ML033110109
| ML033110109 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 11/05/2003 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML033110109 (11) | |
Text
AGENDA Overview of Technical Specification (TS) 02-01 Setpoint and Allowable Value Changes 0
TS 02-01 Proposed Changes I:License/WorddocrTS 02-01 Presentation
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OVERVIEW OF TS 02-01
- Change Proposed to Resolve NRC Resident Inspector Issue - Nominal Trip Setpoint
- Consistent with TSTF-355 (TSB-20)
- For Reactor Trip (RT) and Engineered Safety Features (ESF) Limiting Condition of Operation (LCO):
0 Added "Nominal" Above Trip Setpoint Column and Consistently Revised the Use of "Nominal" Throughout the TSs 0 Deleted Inequalities Signs on Trip Setpoint Values 0 Corrected Reactor Coolant Pump (RCP) Under Voltage/Under Frequency Values 0 Revised Minimum Channels Operable Value for Auxiliary Feedwater (AFW) Loss of Power Timers 1:Liccnsc/Worddoc/TS 02-01 PrcscntIation OVERVIEW OF TS 02-01
- For Consistency With NUREG-1431 and to More Appropriately Accommodate the Safety Function for Some of the Functions Affected:
0 Four New LCOs Were Created
)TS
)TS 3.3.3.11 -
3.3.3.12 -
>TS 3.3.3.13 -
> TS 3.3.3.14 -
Containment Vent Isolation (CVI) Instrumentation Auxiliary Building Gas Treatment System (ABGTS)
Actuation Instrumentation Control Room Emergency Ventilation System (CREVS) Actuation Implementation Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation 0 The Current Radiation Monitoring LCO (TS 3.3.3.1) was Deleted 0 The RCS Leakage Detection LCO SR (SR 4.4.6.1.a) was Modified I:License/WorddoclTS 02-01 Presentation OVERVIEW OF TS 02-01
- Containment Vent Isolation (CVI) Instrumentation (TS 3.3.3.1 1) 0 Actions Tied to Appropriate Containment Isolation TS 0 Applicability Column Utilized Consistent with TSTF-161 0 Setpoint Column Deleted and Allowable Value Relaxed From Current Value 0 Allowable Value (AV) Column Chosen to Allow Flexibility in Setting Radiation Monitor (RM) Setpoints I:Liccnsc/Worddoc/TS 02-01 Prescntation OVERVIEW OF TS 02-01 e Auxiliary Building Gas Treatment System (AGBTS) Actuation Instrumentation - TS 3.3.3.12 0 Relaxed Applicability With Respect to Fuel in Spent Fuel Pool Versus Movement of Irradiated Fuel Assembly 0 Action Made More Conservative by Requiring ABGTS to be Declared Inoperable Versus Increased Monitoring 0 Setpoint Column Deleted and Added AV Column K New AV Value Calculated I:Liccnsc/Worddoc/TS 02-01 Presentation
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OVERVIEW OF TS 02-01 e Control Room Emergency Ventilation Systems (CREVs) Actuation Instrumentation - TS 3.3.3.13 O Actions Have Been Aligned for the Different Modes of Applicability to Match the CREVs Function O Setpoint Column Deleted and Allowable Value Column Created O New AV Calculated I:LicenselWorddoc/TS 02-01 Presentntion OVERVIEW OF TS 02-01
- Loss of Power (LOP) DG Start Instrumentation - TS 3.3.3.14 0 Both sets of DG Start and Load Shed Timers and the SI/Degraded Voltage Logic Enable Timer Changed Required Channels from 2 to 1 0 Added Upper AV for Loss of Voltage and Degraded Voltage (DV)
Sensors (Reference TSTF-365) 0 Added the Lower AV Limit for the DV DG Start and Load Shed Timer I:License/WorddoclTS 02-01 Presentation Setpoints and Allowable Values Changes Change Description Setpoint Methodology in TS 02-01 Impact of Change Reactor Trip System -
Westinghouse methodology, Method 3 with T2 Undervoltage Reactor Coolant calculation check (WCAP-1 1239). NRC review of More restrictive allowable value Pumps Allowable Value from Ž4739 this WCAP performed in conjunction with TS Change resulting from change in methodology volts to 4952 volts 89-27 and Amendments 141 (U1) and 132 (U2)
Reactor Trip System -
Westinghouse methodology, Method 3 with T2 Underfrequency Reactor Coolant calculation check (WCAP-1 1239). NRC review of More restrictive Setpoint to Pumps Setpoint from >56.0 Hz to this WCAP performed in conjunction with TS Change accommodate new instrumentation and Nominal 57 Hz 89-27 and Amendments 141 (U1) and 132 (U2) methodology change Reactor Trip System -
Westinghouse methodology, Method 3 with T2 Underfrequency Reactor Coolant calculation check (WNCAP-11239). NRC review of More restrictive Setpoint to Pumps Allowable Value from >55.9 this WCAP performed in conjunction with TS Change accommodate new instrumentation and Hz to Ž56.3 Hz 89-27 and Amendments 141 (Ul) and 132 (U2) methodology change Setpoint will be controlled in ESF Actuation System and Not Applicable accordance with plant procedures and Radiation Monitoring the setpoint methodology to ensure that Instrumentation - Containment the allowable value is properly Purge Air Exhaust Radioactivity maintained. Actual practice is to use a Monitor Setpoint from s8.5 x 10-3 setpoint more conservative than pCi/cc to no specified value required.
ESF Actuation System -
Containment Purge Air Exhaust TVA's TI-28 methodology, Method 3 without T2 Proposed Allowable Value is less Radioactivity Monitor Allowable restrictive than the current value.
Value from s8.5 x 10-3 pCi/cc to s100,000 cpm in a new LCO for CVI actuation l:Liccnsc/Worddoc/TS 02-01 Prcscniation-Setpoints and Allowable Values Changes (continued)
Change Description Setpoint Methodology in TS 02-01 Impact of Change TVA's TI-28 methodology, Method 3 without T2. This ESF Actuation System - AFW and is a new value but determined consistent with other Current TSs do not utilize an upper EDG loss-of-power start allowable loss of voltage and degraded voltage values. These limit, therefore, this addition is more value added for upper limit of s5688 values and the associated Calculation SQN-EEB-restrictive. This addition supports the volts MS-T106-0008 reviewed by NRC with TS Change NRC requested change to ITS.
93-09 and Amendments 182 (UI) and 174 (U2).
Current TSs do not utilize an upper ESF Actuation System - EDG TVA's TI-28 methodology, Method 3 without T2. This limit, therefore, this addition is more degraded voltage start allowable is a new value but determined consistent with other restrictive. This addition supports the value added for upper limit of loss of voltage and degraded voltage values. These NRC requested change to ITS. This s6522.5 volts. Results in the values and the associated Calculation SQN-EEB-change replaces the current reset value deletion of the current reset value of MS-T106-0008 reviewed by NRC with TS Change which served a similar purpose and c6595.5 volts 93-09 and Amendments 182 (U1) and 174 (U2).
results in a more restrictive value.
TVA's TI-28 methodology, Method 3 without T2. This Current TSs do not utilize a lower limit, ESF Actuation System - EDG is a new value but determined consistent with other therefore, this addition is more degraded voltage start and load loss of voltage and degraded voltage values. These restrictive. Conservative addition to shed timer allowable value added values and the associated Calculation SQN-EEB-better indicate allowable operating for lower limit of >218.6 seconds.
MS-T106-0008 reviewed by NRC with TS Change ranges for the timer and for consistency 93-09 and Amendments 182 (UI) and 174 (U2).
with other timers.
Setpoint will be controlled in Radiation Monitoring Not applicable accordance with plant procedures and Instrumentation - Fuel Storage Pool the setpoint methodology to ensure that Area Monitor, relocated to new LCO the allowable value is properly for ABGTS actuation and current maintained. Actual practice is to use a setpoint of s200 mR/hr not utilized setpoint more conservative than in lieu of an allowable value required.
I:Licensc/Worddoc/TS 02-01 Prcsentation
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Setpoints and Allowable Values Changes (continued)
Change Description Setpoint Methodology in TS 02-01 Impact of Change Addition of an allowable value that ABGTS Actuation Instrumentation -
TVA's TI-28 methodology, Method 3 without T2 protects the safety limit is an alternative Fuel Storage Pool Area Radiation approach to current requirements to Monitor, new LCO for ABGTS only provide a setpoint. The proposed actuation and an allowable value of LCO for ABGTS provides a more safety s307 mR/hr utilized function oriented approach that supports accident mitigation functions.
The proposed allowable value is less restrictive than the current setpoint.
Setpoint will be controlled in Radiation Monitoring Not applicable accordance with plant procedures and Instrumentation - Control Room the setpoint methodology to ensure that Isolation Monitor, relocated to new the allowable value is properly LCO for CREVS actuation and maintained. Actual practice is to use a current setpoint of s400 cpm not setpoint more conservative than utilized in lieu of an allowable value required.
Addition of an allowable value that CREVS Actuation Instrumentation -
TVA's TI-28 methodology, Method 3 without T2 protects the safety limit is an alternative Control Room Intake Radiation approach to current requirements to Monitor, new LCO for CREVS only provide a setpoint. The proposed actuation and an allowable value of LCO for CREVS provides a more safety
<43,400 cpm utilized function oriented approach that supports accident mitigation functions.
The proposed allowable value is less restrictive than the current setpoint.
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