ML19282A788
| ML19282A788 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/28/1979 |
| From: | Green H TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18024A702 | List: |
| References | |
| NUDOCS 7903060501 | |
| Download: ML19282A788 (17) | |
Text
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TENNESSEE VALLEY AUTHORITY Division of Power Production 1
ANNUAL OPERATING REPORT BROWNS FERRY NUCLEAR PLANT January 1, 1978 - December 31, 1978 Docket Numbers 50-259, 50-260 and 50-296 License Numbers DPR-33, DPR-52 and DPR-68 Submitted by Chief, uclear Generation Branch Submitted by q9,03D f
(^>D %
Plant Superintendent
TABLE OF CONTENTS Page Plant Mcdifications Summary..............................
1 Occupational Exposure Date............................... 17 Effluent and Waste Disposal Annual Report.................
18 Fatigue Usage Evaluation................................. 32
PLANT MODIFICATIONS
SUMMARY
January 1, 1978 - December 31, 1978 Modification Safety Evaluation ECN L2077 - High Pressure Modified the lift rod linkage in the control valve Coolant Inj ection - Units 2 linkage assembly on the HPCI turbines of units 2 and and 3 3.
The ECN was completed.
The modification reduced the bending loads on the lift rods to an acceptable level, thus increasing the reliability and availability of the HPCI turbine.
P0056 - Primary Containment Installed potting compound in electrical connectors ic Electrical Penetrations -
unit 3 on the drywell side of penetration. The FCN Unit 3 was completed.
The addition of the potting compound helped to water-pro 6f the connectors and increased their reliability.
ECN's L2020, P0001 -
Installed redundant recirculation pump trip breakers and Reactor Recirculation -
logic on A and B reactor recirculation pumps.
Per-Units 2 and 3 formed iner tion and post-modification testing on the reactor recirculation pump trip system. Both the ECN's were completed.
The USQD stated that the" change was necessary to avoid or mitigate EOC derates and improve safety."
DCR 1656 - Reactor Installed a vertical restraint on a 1-inch sensing Recirculation - Unit 3 line coming of f number 19 and 20 j et pump recirculation risers. The DCR was completed.
The restraint eliminated a vibration problem and improved the reliability of the system.
BF DCR CC#1 - Fuel Replaced up to 168 7 x 7 fuel assemblies with 8 x 8 Handling and Storage -
fuel assemblies in units 1 and 2.
The core component Units 1 and 2 DCR was completed.
The 8 x 8 fuel assemblies are interchangeable with the 7 x 7 fuel assemblies and will provide superior performance.
ECN L1931 - Control Rod Installed piping to loop the south eud of the control Drive - Units 2 and 3 rod drive scram headers and piping and valves for flushing connections. The ECN was completed.
The modification did not affect the ability of the control rod drive system to operate as designed. The design margin of safety was not reduced.
I i i
Plant Modifications Summary January 1, 1978 - December 31, 1978 Modification Safety Evaluation ECS L2031 - Feedwater -
Installed additional supports for the X-29b instrument Unit 3 line in unit 3 drywell. The ECN was cenplerci.
The modification increased the reliabi!
- F-associated reactor vessel level instrunent in the case of a seismic event.
The change did not cffect any functional aspect of the instrument ot
't
~
operation.
ECN L2086 - Main Steam -
Replaced temperature recorder T3-1-1.
at b:N was Unit 3 completed.
The m>dification did not affect the operatict cf tLe main steam relief valves.
It improved t!c operstor's abili:y to monitor the system.
ECS L1862 - Sertron Provided authorization for the use of the Equ rc Manitoring - Units 1, 2 type K switch as replacerant part for exist $ng GL and 3 neutron monitoring bypass switches 7A-S3, S4A, S40, and 7B-52, S3B, and S3A.
The switch changeout will be performed as maintenance on an as-needed basis. All work covered by the ECN was approved to work as necessary.
The replacement switch equal; ar excce s rew ir; a
+
m ments and specificatiens of the original switch ahicu is no lenger being manufactured.
ECN L1967 - Reactor Peplaced exieting recircriation flow transmitters Recirculation System -
FT-68-5A, 5B, CLA and BlB with Rocecont tranatitters.
Unirs 2 13 The Ecstacnt transmitter is an acceptable substitute for the existing transmitter that is no lancar manufactured. The modification did not reduce the design margin of safety.
~. inc ic Ins alled an icprevcu t ir.e t t-n_ m. c t l a; s ur i zat ter - Unit 3 functica previously served by the CR2820 relays.
The ECN was completed.
The modification improved the reliability of automatic depressurization system.
._1
- kod Sequence ReplaceJ PS-85-61A and cl3 with electre _
s E
t' 1, 2, and transmitters and alarn switches The E','
s conpleted.
The modification improved the reliab;1its o"
~
t Rod Sequence Control Systua.
Plant Modifications Summary January 1, 1978 - December 31, 1978 Modification Safety Evaluation ECN P0166 - Neutron Removed 4 neutron monitors installed between the Monitoring - Unit 3 shroud and RPV wall of unit 3 and stored them tempo. rily in the unit 3 fuel pool. The ECN was completed.
The monitors had been installed as part of a test to measure the neutron flux in the core over a pre-scribed period of time.
The testing has been completed by General Electric. The modification affected no safety-related function.
ECN L1741 - High Pressure Replaced temporary valve PCV-73-43T2 with permanent Coolant Injection -
valve PCV-73-43.
The ECN was completed.
Unit 3 An overall gain in aystem availability was obtained.
The margin of safety was not reduced.
DCR 1250 - Main Steam -
Replaced the existing EC pilot solenoid 250V coils Units 2 and 3 with 270V coils on the main steam isolation valves.
The DCR was completed.
The modification should improve operational reliability.
It will not affect the safety-related aspects of the main steam isolation valves.
DCR CC #9 - Neutron Changed LPRM detectors' assemblies; and performed pre-Monitoring - Unit 3 and post-installation testing on LPRM detectors.
The (core component) DCR was completed.
The core componens design change had no effect on plant safety, performance, limits, or the design margin of safety.
ECN L1911 - High Pressure Installed new higher wattage resistors in the power Coolant Inj ection and supply to the HPCI and the RCIC turbine speed control Reactor Core Isolation circuits. The ECN was completed.
Cooling - Units 1, 2, and 3
The nodification increased the availability and reliability of both systems.
DCR 1338 - Main Steam -
Installed improved diaphragms (P/N 200463 Rl) in Unit 3 Target Rock relief valve air operators. The DCR was completed.
t This modification assured that the original operability, reliability, and service life of the main steam rellef valve air operators can be maintained at least at t'Teir "as procured" levels. i h
Plant Modification Summary January 1, 1978 - December 31, 1978 Modification Safety Evaluation ECM L1990 - Control Rod Drive - Removed the control rod drive hydraulic 11ne tv-Unitu l and 2 reactor vessel nozzle safe end and replaced it with a cap.
Rerouted the 4" control rod drive return line froa the reactor pressure vessel to cFt rcccier water cleanup system.
Performed post-ncJiffection testing to access the system performance.
Tha ECh was completed.
Major components in the control rod dri
%. ster remained unchanged. Only the operating moden o n-slightly different due to the rercutine cf th< ret':rn liae.
The operating characteristics of the syster are not changed with respect to accidents
' tr umient DCR 541 - RER Service Relocated residual heat removal service ester ca Water - Unit 3 valves on top of residual heat renoval heat exchanger to allow for easier heat exchanger head removal. The DCR was completed.
The modification does not affect the functien of the vents.
It eliminates the cutting and rewelding of the heat exchanger vent lines each time :
heat exchanger head has to be removed.
It has no effect on design safety.
DCR 1608 - Radioactive Installed threaded bushings f or Icw-level cask cover Waste Cask - Ccercn head bolts for radicactive waste cask BS-33-130.
The DCR was completed.
The modification restores the integrity of the cask and coes not affect any other system or cenpenent.
T C': Pn!!5 - Fuci Pandlini Installed 13 base stprort pictc, in *be n't in-
- L4:1t i spent fuel pool.
The FCN was not ccer"
- Ihe bases rest on the spent fuel pool floor line' ithout mechanical attachments. The addition of the bases does not affect the spent fuel racks under any design basis event.
')
- :N itran Replaced carbon resistcrs R6 and R7 w'r5 a its 1, 2
resistors of equal value.
The DCR war c:
i c od.
ar 4 lapleuentation of this codification helped to irr- :ve
- Se reliability of the Intermediate Range Mrnitor systc n input to the reactor protection sy:m ' ihe Jtsign margin of safety was not reduced.
Changed setpoints for thm to110 wing: LIS-3-56 (A-D)
Units 1, 2, and 3 Contacts 1 and 2 frca 490" tc 470"; LIS-3-58 (A, Contacts 3 and 4 f rom 490" to 470"; LITS-3-58 (A, D)
Contacts 3 and 4 from 490" to 470".
The ECN was ccepleted.
_4_
Plant Modifications Summary January 1, 1978 - December 31, 1978 Modification Safety Evaluation ECN P0124 (Continued)
NRC review and approval of this Technical Specification change and its justification as based upon an analysis by General Electric verified that there was no resultant adverse effect on safety.
DCR 1564 - Condenser Removed the high temperature trips from the 4-kV Circulating Water - Common switchgear for units B and D.
The DCR was completed.
This modification is an interim fix until ECN L2057 can be implemented.
ECN P0081 - AC Auxiliary Changed the alternate power supply for 4-kV unit boards Power - Unit 3 3A, 3B, and 3C to cooling tower transformers "A" and "B" (cooling tower switchgears "B" and "D").
The ECN was completed.
Chang!ng the alternate power supply reduced the load on the common station service transformer and provided improved stability in the voltage levels at the safety-related equipment.
ECN P0064 - Primary Installed potting compound in safety-related electric.d Containment Electrical connectors on the drywell side of penetrations EA, EE, Penetrations - Unit 3 EC, EE, and EF in unit 3.
The ECN was not completed.
Potting these connectors improved their reliability and did not jeopardize or degrade the integrity of thu associated circuits.
P0074 - Reactor Recirculation The modification added a flange. connection to the Unit 2 Grinnell Snubbers on the Reactor Recirculation System which have the 4" double extra heavy pipe welded directly to snubber cylinder.
The ECN was completed.
The change was made to aid in the inspection and maintenance requirements and did not alter the operating characteristics or the reliability of the snubbers. !
Plant Modifications Summary January 1, 1978 - December 31, 1978 Mcdification Safety Evaluation ECN L1443 - Primary Increased the blower blade angle of all ten unit 2 Containment Cooling -
drywell cooling fans to 40. The ECN was completed.
Unit 2 Increasing the fan blade pitch angle prozioad more air flow to cool the drywell. The probability of an accident or safety-related equipment malftnction wa..
not affected.
ECN P0105 - Primary Determined the air flow rate for drywell fans sub-Containment Cocling -
sequent to changing the fan blade angle to 40.
g Unit 2 The ECN was completed.
This ECN was the post-modification testing for the work performed on ECN L1443.
The test result u
satisfactory.
ECN P0072 - Battery Boards -
Replaced CE type CLF Class J fuses with Shawmut Class Common J fuses in 250V DC circuits in Battery Boards 2, 3, and 4.
The ECN was not completed.
The original fuses were rated for AC operation oni, The replacement f uses arc rated for operation on up to 280V volts DC.
The probability of an accident or equipment malfunction important to safety was decreased.
ECS P0105 - Main Steam -
RV70A (TVA 1-501) discharge was reoriented from 30 linit 2 southeast of azimuth 82 15' to 30 northeast of azimuth 82 15'.
The ECN was completed.
The orientation of RV70A's discharge in no way affects safety valve eperability.
JC'.: '.. u; Cantainment Added an isolation anplifier between oxygen sers Atmospheric Monitoring -
n,E-76-42 and input amplifier 0 M-76-42.
New ser -:or 3
Unit 1 9}E-76-42wasinstalled.
The ECN was completed.
The addition of the amplifier prolonged the r
- e o the sensor and did not reduce the accurac:7 or reliability of the instrument.
ECM PG.,17 - Contair. ment Installed conduit and pulled cable to provide alternate
' -ic Meritoring -
H sensors in unit 2 drywell and torus.
Toe ECN 'us 9
Unit J completed.
The probability or censequences of an accident cc safety equipment malfunction was not increased.
Plant Modifications Summary January 1, 1978 - December 31, 1978 Modification Safety Evaluation ECN L1946 - Containment Installed two one-half inch vent lines with a double Atmosphere Dilution -
valve on each line in the unit 2 containment atmosphere Unit 2 dilution system. The ECN was completed.
This modification was necessary to enable a required integrated leak rate test to be conducted.
It did not affect the design safety margin.
ECN Ll728 - Reactor Replaced the 2B shutdown board room emergency supply Building Ventilation -
fan motor.
The ECN was completed.
Unit 1 The modification did not change the mode of operation or the availability of the electrical board room ventilation equipment.
ECN L2073 - Reactor Cut a penetration and installed 4" diameter pipe Building Structure -
stud with internal and external isolation valves to Unit 2 ensure proper containment isolation. The pipe carries air and water for a unit 2 torus modification. The ECN was not completed.
The modification did not violate secondary containment.
The use of the sleeve is necessary to allow modifications and maintenance work required to ensure safe operation of the plant.
ECN L8021 - Standby Gas Installed the internal wiring to provide low flow alarm Treatment - Common circuitry for standby gas treatment blower "C".
The ECN was completed.
This modification did not increase the possibility of an equipment malfunction. It provided the operator with a standby gas treatment train "C" 16w flow annunciation.
ECN P0088 - 161-kV Added 161-kV capacitor banks, auxiliary relay systen Switchyard - Common and controls to the Athens 161-kV line to improve voltage stability. The ECN was completed.
The change improved the margin of safety by improving the voltage stability and reliability of the offsita power supply.
Plant Modification Summary January 1, 1978 - December 31, 197E Modification Safety Evaluation LCN P0063 - Prirary Spliced conductors aroun 1 connector J 3 be t 1: sid e r 'd Ccntainment - Unit 3 outside primary centain:acnt for TE-64-52A and IE-64-52C on electrical penetration CB.
The ECN was conpleted.
Implementation of the FCN did not incre m the probability of occurrence or the censeltences of 9:
accident or malfunction of equipment itpartant to safety previously evaluated in the FdAR er create a different type than previously evaluated.
P0047 - Fire Protection Modified the initiation circuits for the spricklcr and Systems - Common C0 fire protection systems in spreading rocmo a and B 9
to'make sprinklers the autcmatic pr imary cvstea an.1 th-CO the manual backup systen.
The EC was cor a l e t ed.
2 This change allows for greater personnel safety. The high pressure water fire protection system is at least as reliable as the CO, system. The CO, fire protectior system remains operable.
The design safety margin was not reduced.
ECN L'124 - Ceaiensate Removed a Y-connection emi installed a blind flange on Storage end Surply -
the condensate storage and supply header 20-inch line Unit 2 and new piping on the 24-inch line.
The ECN was not completed.
The probability of a pipe break is greatly reduced and, thus, system reliability is enhanced. The modification improved the integrity of the piping inside the reactor building.
ECN L1824 - CO, Fire Replaced the 2-ainute timer with a 4-minute ti mr for Pn
-i Gir 3 the CO EI ##C'5C" "78''
U
'IC'"'
2 Ihe new timer in no way reduced the availability of the CO system nor did it changt the minimum storage tank 2
requirements. The dc3_gn margin of safety ;me not reduced.
EC'T s L1070, P0102 -
Installed piping te vent the reactor p:e n,to se
"(_:tcr Pressure Vesscl -
when it is completely filled with water Remo v e check
_ cit.
valve 10-518 from the react or pressure vessel drain veut line to f acili tate cor tainment integrated laak rat.
test ventin2 in and out of reactor pressure veasel.
The ECN's were completed.
The probability cf occurrence or the enneequer 'es of an accident or malfunctica of equipment import + r to safety are not increaseo by implementation of f "a EC.4 '
-s-
Plant Modifications Summary January 1, 1978 - December 31, 1978 Modification Safety Evaluation BF DCR CC #7 - Fuel Machined two holes i., the lower tie plate of each type 2 Handling Storage and and type 3 fuel assembly. The core component DCR was Supply - Unit 2 completed.
This modification helps reduce the flow-induced vibr -
tion of the core internals. Consequently, the fuel channel corner wear will be reduced. The design safety margin is not reduced.
ECN L1991 - Reactor Revised the supply and distribution ventilation duct Building Ventilation -
system for the main steam vault to icprove the air flow; Units 1 and 2 thus, reducing the operating temperature of the vault.
The ECN was not completed.
The modification greatly reduced the possibility of spurious MSIV closure due to high temperatures caused by poor ventilation. The design safety margin was not reduced.
ECN L1805 - Control Bay Added three-way valves to the control bay chilled water Heating, Ventilation and system. The ECN was completed.
Air Conditioning - Unit 3 The change from two-way valves to three-way valves increased the reliability of chiller operation so that system reliability is increased.
ECN's Ll701, L1763 -
Modified the trip circuit on standby liquid control Standby Liquid Control -
pumps 2A and 2B to remove load shedding logic.
Unit 2 The ECN was completed.
The modification assured compliance with the Final Safety Analysis Report and did not introduce any new potential failure modes to the standby liquid control system.
DCR CC #8 - Neutron Changed local power range monitor detector assemblies; Monitoring - Unit 2 installed new signal cable connectors; and, performed post-installation testing on the local power range monitor detectors. The core component DCR was completed.
The core component design change did not involve a change in any local power range monitor design specification. The design margin of safety was not reduced.
_9_
Plant Modifications Summary January 1, 1978 - December 31, 1978 Modification Safety Evaluation DCR CC #6 - Fuel Handling Modified a single blade guide to act as a transfer and and Storage - Common storage container for the neutron source holder. The core component DCR was completed.
The modification had no adverse effect on core reactivity and no ef fect on the ability to perform functional and suberitical checks on control rods.
ECh LM623 - Radiation This modification was in accordance with GE-FDDR ERl-418 Monitoring - Units 1 and 2 and provided inputs to the radiation release rate monitoring system computer panel to indicate the stack gas detector mode of operation. The ECN was not completed.
The modification did not reduce the margin of safety as defined in the basis for any technical specification.
ECN L1949 - Control Rod Replaced PdT-85-17 and 18 with Rosemont transmitters.
Drive - Unit 3 The ECN was completed.
The previously used transmitters were obsolete and parts were no longer available. Their replacement did not increase the probability or consequences of an accident or safety equipment malfunction.
ECN L1992 - Reactor Reworked the exhaust duct divisions at P-R5, elevation Building Ventilation -
621 and plastered over the removable concrete blocks Unit 1 at the south wall of the heat exchat.ger room, the west wall of the reactor water cleanup pump room 1A and the east wall of the reactor cleanup pump room 1B.
The ECN was not completed.
A small pcrtion of the work was accomplished to help resolve the overheating problem in the reactor water cleanup pump rooms.
The ventilation was not adversely af f ected and, when completed, the modification will bring actual flow rates into agreement with the designed flow.
ECN POOJ4 - Fucl Handling Removed all spent fuel storage racks, control rod racks and Storage - Unit 3 and associated bracing south of the refueling slot excepting the fuel rack centered on the west end of the refueling slot.
The ECN was completed.
Seismic qualification is retained for the remaining racks. The criticality margin of stored new or spent i
fuel is not increased.
Plant Modifications Summary January 1, 1978 - December 31, 1978 Modification Safety Evaluation ECN L1854 - CO Fire Performed post-modification testing of fire protection 2
Protection - Common panels25-328 and 329 which monitor fire protection detectors in the housekeeping areas of elevation 617' and in the elevation 606' mechanical equipment room.
Initiated the preaction sprinkler stations (2 each) supplying the elevation 617' housekeeping areas.
The ECN was completed.
Only the testing of the equipment was accomplished here.
The total modification improved the ability of the fire protection system to protect safety-related equipment.
"CN L1809 - Fire Added chain wheel operators to existing fire protecticn Protection - Common valves in areas not easily accessible in units 1, 2, and 3 of the reactor buflding. The ECN was not completed.
This modification allows more convenient and safer operation of the valves.
ECN L1976 - Fire Installed pressure-restricting devices on 1-1/2" fire Protection - Co= mon hose racks and hose reel outlets. Verified proper pressure settings. The ECN was completed.
The change implemented a commitment to the Nuclear Regulatory Commission to limit the pressure in the hose to a maximum of 75 psig so that non-expert non-fire department personnel can ef fectively handle the hose.
ECN L1978 - Fire Installed a sprinkler system and its associated contral Protection - Common equipment in all three units of the turbine building, elevation 586'; and the battery and battery board rooms, elevation 593'.
Energized the equipment and performed post-modification testing. The ECN was completed.
The modirication was necessary to meet a commitment to the Nuclear Regulatory Commission. The probability or consequences of an accident to safety-related equipment are not increased.
ECN L2084 - High Pressure Enlarged the size of the existing drains in cable Fire Protection - Common spreading rooms A and B to accommodate the design drainage load following actuation of the spreading room sprinkler system. The ECN was completed.
The addition of greater drain capacity helps assure that the use of the high-pressure fire protection system in the spreading rooms will not result in damage to safety-i related equipment.
I
Plant Medifications Summary January 1, 1978 - December 31, 1978 Modification Safety Evaluation ECN L2051 - Main Steam -
Modified the main steam safety / relief valves by enlargine Units 1 and 2 the throat diameters to 5.125" plus 0.005" minus 0.CE0":
installing new seat rings and discs; and chinga.g out the piston on all stems with acme threads.
The ECN was completed.
The implementation of the ECN did not incrcase the probability of occurrence or the consequences of ar accident or malfunction of equipment important to safety previously evaluated in the Safety Analysi-- Repcrt.
ECN L1973 - bbin Steam -
Installed two rams heads with supports end 'ailpitr Unit 1 into the unit 1 torus.
The ECN was corpinted-The modifications were limited to the physical instal-lation of the piping and supports.
No physical tie-in or interaction with any system was implemented by this ECN.
ECN L1730A - Postul,ted Installed a 22" sleeve and hanger around 18" residual Pipe Break outside heat removal containTent spray piping.
Ine ECN wa' Containment - Unit 1 completed.
The addition of the sleeve and hanger had no effect on the safe operation of the,lant and the margin of cafety during a rupture of the residual heat removal system piping was improved.
ECN L9973 - Standts Diesel Installed the logic required to shut down the diesel Generatore - Units 1, 2, generator battery exhaust fans upon receipt of a CO, and 3 discharge actuation signal. The ECN was ^c.pletei The ecdificatica did not increase the arc ailit:
t.
s accident or safety-related equipment ctal func t i c n.
ECN L1977 - Fire Protection -
hedified the spreading rooms sprinkler station, by con-Cerntn verting the manual supply valves to remote 'pe rnt t.i solenoid valves. The ECH was ccepicted.
The replacement cf the manual valves la n<
v ;y ti neat a cer nitment in St pplement 2 of the c.: clear Regula-tory Cornission Safety Evaluation Report.
.he proba-bility or consequence of an accident or safet, ecoprent malfunction is not increased.
Plant Modifications Summary January 1, 1978 - December 31, 1978 Modification Safety Evaluation ECN L1451 - Associated Wired spare primary containment isolation system relay Electrical System - Unit 1 contacts in panels 9-15 and 9-17 to provide an input to the sequential events recorder. Added cables and a sequential recorder card. The ECN'was completed.
The modification did not affect any safety consideration.
The possibility of a malfunction or accident is not increased.
ECN LM200 - Core Spray -
Install two polished sodium chloride (chromate) pumps and Unit 3 associated pressure sensing lines. The ECN was not completed.
The two new pumps are redundant and have separate power supplies. The possibility for a different type of accident or malfunction is not created. The design safety margin was not reduced.
ECN Ll663 - Reactor Added a support for the X-28 reactor water level instrument Recirculation - Unit 1 pipe in the unit 1
- < ell.
The ECN was completed.
The addition of the support did not affect the operction or function of the associated instrumentation.
ECN's L2064 and L1496 -
Removed the valve discs from valves FCV-23-34, -40, -46, RHR Service Water -
and -52 and replaced them with V-notch discs. The valve Unit 1 seats were also replaced. The ECN was completed.
The modification did not affect the design function of the valver; however, it did help the valves operate more reliably and without chatter in a high discharge pressure environment.
DCR CC #5 - Neutron Changed the local power range monitor detector assemblies, Monitoring - Unit 1 installed new signal cable connectors and performed post.
installation testing. The core component DCR was com-pleted for unit 1.
The new detectors meet the same design specifications as those which they replaced. The change had no effect on plant performance, limits, or the design safety margin as defined by the operating license.
Plant Modifications Summary January 1, 1978 - December 31, 1978 Modification Safety Evaluation ECN L2072 - Feedwat.-r -
Installed new feedwater spargers with new singlc ring Unit I nozzles. Machined safc-ends to rerove cladd5n
- o that they would accept the new nozzles. The ECN was completed, implementing the ECN did not create the possibility for an accident or for a malfunction of a dif irent type than evaluated previously in the FSAR.
DCR CC #2 - Fuel llandling Machined two bypass flow holes in the lower tie plate of and Storage - Unit 1 each type 2 and type 3 fuel assembly. This was part cf the corrective action for it. core instrument tute vitraticc problems. The core component DCR was completed.
The margin of safety as defined in the Cycle 2 Technical Specifications was not reduced by this modification.
It was extensively esiluated by NRC prior to the work t ing accomplished.
DCR CC #4 - Nuclear Boiler Renoved the neutron source holders from the reactor pressure Reactor - Units 1, 2, and vessel. The core component DCR was completed.
3 The minimum source range monitor count of three counts per seccad was maintained as required. There waa no adverse effect on the safety analysis for any cf the units.
ECN L1984 - Fire Protection Made a 4" tie-in to the 8" fire protection header and Systcn - Ccmmon blanked the tie-in line with a 4" isolation valve. The ECN was not completed.
The probability of an accident or safety-related equipment malfunctic n was not increased, f"N ' T
- w ccl Rod Isolated the CED 4" return line to the rc^
pren.cc r i'.
it ?
ve':scl and performed tc; ting to risess C B stem
'for-mance.
The ECN was cerapleted.
Maj.r components of the CRD system remain unchanged. The operating characteristics of the system relating to accidents and transients are not changed. TL Arpin of safety was not reduced.