ML081540285

Technical Specifications, Measurement Uncertainty Recapture Power Uprate

ML081540285
Person / Time
Site:	Cooper
Issue date:	06/30/2008
From:	NRC/NRR/ADRO/DORL/LPLIV
To:
Lyon, C F, NRR/DLPM, 415-2296
Shared Package
ML081540278	List: ML081540280 ML081540285
References
TAC MD7385
Download: ML081540285 (14)

Text

{{#Wiki_filter:Definitions 1.1 1.1 Definitions LOGIC SYSTEM FUNCTIONAL TEST (continued) MINIMUM CRITICAL POWER RATIO (MCPR) MODE OPERABLE - OPERABILITY RATED THERMAL POWER (RTP) REACTOR PROTECTION SYSTEM (RPS) RESPONSE TIME SHUTDOWN MARGIN (SDM) from as close to the sensor as practicable up to, but not including, the actuated device, to' verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested. The MCPR shall be the smallest critical power ratio (CPR) that exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power. A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel. A system, subsystem, division, component, or-device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety 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 safety function(s) are also capable of performing their related support function(s). RTP shall be a total reactor core heat transfer rate to the reactor coolant of 2419 MWt. The RPS RESPONSE TIME shall be that time segment .from the time the sensor contacts actuate to the time the .scram solenoid valves deenergize. SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming that:

a.

The reactor is xenon free; (continued) Cooper 1.1-4 Amendment No. 231

Control Rod OPERABILITY 3.1.3 Actions (continued) CONDITION REQUIRED ACTION COMPLETION TIME D.

---

NOTE ----------

D.1 Restore compliance with 4 hours Not applicable when BPWS. THERMAL POWER > 9.85% RTP. OR D.2 Restore control rod to 4 hours Two or more inoperable OPERABLE status. control rods not in compliance with banked position withdrawal sequence (BPWS) and not separated by two or more OPERABLE control rods. E. Required Action and E.1 Be in MODE 3. 12 hours associated Completion Time of Condition A, C, or D not met. OR Nine or more control rods inoperable. Cooper 3.1-9, Amendment No. 231

Rod Pattern Control 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control LCO 3.1.6 APPLICABILITY: OPERABLE control rods shall comply with the requirements of the banked position withdrawal sequence (BPWS). MODES 1 and 2 with THERMAL POWER < 9.85% RTP. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more OPERABLE A.1 - NOTE------- control rods not in Rod worth minimizer compliance with BPWS. (RWM) may be bypassed as allowed by LCO 3.3.2.1, "Control Rod Block Instrumentation." Move associated control 8 hours rod(s) to correct position. OR A.2 Declare associated control 8 hours rod(s) inoperable. (continued) Cooper 3.1-18 Amendment No. 231

RPS Instrumentation 3.3.1.1 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Table Time of Condition A, B, 3.3.1.1-1 for the channel. or C not met. E. As required by Required E.1 Reduce THERMAL 4 hours Action D.1 and POWER to < 29.5% RTP. referenced in Table 3.3.1.1-1. F. As required by Required F.1 Be in MODE 2. 6 hours Action D.1 and referenced in Table 3.3.1.1-1. G. As required by Required G.1 Be in MODE 3. 12 hours Action D.1 and referenced in Table 3.3.1.1-1. H. As required by Required H.1 Initiate action to fully insert immediately Action D.1 and all insertable control rods in referenced in Table core cells containing one or 3.3.1.1-1. more fuel assemblies. Cooper 3.3-2 Amendment No. 231

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.1.1.11 Perform CHANNEL FUNCTIONAL TEST. 18 months SR 3.3.1.1.12 NOTES ----------------------------

1. Neutron detectors are excluded.

2.

For Function 1, not required to be performed when entering MODE 2 from MODE 1 until 12 hours after entering MODE 2. Perform CHANNEL CALIBRATION. 18 months SR 3.3.1.1.13 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months SR 3.3.1.1.14 Verify Turbine Stop Valve - Closure and Turbine 18 months Control Valve Fast Closure, Trip Oil Pressure - Low Functions are not bypassed when THERMAL POWER is > 29.5% RTP. SR 3.3.1.1.15 NOTE ----------------------------- Neutron detectors are excluded. Verify the RPS RESPONSE TIME is within limits. 18 months Cooper 3.3-5 Amendment No. 231

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3) Reactor Protection System Instrumentation APPLICABLE CONDITIONS* MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

1.

Intermediate Rancge Monitors

a.

Neutron Flux - High 2 3 G H 5 (a) 3 SR 3,3.1.1.1 SR 3.3.1.1.3 SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.6 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.1 SR 3.3.1.1.3 SR 3.3.1.1.4 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.3 SR 3.3.1.1.4 SR 3.3.1.1.13* SR 3.3.1.1.3 SR 3.3.1.1.4 SR 3.3.1.1.13 < 121/125 divisions of full scale < 121/125 divisions of full scale

b.

Inop 2 3 3 G H NA NA 5 (a)

2.

Average Power Range Monitors

a.

Neutron Flux - High (Startup)

b.

Neutron Flux-High (Flow Biased) 2 2 2 G SR 3.3.1.1.1 SR 3.3.1.1.3 SR 3.3.1.1.4 SR 3.3.1.1.6 SR 3.3.1.1.8 SR 3.3.1.1,10 SR 3.3.1.1.13 SR 3.3.1.1.15 F SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.4 SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.11 0 (c,d) SR 3.3.1.1. 1 2 (c,d) SR 3.3.1.1.13 SR 3.3.1.1.15 _ 14.5% RTP < 0.75 W + 62.0% RTP(b) (continued) (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies. (b) [0.75 W + 62.0% - 0.75 AW] RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating." (c) If the as-found setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. (d) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures to confirm the channel performance. The NTSP and the methodologies used to determine the as-found and as-left tolerances are specified in station procedures implementing the GE Setpoint Methodology per NEDC-31336P-A approved in TS Amendment 178 SER, Section III.G.2. Cooper 3.3-6 Amendment No. 231

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 3 of 3) Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

7.

Scram. Discharge Volume Water Level - High

a.

Level Transmitter 1,2 2 2 G H 5(a)

b.

Level Switch 1,2 2 H H 5(a)

8.

Turbine Stop Valve - Closure

9.

Turbine Control Valve Fast Closure, DEH Trip Oil Pressure - Low 10.. Reactor Mode Switch - Shutdown Position

11.

Manual Scram > 29.5% RTP > 29.5% RTP 1,2 5(a) 1,2 5(a) 2 E SR 3.3.1.1.4 SR 3.3.1.1.9 SR 3.1,1.112 SR 3.3.1.1.13 SR 3.3.1.1.15 SR.3.3.1.1.4 SR 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.4 SR 3.3.1.1.9 SR 3.3.1..1.12 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.4 SR 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.4 SR 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.13 SR.3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.4 SR. 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.11 SR 3.3.1.1.13 SR 3.3.1.1.11 SR 3.3.1.1.13 SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.9 SR 3.3.1.1.13 < 90 inches < 90 inches . 10% closed

• 1018 psig NA NA NA NA

< 90 inches < 90 inches 2 E 1 1 1 G H G H (a) Withý any contol rod withdrawn from a core cell containing one or more fuel assemblies. Cooper 3.3-8 Amendment No. 231 1

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.2.1.2 NOTE ------ Not required to be performed until 1 hour after any control rod is withdrawn at < 9.85% RTP in MODE 2. 92 days Perform CHANNEL FUNCTIONAL TEST. SR 3.3.2.1.3 -- 7 -...

---

NOTE---------------

Not required to be performed until 1 hour after THERMAL POWER is < 9.85% RTP in MODE 1. Perform CHANNEL FUNCTIONAL TEST. .92 days SR 3.3.2.1.4

---

NOTE-----------------

Neutron detectors are excluded. Verify the RBM: 184 days

a.

Low Power Range - Upscale Function is not bypassed when THERMAL POWER is > 27.5% and < 62.5% RTP and a peripheral control rod is not selected.

b.

Intermediate Power Range Upscale Function is not bypassed when THERMAL POWER is > 62.5% and < 82.5% RTP and a peripheral control rod is not selected.

c.

High Power Range - Upscale Function is not bypassed when THERMAL POWER is > 82.5% RTP and a peripheral control rod is not selected. (continued) Cooper.* -3.3-17 Amendment No. 231

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.2.1.5 - NOTE Neutron detectors are excluded. Perform CHANNEL CALIBRATION. 184 days SR 3.3.2.1.6 Verify the RWM is not bypassed when THERMAL 18 months POWER is < 9.85% RTP. SR 3.3.2.1.7

---

------------ NOTE Not required to be performed until 1 hour after reactor mode switch is in the shutdown position.

Perform CHANNEL FUNCTIONAL TEST. 18 months SR 3.3.2.1.8 Verify control rod sequences input to the RWM are Prior to declaring in conformance with BPWS. RWM OPERABLE following loading of sequence into RWM Cooper 3.3-18 Amendment No. 231

Control Rod Block Instrumentation 3.3.2.1 Table 3.3.2.1-1 (page 1 of 1) Control Rod Block Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE Rod Block Monitor

a.

Low Power Range - Upscale (a) 2 SR 3.3.2.1.1 (h) SR 3.3.2.1.4 SR 3.3.2.1.5

b.

Intermediate Power Range - Upscale (b) 2 SR 3.3.2.1.1 (h) SR 3.3.2.1.4 SR 3.3.2.1.5

c.

High Power Range - Upscale (c),(d) 2 SR 3.3.2.1.1 (h) SR 3.3.2.1.4 SR 3.3.2.1.5

d.

Inop (d),(e) 2 SR 3.3.2.1.1 NA

e.

Downscale (d),(e) 2 SR 3.3.2.1.1 > 92/125 SR 3.3.2.1.5 divisions of full scale

2.

Rod Worth Minimizer 1(f),2(f) 1 SR 3.3.2.1.2 NA SR 3.3.2.1.3 SR 3.3.2.1.6 SR 3.3.2.1.8

3.

ReactorMode Switch - Shutdown Position (g) 2 SR 3.3.2.1.7 NA (a) (b) (c) (d) (e) (f) (g) (h) THERMAL POWER > 27.5% and < 62.5% RTP and MCPR < 1.70 and no peripheral control rod selected. THERMAL POWER > 62.5% and < 82.5% RTP and MCPR < 1.70 and no peripheral control rod selected. THERMAL POWER > 82.5% and < 90% RTP and MCPR < 1.70 and no peripheral control rod selected. THERMAL POWER > 90% RTP and MCPR < 1.40 and no peripheral control rod selected. THERMAL POWER > 27.5% and < 90% RTP and MCPR < 1.70 and no peripheral control rod selected. With THERMAL POWER < 9.85% RTP. Reactor mode switch in the shutdown position. Less than or equal to the Allowable Value specified in the COLR. Cooper 3.3-19 Amendment No. 231

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 of 3) Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

1.

Main Steam Line Isolation

a.

Reactor Vessel Water Level - Low Low Low (Level 1)

b.

Main Steam Line Pressure - Low

c.

Main Steam Line Flow - High

d.

Condenser Vacuum - Low

e.

Main Steam Tunnel Temperature - High

2.

Primary Containment Isolation

a.

Reactor Vessel Water Level - Low (Level 3) 1,2,3 1 1,2,3 1, 2(a), 3(a) 1,2,3 2 2 2 per MSL 2 2 per location D E D D D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4. SR 3.3.6.1.6 SR 3.3,6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 > -113 inches

• 835 psig
• 142.7%

rated steam flow > 8 inches Hg vacuum < 195°F b. Drywell Pressure - High

c.

Reactor Building Ventilation Exhaust Plenum Radiation-High

d.

Main Steam Line Radiation - High

e.

Reactor Vessel Water Level -Low Low Low (Level 1) 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 2 2 2 2 2 G G F F, F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3:3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 > 3 inches. < 1.84 psig < 49 mR/hr

• 3 times full power background

> -113 inches (continued) (a) With any turbine slop valve not closed. Amendment 231 3.3-51 6/30/08 1

RCS P/T Limits 3.4.9 Cooper Heatup/Cooldown, Core Not Critical Curve (Curve B), 28 EFPY i 1,600 1,500 1,400 1,300 0) 1,200 'U " 1,100 0~ -I 1,000 LU C') u) 900 0* Boo O o 800-z 700 600 U. U) 500 ' 400 I I I I I +*L'_'7_'* -iii I I t....... 1:17 I 1-4 iuizzLj - /72 172: zz] ~~~~~~~1 t+-......... l..... h If1 /1 1721 LL 4-1 ~ii7 -I- - *-- -1 I...1........I- -i.. -I--I-i-I-.-

7Yzj:7472[727 z

J I I

4

~H~- 4 i-1-~ i-- 1-- t- - i,------.... // 8 '1F, 341 psig

• "*+f i J V-I X

-il+ I I '14 4mr 41r)',i5 psig 1-- Operating Region i__ I 300 200 100 0-F 80F, 313 psg J 4.4 Boltup >800F 1401I, 313 .o,*+,*-.... t*- Beltline Bottom Head UpperVessel 'II -A----- i---I---i--.i---i+ r 0 50 100 150 200 250 300 MINIMUM REACTOR VESSEL METAL TEMPERATURE (fF) Figure 3.4.9-1 (page 1 of 1) Pressure/Temperature Limits for Non-Nuclear Heatup or Cooldown Following Nuclear Shutdown Valid Through 28 EFPY Amendment 231 3.4-23

RCS P/T Limits 3.4.9 Cooper Pressure Test Curve (Curve A), 28 EFPY 1,600 1,500 1,400 1,300 W 1,200 w 1,100 0 1,000 U) 900 800 w 0, 700 z 600 --I w 500 U) ILU 400 300 200 100 0 P - ~ - P P - 9 - ~ - P 9 - P P - .........3J~I T.:~EzE.I-i I::

• 1-I-

~1~ -.5....-. --At-Ai'i --I I i 4.I-F-41 .'p -llt-. I' I I-I- -/ g ~ I Al 123 0F 753 rsig-S11 f Operating Region 80 1 IF~, 5V97 ;i g 807F,555 rsig ~jz &.1 ..f- =441= il 1 111_- --I I 1E] 1=1 ___- I I l Boltup I> 800ýF 12 3 F, 26 9 1sig -l Beftline..... Bottom Head Upper Vessel LElEIIETLII h-I-4r4~ 0 20 40 60 80 100 120 140 160 180 200 220 240 MINIMUM REACTOR VESSEL METAL TEMPERATURE (=F) Figure 3.4.9-2 (page 1 of 1) Pressure/Temperature Limits for Inservice Hydrostatic and Inservice Leakage Tests Valid Through 28 EFPY Amendment 231 3.4-24

RCS P/T Limits 3.4.9 Cooper Heatup/Cooldown, Core Critical Curve . (Curve C), 28 EFPY 1,600 1,500 1,400 1,300 F'- 7171t.17~ 7i~F71I ._ 1,200 1,100 LU I" a-o 1,000 I- ) 900 o 800 w LU700 600 -J Lu 500 U) u 4 K 400 I I I -L 41 1J z i ] I 1-.- 4-1 ~r4j4iKJir2z: -- i-- -I- .... i -... + .-- 1+--.4----I......... ~Curve C 3

• __"-------__8 P0:F, 313

-+m Sare Operatling

• Rcgioll V p;ig 300 200 100 0

Minimum Criticality with Normal Water Level > B0°F ZT711 220F, 313 psig --m-.......

• +-----{

.4......--. ..... rH

• i~mHt

ý44k.= I i il I ,ji

4rzjz4z4zzlrn 0

50 100 150 200 250 .300 MINIMUM REACTOR VESSEL METAL TEMPERATURE (-F) Figure 3.4.9-3 (page 1 of 1) Pressure/Temperature Limits for Criticality Valid Through 28 EFPY 3.4-25 Amendment 231}}