ML20151Y621
| ML20151Y621 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/14/1998 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20151Y553 | List: |
| References | |
| NUDOCS 9809180294 | |
| Download: ML20151Y621 (200) | |
Text
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Enclosure 2 l
1 BSEP Report Describing Changes, Tests and Experiments 1
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p 9180294 980331 R ADOCK 05000324 PDR
TABLE OF CONTENTS TITLE PAGE NO.
Drywell Equipment Drain Tank E2-1 Main Steam Line Radiation Monitor Logic E2-2 Use of the Auxiliary Work Platform / Jib Crane Over Fuel E2-3 Clarification of the Safe Shutdown Analysis E2-4 Safe Load Path E2-5 Spared Breaker Description E2-6 Decommissioning of the Well Water System E2-7
_ Storage of Plant Records E2-8 Service Building Upgrade E2-9 ,
Radwaste Sample Station Secondary Coolers Vent Lines E2-10 Maintenance Rule, Allowable Repair Time E2-11 Main Turbine Description E2-12 New/ Spent Fuel Storage E2-13 Plant Process Computer Description E2-14 Spent Fuel Rack Criticality Analysis E2-15 Fire Protection Clarifications and Corrections E2-16 Standby Gas Treatment Systera Deluge System Operation E2-17 >
Radwaste Area Mobile Processiag Unit E2-18 Dctergent Drain Tank Filter Veni Valve Installation E2-19 Logic for Low Pressure Coolant Injection Valve Auto Close Circuit E2-20 Analog High Drywell Pressure Instrumentation E2-21 Emergency Diesel Generator Description E2-22 Torus Water Volume Calculation E2-23 Deletion of Response Time Testing Requirements per NEDO-32291 E2-24 Clarify ' Voltage' Class Raceway Identification E2-25
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Removal of Drywell Service Air Line Penetration E2-26 Spent Fuel Pool Support Equipment Update E2-27 Core Spray / Reactor Core Isolation Cooling Description Corrections E2-28 Standby Liquid Control System Description E2-29 Turbine Control System Description E2-30 Reactor Pressure Vessel Design Summary Report E2-31 Brunswick Engineering Support Section Organizational Chang. E2-32 Radioactive Source List Addition E2-33 Use of SIDTEC Condenser Tube Cleaners on Unit 2 E2-34 Environmental Qualification Program E2-35 Emergency Core Cooling System Injection Valve Stroke Times E2-36 Residual Heat Removal Pump Seal Cooling Description E2-37 Drip Shields for Motor Control Centers and Instrument Racks E2-38 Update to Fuel Type or Fuel Cycle E2-39 Transfer of Charcoal and Spent Resin E2-40 i
TABLE OF CONTENTS TITLE PAGE NO.
Residual Heat R.emoval System Description E2-41 Thermo-Lag as Combustible Loading for Unit 2 E2-42 Thermo-Lag as Combustible Loading for Unit 1 E2-43 Safety Relief Valve Description E2-44 Reactor Recirculation Flow Control Component inspectior/ resting E2-45 Main Condenser Tube Cleaning Catch Equipment E2-46 Main Condenser Tube Cleaning for Unit 2 E2-47 .
Emergency Core Cooling System Description Clarification E2-48 Waste Surge Tank Processing E2-49 Loss Prevention Unit Organization Title Cl .ges ~
E2-50 '
Drain Sump Level Instrument Numbering E2-51 j Average Power Range Monitor Channel Designation Correction '~
E2-52 :
Site Facility Building Layout Update E2-53 !
Main Condenser Tube Cleaning for Unit 1 E2-54 i Waste Collector Filter Aid Subsystem Status E2-55 i Update of High Pressure Coolant Injection / Reactor Core Isolation Cooling System E2-56 ,
Process Diagram Data to reflect Power Uprate !
Containment Isolation System and Standby Gas Treatment System Update E2-57 l Mop Water Disposal by Evaporation E2-58 Fuel Pool Holding Pump Seal Water E2-59 l Unit 2 Reactor Building Temporary Cooling E2-60 l
Intake Canal Diversion Structure Description E2-61 l Organization Change - Brunswick Engineering Support Section Technical Services E2-62 Combustible Loading Update - E2-63 !
Control Room Heating Ventilation Air Conditioning (HVAC) Description Update E2-64 l Control Building and Reactor Building HVAC Description Update E2-65 l Response Time Testing Link to Technical Specifications E2-66 l High Pressure Coolant Injection / Reactor Core Isolation Cooling System E2-67 !
Condensate Drain Piping-General Site Buildig Ventilation Descriptions E2-68 !
Xenon Stability Operational Design Guide and Conformance E2-69 Thermal Hydraulic Instability E2-70 '
Use of Nine (9) Rod Spent Fuel Rod Holder E2-71 Control Building Emergency Air Filtration E2-72 !
Auxiliary Boiler Refurbishment E2-73 Abandoning the Well Water System E2-74 Unit 2 Mechanical Vacuum Pump Trip E2-75 i Unit 1 Mechanical Vacuum Pump Trip E2-76 Containment Isolation Valve Closure Times E2-77 Reactor Shutdown from Outside the Control Room E2-78 u
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TABLE OF CONTENTS TITLE PAGE NO.
Associated Circuits - Environmental Qualification E2-79 Updated Final Safety Analysis Report Reference Number Change E2-80 Clearance and Equipment Tagging E2-81 Outage Management Practices E2-82 Suppression Pool Water Volumes E2-83 Inservice Testing Program E2-84 Rod Block Monitor E2-85 .
Low Power Range Monitor Power Supply E2-86 Emergency Core Cooling System Description E2-87 Automatic Depressurization System Logic E2-88 Residual Heat Removal, Shutdown Cooling Isolation Setpoint E2-89 Refueling Interlocks E2-90 Suppression Pool Water Volumes E2-91 Radwaste Building and Waste Handling Equipment E2-92 Electrical Distribution E2-93 Drywell Dome Flange Outage Protection E2-94 Core Spray System Process Diagram E2-95 j Condensate System Filters and Demineralizers E2-96 Control Room HVAC Chlorine Sensors E2-97 Non-Destructive Examination of Piping Welds E2-98 Unit 2 Un-interuptible Power Supply Cable Size E2-99 Central Access Portal Bui! ding E2-100 Turbine Valve Closure Scram Bypass E2-101 Reactor Recirculation System E2-102 Restoration of Updated Final Safety Analysis Report Historical Information E2-103 -
Control Rod Drive System E2-104 Reactor Water Cleanup System E2-105 Reactor Pressure Vessel Design Summary Report E2-106 Unit 2 Bypass System Capability with Power Uprate E2-107 B2Cl2 Core Operating Limits Report and Reload Design E2-108 Radiation Control Organization E2-109 i Solid Waste Processing E2-110 Emergency Response Facility Information System / Process Computer E2-111 Typographical Error for a Valve Number E2-112 Spent Fuel Storage Pools E2-113 Primary Containment Resistance Temperature Detector E2-114 2-El1-F009 Bonnet Pressure Equalization Line E2-115 Secondary Containment Isolation E2-116 Document Control Vault E2-117 Rod Block Monitor Description E2-118 lii
. ._ . _ . _ ~ . _ ___ _ . ._. . .. . .
TABLE OF CONTENTS i TITLE PAGE NO.
Site Fire Protection Features E2-119 Radwaste Building Ventilation E2-120 Corporate and Plant Organization Update E2-121 Reactor Core Isolation Cooling System Turbine Generated Missile Potential E2-122 Temporary Air Operated Pump for Detergent Drain Tank E2-123 Control Building Habitability E2-124 Quality Assurance Program Description Relocation E2-125 ,
General Editorial Corrections E2-126.
Containment Atmosphere Control System E2-127 Main Stack Radiation Monitor Response Time E2-128 Reactor Water Cleanup System Flow Rates E2-129 Emergency Core Cooling System Suction Strainer Replacement - Unit 2 E2-130 ;
B2Cl3 Reload Core Design . E2-131 Supplemental Spent Fuel Pool Cooling E2-132 Unit 2 Power Uprate Miscellaneous Changes E2-133 -
High Pressure Coolant Injection / Reactor Core Isolation Cooling System Valve E2-134 Types Containment Valve Descriptions _ __
E2-135 H20 2Analyzer Realignment E2-136 Drywell to Torus Vacuum Breakers E2-137 Primary Containment Temperature Detection E2-138 Unit 2 Ambertap Tube Cleaning System E2-139 High Pressure Coolant Injection Room HVAC E2-140 i Minor Updated Final Safety Analysis Report Clarifications E2-141 Refueling Bridge - Rigid Pole Hoist System E2-142 '
Update of Drywell Peak Temperature - Unit 2 E2-143 !
Control Room HVAC E2-144 5
Extemal Suppression Pool Bypass E2-145 Unqualified Coatings Inside the Unit 2 Primary Containment E2-146 1997 Operations Reorganization E2-147 Update of Refueling Accident for New Refueling Mast E2-148 i BICI1 Fuel Shuffle - Mid-Cycle Outage E2-149 ;
Drywell Venting Guidance E2-150 Service Water System In-Service Inspection Boundary Change E2-151 Radiation Protection and Health Physics Organization Changes E2-152 Radiation Monitor Descriptions E2-153 Residual Heat Removal / Core Spray Keep-Fill Setpoints E2-154 j Containment Atmosphere Control System Description E2-155 {
Control Room Chlorine Detector Response Time E2-156 l
Updaic of Drywell Peak Temperatures - Unit 1 E2-157
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TABLE OF CONTENTS '
TITLE PAGE NO.
Service Air Relief Valve Setpoint E2-158 Clarification of Controlling Standard NFPA STD 72E E2-159 Crack Arrest Verification System Abandonment - Unit i E2-160 Inservice Inspection Technical Report (0BNP-TR-001) E2-161 Emergency Cole Cooling System Response Time Testing Update E2-162 B2Cl3 Startup Test Results E2-163 Primary Containment Ventilation E2-164 1997 Site Reorganization E2-165 Fire Door Evaluation Results E2-166 Well Water System E2-167 Core Spray Room Sump Identification Numbering E2-168 Seismic Design Basis E2-169 Loss of Coolant Accident Analysis Results E2-170 >
Residual Heat Removal and Core Spray Suction Strainer Replacement - Unit 1 E2-171 Storm Water Level Reference Corrections E2-172 Fatigue Monitoring Program E2-173 Addition of Power Uprate Reference E2-174 Updated Description ofIntake Canal Diversion Structure E2-175 Update of Facility Plof Plan E2-176 Containment Atmosphere Dilution Vessel Pressure Control E2-177 Fuel Pool Cooling System E2-178 Detergent Drain Tank Processing E2-179 i Augmented Off-Gas System Operating Parameters Clarification E2-180 Trip Setpoint Revisions E2-181 Spent Fuel Shipping Cask Handling E2-182 ,
Clerical Change to Table Comment Numbering E2-183 Update for BlCl2 Core Reload E2-184 Control Building Heating Ventilation and Air Conditioning System E2-185 Diesel Fuel Storage Tank Room Fire Barrier E2-186 4 Unit 2 Torus Drain System E2-187 Unit 1 Torus Drain System E2-188 Over-Pressure Protection of Unit 2 Drywell Drain Sump Discharge Lines E2-189 Overpressure Protection of Unit 1 Drywell Drain Discharge Line E2-190 Control Room Annunciator Ring-Back Circuit E2-191 Reactor Cavity Floor Penetration Seals E2-192 Temporarily Disabling the Unit 2 Circulating Water Pump Trip E2-193 Fire Iktection Surveillance Test Frequency E2-194 Evaluation of Core Spray Minimum Flow Valve Operation E2-195 Heater Drain Pump Automatic Start Logic E2-196 Unit 2 Temporary Air Service E2-197 V
TABLE OF CONTENTS r TITLE PAGE NO.
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Unit 1 Temporary Air Service E2-198 Unit i Shutdown Cooling Bonnet Pressure Equalization Line E2-199 Air Purge of the Steam Jet Air Ejector E2-200 l "Smartstems" Testing for Motor Operated Valves E2-201
! Control Building HVAC Tornado Dampers E2-202 Failure of Drywell Equipment Drain Sump Pumps E2-203 Charcoal Testing of Control Room Emergency Ventilation Sys;em Filters E2-204 Fuel Oil Sampling E2-205 Decommissioning Space lleaters E2-206 Temporary Condensate Wash-Line E2-207 Temporary Hose for Unit 2 Torus Refill E2-208 Fire Protection Program E2-209 Check Valve Predictive Maintenance Program E2-210 Reactor Building Radiation Monitor Environmental Qualification E2-211 Discharge Canal Level Control E2-212 I
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CHANGES TO THE FACILITY .
TITLE: Drywell Equipment Drain Tank BRIEF DESCRIPTION:
l A temporary change was installed to bypass the failed Unit 2 Drywell Equipment Drain :
Tank lowlevel switch.
SUMMARY
OF THE SAFETY EVALUATION:
The t.vailable indication still supported the Technical Specification Drywell leakage ,
determinations.
i PLANT
REFERENCE:
96FSAR027, ESR 9600352 l
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CHANGES TO THE FACILITY TITLE: Main Steam Line Radiation Monitor Logic BRIEF DESCRIPTION:
The Main Steam Line Radiation Monitor High High radiation or inoperable signal will be removed from both the reactor scram and Main Steam Isolation Valve closure circuit.
SUMMARY
OF THE SAFETY EVALUATION:
Technical Specification Amendments 176/207 were issued March 31,1995, to support this change.
PLANT REFERENCE; 96FSAR090, PM 92-147,97FSAR068, and 97FSAR069 i
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E2-2
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I CHANGES TO THE FACILITY TITLFJ Use of the Auxiliary Work Platform / Jib Crane Over Fuel BRIEF DESCRIPTION:
The evaluation allows the use of the auxiliary work platform / Jib crane over fuel. !
SUMMARY
OF THE SAFETY EVALUATION: -
The auxiliary platforms jib cranes have a maximum allowed capacity of 500 lbs each, which is less than what is evaluated for as a heavy load.
i PLANT
REFERENCE:
96FSAR100, EER 94-0098 Rev. 8 5
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E2-3
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TITLE: Clarification of the Safe Shutdown Analysis BRIEF DESCRIPTION:
Added clarification and details of certain sections of the safe shutdown analysis, that are incorporated by reference into section 9.5 of the Updated Final Safety Analysis Report (UFSAR).
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SUMMARY
OF THE SAFETY EVALUATION:
i Additional detail was provided for clarification.
PLANT
REFERENCE:
96FSAR106, ESR 95-01198 l
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l CHANGES TO THE FACILITY TITLE: Safe Load Path BRIEF DESCRIPTION:
I The safe load path drawing 81020-M-001, in the UFSAR by reference, was revised to comply with the path given in procedure OSPP-FUE501 and NED GEAR BPN-033032 issued September 26,1990.
SUMMARY
OF THE SAFETY EVALUATION:
The safe load path reference was updated to match plant procedures. ;
1 PLANT
REFERENCE:
96FSAR108, OMMM-015 Rev. 4 and 5 l
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E2-5
CHANGES TO THE FACILITY TITLE: Spared Breakers Description BRIEF DESCRIPTION:
DC breakers GF8 and Un-interruptible Power Supply (UPS) panel 2A Ckt. 5 were spared as the circuits are no longer used to support replacement ofcirculating water pump motors
SUMMARY
OF THE SAFETY EVALUATION:
The plant drawings were updated to reflect the breakers as spares.
PLANT
REFERENCE:
96FSAR109, EDP 92-014 Rev. I 1
l E2-6 l l
CHANGES TO THE FACILITY TITLE: Decommissioning of the Well Water System :
PRIEF DESCRIPTION:
The Well Water system has been decommissioned as a source of water for the fire protection tank. The county system supplies the fire protection tank.
SUMMARY
OF THE SAFETY EVALUATION:
The description was updated to reflect that well water is no longer used.
4 PLANT
REFERENCE:
96FSARI 12, ESR 95-00430 l
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E2-7
i CHANGES TO THE FACILITY TITLFa Storage of Plant Records BRIEF DESCRIPTION- '
Carolina Power & Light (CP&L) Company's, Brunswick Steam Electric Plant (BSEP) has implemented optical disk and magnetic tape storage of plant records.
SUMMARY
OF THE SAFETY EVALUATION:
This method was reviewed, and concurred with in the NRC's July 7,1988, letter to CP&L.
PLANT
REFERENCE:
96FSAR132 l
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- CHANGES TO THE FACILITY TITLE: Service Building Upgrade BRIEF DESCRIPTION:
This revision reflects the relocation of the following facilities that were formally located in the service building: the lunch room, clothes handling and storage room, laundry, and first aid room. The building now includes chemistry and radwaste shipping offices, rooms for instruments, radiation survey instrument calibration, and respirator decontamination.
1
SUMMARY
OF THE SAFETY EVALUATION: ,
The relocation of support functions to or from the service building does not affect the
]
design, function, or qualification of the services provided or their ability to perform their '
intended functions. .
PLANT REFERENCE- 96FSAR135 i
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E2-9 ,
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o CHANGES TO THE FACILITY TITLE: Radwaste Sample Station Secondary Coolers Vent Lines BRIEF DESCRIPTION:
i Vent lines were installed for the radwasce sample station secondary coolers in order to provide a simpler and more thorough method of venting the chilled water lines. The figure also shows the new sample station installed by ESR 94-00227. '
SUMMARY
OF THE SAFETY EVALUATION:
The change made to the radwaste sample station involves non-safety related equipment located in the Radwaste Building. i PLANT
REFERENCE:
96FSAR139, ESR 96-00037 e
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9 ++- - - - ,
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' TITLE: Maintenance Rule, Allowable Repair Time
( BRIEF DESCRIPTION:
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' The change clarified the allowable repair time rules impact on safety system preventive maintenance.
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SUMMARY
OF THE SAFETY EVALUATION:
The clarification to the work scheduling process is in accordance with Maintenance Rule requirements associated with 10 CFR 50.65 and NUMARC 93-01 Rev. 2, which is endorsed by Regulatory Guide 1.160, Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.
PLANT
REFERENCE:
96FSAR140 i
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CHANGES TO THE FACILITY TITLE: Main Turbine Description BRIEF DESCRIPTIONJ The text dealing with the discussion of the Main Turbine was clarified, including the turbine gland seal system.
SUMMARY
OF THE S AFETY EVALUATION:
Text was clarified.
PLANT
REFERENCE:
96FSAR145, ESR 95-00238, OSP-96-003 E2-12 l.
CHANGES TO THE FACILITY TITLE: New/ Spent Fuel Storage BRIEF DESCRIPTION:
f The description was updated to reflect the current configuration and processes associated
. with the refueling ficor crane, fuel preparation machine, fuel pool capacity for storage of control rods, fuel pool cooling, spent fuel shipping cask, and vessel disassembly.
SUMMARY
OF TIIE SAFETY EVALUATION:
The configuration and process changes made are not iaportant to safety or accidents evaluated in the UFSAR.
i
. PLANT REFERENCE- 96FSAR168, OSPP-RPV501
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I CHANGES TO THE FACIL,lTY TITLE: Plant Process Computer Description BRIEF DESCRIPTION:
General editorial changes and corrections to typographical errors were made to the plant process computer description.
SUMMARY
OF THE SAFETY EVALUATION:
The changes were editorial in nature or enhanced the description of the plant process computer.
P_LANT
REFERENCE:
96FSAR172 1
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E2-14
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CHANGES TO THE FACILITY TITLE: Spent Fuel Rack Criticality Analysis BRIEF DESCRIPTION:
The changes clarified that referenced enrichments do not constitute design basis. .
SUMMARY
OF THE SAFETY EVALUATION:
The change provided additional clarification to the description.
PLANT
REFERENCE:
96FSAR175, OSP-96-003 l
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CHANGES TO THE FACILITY )
TITLE: Fire Protection Clarifications and Corrections BRIEF DESCRIPTION: !
The change involved editorial changes to correct or clarify existing fire protection and lighting information/ descriptions, to be consistent with plant configurations and processes.
SUMMARY
OF THE SAFETY EVALUATION:
The change involved editorial changes to correct or clarify existing fire protection and lighting information/ descriptions, to be consistent with plant configurations and processes.
P_LANT
REFERENCE:
96FSAR178, OSP-96-003 i
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E2-16
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CHANGES TO THE FACILITY l
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- TITLE
- Standby Gas Treatment System Deluge System Operation 4
i BRIEF DESCRIPTION: i 1
i j This change reflects the modified operation of the Standby Gas Treatment (SBGT) }
l System charcoal filter deluge system from automatic to manual actuation. Also a j description ofcable spreading room sprinkler systems was included. ;
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SUMMARY
OF TlIE SAFETY EVALUATION: j 1
t The modified operatien isolates the suppression system in order to prevent spurious !
operation of the system during an accident for which SBGT is required to operate.
l Wetting the charcoal bed would render a SBGT train inoperable. The accident under :
j consideration is a fire in the charcoal filters. The evaluation demonstrates that the change !
will not impact the ability to control a fire.
! i PLANT
REFERENCE:
96FSAR191, ESR 96-00d57, ESR 97-00443
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E2-17 !
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n CHANGES TO THE FACILITV i TITLE: Radwaste Area Mobile Processing Unit BRIEF DESCRIPTION:
I-The change replaced temporary piping and components with permanent process piping '
for the Radwaste Area Mobile Processing Unit.
SUMMARY
OF THE SAFETY EVALUATION: ;
This change upgraded the temporary piping and components for the Radwaste Area l
Mobile Processing Unit. The system is not safety-related.
PLANT
REFERENCE:
96FSAR203, ESR 96-00031 !
E2-18 >
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! i CHANGES TO THE FACILITY TITLE: Detergent Drain Tank (DDT) Filter Vent Valve Installation l BRIEF DESCRIPTION: !
r A vent valve was installed on the DDT filter housing cover.
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SUMMARY
OF THE SAFETY EVALUATION-The DDT filter is not safety related equipment. :
PLANT
REFERENCE:
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i CHANGES TO THE FACILITY TITLE: Logic for Low Pressure Coolant Injection (LPCI) Valve Auto Close Circuit l
BRIEF DESCRIPTION:
This change deleted the low reactor pressure vessel pressure permissive for Residual Heat Removal (RHR) El1-F015A/B valves.
SUMMARY
OF THE SAFETY EVALUATION:
The permissive was in series with the limit switches from the El1-F008 and El1-F009 valves which was intended to provide verification that RHR is in the Shutdown Cooling mode. Since the logic for the El1-F008 and El1-F009 valves prevents the valves from being open when the reactor pressure vessel pressure exceeds 133 psig, the additional ;
pressure permissive in the LPCI auto-close logic is redundant. '
l PLANT
REFERENCE:
97FSAR001, ESR 96-00684 1
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E2-20
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' CHANGES TO THE FACILITY TJ_Tgi; . Analog High Drywell Pressure Instrumentation BRIEF DESCRIPTION: l l
This was an editorial change to reflect that pressure switches used to detect high drywell pressure were replaced by transmitter / trip units. l t
SUMMARY
OF THE SAFETY EVALUATION: :
This was an edito.ial change. ,
PLANT
REFERENCE:
97FSAR002, PM 77-268G, PM 77-269G >
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i E2-21 i
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TITLE: Emergency Diesel Generator Description BRIEF DESCRIPTION-Changes updated the UFSAR to reflect "as-built" design features, i f
SUMMARY
OF THE SAFETY EVALUATION: ;
No design changes were made; additional detalk were added and descriptive changes were made to reflect the current design features.
i PLANT
REFERENCE:
97FSAR003 P
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CHANGES TO THE FACILITY IITLE: Torus Water Volume Calculation BRIEF DESCRIPTION:
Calculation OMISCEL-0009 determined new torus volumes associated with the Technical Specification high and low water levels of-27" and -31".
t
SUMMARY
OF THE SAFETY EVALUATION: i The reduction in the minimum and increase in the maximum water volumes on the torus response to the design basis loss of coolant accident (LOCA) has been evaluated and does not cause accident parameters to exceed acceptable values.
'l PLANT
REFERENCE:
97FSAR004, CR 96-02937 F
1 E2-23
l L i-l l i CHANGES TO THE FACILITY !
TITI,E: Deletion of Response Time Testing Requirements per NEDO-32291
- BRIEF DESCRIPTION:
This change captured the instrumentation response time requirements dictated by NEDO-32291. ;
SUMMARY
N THE SAFETY EVALUATION:
Boiling Water Reactor Owners Group (BWROG) Licensing Topical Report NEDO- l 32291-A, " System Analysis for Selected Response Time Testing Requirements," was ,
approved by the NRC in December 1994.
PLANT '
REFERENCE:
97FSAR005, BWROG NEDO-32291 l
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E2-24 ;
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CHANGES TO THE FACILITY TITLE: Clarify ' Voltage' Class Raceway Identification BRIEF DESCRIPTION:
Additional information was added to aid in decoding the racewhy identification coding. 1 i
SUMMARY
OF TIIE SAFETY EVALUATION:
l Clarification was added to aid in decoding raceway identification coding.
PLANT
REFERENCE:
97FSAR006 i 1
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L CHANGES TO THE FACILITY TITLE: Removal of Drywell Service Air Line Penetration BRIEF DESCRIPTION: !
This change updated UFSAR ser tion that had not been previously revised to reflect the !
removal of the drywell service air ibe penetration. ;
SUMMARY
OF THE SAFETY EVALUATION:
This change revised additional UFSAR sections to reflects plant field conditions, -
resulting from the earlier removal of the drywell service air line penetration. ;
PLANT
REFERENCE:
97FSAR007, ESR 95-00212 l
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E2-26
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CHANGES TO THE FACILITY ,
TITLE: Spent Fuel Pool Support Equipment Update [
BRIEF DESCRIPTION: 4 Revixd figure to delete the reference to the portable platfonn that could be mounted from the spent fuel pool curb. Spent fuel pool control rod wall brackets are not required .
because of curb-mounted hooks. The worktable / platform is not needed because handling / cutting of highly radioactive components can be performed successfully without it. Auxiliaryjib cranes are not needed to handle the work tables since they have been removed. Minor editorial corrections / changes have been made to refueling floor activities and equipment use !
SUMMARY
OF THE SAFETY EVALUATION:
The platform, only referenced on the UFSAR figure, is clearly identified as a portable and removable platform Removal of this platform does not affect the design, ftuction, or method of performing spent fuel pool functions that would be called upon to support operation without undue risk to the public health and safety.
PLANT
REFERENCE:
97FSAR008, ESR 97-00045 I
l E2-27
CHANGES TO THE FACILITY TITLE: Core Spray / Reactor Core Isolation Cooling Description Corrections BRIEF DESCRIPTION:
Discussion of Core Spray (CS) and Reactor Core Isolation Cooling (RCIC) systerns had minor description errors that were revised to reflect existing plant design.
SUMMARY
OF THE SAFETY EVALUATION:
Minor corrections have been made to the UFSAR to make it consistent with existing plant design.
PLANT
REFERENCE:
97FSAR010 l
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E2-28
I i:L CHANGES TO THE FACILITY f
TITL_E; Standby Liquid Control (SLC) System Description E_RIEF DESCRIPTION:
Minor editorial corrections to the UFSAR description were made to reflect existing plant design
SUMMARY
OF THE SAFETY EVALUATION:
Minor editorial corrections were made to the UFSAR description.
"1 PLANT
REFERENCE:
97FSAR011 ,
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E2-29 I l
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CHANGES TO THE FACILITY TITLE: Turbine Control System Description BRIEF DESCRIPTION: ,
Minor editorial corrections to the UFSAR description were made to reflect existing plant design. ;
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SUMMARY
OF THE SAFETY EVALUATION: :
The change addressed minor editorial corrections.
PLANT
REFERENCE:
97FSAR012 f
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i CH ANGES TO THE FACILITY TITLE: ' Reactor Pressure Vessel Design Summary Report BRIEF DESCRIPTION: :
A note has been added to Appendix 5.3A clarifying the use of the two temperature values (546 deg. F and 547 deg. F) used in the UFSAR for normal reactor operating temperature. .i
SUMMARY
OF THE SAFETY EVALUATION:
The small difference between the temperatures is insignificant relative to the resultant thermal and pressure stresses in the reactor pressure vessel. Also these temperatures are well below the reactor design temperature of 575 deg. F. Therefore there are no safety concerns relative to this change. ;
PLANT REFERENCFI 97FSAR013 i
r b
5
)
I 1-k l
E2-31
=.. _ _ __ --. . .- -
l l
l l
l L ..
l CHANGES TO THE FACILITY TITLE: Brunswick Engineering Support Section (BESS) Organizational Change BRIEP DESCRIPTION:
' The change reflects the realignment of the BESS organizational structure as required to efficiently face current and future challenges.
SUMMARY
OF THE SAFETY EVALUATION:
The organizational change does not alter the manner in which engineering activities are perfornied, only the reporting structure has been modified.
PLANT
REFERENCE:
97FSAR014, EGR-NGGC-0001 Rev,2 E2-32
.- - . . - - . . .~. ~ - . . .- . - - - - .- . . . ---
i CHANGES TO THE FACILITY TITLE: Radioactive Source List Addition BRIEF DESCRIPTION:
A radioactive soure' list has been added to Chapter 12.2 for sources >100 pei.
SUMMARY
OF THE SAFETY EVALUATION:
This change added a list of radiation sources that are already in use at the plant. This is consistent with Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants.
PLANT
REFERENCE:
97FSAR015 1 l
l l
I i
1 i
E2-33
\
4 CHANGES TO THE FACILITY TITLE: Use of SIDTEC Condenser Tube Cleaners on Unit 2 ,
BRIEF DESCRIPTION: ,
This change documented the use of SIDTEC Condenser Tube Cleaners on Unit 2 in
. addition to the sponge rubber balls in the Amertap condenser tube cleaning' system.
SUMMARY
OF THE SAFETY EVALUATION.;
Per UFSAR Section 10.4.5 the complete outage of the condenser Circulating Water i system will not result in the loss of any service essential to reactor safety. ,
i PLANT
REFERENCE:
97FSAR016,2SP-97-201
~
E2-34 I
r
.. _ _ . . . ~. . . _ - . . - - _ _ _ . . _ _ . . _
i CHANGES TO THE FACILITY .
TITLE: Environmental Qualification (EQ) Program BRIEF DESCRIPTION:
t The UFSAR EQ Program description was rewritten to reflect the existing program.
SUMMARY
OF THE SAFETY EVALUATION:
The change provided clarification to the UFSAR EQ Program description.
l PLANT
REFERENCE:
97FSAR017 t-l l
l.
l l
l l
)
i l l
l
[
4 l
l l
E2-35 l
_ _ _. , _ .t
. . . . . _ _ . - - _- . . . . . - - _ . - . _ . - . . - . - . . - - _ _ - . . . ~
t P
CHANGES TO THE FACILITY TITLE: Emergency Core Cooling System (ECCS) Injection Valve Stroke Times BRIEF DESCRIPTION:
The SAFER /GESTER-LOCA analysis has revised system response times for ECCS systems in the event of a Design Bases Accident (DB A) LOCA, but the Section 7.3 values had not reflected the current system response criteria, and nominal / maximum values had not been consistently captured.
i
SUMMARY
OF THE SAFETY EVALUATION:
This revision provided consistency between various system descriptions within the UFSAR for LOCA response times as defined within the SAFER /GESTER - LOCA analysis.
9 PLANT
REFERENCE:
97FSAR018 l
l I
I l
l i
i E2-36 ;
I
t CHANGES TO THE FACILITY TITLE: Residual Heat Removal Pump Seal Cooling Description BRIEF DESCRIPTION:
The change provided clarification of the RHR pump seal cooling description.
SUMMARY
OF THE SAFETY EVALUATION:
Changes reflect existing plant conditions based on physical plant configuration and '
vendor prints.
PLANT
REFERENCE:
. 97FSAR019 -
k
+
l 1
1 l
1 4
r i E2-37 )
l
CHANGES TO THE FACILITY TITLE: Drip Shields for Motor Control Centers and Instrument Racks BRIEF DESCRIPTION:
Drip shields for motor control centers and Class 1 instrument racks may not always be
. necessary. The UFSAR was revised to indicate an evaluation to determine the need for a drip shield near water spray sources is acceptable.
9
SUMMARY
OF THE SAFETY EVALUATION:
i The change provided clarification that some locations without drip shields have beer previously evaluated as acceptable.
PLANT
REFERENCE:
97FSAR021 f P
4 i
E2 %. , , , . . - . , - - + - , - - -
l !
CHANGES TO THE FACILITY TITIJg Update to Fuel Type or Fuel Cycle BRIEF DESCRIPTION:
Section 15 has been updated to eliminate references no longer needed after outage BlC11. Additional references have been relocated to apprr;.riate parts of section 15.
- Original text implied the Control Rod Drop Accident (CRin) analysis had not been eliminated for 9X9 fuel design.
SUMMARY
OF THE SAFETY EVALUATION:
-The change added clarification to information already in the UFSAR or removed unused references.
ELANT
REFERENCE:
97FSAR022 l
4 E2-39
[.
CHANGES TO THE FACILITY TITLE: Transfer of Charcoal and Spent Resin BRIEF DESCRIPTION:
Transfer of spent Condensate Deep-bed Demineralizer resin to Condensate Backwash Receiving Tanks (CBWRT) provides greater flexibility and capacity during condenser leak events,. Transferring charcoal to the CBWRT uses larger lines which reduces potential plugging.
SUMMARY
OF THE SAFETY EVALUATION:
The transfers will occur within the radwaste building which will contain any spillage from th:: storage tanks or piping leaks that may occur. The systems being used to perform this transfer are designed to perform radwaste transfers.
PLANT
REFERENCE:
97FSAR023,00P-32.1 Rev. 45
)
)
l I
i l
E2-40 l
l
L CHANGES TO THE FACILITY TITLE: Residual Heat Removal System Description B_RIEF DESCRIPTION:
Minor corrections / enhancements to the UFSAR were made to make the RHR system description consistent with existing plant design.
SUMMARY
OF THE SAFETY EVALUATION:
Minor corrections / enhancements to the UFSAR were made to make the description consistent with existing plant design.
PLANT
REFERENCE:
97FSAR025 1
I i
E2-41
.- ~ . . _ . . . . . . . . .- . . - . - - - . . - . - . . . . . . - . . . - . - . - . -
1 l
l r
j CHANGES TO THE FACILITY ;
TITLE: Thermo-Lag as Combustible Loading for Unit 2 BRIEF DESCRIPTION:
. A Thermo-Lag reference was added as a combustible load. '
t
SUMMARY
OF THE SAFETY EVALUATION:
Combustible Loading Calculation 0-89-0001 addresses Thermo-Lag as a combustible load.
PLANT
REFERENCE:
97FSAR027, ESR 95-00127 -
l l
6 k
E2-42
. . . . - . . ~ . . _ . . _ _..._ _ . _ - _ _ . _ - _ _ _ _ . _ _ . . . _ _ _ _ . . ._.
L 3 l
CHANGES TO THE FACILITY l- \
l l TITLE: Thermo-Lag as Combustible Loading for Unit I
! l l
l \
BRIEF DESCRIPTION: 1 A reference to Thermo-Lag was added as a combustible load.
SUMMARY
OF Ti1E SAFETY EVALUATION:
Combustible Loading Calculation 0-89-0001 addresses Thermo-Lag as a combustible load.
PLANT
REFERENCE:
97FSAR029, ESR 95-00130 i
I l
E2-43
i l
f e
i CHANGES TO THE FACILITY !
TITLE: Safety Relief Valve Description BRIEF DESCRIPTION: i 1
UFSAR Figures have been revised to depict Main Steam line Safety Relief Valves used at BSEP, with a single solenoid verses two.
I
SUMMARY
OF THE SAFETY EVALUATION:
!. UFSAR Figures have been revised to reflect current field configuration of the Main Steam line Safety Relief Valves used at BSEP.
PLANT
REFERENCE:
97FSAR030 1
l I
i l
l l i
! I l
- l. E2-44 -
l
. _ _ . . ~.mm. _ _ _ . . . . - . . _ . _ . . _ _ _ . - . . _ . _ - _ . . _ . _ . . _ . _ . _ . . . _ . _ _ .
i i
l I
I l CHANGES TO THE FACILITY i i
Ti fLE: Reactor Recirculation Flow Control Component Inspection / resting 3RIEF DESCRIPTION: !
i i
The change allows tests and maintenance based on owner's operating history, based on I the use of the component in differing conditions and environments than those anticipated ~
by the vendor or based on new technologies.
l 4
SUMMARY
OF THE SAFETY EVALUATION:
l ,
I The change allows inspections and maintenance to be carried out generally in accordance !
with the manufacturers' instructions and good operating practice, and allows the use of ;
analyzed operating data as bases for changes to routine maintenance and inspections. !
PLANT
REFERENCE:
97FSAR031 -
}
l I
t I l 4
l.
)
a l
l E2-45 i i
?
i i
l l
CHANGES TO THE FACILITY II.TLE; Main Condenser Tube Cleaning Catch Equipment !
BRIEF DESCRIPTION; l
To support the collection of SIDTEC condenser tube cleaners, temporary floating booms j and related catch equipment are used in the discharge canal.
j
SUMMARY
OF THE SAFETY EVALUATION:
f The ability to maintain discharge canal level bands and the availability of the ultimate heat sink in support of normal and emergency plant operations is not affected. Per UFSAR section 10.4.5 complete outage of the condenser circulating water system will i not result in the loss of any service essential to reactor safety.
[
PLANT
REFERENCE:
97FSAR032 '
i i
l
[
1 i
i E2-46 :
P
l i
i i
F e
CHANGES TO THE FACILITY TITLE: - Main Condenser Tube Cleaning for Un;t 2 -
l BBIEF DESCRIPTION: l To support the temporary use of SIDTEC condenser tube cleaners on Unit 2 in addition to ;
the sponge rubber balls in the Amertap condenser tube cleaning system. i
SUMMARY
OF THE SAFETY EVAL,UATION:
f 3
i A complete outage of the condenser circulating water system will not result in the loss of j any service essential to reactor safety. j i
i l
PLANT
REFERENCE:
97FSAR033,2SP-97-214 -l i
I
?
i 1
l 1
E2-47
e,- !
i CHANGES TO THE FACILITY ,
i
- TITLE: Emergency Core Cooling System Description Clarification -
BRIEF DESCRIPTION:
l l
This change provided clarification for the ECCS descriptions. I 1
SUMMARY
OF THE SAFETY EVALUATION: l a
This change makes editorial changes to correct inaccuracies in the ECCS descriptions. j PLANT
REFERENCE:
97FSAR035 i i
,6 4
h i
i I
E2-48 l
J
i CHANGES TO THE FACIL,ITY TITLE: Waste Surge Tank Processing BRIEF DESCRIPTION:
This change reflected removal of temporary Waste Surge Tank recirculation line mechanical filter and installation of a permanent branch connection to allow for the i
installation of process equipment, if needed in the future.
l
SUMMARY
OF THE SAFETY EVALUATION:
The system is not classified as a safety related system.
f PI. ANT
REFERENCE:
s7FSAR036, ESR 9500341 l
r f, .
l l
E2-49
e CHANGES TO THE FACILITY
- TITLE: Loss Prevention Unit Organization Title Changes BRIEF DESCRIPTION:
Updatd Loss Prevention Unit organization to reflect title changes.
SUMMARY
OF THE SAFETY EVALUATION:
Updated Loss Prevention Unit organization to reflect title changes.
PLANT
REFERENCE:
97FSAR037,97FSAR167 l
l E2-50
-. . . . . . - . - . . _ . .- . . - _ . - - . . . = - ~ - - - - . . - . - . . . . - ~ . - . - .
?-
u L.-
L i f l t.
l CHANGES TO THE FACILITY l L -!4 TITLE: Drain Sump Level Instrument Numbering
( l BRIEF DESCRIFTION:
i i
Corrected radwaste floor drain sump and equipment drain sump level instrument numbers ,
L on the USFAR figure.
l 1
i
SUMMARY
OF THE EAFETY EVALUATION: !
Corrected to reflect the actual plant configuration.
i PLANT
REFERENCE:
97FSAR039 l
I 1
)
I a
l l
l I
I i !
l l
1 l- i E2-51 i
i .
s o
i CHANGES TO THE FACILITY i
! TITLE: Average Power Range Monitor Channel Designation Correction +
i i
BRIEF DESCRIPTION:
{
l The change corrected the typographical errcr on UFSAR figure 7.2.1.7 for APRM
. Channel designation. :
L >
SUMMARY
OF THE SAFETY EVALUATION:
The change corrected a typographical error.
' PLANT
REFERENCE:
97FSAR040 ;
l l
t 4
t I:
1 l
E2-52 f
, 4
. . - . - . .. - . . . . . ~ ..-. . -. - . = = .- - . . .- - . . - .
i k
CHANGES TO THE FACILITY l TITLE: Site Facility Building Layout Update BRIEF DESCRIPTION: ;
The Snubber Maintenance and Testing Shop, and Calibrated Tool Testing Shop were ,
included in the description of the site facility layout. '
f i
SUMMARY
OF THE SAFETY EVALUATION: i i
These facilities are outside the power block and the facilities are not related to plant i safety systems. j i
P_Is ANT
REFERENCE:
97FSAR041 1 l.
i h
'2 1
- i E2-53 j i
- - - ...-. - . - . ... _ .~. . .
k i
t CHANGES TO THE FACILITY TITLE: Main Condenser Tube Cleaning for Unit 1 -
BRIEF DESCRIPTION:
The UFSAR was changed to support the temporary use of SIDTEC condenser tube
cleaners on Unit 1 in lieu of the sponge rubber balls va the Amertap condenser tube cleaning system.
SUMMARY
OF THE SAFETY EVALUATION:
Per UFSAR section 10.4.5 complete outage of the condenser Circulating Water system
- - will not result in the loss of any service essential to reactor safety.
PLANT
REFERENCE:
97FSAR042,97FSAR032,1SP-97-100 -
)
L
-l j
l I E2-54
i I
1 1
l CHANGES TO THE FACILITY TITLE: Waste Collector Filter Aid Subsystem Status l
BRIEF DESCRIPTION:
The Waste Collector Filter Aid Subsystem was electrically disabled.
SUMMARY
OF THE SAFETY EVALUATION:
The filter aid components had never been used for the Waste Collector Filter and does not interface with safety related equipment. The Waste Collector Filter will still be used for ;
processing ofradioactive wastes.
l 1
. PLANT
REFERENCE:
97FSAR044, ESR 94-00347 l
l t
! E2-55 i- l w
6 l
l CHANGES TO THE FACILITY 3
TITLE: Update of High Pressure Coolant Injection (HPCI)/RCIC Process Diagram Data to reflect Power Uprate ;
- BRIEF DESCRIPTION:
. Increase in Rated Thermal Power from 2436 Mwt to 2558 Mwt on Unit 2 increased the steam conditions for the HPCI and RCIC systems.
SUMMARY
OF THE SAFETY EVALUATION: ;
Power Uprate was evaluated as part of Technical Specification Amendments 183/214.
PLANT
REFERENCE:
97FSAR045, ESR 95-00240 4
E2-56
. _ ~ _ _ . - . . _ . . _ . _ . . . - . . . _ . _ . . _ . _ _ _ . _ . _ ~ _ _ _ _ _.. ._ _. . . . . - - _
l CHANGES TO THE FACILITY
. TITLE: . Containment Isolation and Standby Gas Treatment System Update BRIEF DESCRIPTION:
Updated the descriptions of Containment Isolation system and SBGT system to more accurately reflect current plant configuration.
SUMMARY
OF THE SAFETY EVALUATION:
Containment Isolation system changes were editorial in nature. The SBGT system pre-
' filter efficiency was conservatively revised to 45% per Specification 01-236-08.
PLANT
REFERENCE:
97FSAR046 I I
I l
l i
' E2-57 l
CHANGES TO THE FACILITY TITLE: Mop Water Disposal by Evaporation BRIEF DESCRIPTION:
A description of the process for mop water disposal, by evaporation was added to the -
l l
SUMMARY
OF THE SAFETY EVALUATION: ;
The evaporator will operate within the radwaste building, using the permanently installed ventilation system, both'of which are described in the UFSAR. :
1 i
PLANT
REFERENCE:
97FSAR047, OSPP-MEC507 1
)
I l
l l
l l'
l i
Y A' i n
E2-58 l
l
l CHANGES TO THE FACILITY TITLE: Fuel Pool Holding Pump Seal Water-BRIEF DESCRIPTION:
Seal water was removed from the Fuel Pool holding pumps to alleviate contamination of Demineralized Water system used as sea ~ l water,
SUMMARY
OF THE SAFETY EVALUATION:
Changing the source of the seal water from demineralized water to pump discharge does not change the operation or design function of the pumps. The pumps perform no safety function.
PLANT
REFERENCE:
97FSAR048, ESR 96-00751 E2-59 i
I l
i CHANGES TO THE FACILITY l
TITLE: Unit 2 Reactor Building Temporary Cooling ,
BRIEF DESCRIPTION: i Added temporary cooling coils in the inlet air flow path for the Unit 2 Reactor Building .
HVAC to address summertime personnel cooling concerns. i
SUMMARY
OF THE SAFETY EVALUATION:
The Reactor Building ventilation system will continue to operate as described in the i UFSAR,' and the temporary cooling is provided for personnel comfort, not to provide j additional margin for equipment qualification. i i
s PI, ANT
REFERENCE:
97FSAR050, ESR 97-00168 :
I l
i h
E2-60 l
. . _ .a
I CHANGES TO THE FACILITY TITLE: Intake Canal Diversion Structure Description BRIEF DESCRIPTION:
The description of the intake canal diversion structure screen has been revised to reflect i the current screen shape and opening size.
SUMMARY
OF THE SAFETY EVALUATION:
The new screen shape and size does not effect equipment important to safety.
PLANT
REFERENCE:
97FSAR052 t
i 4
l E2-61
l l i i j l
l-l l
CHANGES TO THE FACILITY l
TITLE: Organization Change - BESS Technical Services '
BRIEF DESCRIPTION:
The UFSAR was revised to reflect that the BESS Technical Services Unit addresses equipment predictive technologies, provides rapid engineering support for emergent plant issues, and directs engineering administrative support for the entire section.
SUMMARY
OF THE SAFETY EVALUATION:
This was an administrative change that makes no change to the facility.
PLANT
REFERENCE:
97FSAR053, OENP-1000 Rev.1
)
i i
I 2
E2-62
CHANGES TO THE FACILITY TITLE: Combustible Loading Update BRIEF DESCRIPTION:
Updated combustible loading values due to the increased combustibles in Radwaste Building fire zone RW-lb (Condensate Filter Demineralizer area).
SUMMARY
OF THE SAFETY EVALUATION:
Per section 9.5.1.5 Fire Hazards Analysis, transient loading is s ' iessed as not being ,
severe. The analyzed increase did not change this conclusion. !
PLANT
REFERENCE:
97FSAR054, ESR 96-00729 l
l E2-63 1: '
l 1
f CHANGES TO THE FACILITY t
TITLE: - Control Room Heating Ventilation Air Conditioning Description Update BRIEF DESCRIPTION:
The UFSAR Control Room HVAC description has been revised to ensure a match to the system design and Technical Specifications. Some additional clarifications were included to further enhance the UFSAR description.
SUMMARY
OF THE SAFETY EVALUATION:
The changes provided clarification to the UFSAR description and reflected current design and Technical Specifications.
PLANT
REFERENCE:
97FSAR056 t
E2-64 ;
CHANGES TO THE FACILITY TITLE: Control and Reactor Building HVAC Description Update BRIEF DESCRIPTION:
The UFSAR Control Room and Reactor Building HVAC descriptions has been revised to ensure a match to the current system design. Some additional clarifications were included to further enhance the UFSAR description.
SUMMARY
OF THE SAFETY EVALUATION:
The changes provided additional detail or clarification to the descriptions of approved plant design.
PLANT
REFERENCE:
97FSAR057 t
E2-65
- .-. . . - . - . . - . . . . - ...~.-- --.-.-.-.._ -- -. . --
l I
CHANGES TO THE FACILITY l TITLE: Response Time Testing Link 'to Technical Specifications
- BRIEF DESCRIPTION
r: 1 This change provided a link between the Response Time tables in the UFSAR and the information captured in Technical Specifications documenting exclusions.
l
SUMMARY
OF THE SAFETY EVALUATION: l This change was for clarification only, and did not change testing requirements. i I
i l PLANT
REFERENCE:
- 97FSAR058 I l
f n
d l
l
!~ E2-66
.~ .. . . - - - - .. . . . - - . - _ . - - _ . - - . _ . . . . - . - . . - . . . - . . . . . . . . . _ . - . ,
d CHANGES TO THE FACILITY TITI.E: . High Pressure Coolant Injection / Reactor Core Isolation Cooling System Condensate Drain Piping BRIEF DESCRIPTION:
The figure, showing the HPCI/RCIC condensate drain piping that was rerouted from the :
radwaste system to the Main Condenser by plant modification, PM 82-137, was updated. !
SUMMARY
OF THE SAFETY EVALUATION:
This change updated the figure to reflect the actual plant field conditions, PLANT
REFERENCE:
97FSAR059, ESR 96-00549, PM 82-137 i l
2
)
I I
I
' E2-67 J
f_HANGES TO THE FACILITY TITLE: General Site Building Ventilation Descriptions BRIEF DESCRIPTION:
The change documented the current as-built condition of the Service Building,
- Maintenance Shop and Warehouse Building, Clean Maintenance Building, and Document Control Building ventilation systems.
SUMMARY
OF THE SAFETY EVALUATION:
The changes did not involve buildings in the power block.
PLANT
REFERENCE:
97FSAR060
)
E2-68 4
l l
CHANGES TO THE FACILITY TITLE: Xenon Stability Operational Design Guide and Confonnance
' BRIEF DESCRIPTION: I Xenon Stability Operational Design Guide and Conformance was updated and clarified.
SUMMARY
OF THE SAFETY EVAL.UATION: ,
Xenon Stability acceptance criteria were not altered by this change.
PLANT
REFERENCE:
97FSAR061 ,
i i
l f
E2-69
.t t
CHANGES TO THE FACILITX !
TITLE: Thermal Hydraulic Instability - !
BRIEF DESCRIPTION:
i This updated the description to reflect Maximum Extended Operating Domain (MEOD) !
operation.
i
SUMMARY
OF THE SAFETY EVALUATION: j l'
This change provide clarification without changing the limiting power / flow condition used in the stability analysis as described in the UFSAR.
PLANT
REFERENCE:
97FSAR062 l
1 l
l L
{
E2-70 I>
l
- ~ . , ,
l l
l I I l !
)
CHANGES TO THE FACILITY
{
1 TITLE: Use of Nine (9) Rod Spent Fuel Rod Holder BRIEF DESCRIPTION: {
l This clarified that the new General Electric (GE) container for storage of failed spent fuel rods accepts nine rods.
SUMMARY
OF THE SAFETY EVALUATION:
The failed spent fuel rods that would be stored in the rod holders would have released the majority of their gases during cycle operation or fuel sipping. The release of fission products would be less than that described by the refueling accident.
PLANT
REFERENCE:
97FSAR063, OENP-57 Rev. 5 l I
I L
E2-71 l
g
... _ _ __ . _ . _ ._ _-_ _ . . _ . . ~ _ . . _ . - .-. . _ _. . _ . _ . _ . . - . . .
t I
i t
CHANGES TO THE FACILITY l TITL,E: Control Building Emergency Air Filtration l l
BRIEF DESCRIPTION: i 1
l This change reflected the bounding calculations for Main Steam Line Break and Control l Rod Drop Analysis dose support the new Control Building Emergency Air Filtration i system charcoal efficiencies.
SUMMARY
OF THE SAFETY EVALUATION:
While the acceptance criteria for charcoal efficiency was slightly relaxed, it does not allow the dose due to the two bounding accidents to rise above the site's acceptance
- limits for such accidents for either the control room or the public.
PLANT
REFERENCE:
97FSAR064, ESR 97-00078 Rev.1 I
i 1
E2-72
t
)
i 1
CHANGES TO THE FACILITY TITLE:
' Auxiliary Boiler Refurbishment BRIEF DESCRIPTION:
. The Auxiliary Boilers were replaced with a single, smaller boiler.
SUMMARY
OF THE SAFETY EVALUATION:
There is no change to safety-related systems, structures, or components.
PLANT
REFERENCE:
97FSAR065, ESR 97-00140, OE&RC-1045, OSP-97-014 I i
i i
)
i l
1 E2-73
l i
CHANGES TO THE FACILITY i
TITLE: Abandoning the Well Water System BRIEF DESCRIPTION:
Updated the UFSAR to reflect the abandonment of the well water system that supplied -
the alternate supply of makeup water for fire protection. .
SJI.!MMARY OF THE SAFETY EVALUATION:
- The County Water system will continue to provide sufficient makeup to the fire protect supply tanks and will not affect the fire protect siipply tank inventory requirements as evaluated in the UFSAR.
PLANT
REFERENCE:
97FSAR067, ESR 95-00430 Rev 0 and 1 i
i l
I 1
l l
l' i .
i E2-74 l
1 l
I l
l l
CHANGES TO THE FACILITY TITLE: Unit 2 Mechanical Vacuum Pump Trip BRIEF DESCRIPTION:
This change reflected re-installation of the mechanical vacuum pump trip from the Main Steam Line Radiation Monitor (MSLRM) Hi-Hi radiation trip on Unit 2.
SUMMARY
OF THE SAFETY EVALUATION:
The MSLRM Hi-Hi radiation trip function is required for the condenser mechanical vacuum pump to maintain control room habitability within General Design Criterion (GDC) 19/ Standard Review Plan (SRP) Section 6.4 limits during a CRDA at less than 5% reactor power. 1 l
i l
PLANT
REFERENCE:
97FSAR068, ESR 97-00040 i I
i i
l l
I E2-75
CHANGES TO THE FACILITY TITLE: Unit 1 Mechanical Vacuum Pump Trip
. BRIEF DESCRIPTION:
This change reflected re-installation of the mechanical vacuum pump trip from the MSLRM Hi-Hi radiation trip on Unit 1.
SUMMARY
OF THE SAFETY EVALUATION:
The MSLRM Hi-Hi radiation trip function is required for the condenser mechanical .
vacuum pump to maintain control room habitability within GDC 19/SRP Section 6.4 limits during a CRDA at less than 5% reactor power.
PLANT
REFERENCE:
97FSAR069, ESR 97-00039 E2-76
l i
CHANGES TO THE FACILITY TITLE: Containment Isolation Valve Closure Times l
BRIEF DESCRIPTION:
The generic note references for affected Containment Isolation Valves (CIV) were replaced by defining a nominal stroke time for the affected CIVs
SUMMARY
OF THE SAFETY EVALUATION:
The change was for clarification only. The valves within the scope of the revision are either passive in nature (normally closed and remain closed during accident mitigation for containment protection), or serve an ECCS function in the open position and do not receive containment isolation signals for auto closure. As such the closure time for these valves was not relevant to their safety function.
PLANT
REFERENCE:
97FSAR071 I l
l i
i l
I I
l .
~
l E2-77
i.
l t
l-CHANGES TO THE FACILITY l
TITLE: Reactor Shutdown from Outside the Control Room l BRIEF DESCRIPTION:
. This change reflected that with the installation of Electrical Protective Assembly (EPA) breakers, reactor shutdown from outside the control room is initiated from these breakers, not the motor control center compartments as previously documented in the UFSAR.
SUMMARY
OF THE SAFETY EVALUATION:
This was an administrative change to reflect current plant configuration and practice.
PLANT
REFERENCE:
97FSAR072 l
E2-78 I
l 1
CHANGES TO THE FACILITY TITLE: Associated Circuits - Environmental Qualification (EQ)
BRIEF DESCRIPTION:
This added clarification of the status of electrical overcurrent protective devices in relation to Reactor Building non-safety related loads and the EQ program.
SUMMARY
OF THE SAFETY EVALUATION:
Electrical design features were not being changed. The clarification provided, related to the unique electrical design condition related to the plant cables, ensures compliance to 10 CFR 50.49.
PLANT
REFERENCE:
97FSAR074, ESR 97-00296 E2-79
]
I CHANGES TO TIIE FACILITY TITLE: UFSAR Reference Number Change BRIEF DESCRIPTION:
This UFSAR change was an administrative change top Section 5.2.2.2.2, to reference ;
Table 15.0.4-1 verses 15.0.2-1, and 15.0.4-2 verses 15.0.2-2.
SUMMARY
OF THE SAFETY EVALUATION: ;
This was a clerical change.
PLANT
REFERENCE:
97FSAR075, ESR 95-01608 I
l l
l l
E2-80
_ . . . _ m _ . _ . _ _ _ - . _ . - . _ - . . . _ _ _ _ . . _ . . . . . _
1 t
CHANGES TO THE FACILITY ,
TITLE: Clearance and Equipment Tagging l I
l BRIEF DESCRIPTION- i l
l The description of the clearance and equipment tagging process has been revised to j
. reflect the current corporate process.' l l
l 1
SUMMARY
OF THE SAFETY EVALUATION:
This change reflected the current administrative process for clearance and equipment tagging.
PLANT
REFERENCE:
97FSAR076, OPS-NGGC 1301
)
l i
l E2-81
a . _. .. _..-2 . .m._ +a -
As , _ - , . _. 4 - . ~ . . - - ......_4. . . . . . . . . . - -. .a. . . -&s CHANGES TO THE FACILITY TITLE: Outage Management Practices I
. BRIEF DESCRIPTION:
)
Outage durations have been greatly compressed and are now managed as groups of !
parallel system windows. The format of Figure 9.1.4-4 has been changed to reflect I current outage management practices.
SUMMARY
OF THE SAFETY EVALUATION:
The change reflected current outage management practices.
PLANT
REFERENCE:
97FSAR078, j l
i l
l i
i r
E2-82 i
i CHANGES TO THE FACILITY TITLE: Suppression Pool Water Volumes
. BRIEF DESCRIPTION:
i Suppression Pool water volumes have been updated to reflect the addition oflarger ECCS strainers and supports.
SUMMARY
OF THE SAFETY EVALUATION:
- l. The suppression pool water volumes remain adequate to support suppression pool requirements.
PLANT
REFERENCE:
97FSAR080, TSC # 97TSB06 l
l 4
E2-83
l.
CHANGES TO THE FACILITY
- TITLE: Inservice Testing Program -
1 BRIEF DESCRIPTION:
The Inservice Testing Program has been updated to reflect the third 10-year interval requirements per 10 CFR 50.55a.
SUMMARY
OF THE SAFETY EVALUATION:
The Inservice Testing Program has been updated to reflect the third 10-year interval . j.
requirements per 10 CFR 50.55a.
' PLANT
REFERENCE:
97FSAR081, OENP-16.1 Rev.16 ;
^
l l' E2-84 i
V . _ , ._ _ - - -- _.
l o
1, .
}
i i
CHANGES TO THE FACILITY I'
l . TITLE: Rod Block Monitor (RBM)
BRIEF DESCRIPTION: ;
l The UFSAR description was changed to reflect a modification which had changed the
! RBM from a flow biased to a power biased setpoint function.
i a
l' ..
l
SUMMARY
OF THE SAFETY EVALUATION:
This change updated the description to reflect the existing plant design.
l PLANT
REFERENCE:
97FSAR082, PM 89-035/036 l
1 l I Ii l
l:
1 j
l-E2-85
I P
I I
CHANGES TO THE FACILITY I l
TITLE: . Low Power Range Monitor (LPRM) Power Supply . !
BRIEF DESCRIPTION:
The UFSAR description has been revised to reflect the current operation of the LPRM ion - )
chamber power supply.which nominally operates at 100Vdc. I l
l.
SUMMARY
OF THE SAFETY EVALUATION:
- i. The change reflects current plant operation.
PLANT
REFERENCE:
97FSAR083 l
l i- I
! j I
l l
1 i
l l
l l
l l- E2-86 i.
~
1 L
i:
l ,
1 l- I l
l !
L CHANGES TO THE FACILITY TITLE: Emergency Core Cooling System Description i l BRIEF DESC.RIPTION:
Descriptions of ECCS configuration, procedures, or processes have been revised to reflect -
current operation.
SUMMARY
OF THE SAFETY EVAL UATION:
The changes wer editorial.
PLANT
REFERENCE:
97FSAR084, OSP 95-003 I
i l
i I
i i
i l
l E2-87 1
i i
CHANGES TO THE _ ACILITY TITLE: Automatic Depresurization System (ADS) Logic '
BRIEF DESCRIPTION:
The ADS logic description has been changed to reflect the plant configuration. !
SUMMARY
OF THE SAFETY EVALUATION:
No changes were made to the actual ADS logic and the safety requirements were met. :
PLANT
REFERENCE:
97FSAR085 ;
+
P i
P P
h l
l l
i E2-88 i
__ _ __. _. . ._. _ . _. . . . . . _ _. _ . . _ _ _ . . _ . _ _ . . . _ - _ - _ _ _ . _~
k i
CHANGES TO THE FACILITY f TITLE: Residual Heat Removal, Shutdown Cooling Isolation Setpoint - l BRIEF DESCRIPTION: ;
The value given was revised to reflect "the Shutdown Cooling Isolation Setpoint" which !
is consistent with the Group 8 isolation permissive within the UFSAR. .
SUMMARY
OF THE SAFETY EVALUATION:
The revision was for clarification only to be consistent with current set point, normal and l abnormal operating procedures, and system descriptions. No physical change to plant parameters were performed as a result of this change.
PI. ANT
REFERENCE:
97FSAR086 i
f E2-89
4 1
i l
CHANGES TO THE FACILITY l l
Till.E: Refueling Interlocks BRIEF DESCRIPTION:
1 This change clarified the description associated with the refueling interlocks and the rigic pole system.
SUMMARY
OF THE SAFETY EVALUATION: I 1
This change clarified that the non-fuel handing hoist is used to facilitate the installation of ,
main steam line plugs and to latch the dryer separator.
PLANT
REFERENCE:
97FSAR087 ESR 94-00502 l
4 l
l 1
E2-90
. . - - _- - -. -. . . + - - n. . . . _ .- . . .. - .
1 1
I CHANGES TO THE FACILITY TITLE: Suppression Pool Water Volumes I BRIEF DESCRIPTION: 3 This was revised to reflect the addition oflarger ECCS strainers and supports.
SUMMARY
OF THE SAFETY EVALUATION: )
i The volume change was insignificant and remains adequate to support Suppression Pool design requirements.
PLANT
REFERENCE:
97FSAR088, TSC TSB06 j i
i l
4 i
I I
I E2-91
r
- CHANGES TO THE FACILIT7
_IlJ12 Radwaste Building and Waste Handling Equipment BRIEF DESCRIPTION:
The change corrected a typographical error to the fission product release number by adding the micro symbol before curie.
SUMMARY
OF THE SAFETY EVALUATION:
The change corrected a typographical error.
PLANT
REFERENCE:
97FSAR089 1
i I
l l
i l
l E2-92
CHANGES TO THE FACILITY TITLE: Electrical Distribution BRIEF DESCRIPTION:
The change clarified the description associated with the power feeds to the 4160 Volt Switchgear and relay function associated with sequential loading on E buses.
SUMMARY
OF THE SAFETY EVALUATION:
The change only clarified the UFSAR descriptions.
PLANT
REFERENCE:
97FSAR090 E2-93
CHANGES TO THE FACILITY TITLE: Drywell Dome Flange Outage Protection BRIEF DESCRIPTION: ,
The method of protecting the drywell dome flange seal surface was changed to use the old gaskets, as the sealing surfaces are the grooves for the gaskets and not the entire flange area.
SUMMARY
OF THE SAFETY EVALUATION:
The sealing surfaces are the groves and the entire flange area does not need to be protected. Use of the old gaskets is adequate protection.
- PLANT
REFERENCE:
97FSAR094, OSPP-RPV501 Rev.15 i
E2-94 I i
i
CHANGES TO THE FACILITY
-TITLE: Core Spray System Process Diagram BRIEF DESCRIPTION:
A note has been added for clarification that valve positions are dependent on system condition as shown on the valve position table.
SUMMARY
OF THE SAFETY EVALUATION:
Change only provided clarification.
PLANT
REFERENCE:
97FSAR095 E2-95
l 1
l CHANGES TO THE FACILITY TITI,E: Condensate System Filters and Demineralizers
' BRIEF DESCRIPTION:
The UFSAR description has been revised to reflect that Condensate systern filters are no longer precoated with resin and demineralizers are no longer regenerated.
SUMMARY
OF THE SAFETY EVALUATION:
This was changed to reflect current operation of the Condensate system.
PLANT
REFERENCE:
97FSAR097, ESR 94-00186 E2-96
CHANGES TO THE FACILITY TITLE: Control Room HVAC Chlorine Sensors BRIEF DESCRIPTION:
Control Room HVAC Chlorine sensors have been relocated downstream of the roll filters
SUMMARY
OF TIIE SAFETY EVALUATION:
The sensors were relocated slightly downstream of the roll filters, but still within the control room air intake. This in no way changes the operation or the original intended function of the system.
PLANT
REFERENCE:
97FSAR098, ESR 97-00147 E2-97
- . - - -. . _ - - . - - - ._ = . -. ~ _. - - _ .- . -- . _ _ . . .
t I
i CHANGES TO THE FACILITY l TITLE: Non-Destructive Examination of Piping Welds
{
BRIEF DESCRIPTION: .
Study report 7992.017-S-M-045, " Piping Specification (s) Code Reconciliation for CP&L BSEP, Safety Related" performed the reconciliation to meet ASME Section XI requirements. The results were adopted in BSEP specification 248-177 " Installation of {
j Piping." This report was used to supersede the old piping fabrication specification.
SUMMARY
OF THE SAFETY EVALUATION:
The UFSAR was partially updated to bring the UFSAR into alignment with the specification and reconciliation.
PLANT
REFERENCE:
97FSAR099, Specification 248-117 Rev.13 l
l 1
L !
i l -
l l
I l l 1
I l
E2-98
_ _ _ . - _ . _ - _ . - - . . . _ ~ .
I i
i l
CHANGES TO THE FACILITY !
t TITLE: Unit 2 Un-interruptible Power Supply Cable Size ,
J BRIEF DESCRIPTION:
)
Unit 2 UPS Inverter cables were replaced with a larger size in order to utilize the !
inverters design kV limit. The Central Access Portal (CAP) building distribution panel )
disconnect switch was added.
SUMMARY
OF THE SAFETY EVALUATION:
While the level of detail of the drawing included the cable size, there was no safety-related impact to revising the wiring size in this application.
PLANT
REFERENCE:
97FSAR100, ESR 97-00202 l
l i
1 l
1 l
l l
)
l E2-99 i
- ,_ _- +. - ,- _ --
. . . ~ - .- . . . . . . - . - . . . - - - . - . . . - . . . .
CHANGES TO THE FACILITY TITLE: Central Access Poital Building BRIEF DESCRIPTION:
1 The site plot plan was revised to reflect the new security building on site. Drawings were revised to reflect the communication tie to the CAP building.
l
SUMMARY
OF THE SAFETY EVALUATION:
The addition of the CAP building met 10 CFR 73.55 requirements for security purposes.
PLANT
REFERENCE:
97FSAR102, ESR 97-00198 l
i I
l 1
i i
l l
E2-100 l
CHANGES TO THE FACILITY TITLE: Turbine Valve Closure Scram Bypass ;
i BRIEF DESCRIPTION: i The change corrected th- description of the Turbine Valve Closure Scram Bypass setpoint to match Technical Specifications.
SUMMARY
OF THE SAFETY EVALUATION:
The change corrected an error in the UFSAR description.
PLANT
REFERENCE:
97FSAR104 I
l l
l l
l r
I i
E2-101 l
CHANGES TO THE FACILITY TITLE: Reactor Recirculation System l BRIEF DESCRIPTION:
1
- This change corrected errors in the UFSAR description of the Reactor Recirculation System.
SUMMARY
OF THE SAFETY EVALUATION:
This change corrected minor errors or clarified the description.
PLANT
REFERENCE:
97FSAR105 E2-102 I
l
1 CHANGES TO THE FACILITY TITLE: Restoration of UFSAR Historical Information BRIEF DESCRIPTION:
Historical information regarding plant nuclear safety operational analysis prior to plant startup has been restored to Section 15.0A.
SUMMARY
OF THE SAFETY EVALUATION:
The change restored historical information.
PLANT
REFERENCE:
97FSAR107 j
e 4
1 i l i
E2-103
- . ~ . _ . . . .- . _ . . _ . . -._ _ __ _. -_ _ _ _ _ - - _ _ . _ . . = _ -
i i
l-i i
CHANGES TO THE FACILITY TITLE: Control Rod Drive System BRIEF DESCRIPTION:
This change corrected errors in the description of the Control Rod Drive system. ;
P
SUMMARY
OF THE SAFETY EVALUATION:
This change corrected minor errors or clarified the description.
PLANT
REFERENCE:
97FSAR108 E2,104
CHANGES TO THE FACILITY TITLE _1 _ Reactor Water Cleanup (RWCU) System BRIEF DESCRIPTION:
This changed the term " unit" to " system" to eliminate confusion with the terms use. This l also added post-filter strainers to the RWCU flow diagram.
SUMMARY
OF THE SAFETY EVALUATION:
This change corrected minor errors or clarified the description. 6 PLANT
REFERENCE:
97FSAR109 l ,
t l
l-t E2-105
1 I !
1 y
l 1
CHANGES TO THE FACILITY T_rfLFJ Reactor Pressure Vessel Design Summary Report BRIEF DESCRIPTION:
This change provided minor updates tv ,ppendix 5.3A, Reactor Pressure Vessel Design Summary Report.
SUMMARY
OF THE SAFETY EVALUATION:
This change corrected minor errors or clarified the description.
PLANT
REFERENCE:
97FSAR110 i
i 1
4 I
l 5
E2-106
l l
l l
l CHANGES TO THE FACILITY l TITLE: Unit 2 Bypass System Capability with Power Uprate ,
i BRIEF DESCRIPTION:
This changed the bypass system capability of approximately 80 % verses 85% due to the Unit 2 Power Uprate from 2436 MWt to 2558 MWt.
SUMMARY
OF THE SAFETY EVALUATION:
Power Uprate was evaluated as part of Technical Specification Amendments 183/214. I PLANT REFERENC_Fa 97FSAR111, ESR 95-00240 l
l l
i
~
l E2-107 l
I -_
CHANGES TO THE FACILITY TITLE: B2Cl2 Core Operating Limits Report (COLR) and Reload Design BRIEF DESCRIPTION:
References were revised to reflect the B2Cl2 COLR and reload design.
SUMMARY
OF THE SAFETY EVALUATION:
These changes were evaluated in the "B2Cl2 COLR and reload design" safety review
. and approved Technical Specification Amendment 212 for GE 13 fuel.
PLANT
REFERENCE:
97FSARI13, B2Cl2 Design Review
)
l l
[.
i t'
i
- I i E2-108 i
i !
)
i' i
CHANGES TO THE FACILITY TITLE: Radiation Control Organization l
l BRIEF DESCRIPTION.
This was changed to reflect the current Radiation Control organization.
I 1
SUMMARY
OF THE SAFETY EVALUATION: ) i L This was an administrative change.
PLANT
REFERENCE:
97FSAR114 l
l r
i
'I l
i t
I i
e t
E2-109
(
l CHANGES TO THE FACILITY TITLE: Solid Waste Processing
~ BRIEF DESCRIPTION:
This updated the descdption of how solid wastes are processed.
SUMMARY
OF THE SAFETY EVALUATION:
This change updated the UFSAR description and activities associated with the trash !
monitoring facility and is bounded by evaluated accidents. I i
i l
PLANT
REFERENCE:
97FSAR115 -l I
i I
l i-l
,. E2-Il0 i
I CHANGES TO THE FACILITY TITLE: Emergency Response Facility Information System (ERFIS)/
Process Computer BRIEF DESCRIPTION:
This change updated the organizational responsibilities for ERFIS and the Process Computer.
SUMMARY
OF THE SAFETY EVALUATION:
This updated organizational responsibilities. i l
PLANT
REFERENCE:
97FSARI16 i
)
I l
l E2-111 i
. __ _ ._ _ _ _ _ _ - _ _ - _ _ _ _ _ _ . . . - ~ _ . . . . _ _ _ _ . _ _ _ _._
P 9
CHANGES TO THE FACILITY !
TITLE: Typographical Error for a Valve Number
- BRIEF DESCRIPTION:
This change corrected the error in the RHR system valve number (2 El 1-V46) for Figure 9.2.1-2A. ,
SUMMARY
OF THE SAFETY EVALUATION:
This was a correction of a typographical error.
Pl ANT
REFERENCE:
97FSARI17 -
1-4 E2-112 l-L
- i. _ . , -
CHANGES TO THE FACILITY TITLE: Spent Fuel Storage Pools l
BRIEF DESCRIPTION:
. The change supported the installation of seismic class I plugs in the refueling canal cavity drains during refueling.
SUMMARY
OF THE SAFETY EVALUATION:
Due to non-seismic drain connections in the refueling canal, plugs are installed during refueling to prevent the loss of water below the top of the spent fuel storage pool barrier after a seismic event.
PLANT
REFERENCE:
97FSAR121, ESR 9700166 Rev 1, OSPP-RPV501 E2-Il3
)
.: i 1
. . _ _ _ _ _ . ~ . _ . ~ _._ _ _ _ ._.. _ _ . _ __ _ .____ . _ _ _ _ _
CHANGES TO THE FACILITY TITI.E: Primary Containment Resistance Temperature Detector (RTD)
BRIEF DESCRIPTION:' l The leads for a Unit 2 Primary Containment Suppression Pool RTD were temporarily lilled due to a ground. The nature of the failure did not allow the automatic compensation for a failed RTD to remove the invalid signal from the bulk temperature indication. ,
i StIMMARY OF THE SAFETY EVALUATION:
The remaining RTDs allowed proper indication of bulk suppression pool temperature with a minimum of 11 out of 12 RTDs per division.
PLANT
REFERENCE:
97FSAR124
-I i
)
l
\
l
)
l i
i E2-Il4
CHANGES TO THE FACILITY TITLE: 2-El1-F009 Bonnet Pressure Equalization Line BRIEF DESCRIPTION:
The description has been revised to address the 2-El1-F009 valve bonnet pressure equalization line installation for the RHR system.
SUMMARY
OF THE SAFETY EVALUATION:
System functions were not altered as a result of this modification.
PLANT
REFERENCE:
97FSAR126, ESR 00041 i
I E2-Il5
i 1
l l
l CHANGES TO THE FACILITY TITLE: Secondary Containment Isolation BRIEF DESCRIPTION:
)
This corrected the description which had linked the drywell floor and equipment drain lines to a Secondary Containment isolation.
SUMMARY
OF THE SAFETY EVALUATION:
This corrected the description to reflect plant configuration.
PLANT
REFERENCE:
97FSAR127 L
l l
l E2-Il6 !
I
L i-I i
l i i
I CHANGES TO THE FACILITY l-l TITLE: Document Control Vault l
J
- i. i BRIEF DESCRIPTION:
l L
l l Revised the humidity range to allow a lower desirable humidity range as recommended in L film stowage standard ANSI IT9.11-1991. Also, operation for short periods with an i l evaluation was included. l
- t. :
l 1
SUMMARY
OF THE SAFETY EVALUATION:
I Changes in this facility did not impact the plant and do not pose a hazard to the records I l- stored there.
l l
l- PLANT
REFERENCE:
97FSAR128 ,
i l
i l.
! l l
i J
o l E2-Il7
. . . . . __ ._ . . - _ _ _ . . . . _ _ . ~ . _ . . _ . _ _ _ . _ _ _ _ _ _ -
4 CHANGES TO THE FACII.ITY TITLE: Rod Block Monitor Description BRIEF DESCRIPTION: f The description of the RBM has been revised to reflect the current design as power biased verses flow biased.
SUMMARY
OF THE SAFETY EVALUATION:
Revised the description to reflect plant design. '
PLANT
REFERENCE:
97FSAR130, PM 89-035 &36 1
1 i
i E2-Il8 ;
i
l I i l l ,
1 l
l l
l l
l CHANGES TO THE FACILITY !
l-l TITLE: Site Fire Protection Features BRIEF DESCRIPTION:
Errors were corrected in the description of the sites features relative to fire protection.
l l
1.
I
SUMMARY
OF THE SAFETY EVALUATION: .I i
i l
Corrections to address the site configuration were made.
l l
PLANT
REFERENCE:
97FSAR131, ESR 94-00345
~
1 l
1 l
l l
l-E2-Il9 l
CilANGES TO THE FACILITY TITLE: Radwaste Building Ventilation !
BRIEF DESCRIPTION:
This change revised the description of the fan line-ups.
SUMMARY
OF THE SAFETY EVALUATION: :
The fan line-ups described maintain an appropriate building negative static pressure; support appropriate filtering, monitoring, and air changes; and maintain temperature / heat ,
removal for the building.
PLANT
REFERENCE:
97FSAR132, ESR 97-00477 I
, E2-120 l
1-l l .
CHANGES TO THE FACILITY :
TITLE: Corporate and Plant Organization Update BRIEF DESCRIPTION: )
, This change reflected current corporate and plant organizations. !
l i
1
SUMMARY
OF THE SAFETY EVALUATION:
i This administrative change reflected current corporate and plant organizations. 1 1
I i PLANT
REFERENCE:
97FSAR133 i
I l
l l
l l
l E2-121 I
I:
l l
1 q
CHANGES TO THE FACILITY TITLE: Reactor Core Isolation Cooling Turbine Generated Missile Potential BRIEF DESCRIPTION:
This clarified the discussion of a RCIC Turbine generated missile potential to reflect that safety related equipment could be impacted, but this is not a credible event, j i
SUMMARY
OF THE SAFETY EVALUATION:
This clarified the equipment performance description. l 1
PLANT
REFERENCE:
97FSAR134 i l
l 4
i i
n Y
v E2-122
CHANGES TO THE FACILITY TITLE: . Temporary Air Operated Pump for Detergent Drain Tank BRIEF DESCRIPTION:
A'n air operated pump was temporarily installed due to a recurrent seal failure on the installed DDT pump.
SUMMARY
OF THE SAFETY EVALUATION:
This equipment is not safety-related.
PLANT
REFERENCE:
97FSAR135 E2-123
CHANGES TO THE FACILITY TITLE: Control Building Habitability BRIEF DESCRIPTION:
The number of self-contained bn:athing apparatus (SCBA) available for the' control room personnel was revised.
SUMMARY
OF THE SAFETY EVALUATION:
The change increased the number of SCBA available by linking it to minimum shift compliment.
PLANT
REFERENCE:
97FSAR137 E2-124
. . - _ -. . . _ . __. _ _ . _ _ _ _ . . _ _ . . = - _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ . . _ . . . _ .. _
l l 4 I i l- l
! 1 L
i l
CHANGES TO THE FACILITY TITLE: Quality Assurance (QA) Program Description Relocation BRIEF DESCRIP110N:
The QA Program description has been relocated to the UFSAR from Technical Specifications as part of the Improved Technical Specifications (ITS) process.
SUMMARY
OF TIIE SAFETY EVALUATION:
The relocation of the QA l'rogram was evaluated with the ITS Amendment 203/233.
PLANT
REFERENCE:
97FSAR138 I
l l
i.
i~
l r
i i E2-125 l
i
P l
i CHANGES TO THE FACILITY TITLE: General Editorial Corrections -
BRIEF DESCRIPTION:
j Editorial Corrections were made to Section 3.0 for typographical and publication errors.
q l
t
SUMMARY
OF THE SAFETY EVALUATION: l l
l Editorial Corrections were made to Section 3.0 for typographical and publication errors. l 1
l l
1 PLANT
REFERENCE:
97FSAR139 i l
L i
I i
i J
E2-126
_ . . . . . _ . . . . . . _ .- .-. _ _ , . . _ _ _ . _ . . _ _ _ _ . _ . . . . _ ~ _ . . . _ . _ _ . _ . _ _ . _ _
1 I
l l ..
i CHANGES TO THE FACILITY l 1
l TITLE: Containment Atmosphere Control System l
BRIEF DESCRIPTION: i Figure changes were made to reflect Containment Atmosphere Control System valve I configuration and operation.
i l
SUMMARY
OF THE SAFETY EVALU ATJON: l The description changes were made reflect the current plant configuration and operation. i s
PLANT
REFERENCE:
97FSAR140, ESR 94-00148,1OP-24 Rev. 66 !
e I
{.
l l
i-l E2-127 I l !
!. i
l I
I e
l 1- !
CHANGES TO THE FACILITY TITLFa - Main Stack Radiation Monitor Response Time 1
BRIEF DESCRIPTION: I This change restores the response time for the' Main Stack Radiation Monitor - High that was inappropriately deleted.
SUMMARY
OF THE SAFETY EVALUATION:
This change restored an inappropriately deleted response time.
)
PLANT
REFERENCE:
97FSAR141,96FSAR015, ISP-97-102 l
1 l
i i
l l
l l
l l E2-128
i CHANGES TO THE FACILITY TITLE: Reactor Water Cleanup System Flow Rates BRIEF DESCRIPTION: i This change revised the RWCU system description to reflect appropriate nominal flow rates.
SUMMARY
OF THE SAFETY EVAL!)ATION:
This change did not affect the design, function, or method of function of the system, but reflected appropriate nominal flow rates.
PLANT
REFERENCE:
97FSAR142 l
l l
E2-129
.- ~ . -
2 CHANGES TO THE FACILITY TITLE: Emergency Core Cooling System Suction Strainer Replacement - Unit 2 BRIEF DESCRIPTION:
This change implemented the ECCS suction strainer enlargement for NRC Bulletin 96-03, Potential Plugging of ECCS Suction Strainers by Debris in BWRs. ;
SUMMARY
OF THE SAFETY EVALUATION:
The installation of the new strainers replaced the existing strainers with ones of sufficient
. si ze and design features to ensure a margin of safety that, during a Design Bases Event, s- the requirements of 10 CFR 50.46 are met for the ECCS.
PLANT
REFERENCE:
97FSAR144, ESR 97-00067 r
4 i ;
J E2-130
i T
l-t
?
CHANGES TO THE FACILITY TITLE: B2Cl3 Reload Core Design BRIEF DESCRIPTION: !
This change was made to reflects the installation of B2Cl3 core reload, and to address !
BIC11 related information and inconsistencies discovered during review.
I i
SUMMARY
OF THE SAFETY EVALUATION:
Operation of the reactor during Cycle 13 and within the limits established in the COLR does not alter the operation of any systems or equipment important to safety.
PLANT
REFERENCE:
97FSAR145, ESR 96-00491 Rev.1 l
l l
l I
E2-131 1
.~ .- .- .-. . . . . - - . - . . ...~ ~_ ... . .-. - - - -.. .
I l ;
i I
l i !
CHANGES TO THE FACILITY - i L
TITLE: Supplemental Spent Fuel Pool Cooling l BRIEF DESCRIPTION:
l The description of the procedural requirements for placing the RHR system in l Supplemental Spent Fuel Pool Cooling mode to maintain the Spent Fuel Pool under 150 ,
L . deg. F, has been restored. !
SUMMARY
OF THE SAFETY EVALUATION:
This restored the description that was inadvertently deleted during UFSAR Rev.15.
PLANT
REFERENCE:
97FSAR147,96FSAR138 j i
i l
l I
l E2-132 i
1 i
l l
e CHANGES TO THE FACILITY l TITLE: Unit 2 Power Uprate Miscellaneous Changes
- BRIEF DESCRIPTION-l Miscellaneous changes associated with the Unit 2 power uprate from 2436 MWt to 2558 MWt were 'made.
SUMMARY
OF THE SAFETY EVALUATION: l This change addressed the setpoint changes needed to achieve the higher flows, pressures, i
temperatures, etc. necessary to implement the higher reactor power output associated with the Unit 2 power uprate (Amendment No. 214 to Facility Operating License No. DPR-62);
PLANT
REFERENCE:
97FSAR148, ESR 95-00240 Rev.1 I
I l
r a
E2-133
.: i
L l'
CHANGES TO THE FACILITY 1
TITLE: High Pressure Coolant Injection / Reactor Core isolation Cooling Valve Types l
BRIEF DESCRIPTION:
Editorial description corrections were made to reflect the Unit 2 HPCI/RCIC vacuum breakers are gate valves, and Unit i vacuum breakers are correctly described as globe valves.
SUMMARY
OF THE SAFETY EVALUATION:
Editorial description corrections were made to reflect the existing Unit differences. ;
I PLANT
REFERENCE:
97FSAR149 i
l i
E2-134
I
- l CHANGES TO THE FACILITY TITLE: Containment Valve Descriptions BRIEF DESCRIPTION:
This change corrected the description of miscellaneous containment valve types and valve power supplies previously changed by plent modification.
SUMMARY
OF THE SAFETY EVALUATION:
The descriptions were changed to reflect the actual plant configuration.
PLANT
REFERENCE:
97FSAR150, PM 80-133 & 134, PM 82-287 & 288 i
1 E2-135
CHANGES TO THE FACILITY
, TITLE: H2/02Analyzer Realignment ERIEF DESCRIPTION:
This change wr.s made to reflect the realignment of the H/02analyzers post-accident and enhanced moisture removal.
SUMMARY
OF THE SAFETY EVALUATION:
EOP-02-PCCP provides requirements for realigning the H2 /02 analyzers post-accident based on generic BWR Owner's Group Emergency Procedure Guidelines which were approved by the NRC.
PL ANT
REFERENCE:
97FSAR151, PM 80-032 & 033, EOP PCCP, NUREG 0737 ,
E2-136
i i
l CHANGES TO THE FACILITY I TITLE: Drywell to Torus Vacuum Breakers ;
BRIEF DESCRIPTION:
1 1
This description was changed reflect the aldition of a substitute Drywell to Torus I Vacuum Breaker seat material.
SUMMARY
OF THE SAFETY EVALUATION:
The replacement material was selected and evaluated to meet the necessary requirements ;
to ensure that the vacuum breakers perform their intended function. The substitute j material is an improvement because the stainless steel encased seal is less susceptible to i folding during installation and the stainless steel pallet is not susceptible to pitting in either the normal or accident environment. 3 1
PLANT
REFERENCE:
97FSAR152, ESR 97-00528 E2-137
CHANGES TO THE FACILITY TITLE: Primary Containment Temperature Detection 1
BRIEF DESCRIPTION:
The leads for a Unit 1 Primary Containment Suppression Pool Temperature RTD were
- temporarily lifted due to a ground. The nature of the failure did not allow the satomatic compensation for a failed RTD to remove the invalid signal from the bulk temperature indication.
SUMMARY
OF THE SAFETY EVALUATION:
The remaining RTDs allow proper indication of bulk suppression pool temperature with a minimum of 11 out of 12 RTDs per division.
PLANT
REFERENCE:
97FSAR156 4
E2-138 i
i l
1 i
l- l CHANGES TO THE FACILITY l l
TITLE: Unit 2 Amertap Tube Cleaning System i BRIEF DESCRIPTION:
The Unit 2 Amertap condenser tube cleaning system has been functionally disabled.
SUMMARY
OF THE SAFETY EVALUATION: l I
The loss of vacuum is addressed in UFSAR section 15.2.4. The reduced vacuum from tube fouling is a gradual decrease that would be seen and acted upon without challenge to
{
safety systems. j l
I PLANT
REFERENCE:
97FSAR157, ESR 97-00576 1-I f
E2-139 l
' CHANGES TO THE FACILITY TITLE: High Pressure Coolant Injection Room HVAC
~ BRIEF DESCRIPTION: '
The UFSAR figure 9.4.2-1B has been revised to reflect actual plant flow rates with the
- installation of blanks off two of the RHR rooms and installs flow diverters on the two HPCI registers.
SUMMARY
OF THE SAFETY EVALUATION:
The UFSAR requires the area temperatures to be kept below 148 deg. F. This requirement did not change.
PLANT
REFERENCE:
97FSARI58, ESR 9700579
~
l i
E2-140 l
t i
i e
i CHANGES TO THE FACILITY i TITLE: Minor UFSAR Clarifications - ;
1 BRIEF DESCRIPTION:
l Minor clarification changes were made to Section 1.2.2 to support descriptions of system I design basis.' l
SUMMARY
OF THE SAFETY EVALUATION:
~
The change provided clarification by adding detail.
PLANT
REFERENCE:
97FSAR159 l
l i
l l l l
I
~ E2-141
i i
CHANGES TO THE FACILITY l t
TITL,E: Refueling Bridge Rigid Pole Hoist System !
i l BRIEF DESCRIPTION: !
I i
l-This change was made to reflect the previous addition of the rigid pole hoist system to the l' refueling bridges, and to delete the incorrect reference to the service platform interface with the refueling ir.terlocks.
SUMMARY
OF THE SAFETY EVALUATION:
The change updated the description to reflect the current configuration of the plants.
PLANT
REFERENCE:
97FSAR160, PM 94-00502 & 95-01149 ,
t 1 ,
f l-L i
{
E2-142
( - - - -. . . . - . - -
CHANGES TO THE FACILITY-TITLE: Update of Drywell Peak Temperatures - Unit 2 BRIEF DESCRIPTION:
1 An update was made to reflect the evaluation and maximum temperature profile for Unit 2 local drywell temperatures for the B213R1 fuel cycle.
I
SUMMARY
OF THE SAFETY EVALUATION:
The bulk' drywell' temperature is limited by Technical Specifications, while the individual temperatures contribute to and remain bounded by it.
1 PLANT
REFERENCE:
97FSAR162, ESR 97-00498 l
l l
4 i
i i
E2-143 l
j
i l
CHANGES TO THE FACILITY TITLE: - Control Room HVAC BRIEF DESCRIPTION:
This change corrected the figure discrepancy that incorrectly indicated the service water system supported the Control Room HVAC.
SUMMARY
OF THE SAFETY EVALUATION:
This brought the UFSAR into agreement with the actual plant design.
PLANT
REFERENCE:
97FSAR163 E2-144
l l l
l l
CHANGES TO THE FACILITY - '
TITLE: External Suppression Pool Bypass BRIEF DESCRIPTION:
This change was made to reflect clarification that a Suppression Pool Bypass path ,
potential exists during simultaneous inerting/ purging /de-inerting of the primary ;
containment and that this is administratively controlled.
SUMMARY
OF THE SAFETY EVALUATION: ,
i This clarified that simultaneous on-line inerting/ purging /de-inerting of the primary containment is not allowed.
PLANT
REFERENCE:
97FSAR164,2-OP-24 Rev 121 & 122, IOP-24 Rev. 67 E2-145
- . . . . . . . . _ _ - - - _ - . - . . . . - . - . . - - . ~ - . ..
)
l l l
l \
l CHANGES TO THE FACILITY l
TITLE: Unqualified Coatings Inside the Unit 2 Primary Containment L . BRIEF DESCRIPTION:
i This clarified that installation oflarger ECCS Suction Strainers in Unit 2 was !
accompanied by reused head loss analysis (Calculation OMISCEL-1027), which increased l the limit for unqualified coatings. I
SUMMARY
OF THE SAFETY EVALUATION:
This clarified that installation oflarger ECCS Suction Strainers in Unit 2 was ;
accompanied by reused head loss analysis (Calculation OMISCEL-1027), which increased l the limit for unqualified coatings. The new limit is based upon the increosed surface area of the new strainers along with more conservative assumptions related to coatings j transport and cloggmg. '
l PLANT
REFERENCE:
97FS AR165, ESR 97-00601,98FSAR009 l l
l E2-146
. . ~ . . , . . .. . - . . . . - - - - . . - . . . - . . . . . . . . - . . . . - . . . . - - . . . .
i i
~
CHANGES TO THE FACILITY 1
TITLE: 1997 Operations Reorganization l BRIEF DESCRIPTION: .
I
)
This change reflected the 1997 Operations Reorganization, including the re-incorporation
- of the Loss Prevention Unit responsibilities into Operations, and the replacement of the fire truck with an equivalent hose cart.
SUMMARY
OF THE SAFETY EVALUATION:
The efTectiveness of the affected organizations and programs was not reduced.
PLAN,T
REFERENCE:
97FSAR167,97-FSAR037, OPLP-01 Rev. 6, OPLP-01.2 Rev.10 i
i l
i.
I i
l i
i-l E2-147 l
. . . - - - . . _ . ~ , . - - . - - - ,. . . . - . . . . . _ - - , - .
i CHANGES TO THE FACILITY j TITLE: Update of Refueling Accident for New Refueling Mast i BRIEF DESCRIPTIONi The refueling mast was replaced with a tubular NF-500 mast.
SUMMARY
OF THE SAFETY EVALUATION:
While weighing more, the operation of the new mast is essentially the same. GE updated GESTAR II to describe the Fuel Handling Accident for the new mast.
Pl. ANT REFERENCE- 97FSAR168 l
i E2-148 r
I __
CHANGES TO THE FACILITY TITLE: BlCll Fuel Shuffle - Mid-Cycle Outage BRIEF DESCRIPTION 1 The change supported the Unit 1 Cycle 11 mid-cycle outage's discharge and replacement of failed fuel bundles. Also, two binary fuel bundle swaps were required to address the '
extend operation with power suppression around the suspected failed fuel location.
)
l
SUMMARY
OF THE SAFETY EVALUATIONI j The BICI1 core following the fuel shuffle can continue to be safeiy operated within the !
licensing basis using the operating limits specified by the current COLR. I PLANT
REFERENCE:
97FSAR169, ESR 97-00559,97-00654 l 1
l 4
i E2-149
CHANGES TO THE FACILITY TITLE: Drywell Venting Guidance -
BRIEF DESCRIPTION:
The change reflected that the referenced figure was previously removed by 96FSAR24.
The change also addresses that the philosophy of the Emergency Operating Procedures (EOPs) is symptomatic verses prescriptive.
SUMMARY
OF THE SAFETY EVALUATION:
The EOPs which affect Drywell venting provide symptomatic guidance. This is as - I opposed to the old method which was prescriptive based on the type of associated l accident when providing venting guidance. j i
I PLANT
REFERENCE:
97FSAR170,96FSAR24
, I
)
l.
l i
l 1 l
l
! I L
1 i'
l l
E2-150 r i
-~-
l-CHANGES TO THE FACILITY TITLE: Service Water System Inservice Inspection (ISI) Boundary BRIEF DESCRIPTION:
Service Water System diagrams have been revised to change the ISI boundary per ASME Section XI to reflect that non-safety related piping downstream of RHR and CS pump room coolers, RHR pump seal coolers, and the El 1-F068A(B) e.re non class components.
SUMMARY
OF THE SAFETY EVALUATION:
Only the ISI classification of non-safety related service water components were changes.
PLANT
REFERENCE:
97FSAR171, ESR 97-00660 I
J l
l l
i l
l i
i.
E2-151 '
CHANGES TO THE FACILITY TITLE: Radiation Protection and Health Physics Organization Changes BRIEF DESCRIPTION:
The Radiation Protection and Health Physics Organization has been revised.
SUMMARY
OF THE SAFETY EVALUATION:
This was an administrative change to the Radiation Protection and Health Physics Organization.
PLANT
REFERENCE:
97FSAR172 9
E2-152
1 I I i
i CHANGES TO THE FACILITY )
l TITLE: Radiation Monitor Descriptions i BRIEF DESCRIPTION:
1 This change corrected or clarified UFSAR descriptions for the MSLRM, Reactor Building Radiation Monitor, and Senice Water monitoring for the Turbine Building j Closed Cooling Water system.
{
J l
SUMMARY
OF THE SAFETY EVALUATION:
These were corrections or clarifications to the description of the plant.
PLANT
REFERENCE:
97FSAR17'3,97FSAR68, and 97FSAR69 I
1 l
l i
E2-153
._._ . . . _ . . . _ . . _ _ . _ . - _ _ _ . _ _ _ _ _ _ . _ . - . _.. ______ . ~ __ _.._..
i
! i l
1 s
l i
l 1
CHANGES TO THE FACILITY j' TITLE: Residual Heat Removal / Core Spray Keep-Fill Setpoints ] !
BRIEF DESCRIPTION: i RHR/CS keep-fill station setpoints have been revised to reflect the optimized operating pressures addressed in EER 94-0021.
SUMMARY
OF TIIE SAFETY EVALUATION:
The keep-fill stations will continue to operate as originally intended.
PLANT
REFERENCE:
97FSAR174, EER 94-0021 l
E2-154 i
i l
G.IANGES TO THE FACILITY i TITLE: Containment Atmosphere Control System Description DRIEF DESCRIPTION:
)
An editorial change to reflect the correctly reference the appropriate section was made. l i
1
SUMMARY
OF THE SAFETY EVALUATION- l 1
1 This was an editorial change. l 1
PJ[, ANT
REFERENCE:
97FSAR175 :
1 i
i f
l !
I I
l E2-155 l
l l
CHANGES TO THE FACILITY TITLE: Control Room Chlorine Detector Response Time BRIEF DESCRIPTION:
The change represented a clarification to the accepted commitment for Control Room Chlorine Detector response time.
SUMMARY
OF THE SAFETY EVALUATION:
The clarification conformed to the requirement of Regulatory Guide 1.95, Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release.
PLANT
REFERENCE:
97FSAR176 l
1.
s i
E2-156
f I
I l
l
. CHANGES TO THE FACILITY TITLE: Update of Drywell Peak Temperatures - Unit 1 l
BRIEF DESCRIPTION:
The description was updated to reflect the evaluation and maximum temperature profile for Unit I local drywell temperatures. A reference to OENP-58 has been included as a source of acceptable monitoring and temperature profile evaluations.
SUMMARY
OF THE SAFETY EVALUATION:
The bulk drywell temperature is limited by Technical Specifications, while the individual temperatures contribute to and remain bounded by it.
PLANT
REFERENCE:
97FSAR177, ESR 97-00529 I
i i
)
i l
l l l E2-157
l P
i i
l CHANGES TO THE FACILITY l
TITLE: Service Air Relief Valve Setpoint i l
BRIEF DESCRIPTION: l l
The Service Air relief valve setpoints were being revised to reflect plant design.
SUMMARY
OF THE SAFETY EVALUATION: l This was not a change to the facility but a change to documentation to reflect design /li:ensing basis.
ELANT
REFERENCE:
97FSAR179, ESR 97-00410 i
i l E2-158 l
CHANGES TO THE FACILITY 31TLE: Clarification of Controlling Standard NFPA STD 72E BRIEF DESCRIPTION:
This clarification added the date (1974) associated with the appropriate edition of NFPA STD 72E.
SUMMARY
OF THE SAFETY EVALUATION:
This clarification added the appropriate edition of NFPA STD 72E used to develop the-plant fire protection program..
PLANT
REFERENCE:
97FSAR180, CR 97-02839 f E2-159 l
1 CHANGES TO THE FACILITY l
. TITLE: Crack Arrest Verification System Abandonment- Unit 1 BRIEF DESCRIPTION:
This change reflected the abandonment of the Crack Arrest Verification (CAV) system - ,
Unit 1, and removal of a piping " hot spot." !
SUMMARY
OF THE SAFETY EVALUATION; l l
The removal of the remaining CAV system will not effect the operation of the Unit nor will it affect equipment or systems important to safety.
PLANT
REFERENCE:
97FSAR181, ESR 95-00236, PM 93-039, ESR 94-00203 i
l l
l l
l-l l
i !
E2-160 l
t i
i CHANGES TO THE FACILITY TITIJJ Inservice Inspection Technical Report (0BNP-TR-001) i
. BEFEF DESCRIPTION:
The :hange reflects the implementation of the third ten year inspection interval per ,
'AMSE Section XI Code. 2 l
l
SUMMARY
OF THE SAFETY EVALUATION:
ISI Technical Report (0BNP-TR-001), identifies the systems or portions of systems whose components will be subject to the rules and requirements of AMSE Section XI i Code.
i PLANT
REFERENCE:
97FSARI82, ESR 97-00639 j l
l 1
i l
j 1
l l
l- ,
l E2-161 !
l CHANGES TO THE FACILITY TITLE: Emergency Core Cooling System Response Time Testing Update 1
l BRIEF DESCRIPTION:
The change updated the ECCS Response Time Testing to more closely reflect the SAFER /GESTR evaluation.
- l.
SUMMARY
OF THE SAFETY EVALUATION:
The' change updated the UFSAR to be consistent with the NRC accepted basis document for ECCS performance.
PLANT
REFERENCE:
97FSAR183, ESR 97-0508 l-l I
o E2-162 l
l
)
l l
d p
1 CHANGES TO THE FACILITY I TITLE: B2Cl3 Startup Test Results ;
l BRIEF DESCRIPTION: l Section 14,4.2.2, which contains startup physics test results from the latest cycle was revised to reflect the recent startup.
SUMMARY
OF THE SAFETY EVALUATION:
The description was revised to include the latest test results.
I l
PLANT
REFERENCE:
97FSAR184, PT-50.0 Rev.18 l
l l
)
1 1
! I l l i- l E2-163 i
1
i l
1 1
I i
CHANGES TO THE FACILITY TITLE: Primary Containment Ventilation BRIEF DESCRIPTION:
The description has been changed to reflect a combination of manual balance dampers and air operated dampers verses motor operated dampers.
SUMMARY
OF THE SAFETY EVALUATION: l l
j The description has been revised to reflect plant configuration, PLANT
REFERENCE:
98FSAR001 ]
I L
l l '
E2-164 l
\-
I CHANGES TO THE FACILITY '
TITLE: 1997 Site Reorganization ;
t
' BRIEF DESCRIPTION:
i This reflected the 1997 site reorganization, except Operations.
)
SUMMARY
OF THE SAFETY EVALUATION: i The changes were organizational and the effectiveness of the organizations and programs ;
involved were not reduced.
PLANT
REFERENCE:
98FSAR002 1
J 1
l l
E2-165 1
.. . .= - - _ - - - . - __ .- . . - . . .
l 4
I i
CHANGES TO THE FACILITY !
TITLE: Fire Door Evaluation Results
- BRIEF DESCRIPTIONi i This change addressed the location of fire door evaluation results. I
SUMMARY
OF THE SAFETY EVALUATION:
This was an administrative change to correct the inconsistency in describing the location of the fire door evaluation results.
PLANT
REFERENCE:
98FSAR003 c
E2-166
CHANGES TO THE FACILITY TITLE: Well Water System BRIEF DESCRIPTION:
The Well Water System has been decommissioned.
SUMMARY
OF THE SAFETY EVALUATION:
l The county water system will continue to provide reliable makeup to the Fire Protection supply tank. The Fire Protection supply tank inventory requirement was not affected.
PLANT
REFERENCE:
98FSAR004 1
I l
l l
l i.
l- E2-167 i
- i k
I ,
L l
E l
1
?
i CHANGES TO THE FACILITY :
TITLE: Core Spray Room Sump Identification Numbering :
BRIEF DESCRIPTION:
t i
Both Units CS sump tag numbers were corrected.
t
?
SUMMARY
OF THE SAFETY EVALUATION: i This was a clerical change.
PLANT
REFERENCE:
98FSAR005 I
t h
I 6
I 1
I
. i l
1 i
i ?
E2-168
~. . . _ - . .. _ __. _ . _ .
i i
CHANGES TO THE FACILITY ,
1 TITLE: Seismic Design Basis i r
-BRIEF DESCRIPTION:
This corrected a reference to the earthquake design basis documentation. !
SUMMARY
OF THE SAFETY EVALUATION:
1 This was an editorial change to correct references to the earthquake design basis l
documentation.
I t
PLANT
REFERENCE:
98FSAR006 i
.i l
F i
i 1
' j i
l
+
I E2-169
l 4
CHANGES TO THE FACILITY TITLE: ' Loss of Coolant Accident Analysis Results BRIEF DESCRIPTION:
l The description of the LOCA analysis results were enhanced. .
SUMMARY
OF THE SAFETY EVALUATION:
l This corrected and added detail to enhance the description. 1 PLANT
REFERENCE:
98FSAR008 i
i I
1 I
i
? ,
l l
t i
Y j
l.
l E2-170 j r
i
, _ _ __ _.. i
)
i ,
?
l j
l CHANGES TO THE FACILITY I l
TITLE: Residual Heat Removal and Core Spray Suction Strainer Replacement - Unit 1 j BRIEF DESCRIPTION:
This change implements the ECCS suction strainer enlargement for NRC Bulletin 96-03.
SUMMARY
OF THE SAFETY EVALUATION:
The installation of the new strainers replaced the existing strainers with ones of sufficient size and design features to ensure a margin of safety that, during a Design Bases Event, the requirements of 10 CFR 50.46 are met for the ECCS.
PLANT
REFERENCE:
98FSAR009, ESR 97-00255, OSD-18,97FSAR165 l
1 1
1 I
l E2-171 i
.I
__ _ . - _ ., -- i
i l'
. i l
l' l CHANGES TO THE FACILITY TITLE: Storm Water Level Reference Corrections
- BRIEF DESCRIPTION:
This corrected references associated with storm water levels.
SUMMARY
OF THE SAFETY EVALUATION: i The corrections were editorial.
PLANT
REFERENCE:
98FSAR010 l L
l E2-172
, 4
L CHANGES TO THE FACILITY TITI.E: Fatigue Monitoring Program BRIEF DESCRIPTIONI Additional information was added to the UFSAR description of the Fatigue Monitoring Program to facilitate conversion to ITS.
SUMMARY
OF THE SAFETY EVALUATION:
Additional detail was added to the description of the Fatigue Monitoring Program.
PLANT
REFERENCE:
98FSAR011 b
i t
t i
f E2-173 )
l
t i
CHANGES TO THE FACILITY ;
t TITLE: Additionof Power Uprate Reference
{.
i BRIEF DESCRIPTION: !
The UFSAR was updated to add a reference to the Brunswick Units 1 and 2 Analysis !
Basis Document for the 105% Power Uprate document. !
l
SUMMARY
OF THE SAFETY EVALUATIO_N_1 I'
Additional detail was provided by the reference for Power Uprate.
PLANT
REFERENCE:
98FSAR012 1
l i
.i l
l I
i l
E2-174
I 1
CHANGES TO THE FACILITY- )
TITLE: Updated Description ofIntake Canal Diversion Structure BRIEF DESCRIPTION; The description of the intake canal diversion structure was updated.
SUMMARY
OF THE SAFETY EVALUATION:
Additional detail has been added to the description and purpose of the intake canal diversion structure related to diverting sea turtles and other large marine life from the canal.
ELANT
REFERENCE:
98FSAR013 l
l i- l l
l l
I i
- l. 1 E2-175
. . . - . - - . - . . . ~ - . . - ~ . . - . _ . . . . .-. .. . - . . . _ . - . . - . - . . .
i l
j CHANGES TO THE FACILITY !
TITLE: Update of the Facility Plot Plan i
BRIEF DESCRIPTION: I The Facility Plot Plan was updated to reflect the removal of Facilities Storage Building.
SUMMARY
OF THE SAFETY EVALUATION:
The storage building, located outside the protected area, was not associated with safety related equipment or activities, i
PLANT
REFERENCE:
98FSAR014 l
i I
l 1
E2-176 i
CHANGES TO THE FACILITY TITLE: Containment Atmosphere Dilution (CAD) Vessel Pressure Control BRIEF DESCRIPTION:
This deleted " automatic" from the description of the CAD vessel pressure control.
SUMMARY
OF TiiE SAFETY EVALUATION: l l
The change provided clarification of the description of current CAD operation.
I PLANT
REFERENCE:
98FSAR017 l l
l l
i s
l E2-177 b !
i i
CHANGES TO THE FACILITY TITLE: . Fuel Pool Cooling System BRIEF DESCRIPTION:
This updated the Fuel Pool Cooling system description to address heavy loads, minimum i water levels, power uprate effects, and to address editorial corrections to the description.
)
i 1
i
SUMMARY
OF THE SAFETY EVALUATION:
Most of the change was editorial, and the power uprate effects being addressed are bounded by the current non-power uprate conditions currently specified in the UFSAR.
I l
PLANT
REFERENCE:
98FSAR019 i
i.
l 1
i.
e i
i I
E2-178 l
I _ _ _
\
CHANGES TO THE FACILITY TITLE: Detergent Drain Tank Processing BRIEF DESCRIPTION:
This updated the description to address the optional DDT vendor processing skid
SUMMARY
OF THE SAFETY EVALUATION:
The current and alternate processing capability of DDT is non safety-related.
PLANT
REFERENCE:
98FSAR022 I
f 1
l E2-179 1
- . .- ,- - . . - . , . . - . . . . . - . - . - . . - . - . _ . - . . . . - - . . . . ~ -
- CHANGES TO THE FACILITY TITLE: Augmented Off-Gas System (AOG) Operating Parameters Clarification BRIEF DESCRIPTION:
This change provided clarification of AOG system operating parameters. The charcoal !
bed temperature as the critical parameter was included.
SUMMARY
OF THE SAFETY EVALUATION:
This was a clarification of AOG system operating parameters.
PLANT
REFERENCE:
98FSAR023,97FSAR092 i
E2-180
. . . . _ _ - . . . . _ - - _ _ . _ . _._.__._ . ._ ..._. _ _ ___-__..m__ . . . . .- _ _ _ _ .
W CHANGES TO THE FACILITY TITLE: Trip Setpoint Revisions BRIEF DESCRIPTION:
Setpoints were changed to support the 24 month cycle and ITS changes.
SUMMARY
OF THE SAFETY EVALUATION:
. ITS was evaluated as part of Technical Specification Amendments 203/233.
PLANT
REFERENCE:
98FSAR025,97FSAR136,97FSAR178, ESRs 97-00025 l and 97-00026 - l i
I
)
l I
i I
i l
l 1
i I
E2-181 1
L CH ANGES TO THE FACILITY TITLE: Spent Fuel Shipping Cask Handling BRIEF DESCRIPTION; This provided clarification that when the cask is up-righted with the primary yoke (non-redundant) an actual lin occurs. The lin during the transfer from tilting cradle to secondary yoke on the 20 foot elevation of the reactor building is a short non-redundant lift
SUMMARY
OF THE SAFETY EVALUATION:
With the December 2,1997, issuance of Technical Specification Amendments Nos.
190/221 for Facility Operating Licenses No. DPR-71/62 the assumption used in the analysis of the credibility of a spent fuel shipping cask drop event was evaluated and ,
supports the change to the UFSAR.
PLANT
REFERENCE:
98FSAR-029, ESR 97-00362,96FSAR-168,97FSAR-123 i
i i
I l
l E2-182
l t
l -:' -
1 i
CHANGES TO THE FACILITY TITLE: Clerical Change to Table Comment Numbering L
BRIEF DESCRIPTION:
1 1'
. Gaps made in the sequential numbering of table comments were eliminated by !
renumbering the comments.
SUMMARY
OF THE SAFETY EVALUATION:
The change was clerical.
l PLANT
REFERENCE:
98 FSAR-030,97FSAR-099 l
l 4
5 l
l l
l l
l E2-183
i l
i l +
CHANGES TO THE FACILITY l TITLE: Update for B1Cl2 Core Reload :
l BRIEF DESCRIPTION: :
This included Unit 1 Cycle 12 nuclear fuel reload updates, and incorporated feedwater
(
transient results to support implementation ofITS Turbine Bypass Valves Out of Service .l l (TBVOOS) operation. Format changes were made for clarification and to simplify future I
! UFSAR maintenance. I i
SUMMARY
OF THE SAFETY EVALUATION:
L The reload core was designed and will be operated in such a manner as to remain within all established safety limits.
PLANT
REFERENCE:
98FSAR036, ESR 97-0680 l
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E2-184
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l CHANGES TO THE FACILITY TITLE: . Control Building Heating Ventilation and Air Conditioning System BRIEF DESCRIPTION:
Temporary condensing units were installed during installation of new Control Building I i HVAC system condensmg umts by ESR 96-00757.
t
SUMMARY
OF THE SAFETY EVALUATION:
The NRC accepted a one time Technical Specification change per Amendments 191/222 i to licenses DPR-71/DPR-62 to support the control building pressure boundary breach, and the environmental exposure of the temporary condensing units.
PLANT
REFERENCE:
ESR 97-00598, (Note: see ESR 96-00757 and 98FSAR042) l I
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- l. .
- i. i i
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i !
E2-185
m CHANGES TO THE FACILITY -
TITLE: Diesel Fuel Storage Tank Room Fire Barrier BRIEF DESCRIPTION:
The fire barrier for the emergency diesel generatorjacket water return piping, passing !
through the emergency diesel generator fuel storage tank rooms, is no longer required. ;
UFSAR section 9.5 referenced Appendix R Safe Shutdown Analysis BNP-E-9.004 was :
revised to include justification for use of off-site power for a fire in the emergency diesel generator fuel storage tank rooms.- 4
SUMMARY
OF THE SAFETY EVALUATION:
A fire in the emergency diesel generator fuel storage tank rooms will not impact the [
cables and components that are required to utilize off-site power as the primary means of -
plant shutdown. i PLANT
REFERENCE:
ESR 96-00311 ;
I 1
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E2-186 l
l 1
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l i
CHANGES TO THE FACILITY TITLE: Unit 2 Torus Drain System i BRIEF DESCRIPTION:
l A temporary pumping system was used to drain / filter the Unit 2 Suppression Pool (i.e., i Torus) through the Unit 2 Condensate Filter Demineralizer system during the refueling i outage. i
SUMMARY
OF THE SAFETY EVALUATION: !
The temporary drainage system will not prevent equipment from performing safety related functions. The Reactor Building design provides physical separation of divisio._ ;
of safety-rated equipment for flooding, and secondary containment is maintained (when l required). The Radwaste Building / systems are designed to contain any spillage or leakage, and bounds any concerns related to the processing oflow level radioactive water. i i
i PLANT
REFERENCE:
ESR 97-00061,2SP-97-206,97FSAR-129 I i
I E2-187
l l
CHANGES TO THE FACILITY j l
TITLE: Unit 1 Torus Drain System l
[
BRIEF DESCRIPTION: l A temporary pumping system was used to drain / filter the Unit 1 Suppression Pool (i.e.,
Torus) through the Unit 1 Condensate Filter Demineralizer system during the refueling outage.
-SU' MMARY OF THE SAFETY EVALUATION:
'l The temporary drainage system will not prevent equipment from performing safety !
related functions. The Reactor Building design provides physical separation of divisions l of safety-rated equipment for flooding, and secondary containment is maintained (when !
required). The Radwaste Building / systems are designed to contain any spillage or leakage, and bounds any concerns related to the processing oflow level radioactive water. ;
i PLANT
REFERENCE:
ESR 97-00280 ;
E2-188
- - , , , ,v..- -
-e
- _ . _ . - ~ _ . _ . _ . _ - . . _ _ . . . _ . . . . . _ . _ _ . _ . _ _ . . . . _ . - . _ _ _ . . _ .
?~ l I
i CHANGES TO THE FACILITY t f
r TITLE: '
Over-Pressure Protection of Unit 2 Drywell Drain Sump Discharge Lines' i BRIEF DESCRIPTION: ;
- Over-Pressure Protection of Drywell Drain Sump Discharge Lines was provided per ,
' Generic Letter 96-06 to address thermal expansion of the fluid in isolated piping sections.
Rupture discs in each pump discharge line, inside the contairunent, were installed. .
SUMMARY
OF THE SAFETY EVALUATION: ,
The rupture discs are passive devices, inside the containment, set above the design pressure of the drain piping. The location is such that the discharge would not impinge on !
other safety related systems. '
i PLANT
REFERENCE:
ESR 97-00232 :
I i
i i
I l
i 1
I l
1 E2-189 -
L l~
i CHANGES TO THE FACILITY .
TITLE: Over-Pressure Protection of Unit 1 Drywell Drain Sump Discharge Lines 1
BRIEF DESCRIPTION:
Over-Pressure Protection of Drywell Drain Sump Discharge Lines was provided per -
Generic Letter 96-06 to address thermal expansion of the fluid in isolated piping sections. ,
Rupture discs in each pump discharge line, inside the containment, were installed.
r
SUMMARY
OF THE SAFETY EVALUATION: :
The rupture discs are passive devices, inside the containment, set above the design pressure of the drain piping. The location is such that the discharge would not impinge on other safety related systems. '
PLANT
REFERENCE:
ESR 97-00274
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! E2-190 l
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F
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CHANGES TO THE FACILITY TITLE: Control Room Annunciator Ring-Back Circuit i BRIEF DESCRIPTION:
The Control Room annunciator ring-back circuit associated with the annunciatorjoy-stick *
' " Silence" position was decommisioned. i i
SUMMARY
OF THE SAFETY EVALUATION: l Disabling the ring-back circuit does not afrect operation of the plant since it performs no system control function and only gave audible indication that a previously annunciated condition had cleared. !
PLANT
REFERENCE:
ESR 9700264 !
l l
J i
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l l
l E2-191 i
/
CHANGES TOlHE FACILITY l'
TITLE: Reactor Cavity Floor Penetration Seals BRIEF DESCRIPTION:
Carbon steel reactor cavity floor penetration seal blind covers were replaced with dimensionally identical aluminum covers.
SUMMARY
OF THE SAFETY EVALUATION:
The covers seal the cavity opening during flooding of the cavity to support refueling. The load drop evaluation has determined that due to the characteristics of potential load objects and missiles, the aluminum covers are of sufficient thickness to prevent penetration.
PLANT
REFERENCE:
ESR 97-00297 l
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1 l- E2-192
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CHANGES TO TFIE FACILITY !
' TITLE: Temporarily Disabling the Unit 2 Circulating Water Pump Trip ;
' BRIEF DESCRIPTION:
i The Unit 2 condenser pit high water level trip of the Circulating Water pumps was temporarily disabled due' to unreliable operation of the level switches. .
i
SUMMARY
OF THE SAFETY EVALUATION: ,
Along with existing annunciation, local level indication or flood status lights, ,
compensatory operator actions are in place to monitor the condenser pit. The disabling of the trip circuit will not create a Balance of Plant related transient outside the UFSAR ;
analyzed transients (e.g., loss of condenser vacuum, turbine trip, etc.). l t
! PLANT
REFERENCE:
97-00357, ESR 96-00759 i i
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l-i l
E2-193 i l
l- -
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I CHANGES TO THE FACILITY i i
TITLE: Fire Detection Surveillance Test Frequency BRIEF DESCRIPTION: ;
I Fire detection surveillance test frequency was extended from six months to annually :
l- based on engineering, and recent NFPA and NML, evaluations of the impact on l
l reliability of the detection systems. '
SUMMARY
OF THE SAFETY EVALUATION:
The change did not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
j PLANT
REFERENCE:
ESR 9700375 j l .
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l E2-194 :
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CHANGES TO THE FACILITY l TITLE: Evaluation of Core Spray Minimum Flow Valve Operation i l
BRIEF DESCRIPTION:
l !
This clarified that at maximum dp and degraded voltage conditions, the CS minimum !
flow valves (i.e., minimum flow pump protection) may fail to automatically close or open l
. by either automatic logic or operation action at the control switches.
i
SUMMARY
OF THE SAFETY EVALUATION: !
l The evaluation demonstrated that each CS loop is capable of pumping the required 4625
. gpm of water from the Suppression Chamber to the Reactor Vessel with the vessel ;
j pressure at 113 psig. A valve failure (open) would not create a system failure due to flow diversion as flow is limited to acceptable values by installed orifices. The valves were also evaluated as meeting acceptable Primary Containment Isolation requirements.
1 i- ,
' t PLANT
REFERENCE:
ESR 97-00407 i
i h
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i t
E2-195 i s
i N ,
i CHANGES TO THE FACILITY TITLE: Heater Drain Pump Automatic Start Logic
- BRIEF DESCRIPTION:
A temporary modification to the Unit 2 Heater Drain Pump automatic start logic w~as required as a Heater Drain Deaerator normal level start permissive switch failed open.
I
SUMMARY
OF THE SAFETY EVALUATION:
i The components affected by this change were non-safety related. The potential Reactor Feedwater transient made possible by bypassing this permissive, was much less severe than the Loss of Feedwater Flow Event analyzed in the UFSAR. :
PLANT
REFERENCE:
ESR 97-00429,97FSAR-122 '
1 i
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l E2-196 I
N CHANGES TO THE FACILITY
. TITLE: Unit 2 Temporary Air Service BRIEF DESCRIPTION:
A temporary portable electric air compressor with manifolds and air conduit was installed to supplement compressed air service during the B213R1 refueling outage in the Unit 2 l Reactor Building and drywell. 3 i
i
SUMMARY
OF THE SAFETY EVALUATION: )
The additional compressed gas cylinders, compressor and manifolds were evaluated as potential initiators of equipment failures (i.e., missiles) and it was determined that the safe shutdown capability was maintained, and safety related functions were not affected..
PLANT
REFERENCE:
97FSAR-146, ESR 97-00494 r
{
l' i E2-197
1 i
9 1
i CHANGES TO THE FACILITY -
. TITLE: Unit 1 Temporary Air Service -
i BRIEF DESCRIPTION' 1
)
A temporary portable electric air compressor with manifolds and air conduit was installed l '
to supplement compressed air service during the B112RI refueling outage in the Unit 1 Reactor Building and drywell.
SUMMARY
OF THE SAFETY EVALUATION:
i The additional compressed gas cylinders, compressor and manifolds were evaluated as potential initiators of equipment failures (i.e., missiles) and it was determined that the i safe shutdown capability was maintained, and safety related functions were not affected.. !
i PLANT
REFERENCE:
ESR 97-00714 l
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E2-198 !
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L CHANGES TO THE FACILITY TITLE: Unit 1 Shutdown Cooling Bonnet Pressure Equalization Line BRIEF DESCRIPTION:
The Unit 1 RIiR Shutdown Cooling suction isolation valve El 1-F009 has had a bonnet equalization line and Local Leak Rate Testing test connection installed.
SUMMARY
OF THE SAFETY EVALUATION:
The Shutdown Cooling suction isolation valve's safety function requires isolation in one direction only and defeating the bi-directional isolation capabilities of the valve does not affect either liigh/ Low interface isolation, containment isolation, or the ability to place l
the system in shutdown cooling.
l l
PLANT
REFERENCE:
ESR 97-00355 l v
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E2-199 -
3 CIIANGES TO TIIE FACILITY TITLE: Air Purge of the Steam Jet Air Ejectors BR!EF DESCRIPTION:
The operating procedure has been revised to support a service air purge of the Steam Jet Air Ejectors (SJAE) during normal operation.
SUMMARY
OF THE SAFETY EVALUATION:
The procedure uses installed piping and equipment and with the service air purge the off-gas flow is still maintained significantly below the point which could cause a loss of vacuum. The injection of service air into the SJAEs can not adversely affect safe shutdown of the reactor following an accident.
PLANT
REFERENCE:
1OP-30, OSP-97-004 E2-200 i
\
l I
4 CllANGES TO TIIE FACILITY TITLE: "Smartstems" Testing for Motor Operated Valves BRIEF DESCRIPTION:
This change supported the implementation of Teledyne "Smartstems" testing of some Motor Operated Valves (MOVs) in the Generic Letter 89-10 test program.
SUMMARY
OF THE SAFETY EVALUATION:
The new test using the improved diagnostic equipment provides greater accuracy of MOV performance testing. With the associated modification to the MOV stems there is still sufficient design margin over other components within the valves. The addition of the associated strain gauges does not impair the capability of the valves to perform their intended functions.
PLANT
REFERENCE:
ESR 97-00158 E2-201
T l.
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CHANGES TO THE FACILITY TITLE: Control Building HVAC Tornado Dampers BRIEF DESCRIPTION:
ESR 97-00161 corrects a minor conflict in the stated operability requirements for the Control Building HVAC tornado' dampers that was documented in ESR 96-0005.
t i
SUMMARY
OF THE SAFETY EVALUATION: :
The ESR only corrected a minor conflict documented in a previous evaluation used to support the Technical Specification surveillance testing of the Control Building HVAC tornado dampers.
t PLANT REFERENCE; ESR 97-00161 i
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E2-202
CIIANGES TO TIIE FACILITY TITLE: Failure of Drywell Equipment Drain Sump Purnps BRIEF DESCRIPTION:
The failure of both Unit 2 drywell equipment drain sump pumps was evaluated to support continued operation, while using the drywell floor drain sump integrating system to meet the drywell leakage monitoring requirements of Technical Specifications.
SUMMARY
OF THE SAFETY EVALUATION:
The available indication still supported the Technical Specification drywell leakage determinations.
PLANT
REFERENCE:
ESR 9700291 E2-203
5 i
i CHANGES TO THE FACILITY t
' TITLE: Charcoal Testing of Control Room Emergency Ventilation System Filters BRIEF DESCRIPTION:
1 As the Control Room Emergency Ventilation System Filters do not have humidity .
controls a more stringent method of charcoal testing is being used. ;
i
SUMMARY
OF THE SAFETY EVALUATION: .
The more stringent method of charcoal testing ensures that the Technical Specification charcoal efficiency requirements are met.
i PLANT
REFERENCE:
ESR 97-00078 i i
i t
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f E2-204 i
,y CHANGES TO THE FACILITY TITLE: Fuel Oil Sampling BRIEF DESCRIPTION:
The procedure (i.e., E&RC-1010) was revised to include additional samples and analysis along with inclusion of Emergency Operating Facility fuel oil tank sampling to support better tracking of fuel oil on site.
SUMMARY
OF THE SAFETY EVALUATION:
The changes allow for better analysis of the fuel oil to catch and correct any problems associated with the fuel oil in a timely manner before it would cause any major problems.
PLANT
REFERENCE:
E&RC-1010 6
i .
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! E2-205 l
I L, ,
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CHANGES TO THE FACILITY
\
TITLE: Decommissioning Space Heaters !
BRIEF DESCRIPTION:
The Unit 2 Reactor Building Motor Control Center (MCC) 120 Volt Distribution Panels j were decommissioned. They generally have supplied motor and MCC space heaters in
- the Reactor Building.
SUMMARY
OF THE SAFETY EVALUATION:
The Reactor Building environment remains relatively steady and the MCCs and motors located there do not require space heating. The associated equipment is capable of performing its desired function after being exposed to accident conditions without the assistance of space heaters.
l PLANT
REFERENCE:
ESR 96000617 I
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r E2-206 f
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l CHANGES TO THE FACILITY TITLE: Temporary Condensate Wash-Line BRIEF DESCRIPTION:
A temporary line was installed to support the outage washdown of the Unit 2 Torus with i
water from the Condensate Storage Tank. This was used to support the ECCS suction
. streiner modifications during the outage.
I S'UMMARY OF THE SAFETY EVALUATION:
i The temporary installation maintained Secondary Containment and Fire Protection i boundary integrity, and did not impact the operability of safety related equipment. i PLANT
REFERENCE:
. ESR 97-00065,97FSAR-079 l l
l l
4 i
E2-207
)
r CHANGES TO THE FACILITY TITLE: Temporary Hose for Unit 2 Torus Refill BRIJ;2. DESCRIPTION:
A temporary flowpath from the Waste Surge Tank to the Unit 2 Torus was installed to support refilling the Torus after installation ofnew ECCS suction strainers.
SUMMARY
OF THE SAFETY EVALUATION:
The temporary installation maintained Secondary Containment boundary integrity and did not impact the operability of safety related equipment.
PLANT
REFERENCE:
ESR 97-00064, ESR 96-00142,97FSAR077 I
r E2-208 a
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CHANGES TO THE FACILITY j l
TITLE: Fire Protection Program l
l BRIEF DESCRIPTION:
The changes made revised the compensatory measures associated with fire hose and !
HPCI CO 2impairments, update titles, and clarified the surveillance frequency of the j diesel driven fire pump such that the Units are not required to be in shutdown for !
inspection. j
SUMMARY
OF THE SAFETY EVALUATION:
I l The changes made to the fire protection program document include additional [
compensatory measures and the clarification of surveillance testing addressed in this ;
change do not affect the ability of the systems to function as required in accident l
mitigation roles. !
t I
PLANT
REFERENCE:
OPLP-01.2 ;
6 i
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E2-209 l
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L CHANGES TO THE FACILITY L- TITI.E: Check Valve Predictive Maintenance Program BRIEF DESCRIPTION:
l Predictive Maintenance routes for the check valve program were adjusted based on engineering review and historical performance. Valves were also added or deleted or rates changed based plant configuration and modifications.
SUMMARY
OF THE SAFETY EVALUATION:
( The program is in response to Institute of Nuclear Power Operations (INPO) l recommendations and is not in response to Regulatory Guide 1.33, Quality Assurance Program Requirements (Operation).
PLANT
REFERENCE:
0ENP-2703 Rev. 3 l
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E2-210 l
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CHANGES TO THE FACILITY t
TITLE: Reactor Building Radiation Monitor Environmental Qualification BRIEF DESGIPTION:
The Reactor Building Radiation Monitors have been excluded from the EQ program as justified per Regulatory Guide 189 . , Appendix E Category 3d l
SUMMARY
OF THE SAFETY EVALUATION:
The safety function of the Reactor Building Radiation Monitors is performed prior to the development of any harsh environment resulting from a postulated LOCA or High
! Energy Line Break.
PLANT
REFERENCE:
98FSAR040, ESR 9700586 l !
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L l
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T E2-211 l
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4 CH ANGES TO THE FACILITY TITLE: Discharge Canal Level Control i BRIEF DESCRIPTION:
The description of discharge canal level control was updated to reflect the current -
process of starting or stopping circulating water discharge pumps and adjusting I circulating water intake flow. Adjustment of the discharge pump valve positions as described is not required.
SUMMARY
OF THE SAFETY EVALUATION:
Operation of the discharge canal is monitored and controlled consistent with the requirement established by the National Pollutant Discharge Elimination System permit. .!
The method oflevel control has no effect on analyzed accidents or the canal's capability l
to support releases from the site.
PLANT
REFERENCE:
97FSAR112 I
t i
L 1
1 l
l E2-212 I I
i )
ENCLOSURE 3 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 BSEP QUALITY ASSURANCE PRGGRAM CIIANGE REPORT l