANDAM*S) 8 'n 14:04:54 DATA R207 PRESS RELIEF VALV RCV-8 OUT TEMP 211.9 ') ' Jy 16:27:01 VATR R220 RC PUMPS A SUCTION TEMP (WICE) 433.7 in 16:27t01 BAD N!45 FLUX a-O LEVEL 7 fNANDAMPS) 2* 16:07:01 CONT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS CA ) 23 14:07:02 BAD N50 FLUX e-P LEVEL 7 (NANCAMP3) -????. 'r 16??'!07 BAD N!a9 FLUY 13-L LEVEL ? (NANCAMS$) 1 14:27:03 CONT K04: RC PUMP B2 3RD SEAL CAVITY PRESS HIGH ' 23 ) 14:27 2 CONT XO4 RC PUMP 82 3RD SEAL CAVITY PRESS 0K ns 16:07:32 NCRM N254 FLUX 7-E tr>EL 7 (NANCAM*S) 9. Jg 16:27:40 BAD N334 FLUX 10-M LEVEL 7 (NANCAMPS) ??. ) .g to:27:42 CONT XO4 RC PUMP 3 3RD SEAL CAVITY PRESS HIGH i in 16:09:00 VATR R200 RC PUMPS A SUCTTCN TEMP (WICE) 430.6

• 10:27:43 CONT XO4 NC F UMP B 3RD SEAL CAVITY PRESS ON

'3~ ) 16:07:45 NCRM N331 FLUX 13-F LEVEL & (NANCAMPS) 8. ( IE 16! 7:44 BAD N390 FLUX 12-F LEVEL 7 (NANCAM*S' 3E 14:27::: N0hM N4:4 FLUX 6-C LEVEL 7 (NANCAMPS) 8. } n 14:27:53 BAD N44 FLUX 5-D LEVEL 7 (NANCAMPS) -??. 8 I~ is:07:54 NC c:= N470 eLUX 4-r trVrt 7 (nan 0a=p93 o. l E 16:07:58 CONT XO4 RC PUMP S: 3RD SEAL CAVITY PRESS HIGH ) -? 3g 16:27:59 CONT XQ45 RC PUMP 3: 3RD SEAL CAVITY PRESS CK 2 l 16:29:01 NCFM NT42 FLUX a-O LEVEL 7 (N4NCAMPT) 10. ( E 14:28:59 VATR R200 RC PUMPS A SUCTICN TEMP (WIDE) 431 4 3 g-zg to: S:00 NCRM N:50 FLUX e-P LEVEL 7 (NANDAMPS) 10. t p 16:08:07 NORM N!99 FLUX 13-L LEVEL

• fNAN08Me9) 9.

j rJ 14:28:08 NORM N406 FLUX 14-D LEVEL 7 (NANCAMPS) 9. l ) g: y; 16:08:11 NCRM SO:1 HEATER 33 INLET COND TEMP 100.0 f p tet 9:13 CONT X045 RC PUMP P2 3R3 erat CAVITY PRrgs wicN f Jg 163:S 14 CCNT XO4 RC PUMP 80 3RD SEAL CAVITY PRESS CK ) 8; 33 16:28:27 CONT X045 RC PUMP 32 3R0 SEAL CAVITY PRESS HIGH m 14:0C!:9 CONT X045 RC PUFP P2 3RD e!AL CAVITY pee-e cm 22 14::S:31 PAD N36 FLUX 9-E LEVEL 5 (NANCAMPS) -T??T. t ,, gm GRCUP e -) l 2* 1a:09!!7

02/6/30 aNatc5 aie?cN*rN? en==aev

( R200 PRESSURI*ER LEVEL L1(IN)(UNCCMP) ATR 1 200.00/ 100.00 4 R207 PREES RELIEF VALV RCV-9 CUT TE=P ATR S 500.00/ 100.00 gg R002 RC OUTLET A PRESS (NARROW) ATR 3 2000.0/ 500.0 j f ( g X304 RC PUMP A2 MTR LCWRGUIDE BRO TMP ATR 4 130.00/ .00 le g W 14:30:28 VATR R220 RC PUMPS A SUCTION TEMP (WIDE) 430.4 ei 14:28:40 BAD N326 FLUX 9-M LEVEL 7 (NANCAMPS) -????. , IU 16:08:40 NORM N334 rLUX 10-M trvrL 7 (NANcAmps) e. 55 14:03:4e NORM N390 FLUX 12-F LEVEL 7 (NANDAMPS) 9. !! 16:03:51 CONT X04: RC PUMP B2 3RD SEAL CAVITY PRE:S HIGH

• istr9tri OcNT vo4r 40 ouMe 9S NRS erar rau?Tv pre--

av

• 16:31:00 VATR R:20 RC PUMPS A SUCTION TEMP (WIDE) 430 1 l

T E3 16:28:53' NORM N46 FLUX 5-D LEVEL 7 (NANDAMPS) 9. F ia:29!22 CONT X045 PC PUPD BS 3RD REAL EAVITY PRfes MTOM 10:09:23 CONT X04: RC PUMP B2 3RD SEAL CAVITY PRESS Oh 14:29:26 BAD SO31

• HEATER 38 DRAIN CP

-??.?? 14:09:28 BAD N20e FLUX,.8-H L.EVEL_7 (NANOAMPS) -????._, _, 1 i M

f. '.

a n .I '3

/"

• ]

Y' P .I t b ( h. i 16 29:30 BAD ST31 NEATER 3B DRAIN FLOW ' ' ' ~i". ' *~ ~~~~~~' .oi.Via4 Nshn N=wo PLwA Y-L.Ev&6 L tieANUAnr 3 J d. r 16:29:33 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS HIGH 16:29:33 BAD N262 FLUX 6-0 LEVEL 7 (NANCAMPE) -??. i 16:32:01 VATR R220 RC PUMPS A SUCTION TEM * (WILE) 429.6 16!29:34 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS Ck A. 141;9137 NGAM A252 AC PUMPS TOTAL 3EAL FLOW (GFM) 40.47 7* 14:29:39 CCNT 7005 HP TURB STEAM SEAL PRESS CK 1 ll 16:28:41 CCNT 7005 NP TURD STEAM SEAL PRESS LOW .* 1o329344 CONT T091 GLAND SPILLGVER BYFASS CPEN YES (( 16:29:45 BAD N381 FLUX 13-F LEVEL 6 (NANDAMPS) -????. ) u. 16!29:46 BAD N390 FLUS 12-r LEVEL 7 (NANDAMPS$ in 16:29:47 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS HIGH Gi 16:29:48 CCNT XQ45 RC PUMP B2 3RD SEAL CAVITY PRESS QM ) 71 16:33:01 VATR R200 RC PUMPS A SUCTION TEMP (WICC) 429.1 ie 1o429 53 e=L Neo2 FLJX 5-0 LEwdb 7 (NANCAMFS) '??'. E 14:30 06 BAD No06 FLUX 14-D LEVEL 7 (NAN 0 AMPS) ??. } Ti 16:30:16 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS HIGN iz ao;Ja;1/ seNi As4L AG euMr B; Jsb 5EAL CAWITY FRESS GK "; 16:30:26 CONT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS HIGH ) Ti 14:30:26 CCNT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS CK w leise&;e NGhn N;Go FLuA 8-M LEVEL 7 (NANCAMFS) 13. 10. ) (( 16:30:30 NORM N229 FLUX 8-F LEVEL 6 (NAN 3 AMPS) 10. ... 16:30:33 NCRM N262 FLUX 6-0 LEVEL 7 (NANDAM*S) no le&J48GO VATR A220 AC FuMPS A SUCIICH TEMP (WICE) 428.7 0 ' is 16:30:39 BAD N317 FLUX 9-N LEVEL 6 (NANCAMPS) -?'??. 1 IC 16:30:40 NCRM N326 FLUX 9-M LEVEL 7 (NANCAMPS) 10. 9. n lo;JJ;eo NOAM N390 PluA 12-F LEVEL 7 (NANCAMFS) ~E 16:30:52 BAD N4:4 FLUX 6-C LEVEL 7 (NAP 9APPS) 9 i .l '3; 16:30:53 NORM N462 FLUt 5-0 LEVEL 7 (NANCAMPS) 8 le;Jo;;o bas N4sa rwwx

-G LEVEL 7 (NaNGAers)

-????. i si 16:30:59 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS HIGH ER 16:31:00 CCNT X045 RC PUMP B2 3RD SEAL CAVITY PRESS CA y a .a.w..wa oA, ....a rowA .-n ws.s.. s n-hw AMr a e -f.'t. l -{ 16:34:59 VATR R220 RC PUMPS A SUCTION TEMP (WIDE) 428.6 ) 16:31:04 DAD N574 FLUX 10-0 LEVEL 7 (NANCAMPS) m loisiiVU h5RM NoJo rwuA 14-L 6EVEL / LNANCAMFS) 9. I i-16:31:10 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS NIGH ) f is 16:31:11 CCNT X045 RC PUMP B2 3RD SEAL CAVITY PRESS OK w 10:31810 CONT XO45 RC FuMP B2 3RD SEAL CAVITY PRE 5S MIGH s is 16:31:18 CCNT XQ45 RC PV9P B2 3RD SEAL CAVITY PRESS CA 3; 16:31830 CONT X045 RC PUMP B2 3RD SFAd CAVITY PRESS HIGH m 16;st;si G;NT A04L AC F UMP a2 3RD 5EAL GAVITY FAE55 On 5; 16:31:32 BAD N254 FLUX 7-E LEVEL 7 (NANDAMPS) -????. i~ 16:31:33 BAD N262 FLUX 4-G LEVEL 7 (NANDAMPS) wo le;so;04 VATA A;20 EL FuMFS A SuCTICN TEMP (WILE) 423.o 7" lo:31:35 CONT XO45 RC PUMP B2 3RD SEAL CAVITY FRESS HIGH j II 16:31:34 CCNT X045 RC PUMP B2 3RD SEAL CAVITY PRESS CK .m ao;414Jo hsAM N;Jo Flux L-n LEvEs 7 (NANGAnPS) 19. 9. J

o 14:31:39 NORM N317 FLUX 9-N LEVEL & (N ANCAP/S)

Co 16:31:40 BAD _ N326 FLUX 9-M LEVEL 7 (NANDAMPS) -'?. => 1e&J1840 CO.f XO45 AC FUMP B2 3RD SEAL CAVITY FRESS HIGH ) gj 16:31:41 CONT X045 RC POMP B2 3RD SEAL CAVITY PRESS OK e 16:31:43 PAD N358 FLUX 12-K LEVEL 7 (NANCAMDS) M. g3 16:31:45 CONT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS HIGH m 16:37:04 VATR R200 RC PUMPS A SUCTION TEMP (UIOE) 429.7 IU 16:31:45 NORM N381 FLUX 13-F LEVEL 6 (NANCAMPS) 8. sa to;31345 NORM N382 FLUX 13-F LEVEL 7 (NANDAMPS) 9. 15 16:31:46 CCNT XQ40 RC **JMP B2 3RD SEAL CAVITY FRESS ON j I S. E 16:3: 52 NORM N454 FLUX 6-C LEVEL 7 (NAN 0 AMPS) sa 14:31:56 NCRM N486 FLUX 2-G LEVEL 7 (NANCAMPS) 8. i; 16:31:58 CCNT X045 RC PUMP B2 3RD SEAL CAVITY PRESS HIGH ) P 16:31:59 CONT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS Ok S. lo;32:00 NCRM N534 FLUX 5-0 LEL'EL 7 (NANCAMPS) 16:32:01 BAD N542 FLUX 6-0 LEVEL 7 (NANCAMPS) -????. 16:38:02 VATP R220 RC PUMPS A SUCTICN TEMP (UILE) 429.0, h 4

3 ~.- i ai

• i

.4 .. s 5 } I. F ( pt i 4.. 16:32:04 "NCRMN574 FLUX'io-0 LEOEC'7 (NANDAMPf) 3[~ ~ ~ ~ ~ ~ ' '

2)

• * - ~

t lo 3:207 BAD N598 FLUX 13-6 LEYEL 7 (NANCAM*38 -????. 16:32:11 NORM S:31 aHEATER 3B DRAIN DP 3.92 16:32:15 NORM S731 HEATER 3B DRAIN FLOW 69.0 [)l to:32:23 CONT XO45 RC PUMP B 3RD SEAL CAVITY PRESS HIGH 16:32:03 CONT x045 RC DU=P P2 2PD eEAL CAVf'Y pee?e cM Oj 16:32:25 MIGH R22: RC QUTLET A PRESS (NARROW) 2059. j ) JJ 16:32:30 BAD N229 FLUX S-F LEVEL 4 (NANDAMPS) -????. n 16:J2:30 CONT YO45 RC PUMP B2 3RD eEAL CAVITY PCESE HION 2; 16:39:00 VATR R2 0 RC PUMPS A SUCTION TEMP (WIDE) 409 6 I ) s 16:32:31 CONT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS CA l' 16:32:30 NORM N254 FLUX 7-E LEVEL 7 (NANOAMPS) S. in 16:32:33 NCRM N:62 FLUX 6-G LEVEL 7 (NANCAMPS) 8. ) ' "[ 16:32:35 HIGH R 23 RC OUTLET A PRESS (NARROW) 2263. u 16:32:35 HIOK R224 RC CUTLET B PREeS (NARRCW) 2265. ) io la:3:*35 HIGH R 25 AC OUTLET B PRESS (NARROW) 0063. } 16:32:37 CONr XO45 RC PUMP B 3RD SEAL CAVITY PRESS HIGH

• t 16:30:35 CONT x045 RF PUMo 92 spD eEAL CAVITY eeree Sw 16:32:40 BAD N334 FLUX 10-M LEVEL 7 (NAN 0 AMPS)

-?'?'. ) i.g t 16:39:59 VATR R200 RC PUMPS A SUCTION TEMP (WIDC) 430.4 's 16:32!43 NCRM N359 rLUT !?-M L E U r'_ ? fNANDAMPe) 9. 23 16::::45 BAD N38 FLUX 13-F LEVEL 7 (NANCAMPS) -????. ) n' lo:32:45 CONT X045 RC PUMP B 3RD SEAL CAVITY PRESS HIGH 's 16:30:46 PAD N300 FLUX 12-r LEVEL 7 (NANCAMes) i: 16:32:46 CONT XO45 RC PUMP B 3R SEAL CAVITY PRESS OK ) = 16:32:50 CONT XO45 RC PUMP B 3RD SEAL CAVITY PRESS HIGH EU 16:30:53 BAD N46: FLUX 5-D LEVEL 7 (NANCAMPS) g 16:30:53 CCNT X045 RC PUMP B: 3RD SEAL CAVITY PRESS CN ) . < w 16:33:00 BAD N534 FLUX 5-0 LEVEL 7 (NANDAMPS) '???. I* 16:33:04 PAD N!74 rLUr 10-0 LEVEL 7 (Nawca-ess 3g 16:41:04 VATR R200 RC PUMPS A SUCTICN TEMP (WIDE) 431.6 [)

• ' 3g 16:33:04 HIGH R210 RC PRESS (WIDE) (LOCP B) 2 97.

s' 16:33:07 NCmM N509 FLUY 13-L LEVEL 7 (NANOA=Pe) o 4 2L 16:33:07 CCNT XO45 RC PUMP B 3RD SEAL CAVITY PRE 35 HIGH ) z 16:33:08 BAD N606 FLUX 14-D LEVEL 7 (NANCAMPS) -????. x 14:33:c0 cSN' vc4? er e"we

• ?

en erv Av+?w eeece et g EU 16:33:10 CONT XO45 RC PUMP B: 3RD SEAL CAVITY PRES 3 HIGH ) ,t-w 16:33:11 CONT X045 RC PUMP B 3RD SEAL CAVITY PRESS CK 3 is!?I:19 CSN' T045 RE DO=D OS TRD e?At *AUTTY PRfee M?NM ,' ) 3 16:33:19 CONT XO45 RC PUMP B 3RD SEAL CAVITY PRES 3 ON I u 16:42:03 VATR RO:0 RC ' UMPS A SUCTION TEMP (WIDE) 432.5 w 16!33:05 HIGW R209 RC PcEGS fufDE) (LOCP a) ??oo. m 16:33:25 CONT XO45 RC PUMP B: 3RD SEAL CAVITY PRESS HIGH ) , E 16:33:26 CONT XO45 RC PUMP B 3RD SEAL CAVITY PRESS CK w 16:33:27 CONT A120 rEESWATER TO HTR 5 HYrRA??NE SM g 16:33 30 NORM NO 9 FLUX 8-F LEVEL 4 (NANCAMPS) 10. g 16:33:32 BAD N 54 FLUX 7-E LEVEL 7 (NAN 0 AMPS) -???'.

• a 13;;;;34 w?nu RS69 Rc ceree cu?re) c' eae a*

a~ee ) !! 16:33:36 CONT XO45 RC PUMP B: 3RD SEAL CAVITY PRESS HIGH i

16:33:37 CONT XQ45 RC PUMP B 3RD SEAL CAVITY PRESS OK

{ av 16:43:01 vaTR RSSo RC puwes a lucT?cN TEMP (UIDF) dia.? 8. ) ft 16:33:40 NCRM N3 6 FLUX 9-M LEVEL 7 (NANCAMPS) g[ 14:33:40 NORM N334 FLUX 10-M LEVEL 7 (NANDAMPS) 9. s we 16:33:45 PAD N3pi FLUX 13-F LEUrt A (NANDAMeM) b* 16:33:52 PAD N454 FLUX 6-C LEVEL 7 (NANDAMPS) -T???. s se 14:33:53 NORM 'N462 FLUX 5-D LEVEL 7 (NAN 0 AMPS) 10. IO 16:34:01 BAD N541 FLUY 6-0 LEVEL 6 (NANOAMPS) m 16:34:03 NORM N558 FLUX 7-R LEVEL 7 (NAN 0 AMPS) 9. E 16:34:04 NORM N574 FLUX 10-0 LEVEL 7 (NAN 0 AMPS) 9. E 16:34:07 PAD N598 FLUY 13-L LEVEL 7 (NAN 0AMes) i u 16:43:59 VATR R200 RC PUMPS A SUCTICN TEMP (WIDE) 430.7 l ~; 14:3408 NCRM N406 FLUX 14-D LEVEL 7 (NANCAMPS) S. l E 16:34:00 CONT x04E RC DUMP DS 1RD MFAf EAUTT' e@ree W?nH g I 16:34:21 CONT XO45 RC PUMP B 3P.D SEAL CAVITY PRESS CA 16:34 03 CONT XO45 RC PUMP D: 3RD SEAL CAVITY PRESS HIGH l 16:34:24. CON T. X0,45,_RC PUM,P,B2 3RD,S,EAL CAVITY,_ PRESS O K. l l 4 a i' l ti

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e I i l. (.# te '~ l' ,F~~~ 16:34:26 CONT' h042 DEMl'NERALI2ER SYSTEM ~ ~ ' 'O, k ~""~~~~~~~' ~ ~ ' "~~~~~' .o o. 1 .n .A 1N me -z.,, 14:34:24 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS HIGH f 16:34:27 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS OK s 16:34:28 BAD N20e FLUX 8-M LEVEL 7 (NANCAMPS) -??'?. 16:45:03 UATR R220 RC PUMPS A SUCTION TEMP (UIDE) 429.3 .s: 163J4447 BAD 57J1 HEATEA JB DRAIN FLGu -???.? ] $1 14:34:32 NORM N254 FLUX 7-E LEVEL 7 (NANCAMPS) 9. Il 14:34:33 BAD N262 FLUX e-G LEVEL 7 (NANCAMPS) a si 14:34:36 CCNT X003 RC PUMP A1 2ND SEAL CAVITY PRESS HIGH ) ~~ 14:34:40 BAD N326 FLUX 9-M LEVEL 7 (NANCAMPS) -????. 9 $I 14:34:42 CONT N045 RC PUMP B2 3RD SEAL CAVITY PRESS H!CH gj 14:34 43 CONT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS CA ) s 16:34:45 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS HIGH y wi 16:34 44 NORM N390 FLUX 12-F LEVEL 7 (NAN 0 AMPS)

• 1o:4o101 VATR R200 RC PUNPS A SUCTION TEMP su1DE) 423.0

) 7; 16:34:46 CONT XO45 AC PUMP B2 3RD SEAL CAVITY PRESS CA II 14:34:49 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS HIGH I in 14 34:49 CONT 4045 RC PUMP B2 3RD SEAL CAVITY PRESS ON i * %2 16:34:52 NCRM N454 FLUX 4-C LEVEL 7 (NANCAMPS) 10. ~~ 14:34:52 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS HIGH .. 16;J ;;s bas =~o; r6VA 5-u LivEw 7 (NANUAnPS) -????. 3 IF 14:34:53 CONT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS CA TE 14:35:01 NORM N541 FLUX 6-0 LEVEL 6 (NAN 0 AMPS) 3. mm leesL;G1 NUAM NL*2 FLUX o-Q LEVEL 7-(NANCAMPS) 10. T EE 14:47:00 VATR R200 RC PUMPS A SUCTION TEMP (WIDE) 427.4 EU 16:35:01 CCNT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS HICH zn 1o:35:02 CONT X045 RC FUMP B2 3RD SEAL CAVITY PRESS CA I y is 16:35:04 CONT XO45 RC PUMP B2 3RD SEAL. CAVITY PRESS HIGH 52 16:35:05 CCNT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS Ok j u lo&25:07 NCAM N598 FLUX 13-6 LEVEL 7 (NANCAMPS) 9. 33 14:35:08 CONT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS HICH

• i ER 16:35:08 BAD N604 FLUX 14-D LEVEL 7 (NANCAMPS)

-????. z. .oess.e. weni As L AG r unr 62 shD adA6 LAVair rAEas wa "" 16:35:17 CONT XO45 RC PUMP 32 3RD SEAL CAVITY PRESS HIGH 16:47:59 VATR R220 RC PUMPS A SUCTION TEMP (WIDE) 427.1 Ao.assi/ wen 6 4ess nL rune ma ans asAL Lavisr rhtaa Uri I pj 16:35:20 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS HIGH j-t ni } 3E 14:35:21 CONT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS CK a lo;35;;o CGNi XV45 AC PunP B2 3RD SEAw CAVITY PNESS MIGn is 16:35:27 CONT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS CA 33 14:35:28 NORM N206 FLUX 8-H LEVEL 7 (NAN 0 AMPS) 8. m 1643L&29 CCNT XO45 RC PUNP B2 3RD SEAL CAVITY PRESS nIGM s 3; 14:35130 CONT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS OK "; 16:35:31 BAD N238 FLUX 9-E LEVEL 7 (NANCAMPS) - ?t". au 1o:35:35 CCNT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS MIGH Is 16:49:04 Vt.TR R220 RC PUMPS A SUCTION TEMP (WIDE) 427.3 "I 16:35:36 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS CA i au lo;3L&Ja CONT A04 RC RUMP B2 3RD SEAL CAVITY PRESS MI5m "; 16:35:39 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS OK )

14

35

40 NORN N326 FLUX 9-M LEVEL 7 (NAN 0 AMPS) 10.

um losJLi44 GGNi XO4L RG PUMP D2 JRD 5EAL CAVITY PRES 5 HIGH lE 16:35:45 NORM N381 FLUX 13-F LEVEL 4 (NAN 0 AMPS) 9. I 55 14:35:45 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS CK j 14335446 BAD N390 FLUX 12-F LEVEL 7 (NAN 0 AMPS) -????. ) 14:35:47 CONT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS HICH ' ~U 16:50:03 UATR R220 RC PUMPS A SUCTION TEMP (WIDE) 428.0 u 1o:35348 CONT X045 RC PUMP B2 3RD SLnL CAVITY PRESS OA 1 IE 16:35:53 CONT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS HIGH E~ 14:35:54 CCNT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS Ck [ u 14435:59 CONT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS HIGH lj l "E 14:35:59 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS OK I 36 14:34 02 CONT X045 RC PUMP B2 3RD SEAL CAVITY PRESS HICH 16:3e:03 CONT XO45 RC PUMP B2 3RD SEAL CAVITY PRESS DA 16:34:07 BAD N598 FLUX 13-L LEVEL 7 (NANCAMPS) -????. 16:34:08 NORM Ne06 FLU.X 14-D.LE.V.EL 7.(NAN 0 AMPS) 8. d fA ? *. 9-9"- n

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