Text

Tech Spec Pages for Amendments 242 and 220 Regarding Average Power Range Monitor/Rod Block Monitor/Technical Specifications/Maximum Extended Load Line Limit Analysis (Arts/Mellla) Implementation
	ML070860376
Person / Time
Site:	Susquehanna
Issue date:	03/23/2007
From:	; NRC/NRR/ADRO/DORL/LPLI-1
To:	;
References
	TAC MC9040, TAC MC9041
	Download: ML070860376 (1)
	v • d • e

(4) .. PLSuqehanna,. LLC,.pursuant to the Act and-.10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) PPL Susquehanna, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level PPL Susquehanna, LLC is authorized to operate the facility at reactor core power levels not in excess of 3489 megawatts thermal in accordance with the conditions specified herein and in Attachment 1 to this license. The preoperational tests, startup tests and other items identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 242 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

For Surveillance Requirements (SRs) that are new in Amendment 178 to Facility Operating License No. NPF-14, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 178. For SRs that existed prior to Amendment 178, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 178.

(3) Conduct of Work Activities During Fuel Load and Initial Startup The operating licensee shall review by committee all facility construction, Preoperational Testing, and System Demonstration activities performed concurrently with facility initial fuel loading or with the facility Startup Test Amendment No. 5, 144-3, 17-8, 180, 188, 4-94, 235, 236, 237, 2-M,-240-, 2421

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) PPL Rev.

1.0 USE AND APPLICATION ............................................................................ 1.1-1 1.1 D efi nitio ns ............................................................................................ 1 .1-1 1.2 Logical C onnectors .............................................................................. 1.2-1 1.3 C om pletion Tim es ................................................................................ 1.3-1 1.4 Frequency ............................................................................................ 1 .4-1 2.0 SAFETY LIMITS (SLs) ............................................................................. TS/2.0-1 2.1 SLs ............................................ TI' .

2.2 S L V iolations ................................................................................... TS /2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ......... TS/3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ................. TS/3.0-4 3.1 REACTIVITY CONTROL SYSTEMS ...................................................... 3.1-1 3.1.1 Shutdown Margin (SDM) ................................................................... 3.1-1 3.1.2 Reactivity Anomalies ......................................................................... 3.1-5 3.1.3 Control Rod OPERABILITY ............................................................... 3.1-7 3.1.4 Control Rod Scram Times ................................................................. 3.1-12 3.1.5 Control Rod Scram Accumulators ..................................................... 3.1-15 3.1.6 Rod Pattern Control .......................................................................... 3.1-18 3.1.7 Standby Liquid Control (SLC) System .............................................. 3.1-20 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ............... TS13.1-25 3.2 POWER DISTRIBUTION LIMITS ............................................................ 3.2-1 3.2.1 Average Planar Linear Heat Generation Rate (APLHGR) ................. 3.2-1 3.2.2 Minimum Critical Power Ratio (MCPR) .............................................. 3.2-3 3.2.3 Linear Heat Generation Rate (LHGR) ............................................... 3.2-5 3.3 INSTRUMENTATION ............................................................................ 3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation ....................... TS/3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation .................................. 3.3-10 3.3.2.1 Control Rod Block Instrumentation .................................................... 3.3-16 3.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrum entation ........................................................................... 3.3-21 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation ......................... TS /3.3-23 3.3.3.2 Remote Shutdown System ........................................................... TS /3.3-26 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrum entation ........................................................................... 3.3-29 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation .................................... 3.3-33 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation .......... TS/3.3-36 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrum entation ........................................................................... 3.3-48 3.3.6.1 Primary Containment Isolation Instrumentation ............ TS/3.3-52 3.3.6.2 Secondary Containment Isolation Instrumentation ............................ 3.3-63 (continued)

SUSQUEHANNA - UNIT 1 TS / TOC - 1 Amendment 184, 2-t5, 2A-7, 2-22, 2-2?5,

ad 242

PPL Rev.

Definitions 1.1 1.1 Definitions (continued)

MINIMUM CRITICAL POWER The MCPR shall be the smallest critical power ratio RATIO (MCPR) (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.

MODE 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.

OPERABLE - OPERABILITY 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).

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:

a. Described in Chapter 14, Initial Test Program of the FSAR;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

(continued)

SUSQUEHANNA - UNIT I 1.1-5 Amendment 17ý8, 242

PPL Rev.

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

-- NOTES -

1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2. When a channel is placed in an inoperable status solely for performance. of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days 0.0357 weeks 0.00822 months provided the associated Function maintains RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.3.1.1.2 Perform CHANNEL CHECK. 24 hours1 days 0.143 weeks 0.0329 months SR 3.3.1.1.3 NOTE Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after THERMAL POWER > 25% RTP.

Verify the absolute difference between the average 7 days power range monitor (APRM) channels and the calculated power is < 2% RTP while operating at

>25% RTP.

SR 3.3.1.1.4 NOTE -

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours0.5 days 0.0714 weeks 0.0164 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 7 days (continued)

SUSQUEHANNA - UNIT 1 TS / 3.3-3 Amendment 17-8, ý2,31, 242

PPL Rev.

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page I 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 Range Monitors

a. Neutron 2 3 G SR 3.3.1.1.1 < 122/125 divisions Flux-High SR 3.3.1.1.4 of full scale SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.11 SR 3.3.1.1.15 5 (a) 3 H SR 3.3.1.1.1 <_1221125 divisions SR 3.3.1.1.5 of full scale SR 3.3.1.1.11 SR 3.3.1.1.15

b. Inop 2 3 G SR 3.3.1.1.4 NA SR 3.3.1.1.15 5(a) 3 H SR 3.3.1.1.5 NA SR 3.3.1.1.15

2. Average Power Range Monitors

a. Neutron 2 3(c) G SR 3.3.1.1.2 5 20% RTP Flux-High SR 3.3.1.1.7 (Setdown) SR 3.3.1.1.8 SR 3.3.1.1.12 SR 3.3.1.1.18

b. Simulated 1 3 (c) F SR 3.3.1.1.2 5 0-62 W Thermal SR 3.3.1.1.3 + 64.2% RTP(b) and Power-High SR 3.3.1.1.8 _ 115.5% RTP SR 3.3.1.1.12 SR 3.3.1.1.18 SR 3.3.1.1.20 (continued)

(a)

With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) 0.62(W-AW) + 64.2% RTP when reset for single loop operation per LCO 3.4.1, "Recrculation Loops Operating."

(c)

Each APRM channel provides inputs to both trip systems.

SUSQUEHANNA - UNiT i TS / 3.3-7 Amendment 178, 225, ýall, 242

PPL Rev.

Control Rod Block Instrumentation 3.3.2.1 3.3 INSTRUMENTATION 3.3.2.1 Control Rod-Block Instrumentation LCO 3.3.2.1 The control rod block instrumentation for each Function in Table 3.3.2.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.2.1-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One rod block monitor A.1 Restore RBM channel to 24 hours1 days 0.143 weeks 0.0329 months (RBM) channel OPERABLE-status inoperable.

B. Required Action and B.1 Place one RBM channel 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion in trip.

Time of Condition A not met.

OR Two RBM channels inoperable.

C. Rod worth minimizer C.1 Suspend control rod Immediately (RWM) inoperable movement except by during reactor startup. scram.

OR C.2.1.1 Verify > 12 rods Immediately withdrawn.

OR C.2.1.2 Verify by administrative Immediately methods that startup with RWM inoperable has not been performed in the last calendar year.

AND (continued)

SUSQUEHANNA - UNIT 1 3.3-16 Amendment 1W, , 242

PPL Rev.

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS KI ,-r rr't.

-------------------- -- -- - - 1, I r_ 0 --------- - -------- --- ---- ------ - - --- - -

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.

2. When an RBM channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days 0.0357 weeks 0.00822 months provided the associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.2.1.2 -.------------------ NOTE---

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn at < 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.3 ----------.....-----.-------- NOTE------------- -.........

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after THERMAL POWER is *10% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.4 Verify the RBM:

a. Low Power Range - Upscale Function is not bypassed 24 months when APRM Simulated Thermal Power is Ž 28% RTP and < Intermediate Power Range Setpoint specified in the COLR.

(continued)

SUSQUEHANNA - UNIT 1 TS / 3.3-18 Amendment 1,78, .. O, 242

PPL Rev.

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

b. Intermediate Power Range - Upscale Function is not bypassed when APRM Simulated Thermal Power is > Intermediate Power Range Setpoint specified in the COLR and _<High Power Range Setpoint specified in the COLR.

c. High Power Range - Upscale Function is not bypassed when APRM Simulated Thermal Power is > High Power Range Setpoint specified in the COLR.

SR 3.3.2.1.5 Verify the RWM is not bypassed when THERMAL POWER. 24 months is*< 10% RTP.

SR 3.3.2.1.6 -- NOTE-----

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after reactor mode switch is in the shutdown position.

Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.2.1.7 OT E .............

Neutron detectors are excluded.

24 months Perform CHANNEL CALIBRATION SR 3.3.2.1.8 Verify control rod sequences input to the RWM are in Prior to declaring conformance with BPWS. RWM OPERABLE following loading of sequence into RWM SUSQUEHANNA - UNIT 1 TS / 3.3-19 Amendment M, 242

PPL Rev.

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

1. Rod Block Monitor

a. Low Power Range- (a) 2 SR 3.3.2.1.1 (f)

Upscale SR 3.3.2.1.4 SR 3.3.2.1.70)(1)

b. Intermediate Power (b) 2 SR 3.3.2.1.1 (f)

Range - Upscale SR 3.3.2.1.4 SR 3.3.2.1..(*)

c. High Power Range - (c), (d) 2 SR 3.3.2.1.1 (f)

Upscale SR 3.3.2.1.4 SR 3.3.2.1.7("j)

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

2. Rod Worth Minimizer 1(g), 2(g) 1 SR 3.3.2.1.2 NA SR 3.3.2.1.3 SR 3.3.2.1.5 SR 3.3.2.1.8

3. Reactor Mode Switch - (h) 2 SR 3.3.2.1.6 NA Shutdown Position (a) THERMAL POWER is >_28% RTP and < Intermediate Power Range Setpoint specified in the COLR and MCPR is less than the limit specified in the COLR.

(b) THERMAL POWER is > Intermediate Power Range Setpoint specified in the COLR and _ High Power Range Setpoint spedfied in the COLR and MCPR is less than the limit specified in the COLR. I (c) THERMAL POWER is > High Power Range Setpoint specified in the COLR and < 90% RTP and MCPR is less than the limit specified in the COLR.

(d) THERMAL POWER is > 90% RTP and MCPR is less than the limit specified in the COLR.

T (e) THERMAL POWER is _Ž28%Y RTP and < 90% RTP and MCPR is less than the limit specified in the COLR.

\1) Aluabe* value spedfied iii Uie COLR.

(g) With THERMAL POWER 5 10% RTP.

(h) Reactor mode switch in the shutdown position.

(i) If the as-found channel setpoint is not the Nominal Trip Setpoint but is conservative with respect to the Allowable Value, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(3) The instrument channel setpoint shall be reset to the Nominal Trip Setpoint at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The NTSP and the methodology used to determine the NTSP is specified in the SSES SUSQUEHANNA - UNIT 1 TS 1 3.3-20 Amendment 1,78, 2.0, 242

PPL Rev.

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 Not Used 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. The Average Planar Linear Heat Generation Rate for Specification 3.2.1;

2. The Minimum Critical Power Ratio for Specification 3.2.2;

3. The Linear Heat Generation Rate for Specification 3.2.3;

4. The Shutdown Margin for Specification 3.1.1;

5. Oscillation Power Range Monitor (OPRM) Trip Setpoints, for Specification 3.3.1.1; and

6. The Allowable Values and power range setpoints for Rod Block Monitor Upscale Functions for Specification 3.3.2.1, Table 3.3.2.1-1.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC.

When an initial assumed power level of 102 percent of rated power is specified in a previously approved method, this refers to the power level associated with the design basis analyses, or 3510 MWt. The power level of 3510 MWt is 100.6% of the rated thermal power level of 3489 MWt. The RTP of 3489 MWt may only be used when feedwater flow measurement (used as input to the reactor thermal power measurement) is provided by TM the Leading Edge Flow Meter (LEFM&gTM)as described in the LEFMV' Topical Report and supplement referenced below. When feedwater flow measurements from the LEFMVTM system are not available, the core thermal power level may not exceed the originally approved RTP of 3441 MWt, but the value of 3510 MWt (continued)

SUSQUEHANNA - UNIT 1 TS / 5.0-21 Amendment 1M6, 194, 21-5, 2 z1,q- 23a- 242

(4) PPL Susquehanna, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or componehts; and (5) PPL Susquehanna, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level PPL Susquehanna, LLC is authorized to operate the facility at reactor core power levels not in excess of 3489 megawatts thermal ( 1 0 0 % power) in accordance with the conditions specified herein and in Attachment 1 to this license. The preoperational test, startup tests and other items identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 220 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

For Surveillance Requirements (SRs) that are new in Amendment 151 to Facility Operating License No. NPF-22, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 151. For SRs that existed prior to Amendment 151, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation-of-

.... Amendment-1 51.-- - - -- *-* - .. .. .

2.C.(3) PPL Susquehanna, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Fire Protection Review Report for the facility and as approved in Fire Protection Program, Section 9.5, SER, SSER#1, SSER#2, SSER#3, SSER#4, SSER#6, Safety Evaluation of Fire Protection Report dated August 9, 1989, Safety Evaluation Amendment No. +, , +0, --5, +51-, +5-3, +62, 1-69, 2+2, 2+3, 2-4, 2+5,-24-7-,

220

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) PPL Rev.

1.0 USE AND APPLICATION ................................. 1.1-1 1.1 Definitions ........................................ 1.1-1 1.2 Logical Connectors ....................................................... 1.2-1 1.3 C om pletion T im es ............................................................................... 1.3-1 1.4 F reque ncy ........................................................................................... 1.4-1 2.0 SA FETY LIM ITS (SLs) ............................................................................. TS/2.0-1 2 .1 S Ls ................................................................................................. T S /2 .0-1 2.2 S L Violations ................................................................................... T S /2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ......... TS/3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ....................... TS/3.0-4 3.1 REACTIVITY CONTROL SYSTEMS ....................................................... 3.1-1 3.1.1 Shutdown Margin (SDM) ............................. 3.1-1 3.1.2 Reactivity Anom alies ......................................................................... 3.1-5 3.1.3 Control Rod OPERABILITY ............................................................... 3.1-7 3.1.4 Control Rod Scram Tim es ................................................................. 3.1-12 3.1.5 Control Rod Scram Accumulators ..................................................... 3.1-15 3.1.6 Rod Pattern Control .......................................................................... 3.1-18 3.1.7 Standby Liquid Control (SLC) System ..................... 3.1-20 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ............... TS/3.1-25 3.2 POWER DISTRIBUTION LIMITS ............................................................ 3.2-1 3.2.1 Average Planar Linear Heat Generation Rate (APLHGR) ................. 3.2-1 3.2.2 Minimum Critical Power Ratio (MCPR) .............................................. 3.2-3 3.2.3 Linear Heat Generation Rate (LHGR) ............................................... 3.2-5 3.3 INSTRUMENTATION .................................. 3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation ........................ TS/3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation .................................. 3.3-10 3.3.2.1 Control Rod Block Instrumentation .................................................... 3.3-16 3.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrum entation .......................................... ............................... 3.3-21 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation ......................... TS/3.3-23 3.3.3.2 Remote Shutdown System ........................................................... TS/3.3-27 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrum entation ........................................................................... 3.3-30 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation .................................... 3.3-34 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation .......... TS/3.3-37 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrum entation ........................................................................... 3.3-48 3.3.6.1 Primary Containment Isolation Instrumentation ............................. TS/3.3-52 3.3.6.2 Secondary Containment Isolation Instrumentation............................ 3.3-63 3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)

System Instrum entation .................................................................. 3.3-67 (continued)

SUSQUEHANNA - UNIT 2 TS / TOC - 1 Amendment I*, 15, 190, 1*2, 1K,'9 2_,2 , 2ý1, 220

PPL Rev.

Definitions 1.1 1.1 Definitions (continued)

MINIMUM CRITICAL The MCPR shall be the smallest critical power ratio (CPR) that exists in POWER RATIO the core for each class of fuel. The CPR is that power in the assembly (MCPR) 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.

MODE 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.

OPERABLE-- A system, subsystem, division, component, or device shall be OPERABLE OPERABILITY 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).

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:

a. Described in Chapter 14, Initial Test Program of the FSAR;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

(continued)

SUSQUEHANNA - UNIT 2 1.1 -5 Amendment 1,91, 220

PPL Rev.

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days 0.0357 weeks 0.00822 months provided the associated Function maintains RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.3.1.1.2 Perform CHANNEL CHECK. 24 hours1 days 0.143 weeks 0.0329 months SR 3.3.1.1.3 NOTE-Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after THERMAL POWER > 25% RTP.

Verify the absolute difference between the average power 7 days range monitor (APRM) channels and the calculated power is *2% RTP while operating at Ž> 25% RTP.

SR 3.3.1.1.4 -NOTE Not required to be performed when entering MODE 2 from MODE 1 until 12 hours0.5 days 0.0714 weeks 0.0164 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 7 days (continued)

SUSQUEHANNA - UNIT 2 TS / 3.3-3 Amendment 1ýý, 20, 220

PPL Rev.

3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)

Reactor Protection System Instrumentation APPLICABLE MODES OR CONDITIONS OTHER REQUIRED REFERENCED SPECIFIED CHANNELS PER FROM REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS TRIP SYSTEM ACTION D.1 REQUIREMENTS VALUE

1. Intermediate Range Monitors

a. Neutron 2 3 G SR 3.3.1.1.1 <! 1221125 divisions Flux-High of full scale SR 3.3.1.1.4 SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.11 SR 3.3.1.1.15 5(a) 3 H SR 3.3.1.1.1 _<

122/125 divisions SR 3.3.1.1.5 of full scale SR 3.3.1.1.11 SR 3.3.1.1.15

b. Inop 2 3 G SR 3.3.1.1.4 NA SR 3.3.1.1.15 5(a) 3 H SR 3.3.1.1.5 NA SR 3.3.1.1.15

2. Average Power Range Monitors

a. Neutron 2 3(c) G SR 3.3.1.1.2 _ 20% RTP Flux-High SR 3.3.1.1.7 (Setdown) SR 3.3.1.1.8 SR 3.3.1.1.12 SR 3.3.1.1.18

b. Simulated 1 3 (c) F SR 3.3.1.1.2 < 0.62W Thermal SR 3.3.1.1.3 + 64.20/c RTP(b)and Power-High SR 3.3.1.1.8 _<115.5% RTP SR 3.3.1.1.12 SR 3.3.1.1.18 SR 3.3.1.1.20 (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) 0.62(W-AW) + 64.2% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."

(c) Each APRM channel provides inputs to both tuip systems.

SUSQUEHANNA - UNIT 2 TS / 3.3-7 Amendment 1,0, 292, 2,d7,220

PPL Rev.

Control Rod Block Instrumentation 3.3.2.1 3.3 INSTRUMENTATION 3.3.2.1 Control Rod Block Instrumentation LCO 3.3.2.1 The control rod block instrumentation for each Function in Table 3.3.2.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.2.1-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One rod block monitor A.1 Restore RBM channel to 24 hours1 days 0.143 weeks 0.0329 months (RBM) channel OPERABLE status.

inoperable.

B. Required Action and B.1 Place one RBM channel in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion Time of Condition A not met.

OR Two RBM channels inoperable.

C. Rod worth minimizer C.1 Suspend control rod movement Immediately (RWM) inoperable except by scram.

during reactor startup.

OR C.2.1.1 Verify > 12 rods withdrawn. Immediately OR C.2.1.2 Verify by administrative methods Immediately that startup with RWM inoperable has not been performed in the last calendar year.

AND (continued)

SUSQUEHANNA- UNIT 2 3.3-16 Amendment 181220

PPL Rev. 1 Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS I Ir"C' k If%*'1-I. v --------- -----------

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.

2. When an RBM channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days 0.0357 weeks 0.00822 months provided the associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.2.1.2 ----- ---------- NOTE --.-.--..........---------- -- -

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn at _ 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.3 --------- ------ NOTE -.............---------- .-----

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after THERMAL POWER is*< 10% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.4 Verify the RBM:

a. Low Power Range - Upscale Function is not bypassed when 24 months APRM Simulated Thermal Power is _>28% RTP and

_5Intermediate Power Range Setpoint specified in the COLR.

(continued)

SUSQUEHANNA - UNIT 2 TS / 3.3-18 Amendment 1ý51, 2el, 220

PPL Rev.

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2.1.4 Verify the RMB: (continued)

b. Intermediate Power Range - Upscale Function is not bypassed when APRM Simulated Thermal Power is > Intermediate Power Range Setpoint specified in the COLR and < High Power Range Setpoint specified in the COLR.

c. High Power Range - Upscale Function is not bypassed when APRM Simulated Thermal Power > High Power Range Setpoint specified in the COLR.

SR 3.3.2.1.5 Verify the RWM is not bypassed when THERMAL POWER 24 months is < 10% RTP.

SR 3.3.2.1.6 NOTE-.-.-.-.-.-----------.

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after reactor mode switch is in the shutdown position.

Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.2.1.7 NOTE Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 24 months SR 3.3.2.1.8 Verify control rod sequences input to the RWM are in Prior to declaring conformance with BPWS. RWM OPERABLE following loading of sequence into RWM SUSQUEHANNA-UNiT 2 TS i: 3.3-19 Amendment 10 1220

PPL Rev.

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

1. Rod Block Monitor

a. Low Power Range - (a) 2 SR 3.3.2.1.1 ()

Upscale SR 3.3.2.1.4 SR 3.3.2.1.70i)j)

b. Intermediate Power (b) 2 SR 3.3.2.1.1 Range - Upscale SR 3.3.2.1.4 SR 3.3.2.1. 7 ()(iJ)

c. High Power Range - (c), (d) 2 SR 3.3.2.1.1 M Upscale SR 3.3.2.1.4 SR 3.3.2.1.7I

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

2. Rod Worth Minimizer 1 (g), 2 (g) 1 SR 3.3.2.1.2 NA SR 3.3.2.1.3 SR 3.3.2.1.5 SR 3.3.2.1.8

3. Reactor Mode Switch- (hI) 2 SR 3.3.2.1.6 NA Shutdown Position (a) THERMAL POWER is _ 28% RPT and _ Intermediate Power Range Setpoint specified in the COLR and MCPR is less than the limit specified in the COLR.

(b) THERMAL POWER is > Intermediate Power Range Setpoint specified in the COLR and _<High Power Range Setpoint specified in the COLR and MCPR is less than the limit specified in the COLR.

(c) THERMAL POWER is > High Power Range Setpoint specified in the COLR and < 90% RTP and MCPR is less than the limit specified in the COLR.

(d) THERMAL POWER is > 90% RTP and MCPR is less than the limit specified in the COLR.

I I

(e) THERMAL POWER is _>28% RTP and < 90% RTP and MCPR is less than the limit specified in the COLR.

(f) Allowable Value specified in the COLR.

(g) With THERMAL POWER 5 10% RTP.

(h) Reactor mode switch in the shutdown position.

(i) If the as-found channel setpoint is not the Nominal Trip Setpoint but is conservative with respect to the Allowable Value, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(j) The instrument channel setpoint shall be reset to the Nominal Trip Setpoint at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The NTSP and the methodology used to determine the NTSP is specified in the SSES Final Safety Analysis Report.

SUSQUEHANNA - UNIT 2 TS / 3.3-20 Amendment IZI, 2K, 220

PPL Rev.

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 Not Used 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. The Average Planar Linear Heat Generation Rate for Specification 3.2. 1;

2. The Minimum Critical Power Ratio for Specification 3.2.2;

3. The Linear Heat Generation Rate for Specification 3.2.3;

4. The Shutdown Margin for Specification 3.1.1;

5. Oscillation Power Range Monitor (OPRM) Trip setpoints, for Specification 3.3.1.1; and

6. The Allowable Values and power range setpoints for Rod Block Monitor Upscale Functions for Specification 3.3.2.1, Table 3.3.2.1-1.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC.

When an initial assumed power level of 102 percent of rated power is specified in a previously approved method, this refers to the power level associated with the design basis analyses, or 3510 MWt. The power level of 3510 MWt is 100.6% of the rated thermal power level of 3489 MWt. The RTP of 3489 MWt may only be used when feedwater flow measurement (used as input to the reactor thermal power measurement) is provided by the Leading Edge Flow Meter (LEFM VTM) as described in the LEFM,,1M Topical Report and supplement referenced below.

When feedwater flow measurements from the LEFMVTM system are not available, the (continued)

SUSQUEHANNA - UNIT 2 TS / 5.0-21 Amendment 109, 190, 19W, 20, 2*0, 220

v t e Letter Sequence Acceptance Review
TAC:MC9040, (Approved, Closed) TAC:MC9041, (Approved, Closed)
Initiation Request Acceptance Supplement Administration Withholding Request Acceptance Questions 19 October 2006 19 October 2006 Answers 1 December 2006 29 November 2006 Results Approval Other:
MONTHYEAR2006-12-15 [Table View]

ML070860376

Text

Navigation menu

Search