ML20140E535
| ML20140E535 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/31/1984 |
| From: | Enos J ARKANSAS POWER & LIGHT CO. |
| To: | John Miller, Stolz J Office of Nuclear Reactor Regulation |
| References | |
| 0CAN-128408, CAN-128408, NUDOCS 8501110115 | |
| Download: ML20140E535 (18) | |
Text
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ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72203 (501) 371-4000 December 31, 1984 BCAN128408 Director of Nuclear Reactor Regulation ATTN: Mr. J. F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555 Director of Nuclear Reactor Regulation ATTN: Mr. James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 10CFR50.59 Report Design Changes Gentlemen:
In accordance with 10CFR50.59, attached is a report containing a brief description of our safety evaluation for design changes made to Arkansas Nuclear One - Units 1 and 2 (ANO-1 and ANO-2).
This report contains those changes which were completed during 1983 and required a safety evaluation.
Ver truly yours, J. Ted Enos Manager, Licensing JTE/RJS/ds Attachment 8501110115 841231 PDR ADOCK 05000313 p
PDR MEMBEA MIDDLE SOUTH UT UTIES SYSTEM
r ARKANSAS NUCLEAR ONE - UNITS 1 AND 2 DOCKET N05. 50-313 AND 50-368 LICENSE NOS. DPR-51 AND NPF-6 ANNUAL 10CFR50.59 REPORT FOR 1983 Introduction This report,_in accordance with 10CFR50.59, contains a brief description of reportable design changes made to Arkansas Nuclear One - Units One and Two (ANO-1&2). Only those design changes which required a safety evaluation and were completed in 1983 are contained in this submittal.
Additionally, it was determined that none of these changes created the possibility of cny unanalyzed accident, nor was there any increase in the probability or consequences of any previously analyzed accident.
In no case was any margin of safety reduced as related to the health and safety of the public.
1983 10CFR50.59 REPORT DESIGN CHANGES FOR ARKANSAS NUCLEAR ONE - UNITS 1 AND 2 UNIT 1 Change Number Descriptive Summary DCR 574 DCPs 574 and 574A modified the Decay Heat Removal System and the Reactor Building Spray System.
The control valves in the Decay Heat Removal System were replaced with anti-cavitation flow control values.
This involved pipe rerouting to fit in the larger replacement valves. Monorails also were added over CV-1428 and CV-1429 Decay Heat Removal Control Valves.
Pressure reducing flow orifices (F0-1400 and F0-1401) were installed in the Reactor Building Spray System to prevent cavitation through valve BS-3.
DCP 79-1035A DCP 79-1035A provided isolation valves and vacuum breakers for the liquid radwaste tanks on the gas collection header.
Enhancement of operation flexibility was achieved by this change.
This DCP affected FSAR Figures 11-1, 11-2, and 11-3.
DCP 79-1061 DCP 79-1061 installed two new high range containment radiation monitors.
Indicators for the new monitors were installed in bays 3 &
4 of panel C-486 in the control room.
This DCP affected FSAR Figures 11-6 and 11-9, and Tables 7-11 and 11-7.
DCP 80-1120 DCP 80-1120 designed and installed permanent ladders and cages inside the north steam generator cavity.
This DCP was.in partial response to the D.O.E. Report C00-4068-14, " Refueling Outage Availability Study," Item 5.2.5.'
DCP 80-1137 DCP 80-1137 prod ded a catwalk between the reactor cooling pumps.
This walkway allowed personnel to get from pump C/D platform to pump D/C platform, and from pump A/B platform to pump B/A platform.
This walkway also provided access to the snubbers for maintenance, inspection, or repair.
1 i:
Change Numb:r Descriptive Summary DCP 80-1138 DCP 80-1138 changed the existing transformer deluge system actuation subsystem from a pneumatic system to an electrical one similar to that installed in Unit Two.
This provided an electric detection and actuation system for the station transformers and simplified the fire protection system alarms.
DCP 80-1152 DCP 80-1152 required brazing on both sides, top and bottom, of the generator stationary blower blades which are attached to the outer and inner blade rings.
This modification was made to enhance the service life and reliability of the blades.
DCP 80-1154 DCP 80-1154. required a material change to the existing piping to help prevent erosion, and did not effect any of the turbine rotating parts which might contribute to a missile problem. The present carbon steel high pressure turbine interstage cylinder drains were replaced using type 304 stainless steel to increase the operating life of the lines shown in Figure 1 of Availability Information Bulletin 7915.
DCP 80-1155 DCP 80-1155 required the inspection and alteration of any blade on the high pressure (HP) rotor of the turbine with abrupt discontinuities at the intersection of the foil and platform.
Such discontinuities were believed to have potentially resulted from previous assembly operations and may have resulted in increased susceptibility to cracking.
DCP 80-1156 DCP 80-1156 required removal of an existing pipe plug and the addition of drain lines from the gland leakoff chamber along the outside of the high pressure case to the gland leakoff.
DCP 80-1160 DCP 80-1160 required the installation of new dual filters in the high pressure oil supply of "A" and "B" feedwater pump turbines to improve the control of the feedwater turbines by reducing the contaminants in the lube and control oil system.
FSAR Figure 10.4.7 was affected.
DCP 80-1163 DCP 80-1163 replaced existing relays and triacs in the turbine generator auxiliary governor control circuit with mercury wetted relays. This modification was recommended by the turbine generator manufacturer to prevent a potential failure of the original circuit.
2
Ch nge Number Descriptive Summ:ry DCP 80-1184 DCP 80-1184 provided increased reliability for the decay heat cooler radiation monitors by reducing the amount of corrosion product building on the service water pipes.
The carbon steel pipe was replaced with stainless steel pipes.
DCP 81-1014 DCP 81-1014 added a thermal shield to the high pressure (HP) cylinder base of the turbine in an attempt to stop steam leakage at the HP joint.
Due to the location of the HP cylinder, it will not come into contact with any rotating parts of the turbine to cause any missile hazards that have not been analyzed.
DCP 81-1021 DCP 81-1021 allowed automatic transfer of AN0-1 or 2 to Startup Transformer #2 without the chance of both units attempting transfer at the same time.
DCP 81-1023 DCP 81-1023 modified the starting logic of decay heat room unit coolers, VUC-1B and VUC-10.
The starting logic was changed to depend on the status of the decay heat pump, the reactor spray pumps, and status of unit coolers VUC-1A and VUC-1C.
DCP 81-1051 DCP 81-1051 covered the installation of improved seal parts in the reactor coolant pump (RCP) seal assembly.
The RCP modification consisted of the following:
- Carbide rotating ball seal rings (3 stages) which incorporated the addition of radial slots on the outer diameter of the sealing surface..
- Modified staging coil assemblies which produce a nominal staging
. flow of 1.5 gpm (gallon per minute).
- Modified cap nut in the lower pressure breakdown device to permit flow from the lower seal cavity.
- Plugged the existing flow passage to the lower breakdown device to eliminate bypass flow.
- An improved design "U" cup (3 stages).
-,3-
TChange NumbGr Descriptive Summary
'DCP 81-1057 DCP 81-1057 replaced the main feedwater nozzles on the "A" Once
.Through Steam Generator (OTSG) with a redesigned nozzle.
The new
-nozzles are made from Inconel.
This DCP affected FSAR Paragraph
.4.1.3.1 and Table 4-2.
t
'DCP 81-1067 DCP 81-1067 made the process monitor and the area monitor indicators compatible so that the operators will not have to convert the recorded reading to obtain a more accurate reading.
DCP 81-1080
- DCP 81-1080 provided a means for taking manual action so that the diesel generator can be started without DC power being available.
This DCP affected FSAR Paragraph 8.2.2.3.
DCP 81-1086 DCP 81-1086 relocated the diesel generator differential relays from the door of-the generator control cabinet Ell to the inside control subpanel.
This change was required for seismic design of generator
-differential relays for DG1 and DG2. When the relays were mounted on the door, rattling effect of the door was unpredictable, relocating to a stationary subpanel increased the confidence level in performance of such protective devices.
DCP 82-1002 I;
DCP 82-1002 replaced the' instrument air compressor unloading solenoid valve with a different model valve requiring no change of existing design.
DCP 82-1004 DCP 82-1004 modified annunciator panels K15 and K16 by combining:
related alarms and eliminating nuisance alarms. These alarms serve as i.idicators and not as control functions.
DCP 82-1017 DCP'82-1017 removed differential pressure transmitters, PDT-6819, PDT-6848, PDT-6849, and PDT-6850 (the reheat steam distiller drain flow instrumentation). These instruments which provided reheat steam
~ distiller drain flow signals to.the computer were no longer
.necessary.
4
Change Number Descriptive Summary DCP 82-1018 t'-W DCP 82-1018 implemented repairs on three HPI nozzles.
On "B" nozzle
]-
the pipe-to-safe end field weld was cut, and the existing thermal sleeve was re-rolled.
On both "A" and "D" nozzles, the safe end and thermal s'leeve were cut out and replaced.
-DCP 82-1020 DCP 82-1020 deleted and combined control room annunciator windows as parL of.the overall annunciator upgrading project.
DCP 82-1023 DCP 82-1023 added Seal-in to the "open" control circuits, therefore, valves were prevented from closing due to air leakage.
-DCP 82-1024 DCP 82-1024 upgraded annunciator panel K07.
The K07-F5 alarm, " Main U
Feedwater Pump 1P1A Turbine 1K2A Direct Current Power Loss", and the K07-F8 alarm, " Main Feedwater Pump 1P1B Turbine 1K2B Direct Current Power Loss", was combined into a single alarm, " Main Feedwater Pumps 1P1A/B Turbine 1K2A/B Direct Current Power Loss." This combined alarm was placed at K07-F5 and the K07-F8 window was spared.
The T
K07-F1 alarm, " Main Feedwater Pump 1A/1B Low Flow Protection.
By-Pass", was deleted and the window was spared. The entire low flow trip was removed from the main feedwater trip auxiliary controls.
The K07-B8 alarm, " Main Steam Temperature High", was deleted and the window was spared.
DCP 82-1026 DCP 82-1026 upgraded annunciator panel K09.
This DCP affected FSAR Figures 7-20 and 9-3.
t DCP 82-1027 me DCP 82-1027 was.tho' upgrade'for annunciator panel K11.
This change-combined and moved some alarm windows to reduce the number of alarms to the operators and incorporate human factor considerations into the control room.
FSAR Figures 9-7 and 9-12 were affected..
DCP82-1029 1
DCP 82 1029 upgraded' annunciator panels K04 and K05 to aid the operators in determination of the course of generator / turbine trips, to combine annunciator alarms to consolidate similar alarms and deleted unnecessary alarms.
FSAR-Figure 10.1 A.9 was affected.
5.
I
Change Number Descriptive Summary DCP 82-1030 DCP 82-1030 combined numerous annunciator windows and alarm functions on annunciator panel K06.
It also removed the low bearing water flow trip on the circulating pumps.
DCP 82-1038 DCP 82-1038 used new monorail beams designed for required seismic loads to eliminate the possibility of the beams damaging any safety-related equipment.
DCP also provided instructions for storing the monorail trolleys in a place on the beam to prevent their
. damaging any equipment.
DCP 82-1051 DCP 82-1051 deleted the automatic dispatch control from the unit load control of the ICS.
This package spared 10 cables which were connected from C35 to C46.
DCP 82-1072 DCP 82-1072 provided control room indication for the status of the been installed above HS-7457 (C178, control switch) green light !. ave hydrogen analyzer sample pumps.
A red light and a
, and HS-7459 (C179, control switch) on )anel C26 in the control room.
The green light will be lighted if tie handswitch is in the "STOP" nosition and the system is energized. The red light is wired in paral'lel with the sample pump and will be lighted when the handswitch is in the " START" position and the system is energized.
The change was entirely internal to the control room panel C26.
DCP 82-1077 DCP 82-1077 replaced a defective transformer in inverter cabinet Y-11 with a new 2KVA transformer. The mounting of the new transformer was different from the original. The framing system for the new transformer consisted of the addition of a brace to act as a mounting
'with an existing brace.
The existing 10KVA transformer had to be moved to allow additional room for the new 2KVA transformer to be added.
DCP 82-1079 DCP 82-1079 deleted the condensate hotwell low level trip on the condensate pumps.
DCP 82-1091 DCP 82-1091-removed extraction line drain valves SV-3059, SV-3046, SV-3084, and SV-3097 and replaced them with manually operated gate valves.
6
Change Numbar Descriptive Summary DCP 82-1092
.DCP 82-1092 replaced pressure switches, PS-2808 and PS-2809,tches which are utilized on heater drain pumps 1P8A and 1P88.
These swi
.were replaced because their adjustable ranges were significantly
- greater than system operating pressure rendering them ineffective.
. In addition, their dead band was too large to be responsive to system pressure changes.
Therefore, these switches were replaced with switches having a smaller adiustable range and dead band. The replacements, being compatible with and responsive to system operating pressures, should eliminate nuisance alarms in the control room.
RCP 82-1093 DCP 82-1093 deleted two main control room alarms (K11-B7 and K11-C7) and deleted a local alarm panel (ANN-1) at the Condensate Demineralizer Regeneration Station (C-111).
DCP 82-1095 DCP 82-1095 installed time delay relays in the main control room, and administration building chiller start circuits.
These time delay relays allow the chillers to start a7d run for 30 seconds before
- chiller. condenser cooling water is monitored.
' DCP 82-1097 DCP 82-1097 replaced the individual conductivity annunciator function on demineralizer tanks T54A through T54F (Panels C361 through C366) with a single total effluent high conductivity alarm in the Unit One control room.
DCP 82-1098 DCP 82-1098 removedthesealinjectionandsealcoolingflowlow trips on the reactor cooling pump seal'bleedoff isolation closing (CV-1270, CV-1271, CV-1272,'and CV-1273).
valves This DCP made the system more reliable during operation by preventing. inadvertent
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closure of the bleedoff valves and causing the reactor coolant pump seal to overheat.
DCP 82-1109 DCP 82-1109 installed bypasses around steam traps ST-6, ST-7, and ST-9. This change allcwed for the continued operation of the system x
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should a trap fall'and help prevent water hammer in the main steam
- lines during startup.
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Change Number Descriptive Summary DCP 83-1001 DCP 83-1001 removed the control room alarms and instrumentation associated with the city water system.
The alarms involved are the
" raw water differential pressure high" and " raw water aressure low "
locatedatK15andwerecombinedintoasinglealarmw1ichread" City Water System Trouble".
DCP 83-1004 DCP 83-1004 replaced nine 1350 amp-hour battery cells with 1500 amp-hour cells.
A surveillance test on D07, 125 volt direct current station battery, revealed three failed cells and six other cells which were a)proaching failure.
These cells were replaced with new cells of higier amp-hour capacity.
The existing battery rack has been modified to house the modified battery arrangement.
DCP 83-1021 DCP 83-1021 changed the auctioneering diode circuits for the Control Rod Drive Contrcl System (CRDCS).
Tiiis change permitted the power supply sensing circuits to better control voltage, thus reducing the number of nuisance annunciator alarms.
DCP 83-1040 DCP 83-1040 adjustedthepressurizersafetyvalvestoassure sufficient capacity from the valves.
8
r Change Number Descriptive Summary UNIT 2 DCR 2-47 DCR 2-47 revised indication circuits for 2PM76, 2VEF-37 and 2VSF-30.
The schematics, connection diagrams, panel wiring, draw,ings, and circuit schedules were revised.
DCR 2-96
-DCP 2-96 deleted air supply and return to the visitors viewing room from the control room system and provided ventilation to visitors' room from the turbine building elevator machine room system 2VSF33.
This DCP affected FSAR Figures 9.4-3 and 9.4-1.
DCR 2-98 DCP 2-98 added the sight glass and pressure indicators to make the resin transfer operations more efficient.
This efficiency will be achieved by increasing the amount of information available to the operator.
This DCP affected FSAR Figure 10.4-7.
DCR 2-99 DCP 2-99 replaced check valves 2HPA58 and 2HPA59 installed in the hydrogen purge system piping with motor operated gate valves which receive a containment isolation signal.
This DCP affected FSAR Figure 9.4-4, Paragraph 6.2.5.2.4, and Technical Specification Table 3.6-1.
IDCR 2-79-38 IDCR 2-79-38 replaced the existing motors for stator cooling pumps 2P-25A and 2P-25B.
IDCR 2-79-45 IDCR 2-79-45 modified the ANO-2 Core Protection Calculator / Control Element Assembly Calculator (CPC/CEAC) software in order to reduce the probability of spurious plant trips and improve overall CPC/CEAC performance.
IDCR 2-79 IDCR 2-79-47 modified AN0-2 CPC/CEAC software by making the CEA deviation penalty factor al arithm use the actual calculated penalty t
factor during initializatica rather than the maximum penalty factor, which is presently used in the Modification Zero or Modification One software.
9
t Change Number ~
Descriptive Summary
=.:
DCP 79'-2010
.DCP 79-2010 added six test canisters to the fuel handling floor filter system and three test canisters to the containment purge system. This DCP affected FSAR Table 9.4-3.
4.
DCP 79-2027
~DCP 79-2027 added one anchor and one vertical restraint to the RCS letdown line. This modification was made to conform to the piping
. stress analysis.
DCP.79-2028 DCP 79-2028 installed pipe hangers on lines 2DBD-23-3 and 2FCB-22-1.
DCP 79-2105 This DCP'added redundant main feedwater isolation valve to each main
-feedwater heater,- 2DB01 and 2DB02.
DCP 79-2147 DCP 79-2147 provided differential pressure indicator across the Reactor Coolant Pump (RCP) seal injection filter (2F309).- This DCP affected FSAR Figure 9.3-4 Sheet 1.
-DCP 79-2151
-DCP 79-2151 replaced the two existing reactor building flood level transmitters and receivers with new ones and the existing sump level.
transmitter and receiver with a qualified equipment system.
This DCP Laffected FSAR Figures 8.3-72, 8.3-77, 8.3-78, 8.3-79, 8.3-84, 8.3-85, 7.3-7, 6.2-17, 3A.2-5, 3A.2-6,.3A.2-18, and 3A.2-19.
DCP'79-2153
-DCP 79-2153 provided a-10" service water bypass line around the component cooling water heat exchangers.
The material used was-equivalent to that used on the existing system.
Hanger modifications were also made to ensure the integrity of the service water =line.-
DCP.79-2206
- DCP 79-2206 was an amendment to DCR-2010.
It replaced six charcoal test canisters with a single large-canis'.er capable of holding the required amounts of charcoal for testing.
[DCP79-2211-
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DCP 79-2211 replaced the1 manual. instrument isolation. valve 2SI-50918 with a^new manual valve requiring'a revision to the Manual Valve List M-2082.
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Change Number Descriptive' Summary DCP 80-2003 DCP 80-2003-installed the reactor vessel vent.
This venting system allows removal of non-condensable gases to enhance natural circulation.
This DCP affected FSAR Figures 5.1-3, 8.3-81B, 8.3-84, 8.3-80, 8.3-20, 8.3-76A, 8.3-85, 8.3-18, 8.3-81,.and 8.3-76.
Amendment B installed an alarm for this system which affected the
.same FSAR Figures.
Amendment C added some high point vent piping and hangers.
DCP 80-2015 DCP.80-2015 installed a solenoid valve 2SV-1081A and an interlock with pumps 2P139A and 2P-1398 to allow for better pressure regulation
'of the steam generator blowdown system.
DCP 80-2057 DCP 80-2057 installed heat tracing sensors and insulation along the sodium hydroxide tank.
This modification provided a more uniform tem)erature distribution which reduced stratification of Na0H in the tanc.
This DCP affected FSAR Figures 6.2-17 and 8.3-66A.
DCP-80-2069
.DCP 80-2069 insta11ated a water spray and CO2 fire protection for the turbine generator bearings and exciter housing per ANI recommendation 10.
This~DCP affected FSAR Figures 9.3-1 and 9.5-1.
-DCP 80-2083A DCP 80-2083A provided permanent non-vital AC power to the boathouse by replacing the temporary power supply with a new underground cable.
DCP 80-2113 DCP.80-2113, this DCP constructed platforms in the'AMERTAP pit which improved personnel: safety by providing access to existing-valves on-
' circulating water lines.
DCP-80-2127 DCP 80-2127 provided the design details for draining the ANO-2 7<
. atmospheric dump valves (2CV-1001/1051).
This modification prevented water slugging in the atmospheric dump valves.
FSAR Figures 10.2-3.
were affected.
1 DCP 80-2155
. (LTOP) of: the reactor vessel during over pressurization protection DCP 80-2155 provided low temperature startup and shutdown.
The:
-RCS when it 'is at low temperatures (< 270*y venting pressure from the protection' system ensured a means'of safel F) and thus decreased the
- probability of damage to the vessel due to material embrittlement.
11
~
Change Numbar Descriptive Summary This DCP affected FSAR Figures 5.1-3, 8.3-8, 8.3-12, 8.3-67A, 8.3-78, 8.3-79,'8.3-80, and 8.3-81F.
DCP 80-2160 DCP 80-2160 changed the logic for annunciator 2K12, Alarms G2, H2 and J2, and changed the charging pumps low oil pressure alarm.
These alarms will only be annunciated if the charging pump is running and a low oil pressure condition exists.
DCP 80-2210N DCP 80-2210N replaced 23 sigma model 9262 indicators with model 9270 indicators on control room console 2C112.
Indicators were wired with new cables furnished with quick-disconnects at the indicator end.
DCP 80-2210Q DCP 80-2110Q replaced nine sigma 9262 indicators with model 9270 indicators on control room panel 2C115.
The indicators were rewired with new cables furnished with quick disconnects at the indicator ends.
DCP 80-2210T DCP 80-2210T replaced one sigma model 9262 indicator with model 9270 indicators on control room console 2C161.
Indicators were wired with new cables-furnished with quick disconnects at the indicator end.
DCP 80-2210V DCP 80-2210V replaced nine sigma model 9262 indicators with model 9270-indicators on control room console 2002.
Indicators were wired t
with new cables furnished with quick disconnects at the indicator end.
DCP 80-2210Y DCP 80-2210Y replaced four sigma model 9262 dual indicators with model 9270 indicators on control _ room panel 2004 with sigma model 9270 Din-03 Lumigraph dual indicators.
DCP 80-2210Z DCP 80-2210Z replaced the remaining six sigma indicators on control room panel 2003 with model 9270 Lumigraph indicators, which utilize quick disconnect cables at the indicator end.
DCP 80-2213 DCP 80-2213 added two 12' long x 3'-9" wide platforms, one-on each side of the strainer, in the AMERTAP system pit.
The platforms improved personnel safety by providing access to existing valves.
12
i Change' Number Descriptive Summary DCP 81-2025 DCP 81-2025 moved the sensors and tubing to facilitate draining of condensation to restore the intended reliability of the Hydrogen Purge HEPA Filter Pack ^P instrumentation.
DCP 81-2031 DCP 81-2031 improved the drainage of the shutdown cooling heat changer.
This improved the performance of the heat exchanger by allowing a larger area of back flushing to remove silt and organic matter.
This DCP affected FSAR Figure 6.2-17.
DCP 81-2043 DCP 81-2043 installed modifications to the dry sipping system to improve the systems overall safety and reduce the potential radiation exposure of operating personnel.
DCP 81-2044 DCPs 81-2044, 81-2044A, 81-2044B, 81-2044C, and 81-20440 modified hangers due to the. addition of redundant main feedwater isolation valves.
FSAR Figures 10.2-3 and 7.3-1 in addition to Sections 10.4.7.2 and 7.3.1.1.11.4 were affected.
DCP 81-2094 DCP 81-2094 used a guard designed to cover the TB-12 terminal box wiring to prevent accidental bumping of wiring.
This was done by adding a metal cover to the existing cabinet in the area of the terminal TB-12.
DCP 82-2018 DCP 82-2018, this DCP added contacts from the remote circulatory water pump handswitches on panel 2C14 to the alarm circuit for the pump trip alarms on local annciator 2K17. 'This modification will ensure that the pump trip alarm is not inadvertantly defeated by having the local handswitch on panel 2C125 (2HS-1212 & 2HS-1212A) in the stop position with the actual operation of the pumps being controlled remotely from panel 2C14.
FSAR Figure 10.4-1 was affected by this change.
DCP 82-2020 DCP 82-2020, this DCP deleted the low level interlocks of the condensate storage tanks. The condensate hotwell makeup valve, 2SV-0634,' interlock was also removed. The tank selector switch
-(2HS-1999).was added to the alarm circuitry for the 2K11-B7 and F7 alarms (condensate storage tank 2T41A (2T41B) level low) to eliminate the nuisance alarm from the tank not being used as the emergency feedwater suction.
13 i
i D
' Change Number-Descriptive Summary i
DCP 82-2024 D
DCP 82-2024 modified the (2CV-1017 & 2CV-1067) steam generator blowdown drag valves.
The valves needed to be removed for disassembly, inspection, and machining to fit new internal parts.
'DCP 82-2031'-
DCP 82-2031 provided handswitches in the post accident sampling system building to allow selection of the reactor coolant system sample point (currently cane from hot lab).
DCP 82-2033 j
DCP 82-2033 removed control room indication for a number of c
non-safety related annunciators.
Remote indication was maintained.
^
This DCP affected FSAR Figures 10.4-7, 9.2-7, 10.4-5, 9.4-3 and paragraphs 9.2.3.2.1 and 10.4.10-4.
l DCP 82-2043 I
DCP 82-2043 modified. annunciator 2K06 by combining the 18 channel / pre-trip / trip alarms into a single alarm.- This modification, which is part of the overall annunciator upgrading project, reduced the complexity of the alarms.
.DCP 82-2046 DCP 82-2046 deleted-five alarms associated with the-hydrogen and nitrogen ~ addition system. 'Also, two logic changes for alarm i:.
functions for reactor makeup water and boric acid flow were deleted.
DCP 82-2047
.DCP 82-2047 added a level recorder (2LR.4857) to 2009 which allows the' operator to monitor level trends of the volume control -tank 2T4.
It also added a level recorder-(2LR 4625) to-2C04 to allow the e
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operator to monitor level trends of the_ pressurizer. This'DCP affected FSAR Figures 5.1-3 and 9.3-4.
f DCPI82-2054 g
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DCP 82-2054 relocated the condenser waterbox drain pump level. control
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switch which maintains the condenser waterboxes pumped dry during L
. shutdown.
This change allowed the condenser waterboxes to be more thoroughly drained during automatic operation of the drain pump.
This DCP affected FSAR Figure 10.4-1.
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DCP 82-2055 DCP 82-2055 removed the annunciator alarms for bypass'and dump valves' l
handswitches of the steam dump system.
This change deleted 2K02
' annunciator alarms:
D13, E13, F13, C14, 014, E14 and F14.
This g
change.was made to reduce the number of nuisance alarms.
14.
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Change Number Descriptive Summary DCP 82-2056 DCP 82-2056 deleted three unneeded alarms from annunciator 2K03 and eliminated the " split-window" alarms on the annunciator as part of the overall annunciator upgrading project.
This DCP affected FSAR Figure 10.4-2.
DCP 82-2066 DCP 82-2066 disabled the low pressure annunciator alarms associated with 2P136A and 2P136B when the pumps are not running.
DCP 82-2070 DCP 82-2070 changed the logic for annunciator 2K12 alarms F4 and F5 component cooling water Loop I and Loop II low flow.
This change reduced the number of locked in annunciator windows at power and during shuta,own periods.
DCP 82-2075 DCP 82-2075 installed an electronic load weighing device on the refueling machine hoist system.
This new device improved the reaction time.
FSAR Paragraphs 9.2.3.2.1 and 10.4.10-4 were p
affected.
DCP 82-210_0 DCP 82-2100 addad a 10" check valve to a 42" personnel hatch in the.
reactor vessel cavity to prevent flooding and possible thermal shock under certain conditions.
This DCP affected FSAR Section 6.2.
DCP 82-2107 DCP 82-2107 increased the efficiency of the Moisture Separator Reheaters (MSR's) by baffling the initial separation.
Ei impiiigement baffle modifications were installed (welded) ght inside'the MSR s at the inlet nozzle.
DCP 82-2123 DCF 82-2123 repaired weld cracks and buckling of the vertical plate of the condensate trough at the false bottom in condenser 2A.
~
DCP 82-2137 DCP 82-2137 removed the Unit 2 main condensate pump hotwell level
. trips by removing 2LS-0607 and 2LS-0634 from the_ pump breaker trip circuits.
15
Change Number Descriptive Sumary
= -
DCP 83-2033 DCP 83-2033 removed the high pressure alarm from the condensate pumps.
2P2A, 2P28, 2P2C, & 2P2D seal water system, leaving the low pressure alarm intact. High pressure transients were mitigated by pressure relief valves set for 50 psig are currently in use.
This DCP affected FSAR Figure 10.4 (sheet 1 of 4).
5 1
x i
-16 L __