RS-10-001, LaSalle, Units 1 and 2, Attachment 3 - Markup of Proposed Technical Specifications Bases and Technical Requirements Manual Pages

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LaSalle, Units 1 and 2, Attachment 3 - Markup of Proposed Technical Specifications Bases and Technical Requirements Manual Pages
ML100321307
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 01/27/2010
From:
Exelon Generation Co, Exelon Nuclear
To:
Office of Nuclear Reactor Regulation
Shared Package
ML100321303 List:
References
RS-10-001
Download: ML100321307 (11)
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ATTACHMENT 3 Markup of Proposed Technical Specifications Bases and Technical Requirements Manual Pages LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 REVISED TECHNICAL SPECIFICATIONS BASES PAGES 3.3.1.1-31 3.3.1.3-3 3.3.1.3-8

3.3.1.3-9

REVISED TECHNICAL REQUIREM ENTS MANUAL PAGES 1.1-3 3.3.c-5 3.3.q-1 3.3.q-2 Appendix D, Page D-1

RPS Instrumentation B 3.3.1.1

LaSalle 1 and 2 B 3.3.1.1-31 Revision 13 BASES

SURVEILLANCE SR 3.3.1.1.9 and SR 3.3.1.1.12 (continued)

REQUIREMENTS transient if the Surveillance were performed with the

reactor at power. Operating experience has shown that these

components usually pass the Surveillance when performed at

the 24 month Frequency.

SR 3.3.1.1.10, SR 3.3.1.1.11, and SR 3.3.1.1.13 A CHANNEL CALIBRATION is a complete check of the instrument

loop, including associated trip unit, and the sensor. This

test verifies the channel responds to the measured parameter

within the necessary range and accuracy. CHANNEL

CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

Note 1 of SR 3.3.1.1.11 and SR 3.3.1.1.13 states that

neutron detectors are excluded from CHANNEL CALIBRATION

because of the difficulty of simulating a meaningful signal.

Changes in neutron detector sensitivity are compensated for

by performing the 7 day calorimetric calibration (SR 3.3.1.1.2) and the 1000 EFPH LPRM calibration against

the TIPs (SR 3.3.1.1.8). A second Note to SR 3.3.1.1.11 and

SR 3.3.1.1.13 is provided that requires the APRM and IRM SRs

to be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entering MODE 2 from MODE

1. Testing of the MODE 2 APRM and IRM Functions cannot be performed in MODE 1 without utilizing jumpers, lifted leads, or movable links. This Note allows entry into MODE 2 from

MODE 1 if the associated Frequency is not met per SR 3.0.2.

Twenty-four hours is based on operating experience and in

consideration of providing a reasonable time in which to

complete the SR. The Frequencies of SR 3.3.1.1.10 and

SR 3.3.1.1.11 are based upon the assumption of a 92 day and

184 day calibration interval, respectively, in the

determination of the magnitude of equipment drift in the

setpoint analysis. The Frequency of SR 3.3.1.1.13 is based

on the assumption of a 24 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

(continued)

TS Bases Inserts Bases Insert 1 For Function 2.b, SR 3.3.1.1.11 is modified by two Notes. The first Note requires evaluation of channel performance for the condition where the as-found setting for the channel setpoint is outside its as-found tolerance but conservative with respect to the Allowable Value. Evaluation of channel performance will verify that the channel will continue to behave in accordance with safety analysis assumptions and the channel performance assumptions in the setpoint methodology. The purpose of the assessment is to ensure confidence in the channel performance prior to returning the channel to service. For channels determined to be OPERABLE but degraded, after returning the

channel to service the performance of these channels will be evaluated under the plant

Corrective Action Program. Entry into the Corrective Action Program will ensure required review and documentation of the condition. The second Note requires that the as-left setting for the channel be within the as-left tolerance of the nominal trip setpoint (NTSP). Where a setpoint more conservative than the NTSP is used in the plant surveillance procedures, the as-left and as-found tolerances, as applicable, will be

applied to the surveillance procedure setpoint. This will ensure that sufficient margin to the Safety Limit and/or Analytical Limit is maintained. If the as-left channel setting cannot be returned to a setting within the as-left tolerance of the NTSP, then the channel shall be declared inoperable.

OPRM Instrumentation B 3.3.1.3 LaSalle 1 and 2 B 3.3.1.3-3 Revision 23 BASES APPLICABLE The nominal setpoints for the OPRM Period Based Trip SAFETY ANALYSES Function are specified in the Core Operating Limits Report. (continued) The trip setpoints are treated as nominal setpoints and do not require additional allowances for uncertainty.

Trip setpoints are those predetermined values of output at which an action should take place. The setpoints are compared to the actual process parameter value and when the measured output value of the process parameter exceeds the setpoint, the associated device (e.g., trip unit) changes state. The OPRM period based setpoint is determined by cycle specific analysis based on positive margin between the Safety Limit MCPR and the Operating Limit MCPR minus the change in CPR (CPR). This methodology was approved for use by the NRC in Reference 5.

LCO Four channels of the OPRM System are required to be OPERABLE to ensure that stability related oscillations are detected and suppressed prior to exceeding the MCPR safety limit. Only one of the two OPRM modules (with an active period based detection algorithm) is required for OPRM channel OPERABILITY. The minimum number of LPRMs required to maintain the APRM system OPERABLE per LCO 3.3.1.1 provides an adequate number of LPRMs to maintain an OPRM channel OPERABLE.

APPLICABILITY The OPRM instrumentation is required to be OPERABLE in order to detect and suppress neutron flux oscillations in the event of thermal-hydraulic instability. As described in References 1, 2, 3, and 9, the region of anticipated oscillation is defined by THERMAL POWER 28.6% rated thermal power (RTP) and recirculation drive flow < 60% of rated recirculation drive flow. The OPRM trip is required to be enabled in this region, and the OPRM must be capable of enabling the trip function as a result of anticipated transients that place the core in that power/flow condition. Therefore the OPRM instrumentation is required to be OPERABLE with THERMAL POWER 25% RTP. It is not necessary for the OPRM instrumentation to be OPERABLE with THERMAL POWER < 25% RTP because the MCPR safety limit is not applicable below 25% RTP.

(continued)

OPRM Instrumentation B 3.3.1.3 LaSalle 1 and 2 B 3.3.1.3-8 Revision 23 BASES SURVEILLANCE SR 3.3.1.3.3 (continued)

REQUIREMENTS The nominal setpoints for the OPRM trip function for the period based detection algorithm (PBDA) are specified in the Core Operating Limits Report. The PBDA trip setpoints are the number of confirmation counts required to permit a trip signal and the peak to average amplitude required to generate a trip signal.

The Frequency of 24 months is based upon the assumption of the magnitude of equipment drift provided by the equipment supplier (Ref. 6).

SR 3.3.1.3.4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel. The functional testing of control rods, in LCO 3.1.3, "Control Rod OPERABILITY," and scram discharge volume (SDV) vent and drain valves, in LCO 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves," overlaps this Surveillance to provide complete testing of the assumed safety function. The OPRM self-test function may be utilized to perform this testing for those components that it is designed to monitor.

The 24 month Frequency is based on engineering judgment and reliability of the components. Operating experience has shown these components usually pass the surveillance when performed at the 24 month Frequency.

SR 3.3.1.3.5 This SR ensures that trips initiated from the OPRM System will not be bypassed (i.e., fail to enable) when THERMAL POWER is 28.6% RTP and recirculation drive flow is < 60%

of rated recirculation drive flow. This normally involves calibration of the bypass channels. The 28.6% RTP value is the plant specific value for the enable region, as described in Reference 9.

These values have been conservatively selected so that specific, additional uncertainty allowances need not be applied. Specifically, the THERMAL POWER, the Average Power Range Monitor (APRM) establishes the reference signal to enable the OPRM system at 28.6% RTP. Thus, the nominal (continued)

OPRM Instrumentation B 3.3.1.3 LaSalle 1 and 2 B 3.3.1.3-9 Revision 23 BASES SURVEILLANCE SR 3.3.1.3.5 (continued)

REQUIREMENTS setpoints corresponding to the values listed above (28.6%

of RTP and 60% of rated recirculation drive flow) will be used to establish the enabled region of the OPRM System trips. (References 1, 2, 5, 9, and 11)

If any bypass channel setpoint is nonconservative (i.e., the OPRM module is bypassed at 28.6% RTP and < 60% of rated recirculation drive flow), then the affected OPRM module is considered inoperable. Alternately, the bypass channel can be placed in the conservative condition (nonbypass). If placed in the nonbypass condition, this SR is met and the module is considered OPERABLE.

The Frequency of 24 months is based on engineering judgment and reliability components.

SR 3.3.1.3.6 This SR ensures that the individual channel response times are less than or equal to the maximum values assumed in the accident analysis. The OPRM self-test function may be utilized to perform this testing for those components it is designed to monitor. The RPS RESPONSE TIME acceptance criteria are included in Reference 10.

RPS RESPONSE TIME may be verified by actual response time measurements in any series of sequential, overlapping, or total channel measurements. As noted, neutron detectors are excluded from RPS RESPONSE TIME testing because the principles of detector operation virtually ensure an instantaneous response time. RPS RESPONSE TIME tests are conducted on a 24 month STAGGERED TEST BASIS. This Frequency is consistent with the refueling cycle and is based upon operating experience, which shows that random failures of instrumentation components causing serious time degradation, but not channel failure, are infrequent.

REFERENCES 1. NEDC-39160, "BWR Owners Group Long-Term Stability Solutions Licensing Methodology," June 1991.

2. NEDO-39160, "BWR Owners Group Long-Term Stability Solutions Licensing Methodology," Supplement 1, March 1992. (continued)

TRM Definitions 1.1 LaSalle 1 and 2 1.1-3 Revision 1 1.1 Definitions (continued)

OFFSITE DOSE CALCULATION MANUAL (ODCM) The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Program and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports.

OPERABLE -

OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified function(s) are also capable of performing their related

support function(s).

RATED THERMAL POWER (RTP) RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3489 MWt.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRM Control Rod Block Instrumentation 3.3.c LaSalle 1 and 2 3.3.c-5 Revision 2 Table T3.3.c-1 (page 1 of 2) Control Rod Block Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Average Power Range Monitors a. Flow Biased Neutron Flux - Upscale 1 4 TSR 3.3.c.2 TSR 3.3.c.4 0.62W + 57.9%(a) RTP b. Inoperative 1,2 4 TSR 3.3.c.2 N.A. c. Downscale 1 4 TSR 3.3.c.2 TSR 3.3.c.4 3% RTP d. Neutron Flux - High 2 4 TSR 3.3.c.2 TSR 3.3.c.4 14% RTP 2. Source Range Monitors a. Detector not full in 2(b) 5 3 2 TSR 3.3.c.1 TSR 3.3.c.1 N.A. N.A. b. Upscale 2 (c) 5 3 2 TSR 3.3.c.1 TSR 3.3.c.5 TSR 3.3.c.1 TSR 3.3.c.5 5 x 10 5 cps 5 x 10 5 cps c. Inoperative 2 (c) 5 3 2 TSR 3.3.c.1

TSR 3.3.c.1 N.A.

N.A. d. Downscale 2(d) 5 3 2 TSR 3.3.c.1 TSR 3.3.c.5 TSR 3.3.c.1 TSR 3.3.c.5 0.5 cps 0.5 cps (a) Allowable Value is (0.55W + 45.4%) RTP when reset for single loop operation per Technical Specification 3.4.1, "Recirculation Loops Operating."

(b) With detector count rate < 100 cps and the Intermediate Range Monitor (IRM) channels are on range 2 or below.

(c) With IRM channels on range 7 or below.

(d) With IRM channels on range 2 or below.

TRM Feedwater Flow Instrumentation 3.3.q LaSalle 1 and 2 3.3.q-1 Revision 0

3.3 INSTRUMENTATION

3.3.q Feedwater Flow Instrumentation

TLCO 3.3.q The Leading Edge Flow Meter instrumentation system shall be OPERABLE.

APPLICABILITY: MODE 1, with THERMAL POWER > 3489 MWt

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more systems inoperable.

A.1 Restore required instruments to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. REQUIRED ACTION and associated COMPLETION TIME of CONDITION A not met.

B.1 Reduce power to <

3489 MWt.

Immediately

TRM Feedwater Flow Instrumentation 3.3.q LaSalle 1 and 2 3.3.q-2 Revision 0

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

TSR 3.3.q.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

TRM Appendix D Instrumentation Trip Setpoints Table T3.3.1.1-1 (page 1 of 1)Reactor Protection System Instrumentation Trip Setpoints FUNCTION 1.Intermediate Range Monitors a.Neutron Flux-High b.Inop 2.Average Power Range Monitors a.Neutron Flux-High, Setdown b.Flow Biased Simulated Thermal Power-Upscale c.Fixed Neutron Flux-High d.Inop 3.Reactor Vessel Steam Dome Pressure-High 4.Reactor Vessel Water Level-Low, Level 3 5.Main Steam Isolation Valve-Closure 6.Drywell Pressure-High 7.Scram Discharge Volume Water Level-High a.Transmitter/Trip Unit b.Float Switch 8.Turbine Stop Valve-Closure 9.Turbine Control Valve Fast Closure, Trip Oil Pressure-Low 10.Reactor Mode Switch-Shutdown Position 11.Manual Scram NOMINAL TRIP SETPOINT CALCULATION NUMBER L-001344 NA L-001345 L-001345(a)

L-001345 NA NED-I-EIC-0174 NED-I-EIC-0201 (Unit 1)NED-I-EIC-0203 (Unit 2)L-002596 NED-I-EIC-0178 NED-EIC-0179 NED-I-EIC-0263 L-002596 NED-I-EIC-0181 NA NA (a)Nominal Trip Setpoint is shown in calculation L-001345 for single loop operation per LCO 3.4.1,"Recirculation Loops Operating." LaSalle 1 and 2 D-1 Revision 0

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