ML20236L916
| ML20236L916 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/30/1998 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20236L893 | List: |
| References | |
| NUDOCS 9807130228 | |
| Download: ML20236L916 (94) | |
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I i Docket No. 50-423 B17349 I
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I Attachment 2 -
Millstone Nuclear Power Station, Unit No. 3 Addendum 9 - June 30,1998 to Annual Report dated February 28,1997 1
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1 I i June 1998 9807130228 990630 I PDR ADOCK 05000423 i K PDR i;-
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Docket No. 50-423 B17349 INTRODUCTION None of the plant design changes described herein constitute, nor constituted, an unreviewed safety question per the criteria of 10CFR50.59.
PLANT DESIGN CHANGES DCR Number - Title (FSAR Sections, Tables, and Fiaures Affected)
' M3-96054 Containment Quench Spray System, Recirculation Spray System, and Safety. Injection System Changes (6.2.1, 6.3.1; processed with FSARCR 97-MP3-550)
M3-96064 Safety Grade Cold Shutdown Analysis (5.4, 6.3, 7.4, 7.6, 9.1, 9.2, 9.3,10.3,10.4, T3.6-3, T5.4-7, T9.2-1, T9.2-2, T9.2-10; processed with FSARCR 98-MP3-45)
M3-96069 Containment Quench Spray System, Recirculation Spray System, and Safety injection System Changes (6.2.1, 6.3.1; processed with FSARCR 97-MP3-550)
M3-96070 Steam Generaar Pressure Relief Valve Disc Material Change (T10.3-3; proc Jssed with FSARCR 96-MP3-36)
L M3-97007 Power Operated Relief Valve Block Valves (5.4.12, 5.4.13; L processed with FSARCR 97-MP3-528)
M3-97045 Containment Recirculation System Pump Restriction Orifices (38, 6.2, 6.5, 7.3, T6.2, T6.3, .T7.5, F.6.2; processed with FSARCR 97-MP3-543)
. M3-97057- Containment Electrical Penetration Area Modifications (FPER 5,8, T4-1; processed with FSARCR 98-MP3-17) i.
' M3-97093 Active Valve Reconciliation Project (T3.98-13, T3.9N-12, 9.3.4; processed with FSARCR 97-MP3-592)
M3-97097 Service Water Design' Temperature Changes (9.2.1,T9.2-1, T9.2-2); processed with FSARCR 97-MP3-561) 1
a Docket No. 50-423 B17349
- M3-97100 Loss of Component Cooling Water to Chemical Volume Control Letdown Heat Exchanger Modifications (T9.3-5; processed with FSARCR 98-MP3-9)
M3-97102 Emergency ~ Core Cooling System Limited Passive Failure Design Criteria Changes (5.2.5, 6.3.2, T6.3-6; processed with FSARCR 97-MP3-569)
M3-97106 Refueling Water Storage Tank and Quench Spray Pumps Setpoint Changes (6.3.2, 6.3.3, T6.3-11, F6.3-6; processed with FSARCR 97-MP3-594) .
M3-97119 - Relocation of the Post Accident Sampling Drain (5.2.5, 9.3.2; processed with FSARCR 98-MP3-7)
( M3-98003 ' Inadvertent' Safety injection Actuation at Power (3.9N, 5.4, 7.2, 7.6,- 7.7, 8.3,15.5, T1.10-1, T3.6, T5.4, T15.5-1, F3.6-14, F7.7-4, F15.5; processed with FSARCR 98-MP3-55) i . M3-98005 Steam Atmospheric Relief Isolation Valve Reinstatement (3B,'
10.3.3; processed with FSARCR 98-MP3-11)
- n M3-98011 Containment ' Atmosphere Radiation Monitor Setpoint Change (T1.8-1, 5.2.5; processed with FSARCR 98-MP3-22)
L M3-98015 Travel Limiter Installation (T9.2-10; processed with FSARCR 98-MP3 51)
DCN Number Title (FSAR Sections. Tables, and Fiaures Affected) i
' DM3-02-479-97 Containment isolation System Changes (F6.2-47; processed i with FSARCR 97-MP3-545) j
. DM3-03-479 97 Containment Isolation System Changes (F6.2-47; processed l i with FSARCR 97-MP3-545) i l
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Dockct Mc. 50-423 B17349 J LL-B Number Title (FSAR Sections, Tables, and Fioures 'Affected) 3-93-181 Temporary Transfer From Calgon Bin to Condensate Chemical Fee'd System (10.3.5,10.4.7, F10.3.3(1(A)); processed with FSARCR ,
98-MP3-58) ,
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3-95-109 Boron Evaporator Reboiler Pump Seal Water Flow Switch Bypass 1 Jumper (F9.3-9(2A)); processed with FSARCR 98-MP3-56) 3-96-108 Oil Water Separator Alternate Discharge Path (10.4.10, '
F10.4-9(1(A)); processed with FSARCR 98-MP3-50) 3-97-061 Auxiliary Boiler Chemical Addition Tank Flow Vent and Drain Modification (10.4.10, F10.4-9(1(A)); processed with FSARCR 98-MP3-50)
PTSCR Number Title (FSAR Sections, Tables, and Fiaures Affected) 3-21-97 Updated Pressure / Temperature Limits Curve (5.2.2, 5.3.2,' 5.4.7, 9.3.4; processed with FSARCR 98-MP3-24) 3-27-97 Steam Generator Atmospheric Relief Bypass Valve (10.3.3; processed with FSARCR 97-MP3-578) 3-36-97 Residual Heat Removal System Interlock Setpoint Change (5.4.7, 7.6.2, T5.4-9, F7.6-1; processed with FSARCR 97-MP3-514) l p
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Docket No. 50-423 B17349 FSARCR Number Title (FSAR Sections. Tables, and Fiaures Affected)
! 97-MP3-539 Gaseous Effluent Releases Changes (11.3.3, T11.3) 97-MP3-547 Environmental Design Conditions Changes (3B) 97-MP3-552 Station Blackout Diesel Cable Installation Clarification (8.3.1) 97-MP3-554 Non-Seismic Vibration Statement Clarification (3.11) 97-MP3-565 Fuel Building Exhaust Monitoring Clarification (T1.8-1, 3.1.2) 97-MP3-583 Clarification to Fission Product Inventories, Spent Fuel Cask Drop Accidents, Feedwater System Malfunctions, Failure of Small Lines, and Pipe Break Sections (15.0,15.1,15.2,15.6,15.7, T15.7-9) 97-MP3-585 Standard Review Plan Changes (3.6, T3.6, F3.6) -
97-MP3-588 Power Operated Relief Valve Leakage Connection Clarification (5.2.5) .
97-MP3-590 Ventilation Design Features Changes (9.4.3,12.3.2,12.3.3) 97-MP3-595 Fire Protection Program Changes (FPER 3, 4, 5, App B) 97-MP3-596 Post Fire Safe Shutdown Illumination Clarification (9.5.3, FPER 4.4, 7.6, App B) ,,
98-MP3-1 Channel Accuracy Definition Clarification (7.1) 98-MP3-2 System Quality Group Classification Identification Changes (3.2.2, F3.2-2) 98-MP3-5 Missile Protection Clarification and Changes (3.5.1, T3.5-7, T3.5-10, T3.5-11, T3.5-12, T3.5-15) 98-MP3-6 Reactor Coolant System Mass Inventory Balance Change (5.2.2) 98-MP3-8 Bypass Leakage Penetration Clarification (6.2.6, T6.2-65) 98-MP310 Single Failure Criterion Conformance Clarifications (3.1.1) 4
Docket No. 50-423 B17349
~ 98-MP3-12 Supplementary Leak Collection and Release System Clarification (3.1.2) 98-MP3-13 Radiation Worker Training Description Clarification (12.5.3) 98-MP3-14 Electrical Equipment Not Requiring Internal Cable Separation
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- l. ' 98-MP3-16 Break Exclusion Zone Definition Clarification (6.2.4, 6.6.8) 98-MP3-20 Reduced Auxiliary Flow Rate Changes (6.3,10.4,15.0,15.2,
- 15.6l T15.0, T15.2, T15.6, F15.0, F15.2, F15.6) 98-MP3-25' Operational Limits for Reacto'r Coolant Pump Heat injectio'n Transients (5.2.2) 98-MP3-26 Changes to Environmental Design Conditions (3.11, T3.11N-1, 3B) 98-MP3-28 Containment Quench Spray System Changes (6.2.1, 6.2.2, 6.5.2, T6.2-60, T6.2-77, T6.2-78) 'i
! 98-MP3-29 Containment Recirculation Spray Cooler Component -
Reclassification (T3.2-1, T6.2-62)
' 98-MP3-33 ' Main Steam Pressure Relieving Valves Material Change (T10.3-3) 98-MP3 35- Accumulator Isolation Valves Power Supply Clarification (5.4.7) i 98-MP3-36 Fan Vibration Criteria Clarification (T1.8-1) 98-MP3-37 Turbine Bypass Valves Changes '10.4.4, T10.1-1)
.98-MP3-38 Moisture Separator Chamber Draining Clarification (T1.8-1) l l'
98-MP3-40 Filter Housing Pressure Limit Clarification (T1.8-1, T6.5-1) ,
i 98-MP3-41 Secondary Containment Supplementary Leak Collection and Release System Clarification (T6.2-63, T6.5-1)
. 98-MP3-42 Emergency Generator Closure Ventilation System Changes (9.4.6) ;
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Docket No. 50-423 B17349 98-MP3-43 Feedwater System Description Changes (15.1.1,15.1.2, T15.0-2, T15.0-6) 98-MP3-44 Boric Acid Tanks Changes (9.3.4. T9.3-5) 98-MP3-47 Chemical and Volume Control System Excess Letdown Flowpath Limitations (9.3.4) 98-MP3-49 Reactor Coolant Pressure Boundary Leakage Detection Systems (T1.8-1) 98-MP3-53 Residual Heat Removal System Capability for Normal Cooldown (5.4.7, 5.4.16) 98-MP3-57 Water Treating System Demineralized Bypass, Cross-tie, and System isolation (9.2.3, F9.2-7(2(A)), F9.2-7(5(A)) )
98-MP3-62 Three Mile Island Action Items Changes (T1.10-1) 98-MP3-64 Auxiliary Feedwater System Initiation Clarification (T1.8-1, T1.10-1 )
98-MP3-68 Containment Hydrogen Monitoring Clarification (6.2.5) 98-MP3-69 Pressurizer Valve Interlock Clarification (7.6.8) 98-MP3-70 Reactor Coolant System Volume increase (T5.1-1, T6.1-2, T6.2-3, T6.2-68) 98-MP3-72 Containment Recirculation Pump Seal Cavity Clarification (6.2.2) 98-MP3-73 Containment Bypass Leakage Penetrations Changes (T6.2-65) 98-MP3-74 Engineered Safety Features Filter Housing Clarification (T1.8-1, T6.5-1) 98-MP3-76 Safety Parameters Display System Computer Point Update (T1.8-1, T1.8N-1, T7.5-1) 98-MP3-77 Reactor Coolant System Check Valve Testing Clarification (5.4.12) 98-MP3-78 Standby Diesel Generator Fuel Oil System Clarification (T1.8-1) 6
l l Dockel No. 50-423 B17349 98-MP3-79 . Charcoal Adsorber Removal Efficiency Clarification (T1.8-1) 98-MP3-80 Radiation Shielding During Spent Fuel Handling Operations (9.1.4) 98-MP3-85 Emergency Generator Cooling Water Systems Changes (T9.5-3) 98-MP3-86 Radiological Changes and Clarifications (T11.1-2,15.1.5,15.6.2, 15.6.3,15.7.4) 98-MP3-87 Accident Monitoring Instrumentation List Changes (T7.5-1) 98-MP3-88 Environmental Design Conditions Changes (38) 98-MP3-91 Table of Three Mile Island Action items Changes (1.10, T1.10-1) 98-MP3-94 Service Water Pump Strainer Motor Switch and Switch Escutcheon Plate Change (9.2.1)
' 98-MP3-96 Containment Temperature Change (9.2.2, T9.2-7, T9.4-9,
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DCR Number Title M3-96054 Containment Quench Spray System, Recirculation Spray System, and Safety Injection System Changes Description of Channe The design basis of the containment quench spray system, recirculation spray system, and portions of the safety injection system piping and supports were re-qualified to accommodate higher thermal loads. The components within the affected systems were also qualified for a higher operating limit.
Reason for Chance This change was implemented to correct design deficiencies in the safety systems required to mitigate the consequences of a loss of coolant accident or a steam line break inside the containment.
Safety Evaluation The change to re-rate and qualify piping and components to accommodate higher temperatures does not degrade system capabilities. The loss of service water flow to thc recirculation spray system heat exchangers will not impact long-term cooling of the core after an accident and the change does not prevent the safety systems from performing their intended safety function. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
DCR Number Title M3-96064 Safety Grade Cold Shutdown Analysis Description of Change A new safety grade cold shutdown analysis was incorporated that resolves design deficiencies associated j with domestic water storage tank inventory, containment cooling primary temperature, spent fuel pool j cooling heat load, residual heat removal system flow control, and service water temperature, h i Reason for Chance '
This change was implemented to reflect actual plant configuration, correct design deficiencies and be consistent with licensing documents.
Safety Evaluation This change improves the level of plant safety and allows the plant to be put in cold shutdown more quickly. The change is an overall safety benefit. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
DCR Number Title M3-96069 Containment Quench Spray System, Recirculation Spray i System, and Safety Injection System Changes
! Description of Channe The design basis of the containment quench spray system, recirculation spray system, and portions of the
! safety injection system piping and supports were re-qualified to accommodate higher thermal loads. The components within the affected systems were also qualified for a higher operating limit.
Reason for Channe This change was implemented to correct design deficiencies in the safety systems required to mitigate the consequences of a loss of coolant accident or a steam line break inside the contaimnent.
Safety Evaluation The change to re-rate and qualify piping and components to accommodate higher temperatures does not degrade system capabilities. The loss of service water flow to the recirculation spray system heat exchangers will not impact long-term cooling of the core after an accident and the change does not prevent the safety systems from performing their intended safety function. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
DCR Numble Title M3-96070 Steam Generator Pressure Relief Valve Disc Material Change Description of Channe The valve disc material was changed from a low carbon cast steel with hard facing product to a low carbon wrought steel with hard facing product.
Reason for Chance This change was implemented to reflect actual plant configuration due to changes in the disc material by the manufacturer.
Safety Evaluation The original and alternate material properties are essentially equivalent and the change will not degrade the design basis nor alter the performance of the valves. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
DCR Number Title M3-97007 Power Operated Relief Valve Block Valves Description of Chance The reactor coolant system power operated relief valve block valves and actuators were .wed and replaced with improved valves and actuators.
', Reason for Chance This change was implemented to ensure valve performance under design basis conditions.
Safety Evaluation This change provides continued assurance that the power operated relief valve block valves will open and close as required to fulfill safety functions for accident mitigation. The change does not have an impact on the seismic performance of the system or the electrical qualification of the cables or actuator.
Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
DCR Number Title M3-97045. Containment Recirculation System Pump Restriction Orifices Descnotion of Change .
A flow orifice was installed downstream of each containment recirculation system pump outlet nozzle and -
the me==*ad valves and interlocks were modified. Containment recirculation system pump casmg vents were installed and valve position and logic changes were implemented.
Reason for Channe
. This change was implemented to reduce flow in the system, thus eliminating the potential for flashing in i the suction line and the potential for water hammer in the heat exchanger. This change also prevents vapor lock of the pumps and improves system configuration.
Safety Evaluation This change is consistent with system design and operating requirements. The containment design pressure, temperature, and liner temperature are not exceeded and the core cooling function of the system following a loss of coolant accident is maintained. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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DCR Number lit je M3 97057 Containment Electrical Penetration Area Modifications Description of Chance The copper line that supplies control air to various letdown valves was replaced with stainless steel. Fire stops and tray covers were installed on certam cable trays. Eight additional sprinkler heads were installed l and sixteen sprinkler heads were replaced in the electrical penetration area of containment. ..,.
3 Beason for Chance This change was implemented to enhance the fire protection in the electrical penetration area of the containment.<
Lafety Evalual.i,gn i
- This change enhances the ability to safely shutdown the plant should a fire occur in the containment building. This change is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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DCR Number Title M3-97093 Active Valve Reconciliation Project j 1
Description of Change '
.l The total population of active valves was verified and the active function for each valve was identified and . {
h=ated. This information was consolidated into a new data base and affected programs, procedures I and calculations were revised as necessary.
Reason for Channe This change was implemented to ensure all active valves are designed, tested, maintained and operated in accordance with applicable programs and procedures commensurate with their intended safety function. .
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Safety Evaluation This change is editorial in nature and all active valves have been designed and qualified to meet licensing requirements. ' Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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M3-97097 Service Water Design Temperature Changes
. Description of Channe <
The temperatures of service water 9=; =Ets and papag downstream of the coolers to the circulating I
water discharge tunnel were revised. Pressure switches were removed and existing or new tuners are utilized to delay startmg of the booster pumps.
Reason for Channe This change was implemented to reflect revised flow calculations which indicate a decrease in reactor coolant inventory and increase in heat removal by the secondary system.
Safety Evaluation l: The terating of the piping and components, removal of the pressure switches, addition of time delay relays l
and flow switch setpoint changes have been evaluated and determined to be safe to operate at the revised temperature. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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DCR Number Title
- M3-97100 Loss of Component Cooling Water to Chemical Volume O Control 12tdown Heat Exchanger Modifications 2:
L Description of Change ;.
Pipe support modifications were performed and component re-rating was implemented in the chemical y and volume control letdown flowpath from the letdown heat exchanger to the volume control tank. -
Reason for Channe
["1 This change was implemented to incorporate new design basis analysis which revealed the limiting design capability of two diaphragm valves in the flow stream. y Sa_fety Evaluation The modification and redesign'of the support system and replacement of plug valve seals ensures acceptable operation of the chemical and volume control system piping. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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l DCR Number Title M3-97102 < Emergency Core Cooling System Limited Passive Failure
[' Design Criteria Changes t l
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! Description of Chaaae I
A notch was cut in the curb around the aux bary building pipe tunnel to allow sump overSow to the l
- tunnel. Various et 4.24 mive changes west incorporated to assist in Wing leaks in the auxthary or engineered safety features buildings. This change also reinstates the reactor spray system cold leg direct j injection flow paths to the engineering design basis.
t Reason for Channe )
L This change was implemented to comply with current design basis accident licensing requirements. )
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Safety Evaluation l
This change will either improve the time to detection of an emergency core cooling system limited passive ]
failure or improve response time after a failure is detected but has no impact on its probability, I Reinstatement of the reactor spray system cold leg injection flow path provides assurance the emergency core cooling system performance criteria are satisfied following the most limiting emergency core cooling system passive failure. Therefore, the change is safe and does not constitute an Unreviewed Safety {
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DCR Number Titig M3-97106 Refueling Water Storage Tank and Quench Spray Pumps Setpoint Changes .
Description of Chanaq The tank empty level setpoint of the refueling water storage tank which trips the quench spray pumps, closes the containment isolation valves, and actuates a tank empty alarm was changed. Additionally, the refueling water storage tank drawdown and switchover times were revised and the emergency core cooling
- system runout flow rates were changed.
Reason for Chan_gg This change was implemented to reflect actual plant configuration and document revisions in the refueling water storage tank drawdown and switchover analysis resulting from new emergency core cooling system runout flow rates and associated analyses. The refueling water storage tank level setpoint 5 change was impicmented to reflect an increase in the assumed instrument uncertainties.
Safety Evaluation l This change is editorial in nature and is consistent with design and licensing documents. All systems and components continue to function with no change in performance, and with no reduction in margin of .
safety. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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W DCR Number Titig M3-97119 Relocation of the Post Accident Sampling Drain Description of Change The post accident sampling system sample flush and drain line was extended and rerouted from the
! containment unidentified leakage sump to the containment drains sump.
Reason for Change This change was implemented to direct the known sample flush and drain water to the proper sump for processing as radioactive waste.
1 Safety Evaluation This change enhances the ability to monitor for unidentified leakage inside containment. This drain line performs no safety-related function in the mitigation of any design basis accident nor does it initiate any accident. If for any reason the drain pathway is blocked, an alternative pathway to the charging pumps suction is available. Therefore, the change is safe and does not constimte an Unreviewtxl Safety Question.
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!. M3-98003 Inadvertent Safety injection Actuation at Power l-Description of Channe The power operated relief valves opening circuitry was upgraded to safety grade in the safety analysis for "
the inadvertent safety injection event.
Reason for Channe i This change was implemented to qualify the pressunzer power operated relief valves and associated I piping for water release, upgrade the power operated relief valves control circuitry for automatic actuation and bypass the thermal overload limit switch for opening the power operated relief valves block valve. !
Safety Evaluation This change provides added assurance that the operators will be able to mitigate an hiadvertent emergency core cooling system actuation at power without challenging the pressurizer safety valves during solid ;
water conditions. Although the change in the power operated relief valves logic does increase the '
probability that the power operated relief valves will inadvertently open and remain open, multiple failures are necessary for this to occur and the consequences are bounded by the current accident analysis.
This change is an Unreviewed Safety Question determined to be safe.
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DCR Number Title M3 98005 Steam Atmospheric ReliefIsolation Valve Reinstatement Description of Channe The steam atmospheric reliefisolation valves were reinstated into the equipment environmental qualification program.
' Reason for Chanor.
This change was implemented to reflect actual plant configuration and to allow taking credit for the valve operation in a harsh environment Safety Evaluation Adding the main steam pressure relief valve isolation valves to the equipment environmental qualification list assures that they are available to operate in the event of a failed open main steam pressure relief valve.
This will provide assurance to the operator that the discharge of the steam generator to the environment can be isolated. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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M3-98011 - Contair. ment Atmosphere Radiation Monitor Setpoint Change Description of Channe The ALERT and ALARM setpoints for the containment atmosphere particulate and gaseous radiation I monitor system were revik.d downward to respond, within one hour, to a one gallon per minute reactor l coolant leak. !
i Reason for Channe This change was implemented to be consistent with setpoint basis and regulatory guidance.
Safety Evaluation The changing of the setpoints to lower values makes the coolant leak detection process more safe.
Therefore, the change is safe and does not crstitute an Unreviewed Safety Question. l i
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l DCR Number Title M3-98015 TravelLimiterInstallation l
l Description of Channe j Travel limiters were installed on the 3-way temperature control valves which fail open upon loss of '
instrument air to direct flow through the service water cooled charging pump coolers. In addition, the charging pump lube oil pressure relieving valve was adjusted.
Reason for Channe This change was implemented to prevent full stem travel so that on a loss of air signal with low service water temperature, heat exchanger bypass flow is sufficient to maintain a minimum tube oil temperature. l The limiters will also provide adequate cooling flow with high service water temperatures.
' Safety Evaluation I l 1 This change ensures that the emergency core cooling system components are operated within their design limits consistent with the assumption in the final safety analysis' report accident analysis. There are no i g changes to the functional requirements for any safety related systems, structures or components. The change does not degrade the performance of any safety system of prevent actions assumed in the accident analysis. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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l DCN Number Title DM3 02-479-97 Contamment Isolation System Changes Description of Channe The vent, drain, leakage monitoring, and test connections consisting of a single valve and located between containment isolation valves were moddied to luive closures.
Reason for Channe This change was implemented to provide an additional barrier between the containment atmosphere and the atmosphere outside containment.
Safety Evaluation This change protects the valve and does not compromise containment integrity. This change does not affect the design or operation of any system penetrating containment nor does it affect the ability of the penetration to maintain pressure boundary. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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DCN Number Ti1lg DM3-03-479-97 Containment Isolation System Changes Dggription of Ch.mgg The ve4 drain, leakage monitoring, and test connections consisting of a single valve and located between containmat isolation valves were modified to have closures.
Reason for Channe This change was implemented to provide an addatumal barrier between the containment afma=here and the a'ma=here outside containment.
Safety Evaluation This change protects the valve and does not compromise containnant integrity. This change does not affect the design or operation of any system penetrating containment nor does it affect the ability of the penetration to maintain pressure boundary. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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l Bvoass Jumoer Title l Humber Temporary Transfer From Calgon Bin to Condensate
- l. 3-93-181 Chemical Feed System Description of Chanaq Stainless steel tubing and associated valves, controller, pump, gauge and pressure regulator were installed
- l. to transfer ethanalamme from a calgon bin to the normal chemical measunng tank fill line.
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This change was implemented to enhance water chemistry control of the secondary plant systems. The i bypassjumperis stillinstalled.
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Safety Evaluation This change enhances water chemistry control and does not affect safety related components. Therefore.
the temporary change is safe and does not constitute an Unreviewed Safety Question.
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i Bvoass Jumper Title I
.NpJ_nb.r e Boron Evaporator Reboiler Pump Seal Water Flow Switch 3-95-109 Bypass Jumper f
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i Description of Change l
The low seal water flow alarm and associated flow switch interlock for the boron ' evaporator reboiler j pump was diannectM.
Reason for Change This temporary change was implemented to eliminate nuisance pump trips and alarms, due to the flow switch malfunction, until a permanent design change can be implemented. The bypass jumper is still installed.
Safety Evahiation Compensatory measures are in place to check for adequate seal flow, detect leakage, and prevent damage l to the pump. Therefore, the temporary change is safe and does not constitute an Unreviewed Safety l Question.
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Dyoass Jumper Title Number Oil Water Separator Alternate Discharge Path 3- % 108 Description of Channe The auxiliary boiler room oil water separator efDuent discharge path was changed from manhole munber fifteen to the circulating water tunnel.
Reason for Channe This change was implemented to prevent the discharge of hydrazine to manhole number fifteen. The bypassjumperis stillinstalled.
Safety Evalualiqq The bypass jumper enhances control of the discharge of hydrazine and does not impact any safety related systems or components. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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Bynass Jumner Title Number Auxiliary Boiler Chemical Addition Tank Flow Vent and 3-97-061 Drain Modifications Description of Chanac 4 The vent and drain lines of the auxiliary boiler chemical addition tank were routed to temporary collection contamers l Paama for Oma a This change was implemented to prevent water with a high hydrazine concentration from entering floor drains. The bypassjumper is stillinstalled.
Safety Evaluation The bypassjumper ediances control of hydrazine and does not impact any safety related systems or !
components. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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3-21-97 Updated Pressureffemperature Limits Curves I Description of Channe This change incorporated the current pressure / temperature limits, corresponding cold overpressure protection requirements and a revised cold overpressure protection enabling temperature.
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Reason for Channe This change was implemented to reflect actual plant configuration and to be consistent with design and licensing documents.
Safety Evaluation This change is editorial in nature and ensmes that heatup, cooldown and low temperature operation does not compromise the structural margins of safety of the system pressure boundary. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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I l~ PTSCR Number Title 3-27-97 Steam Generator Atmospheric Relief Bypass Valve l Proposed Technical Specifications Change Request Description of Chanoe A new Technical Specificaten and associated bases section was incorporated to provide information about the required number of steam generator atmospheric relief bypass valve's, allowed outage times, and surveillance frequency.
Reason for Change This change was implemented to conform to licensing requirements and required actions contained in Westinghouse Improved Standard Technical Specifications.
Safety Evaluation This change is editorial in nature and adds a new Technical Specification limiting condition for operation and associated surveillance requirements to ensure accident mitigating functional capability. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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PTSCR Number I. iigg 3-36-97 Residual Heat Removal System Interlock Setpoint Change Description of Chnno, The reactor coolant system low pressure interlock setpoint was charged from 390 psig to 412.5 psia.
Reason forr %aae This change was implemented to reflect actual plant configuration and to be consistent with design and licensing documents.
Safety Evaluation This change accounts for instrument calibration accuracy's and deadband resas but does not change the ;
operation of the residual heat removal system. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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r 97-MP3 539 Gaseous Effluent Releases Changes !
l Description of Channe -
The description of the potentially radioactive gaseous release paths for the Unit I stack, the engineered safety features building normal ventilation system, the steam generator blowdown flash tank vent, and the turbine building normal ventilation was clarified and corrected.
Reason for Change This change was implemented to reflect actual plant configuration and to be consistent with design and licensing documents. j Safety Evaluation Tids change is editorial in nature and does impact the ability of the systems to perform their function of monitoring radioactivity of gaseous effluents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question. '
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l ll ES ARCR Number Title 97-MP3 547 ~ Environmental Design Conditions Changes Description of Channe The equipment environmental qualification classdication for fuel building zone FB-05 was changed from a " mild" environment to a " harsh" environment.
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This change was implemented to reflect the actual design classdication for the zone. The original l
, classification was changed to " mild" to reflect field modifications which were not performed. l Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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!- FSARCR Number Title i 97-MP3-552 Station Blackout Diesel Cable Installation Clanfication Description of Ch=a-a A clarification was incorporated into th cable installation description to discuss the approximately four feet of cable between the cable tray and each duct bank which is unprotected by conduit or a cable tray.
' Reason for Chan_gg This change was implemented to reflect ac ys plant configuration and to clarify that the tranation area is installed in open air and only protected by the cablejacket.
Safety Evaluation l
The cables outside the duct bank or cable tray are capable of withstanding physical loading as prescribed '
in the local building code and conform to licensing requirements. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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l FSARCR Numb _et ))Ge i 97-MP3 554 Non-Scismic Vibration Statement Clarification
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f Description of Chan=a l The description of how the effects of non seasnuc vibration are considered as part of the regular in service surveillance and preventative maintenance programs was incorporated into the environmental conditions section.
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l Rea:on for Chaggs This change was implemented to be consistent with cunent industry standards and to reflect actual plant surveillance and maintenance programs.
- Safety Evaluation I
This change provides early warning against premature failure due to non seismic vibration and does not otherwise impact operation of the facility. Therefore, the change is safe and does not constitute an Unreviewed Safety Question. -
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FSARCR Numhg Title 97-MP3-565 Fuel Building Exhaust Monitoring Clarification Description of Channe The requirements of the fuel building ventilation system exhaust to be remote manually diverted to its exhaust filtration system on recemng a high area radiation alarm were deleted.
-i Reason for Chanaa "
This change was implemented to reflect actual plant configuration because the area radiation monitor does "
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not perform the function of measurmg the air contasmation in the fisel building ventilation system. I I
Safety Evaluation l This change is editorial in nature and does prevent potentially contaminated air from leaving the fuel building. Therefore, the change is safe and does not constitute an Unreviewed Safety Question. ;
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, 97-MP3 583 Clarifications to Fission Product Inventories, Spent Fuel Cask Drop Accidents, Feedwater System Malfunctions, Failure of Small Lines, and Pipe Break Sections Description of Change i i
Various editorial changes were incorporated into the text of the Chapter 15 descriptions in the Final I Safety Analysis Report.
l l Reason for Change This change was implemented to reflect actual plant configuration and to be consistent with design and i licensing documents.
Safety Evaluation This change is editorial in nature and does not change the accident analysis described in Clupter 15 of the .
final safety analysis report. Therefore, the change is safe and does not constitute an Unreviewed Safety l Question. I I
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FSARCR Number Tit.l.q 97-MP3-585 Standard Review Plan Changes Description of Quagg The text and tables that describe effects of postulated pipe ruptures were revised and the results of pipe break analysis were evaluated for potential <Iamage to essential systems and incorporated into a specific l table.
1 Reason for Chaaaa I This change was implemented to reflect actual plant configuration and to be consistent with design and licensing documents.
Safety Evaluation This change is editorial in nature and there are no changes to system design specification, operating parameters or methodology, nor any additional conditions that would cause the system to be outside its design envelope. Therefore, the change is safe and does not constitute an Unreviewed Safety Question. l l
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FSARCR Numhgg 7jiijg 97-MP3-588 Power Operated Relief Valve Leakage Connection Clanfication I
Dgscriotion of Channe 1 The reference to power operated relief valves was delceed from the list of valves that have their valve stem leakofflines piped to the reactor plant gaseous waste drains header.
Reason for Change I This change was implemented to reflect actual plant conditions because the design of these valves does not utilize Icakoff connections. l l
S3fety Evahiation This change is editorial in nature and is a valve design enhancement which prevents a release of reactor coolant that was formerly associated with valve stem leakoff. Therefore, the change is safe and does not constitute an Unreviewed Safety Question. -
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l FSARCR Number Titic 97-MP3-590 Ventilation Design Features Changes Description of Change
! A clarification was incorporated to allow for exceptions to the general practice ofventilation flow being
- from areas of potential low contanunation to areas of high contamination.
l Reason for Ch==
This change was implemented to reflect actual plant configuration and to clarify that typical conditions change during winter mode alignment.
Safety Evaluation This change is editorial in nature and the recirculation winter mode of operatiori does not effect offsite dose. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Title 97-MP3-595 Fire Protection Program Changes l
Description of C ===a 1 l The description of the combustible loading section of each fire area and zone were changed to revise the i
types of combustible materials, relative fire severity, and area and zone dimensions. In addition, the ;
descriptions of the underground fire protection water supply piping, fire brigade breathing air, and station i black out fire protection system cutout valve alignment were changed.
Reason for Channe This change was implemented to reflect actual plant configuration and to be consistent with design and licensing documents.
1 Safety Evaluation '
This change is editorial in nature and does not change plant equipment, barriers / boundaries, or any actions associated with limiting any fire protection equipment. Therefore, the change is safe and does not constitute an Unreviewed Sfety Question.
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l FSARCR Number i litig 97 MP3 5% Post Fire Safe Shutdown Illumination Clarifications Description of Chaaaa I A change was made to include security lighting to the descripdon oflighting available to support operator actions for access or egress between buildings to support safe shutdown post fire events.
Reason for Ch===a This change was i=;'==ted to correct an ermt in the licensing basis of the plant and to include outside lighting in the evaluation of fire safe shutdown lighting.
i Safety Evaluation '
l l This change is editorial in nature and does not reduce the ability to achieve and maintain safe shutdown in .
l the event of a fire. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Ti!!g j
98-MP3-1 Channel Accuracy Definition Clarification Descri_ation of Chan=a The definition of channel accuracy was corrected to clanfy what effects are included in deterunning the accuracy, l
Reason for Chanae !
This change was implemented to correct the dananet of channel accuracy and reflect industry standards Safety Evaluation This change is editorial in nature and does not impact the calculation ofinstrument uncertainty.
Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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l 98-MP3-2 System Quality Group Classification Identification l Changes l
Description of Ch===e
- The system quality group classification text was revised to indicate the requirements for plant equipment l
identification conventions is being controlled wa engmeenng design specifications.
' i Reason for Chan=a l This change was implemented to reflect actual plant configuration and to be consistent with design
- documents.
Safety Evaluation l This change is editorial in nature and is consistent with design and licensing documents. Therefore, the l change is safe and does not constitute an Unreviewed Safety Question.
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I l FSARCR Number Tjigg 98-MP3-5 Missile Protection Clarifications and Changes
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Description of Chanaa Various editorial changes were incorporated into the text and tables which describe missile protection.
Famn for Chaaae This change was implemented to correctly identify potential missile probability and probabdity data not previously available. The change also provides clanfication regarding valve missiles and their evaluation and corrects terms in equations which were previously omitted.
Safety Evaluatign This change is editorial in nature and does not result in any less conservative evaluation of missile generation or damage. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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l FSARCR Number Title 98-MP3-6 Reactor Coolant System Mass Inventory Balance Change Description of Chanaa l An alternate provision for maintaining a reactor coolant system mass inventory balance prior to isolating j- the residual heat removal system was incorporated into the precaution recommendation text.
l Reason for Chanan
!' This change was implemented to minimize the potential for developing an overpressurization transient l during system operation when solid water operation m ; be possible.
l l Safety Evaluation This change is editorialin nature and does not increase the probability of an ove pressure transient because the residual heat removal system letdown path is not removed from service until reactor coolant system inventory mass balance is established through an alternate flowpath. Therefore, the change is safe and does not constitute an Unreviewed Safety Question. -
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l FSARCR Number Titic 98-MP3-8 Bypass Leakage Penetration Clarifications Description of Chanaa Additional bypass leakage paths were identi6ed, classified and incorporated into the corresponding containment penetration tables.
t l Reason for Chanae This change was implemented to reflect actual plant configuration resulting from correcting previous calculations.
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This change is editorial in nature and is consistent with design and licensing documents. Therefore, the l'
change is safe and does not constitute an Unreviewed Safety Question. '
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t FSARCR Number Title l 98-MP3-10 Single Failure Criterion Conformance Clarifications l Description of Chan e l The description for single failure criterion was corrected and inconsistencies between plant design features j and the description and application of the single failure criterion were clanfied.
Reason for ch===a --
This change was implemented to reflect actual plant configuration and the original single failure design Philosophy.
l Safety Evaluation This change has no impact on the functional and operational design basis of any plant system, structure or -
component. Tierefore, the change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Title 98-MP3-12 Supplemental Leak Collection and Release System Clarification Description of Change The description of the supplementary leak collection and release system was changed by deleting the reference to a fuel handling accident.
Reason for Channe This change was implemented to reflect actual plant configuration because the fuel handling accident activity retained in the containment atmosphere is reduced by the containment air filtration system and purged under controlled conditions.
Safety Evaluation This change is editorial in nature and is consistent with design end licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
FSARCR Number Title _
98-MP3-13 Radiation Worker Training Description Clarifications Description of Channe The description of the radiation worker training program was changed to' clarify that verification of prior i
' training is permitted for new personnel and that personnel outside the training department are recognized
. as able to provide radiation worker training. Other minor editorial changes were incorporated and the specific quotation of test objectives was deleted.
Reason for Channe l This change was implemented to correct identified inadequacies in the program and to reflect the current approach for radiation worker training.
Safety Evaluation l This change is editorial in nature and is consistent with existing licensing documents. Therefore, the j change is safe and does not constitute an Unreviewed Safety Question.
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1 FSARCR Number Title l 98-MP3-14 Electrical Equipment Not Requiring Internal Cable Separation 1
Dggription of Channe The emergency diesel generator air dryer panels were added to the table in the final safety analysis report which lists equipment not requiring internal cable separation.
Reason for Channe This change was implemented to reflect the actual plant configuration because the circuits in the panels have been isolated through qualified isolation devices.
Eafety Evaluation This change is editorial in nature und the wiring to the diesel generator pancis are properly isolated.
Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Title 98-MP3-16 Break Exclusion Zone Definition Clarification Description of_Changg The definition of the break exclusion zone for the containment vacuum system pump suction penetrations and hydrogen recombiner system suction penetrations were revised along with the augmented inservice inspection requirements.
Reason f_qr Chance This change was implemented to reficct actual plant configuration and to be consistent with design and licensing documents.
Safety Evaluation This change is editorial in nature and the containment isolation system will continue to function as designed. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
FSARCR Number Title 98-MP3-20 Reduced Auxiliary Flow Rate Changes Description of Change The text, tables, and figures which describe various accident conditions were changed to incorporate new analyses using revised auxiliary feedwater flows and increased turbine driven pump startup delay time.
Reason for Chance-This change was implemented to reflect actual plant configuration and to incorporate new Feedwater Line Break analysis and new Loss of Normal Feedwater flow / Loss of AC Power analysis.
Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. The change does not affect or introduce new malfunctions, nor affect the Loss Of Coolant Accident and main steam line break mass and energy release values. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
t FSARCR Number i lillg 98-MP3-25 Operational Limits for Reactor Coolant Pump Heat Injection Transients DeScriDlion of Chance The description of restrictions for starting the first reactor coolant pump during water solid conditions was -
revised.
f Reason for Channe This change was implemented to reflect actual plant configuration and to provide additional operational flexibility.
1 Safety Evaluation A combination of operator action and existing pressure margin between the pre-pump startup reactor coolant system pressure and the relief valve setpoint will minimize the probability that the relief valve will actuate. Therefore, the change is safe and does not constitute an-Unreviewed Safety Question.
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FSARCR Number Title 98-MP3-26 Changes to Environmental Design Conditions I
Dggriotion of Channe Portions of the environmental qualification text and the discussion of normal and accident environments i
. were revised.
Reason for Chan=a This change was implemented to maintain consistency between the final safety analysis report, the L environmental qualification program manual and design specification.
l Safety Evaluation l This change provides consistency with the environmental design specification and licensing documents.
The analysis results from program documents does not increase the probability or consequences of a postulated accident nor does it introduce and accident of a different type. Therefore, the change is safe l and does not constitute an Unreviewed Safety Question. ' -
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ESARCR Number Title
. 98 MP3-28 Containment Quench Spray Sy1 stem Changes Description of Channe Several containment quench spray system related assumptions were revised and incorporated into the text ;
and tables which describe the system.-
Reason for Channe This change was implemented to reflect actual plant configuration and to be conastent with current '
j design documents. 1 S_afety a Evahtatiqq l
This change is editorial in nature and does not change the ability of the containment spray to operate as needed to reduce containment pressure and scrub fission products following design basis accidents
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described in the final safety analysis report. Therefore, the change is safe and does not constitute an Unreviewed Safety Question. )
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98-MP3-29 Containment Recirculation Spray Cooler Component t
Reclassification Description of Channe l The indicated clumfication of the containment spray cooler tube side and shell side was corrected.
l Pa=a for Cha==a
. This change was implemented to reflect actual plant configuration.
l Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the .
change is safe and does not constitute an Unreviewed Safety Question.
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1 FSARCR Number Tit _lg 98-MP3-33 Main Steam Pressure Relieving Valves Material Change Description of Chanac
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The material specified for the main steam pressure relieving valves bonnet bolts was revised to include l
- Grade 7 in addition to Grade 2H. I l
Reason for Channe This change was implemented to reflect actual plant configuration and to be consistent with design documents.
Safety Evaluation .
l This change is editorial in nature and the two grades have the identical mechanical properties and therefore will behave the same. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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FS ARCR Number IR!g 98-MP3 35 Accumulator Isolation Valves Power Supply Clarification Description of Chaaaa The statement that all four of the motor operated manatator isolation valves are powered from the same electrical train was deleted The correct statement that two of the accumulator isolations are powered l from the orange safety train and two valves are powered from the purple safety train was added.
1 Reason for Channe !
This change was implemented to reflect actual plant conditions and to be consistent with design documents.
Safety Evaluation This change is editorial in nature and since there is no power to the valves during normal plant operation the valves will always be aligned consistent with the accident analysis regardless of the availability of power to the valve operator. Therefore, the change is safe and does not constitute en Unreviewed Safety Question.
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FSARCR Number Title <
98-MP3-36 Fan Vibration Criteria Clarification j
Description of Channe L The description of fan vibration performance criteria was revised.
Reason for Change I
, This change was implemented to demonstrate the degree of compliance with licensing documents and to l l
define acceptance standards. l Safety Evaluation This change is consistent with design documents and meets the intent oflicensing docaments. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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l FSARCR Number Titig it 98-MP3-37 Turbine Bypass Valves Changes Description of Change The reference to periodic partial stroke testing of the valves was deleted and clear descriptions of the valve stroke time requirements and the valve controls were incorporated into the text.
Reason for Chanae This change was implemented to more accurately reflect the design basis of the turbine bypass valves Safety Evalualigg .
This editorial change clarifies the relationship of the operation of the turbiae bypass valves with the ,
reactor protection system. The change has no affect upon the main steam system to provide safety related !
plant cooldown or secondary plant overpressurization protection. Therefore, the change is safe and does .
not constitute an Unreviewed Safety Question. l I
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I l FSARCR Number Iigg 98-MP3-38 Moisture Separator Chamber Draining Clarification Description of Cimnae l An additional exception was added to the degree of compliance text statmg that "Corulanense from the moisture separator chamber will motmue to drain via normally open drain valves."
Reason for Channe l This change was implemented to reflect actual plant configuration and to provide clarification on
- open/ closed status of drain valves.
1 Safety Evaluation l This change is editorial in nature and does is consistent with design and licensing documents. Therefore, l the change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Iills 98-MP3-40 Filter Housing Pressure Limit Clarification Descrinaion of r'hmaa ,
Additional clarificahon was added to the text which describes how Mdistone 3 complies with designing l inlet units and components wisich can be isolated from the fan to withstand a peak negative pressure by ensuring that such isolation is precluded via the design logic between the fans and the inlet dampers l
l Reason for Channe This change was implemented to reflect actual plant configuration.
Safety Evaluati.gg
! . This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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ES2RCR Number Tigg 98-MP341 Secondary Containment Supplementary Imk Collection and Release System Clarifications Descriot'on of Channe The indicated secondary containment supplementary leak collection and release system equipment design capacities were revised to be consistent with the actual equipment maximum capacities.
Reason for Channe This change was k piemented to reflect actual plant configuration and to ensure the licensing l requirements of u system are bounded by the filtration maximum capacity.
Safety Evaluation This change revises design parameters of the filtration units. The filtration units will continue to function properly with the new maximum flow rates and will continue to perfonn their safety functions. Therefore, the change is safe and does not constitute an Um.sd Safety Question.
s FSARCR Nn=har Title 98-MP3-42 - Emergency Generator Closure Ventilation System -
Changes Descnotion of Change The reference to ".. .minimn= cpen position" was deleted from the description of the diesel generator enclosure airinlet dampers Renann for Chanw This change was implemented to reflect actual plant configuration because the dampers have no provisions to prevent full closure.
Safety Evaluation The damper stops do not prevent the dampers from opening nor enable the dampers to open. Failure of the dampers to open does not preclude the ability of the exhaust fan to operate as designed. Therefore, the ,
change is safe and does not constitute an Unreviewed Safety Qu6stion.
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FSARCR Number Title 98-MP3 43 Feedwater System Description Changes
' Description of Channe Various changes were incorporated into the text, tables and description of the feedwater system malfunction events.
n Reason for Channe This change was incorporated to reflect actual plant configuration and the results of recent reanalyses.
Safety Evaluatip_r1 ;
This change is editorial in nature and is consistent with design and licensing documents. Revised j analyses and evaluations were performed and the results show the conclusions of the affected sections are unchanged. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Egg 98-MP3-44 Boric Acid Tanks Changes Description of Channe l 1he references to the low-low alarm were deleted and a revised capacity and descriptive footnote were .
- added to the description of the boric acid tanks.
t' Esson for Change i ~ This change was implemented to reflect actual plant configuration and to be consistent with design f
documents.
Safety Evaluation
- This change is editorial in nature and does not impact any boric acid tank setpoint or storage requirement. (
The change does not alter the function of the system nor prevent it from perfornung its intended function. {
! Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Tillg 98-MP3-47 Chemical and Volume Control System Excess Letdown Flowpath Limitations Description of Chad &G The description of the chemical and volume control system excess letdown flowpath was changed to restnct the use of the excess letdown flowpath to time cases where the normal letdown flowpath is
. inoperable.
Reason for Change This change was implemented to prevent outlet temperatures being higher than analyzed in the event of -
' loss of cooling to the excess letdown heat exchanger and the potential damage to the charging pumps Safety Evaluation The use of the excess letdown will be limited to those cases where normal letdown is unavailable
' therefore, postulating failure of the chemical and volurne control' systems is not required. During safety .
grade cold shutdown, the design basis relief path is from the reactor vessel head vent to the pressunzer relicf tank and therefore does not impact the safety grade cold shutdown. For the unlikely instance in -
which normal letdown is unavailable, the safety grade alternate letdown path via the reactor vessel head vent to the pressurizer relief tank may be used. Therefore, the clange is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Tigg 98-MP3-49 Reactor Coolant Pressure Boundary Leakage Detection Systems Description of Channe The degree of compliance was revised to eliminate the need to provide a procedure that determmes a t reactor coolant pressure bondary leak rate based on containment atmosphere gaseous and particulate s radioactivity monitoring system.
1 Reason for Channe This change was implemented to reDect actual plant configuration because a proadure does not exist for tids activity due to the large number ofvariables which would be unknown at the time of a leak.
Safety Evaluation This change is editorial in nature and presently leak rates are determined using the plant process computer. Therefore, the change is safe and does not constitute An Unreviewed Safety Question.
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FSARCR Number 11119 98-MP3-53 Residual Heat Removal System Capability for Normal Cooldown Description of Channe The text which describes plant operation dunng normal cooldown was revised to state that for a normal plant cooldown the residual heat removal system is capable of cooling the reactor coolant from 350 .
.g degrees F to 200 degrees F in 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> for one reactor coolant system pump operating and 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br /> for 5 two reactor coolant system pumps operating.
Reason for Change This change was implemented to reficct current operating procedures for normal cooldown and results of revised analysis.
Safety Evaluation This change is editorial in nature and provides assurance that normal cooling, performed in accordance with plant operating procedures, meet licensing time requirements for reaching cold shutdown.
Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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. ESARCR Number Title 98-MP3-57 Water Treating System Demineralized Bypass, Cross-tic, and System Isolation Description of Ch--
This change dar=ments the L-per.iy modifications (B/h 3-86-100/3-94-042/3-86-118) which installed a direct path fmm the water treatment system filtration skids to the final filtration and demineralization
, equipment.- A blank <WFplate was also installed to isolate a portion of the water treatment system i currently not in use and a cross-tic was installed to supply or transfer makeup water between Unit 2 and i Unit 3. !
Reason for Change This change was implemented to provide a means to supply or transfer makeup water to Unit 2 and to provide a direct water treatment path to the final filtration and demineralization equipment. The temporary modifications are still installed. 4 I
Safety Evaluation This change does not degrade any safety component design or function and the licensing conductivity requirements continue to be met. Therefore, the change is safe and does not constitute an Unreviewed i
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FSARCR Number Title 98-MP3 Three Mile Island Action items Changes Description of Channe
(- The table which describes the Unit 3 position on various Three Mile Island items was revised to clanfy the -
description and results of a new small break loss of coolant accident analysis.
l Reason for Channe His change was implemented to reflect new analysis resulting from core moddications and to be l consistent with design and licensing documents.
Sgety Evaluation This change is editorial in nature and the new analysis shows that the probability for introducing a snell break loss of coolant accident resulting fmm a stuck-open power operated relief valve is substantially unaffected by confining anticipatory reactor trip to higher power levels. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Title 98-MP3-64 Auxiliary Feedwater System Initiation Clarification Description of Chanac
' The description of auxiliary feedwater system initiation was revised to clarify that manual auxiliary feedwater system initiation is accomplished by the operator starting the pumps.
Reason for Channe This change was implemented to add additional information and to clarify compliance with licensing documents.
Safety Evahiation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Title 98-MP3-68 Containment Hydrogen Monitoring Clanfication Description of Change The time duration required to place the containment hydrogen monitoring system in service after an accident was added to the system description.
Reason for Change This change was implemented to reflect a maximum time required for an operator to place hydrogen monitors in service and to acknowledge the deviation fomi licensing documents.
Safety Evahiation This change is editorial in nature and does not compromise accident mitigation or hydrogen monitoring requirements. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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l FSARCR Number Titig 98-MP3-69 Pressurizer Valve Interlock Clarification l 1
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!- Description of Channe The description of the pressurizer power operated relief and block valves was corrected to state that, when ,
in auto control, the interlock would open the block valves. '
I l Reason for Change l This change was implemented to reflect actual plant configuration and to be consistent with design 1 documents.
I Safety Evaluation This change is editorial in nature and the interlocks were evaluated to demonstrate that they provide the l required mechanical flow path. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Tit!c 98-MP3-70 Reactor Coolant System Va'.ume Increase Description of Channe The vatious tables that reference reactor coolant system volume and mass parameters were revised to reflect as built values.
Reason for Change This change was implemented to correct volume discrepancies resulting from changes to the initial reactor coolant system design.
Safety Evaluation This change is editorial in nature and all acceptance criteria for the design and safety analysis continue to be met. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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l FSARCR Number Title 98-MP3-72 Containment Recirculation Pump Seal Cavity Clarification l Description of Channe ,
l The text in the description of the containmed recirculation pump seal design and operation was revised. l l
Reason for Channe This change was implemented to more accurately describe the containment recirculation pump seal design and operation and to reflect actual plant configuration.
i Safety Evaluation This change is editorial in nature and the operation of the containment recirculation spray pumps is not .
l affected. Therefore, the change is safe and does not constitute an Unreviewed Safety Question. l l
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FSARCR Number Title 98-MP3-73 Containment Bypass leakage Penetrations Changes Description of Chance The bypass leakage penetration column of the containment penetrations table was revised to identify additional penetrations which are bypass leakage paths.
Ileason for Change This change was implemented to reflect actual plant configuration and to be consistent with design and licensing documents.
Safety Evaluation The activity to add new containment bypass leakage path penetrations is consistent with the functions these penetrations and systems perfonn as evaluated in the current accident analysis. The penetrations are all tested which assures the penetrations will limit leakage from the containment to within licensing and design basis limits. Therefore, the change is safe and does not constitute an Unre dewed Safety Question.
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1 FSARCR Numbg Title 98-MP3-74 Engineered Safety Features Filter Housing Clarification )
Description of Channe The description of the fiber housing design was revised to indicate adequate access panels and doors exist for maintenance and tesung, even though acmss doors are not provided on both sides of each bank of components.
Reason for Change This change was implemented for clarification and to reflect actual plant configuration.
Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Title 98-MP3-76 Safety Parameters Display System Computer Point Update Description of Change The accident monitoring instrumentation list was updated to include two additional computer points to the table for flow to the containment recirculation heat exchangers.
B.cason for Channe This change was implemented to reflect actual plant configuration and to be consistent with licensing documents.
Safety Evaluation This change is editorial in nature and only provides additional non-safety related information. Therefore, .
the change is safe and does not constitute an Unreviewed Safety Question. l I
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FSARCR Number )).t_lg 98-MP3-77 Reactor Coolant System Check Valve Testing Clarification l Description of Channe A statement that non-intrusive techniques in the testing program are used to verify closure of normally open reactor coolant system check valves in series was added to the system description. ,
1 Reason for Channe ' I l~ This change was implemented to reflect actual testing techniques because some check valves were not provided with means to periodically assess back flow leakage.
Safety Evaluation This change is editorial in nature because the non-intrusive techniques for verifying check valve closure provide assurance that the check valves are capable of performing their intended safety function.
Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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i FSARCR Number Title j 98-MP3 78 Standby Diesel Generatur Fuel Oil System Clarification j l
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A statement was added to the description of the standby diesel generator fuel oil system to clarify that procedural controls and sampling assure that fuel oit quality meets or exceeds the ma-%rer's acceptance criteria.
Reason for Chang This change was implemented to reflect actual plant configuration because two of the four fuel forwarding pumps do not have discharge strainers installed.
!- Safety Evaluation This change is editorial in nature and current procedures and sampling programs confirm acceptability of the fuel oil quality. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Iillq 98-MP3-79 Charcoal Adsorber Removal Efficiency Clarification Descilotion of Ch=aae i' A clarification was incorporated into the <tananeamination efficiency description of the auxiliary building l filtration system.
1 Reason for Ch_angg
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This change was implemented to correct an inconsistency between various licensing documents. j 1
Safety Evaluation !
This change is editorial in nature and is conmusent with design and licensing documents. Therefore, the change is safe and does not constitute an Unteviewed Safety Question.
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FSARCR Number Title 98-MP3-80 Radiation Shielding During Spent Fuel Handling Operations i
Description of Channe The description of how the dose rate limit at the water level is maintained when movtag spent fuel was !
clarified to state that the water level is maintained above the active fuel rather than the top of the fuel assembly.
Reason for Channe This change was implemented to reflect actual plant configuration based on normal spent fuel pool and refueling cavity water levels and fuel racks /upenders elevations.
Safety Evaluation i This change is editorial in nature and does not change the ability to limit the gamma dose rate from the fuel at the water surface. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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ESARCR Number Titi.g ,
98-MP3-85 Ernergency Generator Cooling Water Systems Changes l Description of Cha-l The list of major heat load contributors for each heat exchanger was deleted and replaced with values for the totalloads. !
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Reason for Chanaq This change was implemented to reflect actual plant configuration and to be consistent with the manufacturer's design documents.
Safety Evaluation 1his change is editorial in nature and does not affect the performance or reliability of the heat exchangers.
The change accurately represents the diesel generator maud imm's design heat removal rates and does not make any physical changes to plant equipment or auxiliaries. Therefore, the change is safe and does not constitute an Unreviewed Safety Question. -
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ESARCR Number lilla 98-MP3-86 Radiological Changes and Clarifications Descrinaion of Ch===a The text, tables, descriptions, and dose guidelines contained in various sections related to radiological design basis and consequences were revised, corrected and clarified.
Reason for Channe Tids change was implemented to correct a mathematical error, clarify text, and to be consistent with design documents.
Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unrevie#. Safety Question.
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FSARCR Number Title 98-MP3-87 Accident Monitoring Instrumentation List Changes Description of Chan=a The accumulator tank pressure transmitters were removed from the equipawnt qualification master list and were also identified as being electncal equipment qualified "no" on the accident monitoring instrumentation list. j!
O Reason for Channe This change was implemented to reflect actual plant configuration with regards to equipment that is environmentally quahfied for use inside containment.
Safety Evaluation This change is editorial in nature and is consistent with environmental qualification requirements for accumulator pressure instrumentation. Therefore, the change is safe and docs not constitute an Unreviewed Safety Question. -
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l l ESARCR Number Title l 98-MP3-88 Environmental Design Conditions Changes Description Of Chanee The designation of harsh radiation environment was changed to mild radiation environment for various areas and a note to clarify the multiplication requirement regarding conenminated fluids was added.
Reason for Channe This change was implemented to remove excessive conservatism in the radiation calculation for the engineered safety features building.
Safety Evaluation This change is editorial in nature and identifies more realistic actual radiation zonc values. Therefore, the i ' change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Tiljle l 98-MP3 91 Table of Tlute Mile Island Action Items Changes !
Description of Chanae The table that lists the position and references for the emerspecy core cooling system component reliability and tracking program was revised to incorporate an accurate description of how the commitment has been satisfied.
Reason for Channe This change was implemented to reflect how the emergency core cooling system component reliability and tracking program commitment is met.
i Safety Evaluation l This change is editorial in nature and the intent of the original reliability commitment has been met.
Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Iilla 98 MP3-94 Service Water Pump Strainer Motor Switch and Switch Escutcheon Plate Change i Description of Chanaa j A portion of the system description was changed to clarify that the servia water pump stramer motor is 1 controlled from the main board by an OFF/ AUTO /ON switch with indication lights for the associated service water pump strainer backwash valve.
Reason for Change j This change was implemented to reflect actual plant configuration and to be consistent with design I
drawings.
Safety Evaluation This change is editorial in nature, and the performance of components involved with this change remains functionally unchanged. Therefore, the change is safe and does not constitute an Unreviewed Safety l Question. l 1
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FSARCR Number Title 98-MP3-96 En~tainment Temperature Change Description of Chanee The containment temperatures, during normal operation and during loss of offsite power, were revised and the affected design parameters, fan capacities and heat loads were updated.
Reason for Changg This change was implemented to be consistent with licensing documents and to reflect new calculations and actual fan flow from tests used in the analysis.
Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.
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