Text

Technical Specifications for Susquehanna Steam Electric Station, Unit 2
	ML093290177
Person / Time
Site:	Susquehanna
Issue date:	11/24/2009
From:	; Office of Nuclear Reactor Regulation
To:	; Susquehanna
	Gettys E, NRR/DLR, 415-4029
Shared Package
ML093160203	List: ML093160212; ML093160240; ML093160276; ML093160281; ML093290177;
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	Download: ML093290177 (415)
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LIES AUTog LICENSE ATHORITY FILE Copy - DO NOTO REM EM E; Y ATTACHMENT 1 tow Pao e* TEA; ,7 A.'ce n9SC 3/2L3 /PY

1. Outstanding Items to be Accomplished Prior to Initial Criticality

a. Complete permanent modification to correct the deficiency involving the isolation of the Nitrogen Makeup System. (Construction Deficiency Report 83-00-15)

b. Complete system modifications to ensure electrical separation for safety-related circuits. (Construction Deficiency Report 81-00-10)

c. Verify that waterhammer loads due to scram discharge volume vent and drain valve operation on scram reset do not affect system integrity.

(Construction Deficiency Report 83-00-07)

d. Verify that system piping, for which improper design input was included in the piping specification, are qualified for the proper design stresses.

(Construction Deficiency Report 83-00-17)

e. Verify that signal isolation devices installed in Class IE circuits pro-vide adequate electrical separation/isolation between Class lE and Non 1E circuits. (Construction Deficiency Report 84-00-01)

f. Upon issue of the Operating License Technical Specifications, verify that specified conditions, setpoints, and action points in facility procedures are consistent with those Technical Specifications.

g. Verify electrical separation criteria is met inside multiple division pull boxes and junction boxes. (Construction Deficiency Report 83-00-14)

h. Complete modification to CRD insert/withdrawal line supports to ensure the system is qualified for design stresses. (Construction Deficiency Report 83-00-20)

2. Outstanding Item to be Completed Prior to Exceedina 5% Power

a. Submit technical specification change requests for both units to reflect bypass leakage limits on the feedwater lines and to require pneumatic local leak rate tests. (Construction Deficiency Report 83-00-03)

b. Verify the installation of additional post-accident monitoring instru-mentation in accordance with NUREG-0737 items II.F.1.1, II.F.1.? and II.F.1.3 and FSAR Section 18.1.30.

3. Outstandino Items to be Corrected by the First Refueling Outage

a. Complete corrective action for deficiency involving cavitation caused by throttling valve in the RHR system. (Construction Deficiency Report 81-00-33)

b. Complete corrective action for deficiency involving capstan springs in Pacific Scientific snubbers. (Construction Deficiency Report 83-00-18)

4. Oustanding Items to be Corrected by a Specific Date

a. Complete correction of the remaining HED deficiencies in the Unit 2 control room documented in Inspection Report 50-388/84-08 by June 1, 1984.

b. Complete corrective action for deficiency involving corrosion allowance for the ESW piping to and from the RHR pump motor oil coolers by 1988.

(Construction Deficiency Report 83-00-16)

c. Submit revisions to the FSAR to correct the discrepancies noted below by July 31, 1984.

(i) Delete reliance on the 30 day water seal on feedwater lines in Section 6.2.3 (Construction Deficiency Report 83-00-03).

(ii) Correct statements concerning sizing of the ADS accumulators in Section 18.1.60 (TMI II.K.3.28).

(iii) Correct information concerning containment isolation signals in Tables 18.1-10, 18.1-11, 18.1-12 and 6.2-12 (TMI II.E.4.2)

(iv) Correct information concerning performance of the SBGTS in Section 6.2, 6.5, 9.4 and 15.6 (Construction Deficiency 83-00-19).

(v) Chapter 14 must be updated to correctly reflect the Unit 2 test program (UNR 83-04-01).

d. Verify that angle fittings used for class lE racewav supports and seismic category 1 HVAC duct supports are capable of supporting their associated design loads by June 1, 1984. (Construction Deficiency Report 84-00-03)

e. By September 1, 1984, submit to NRC Region I an acceptable long-term solution for spray pond spray network freezing. (Unresolved Item 83-32-02)

f. Complete corrective action for deficiency involving Emergency Service Water system water hammer by September 1, 1985. (Construction Deficiency Report 82-00-06)

LICENSE AUTHOG-ITy FILF COlPY DONO-1 70-r ATTACHMENT 2 The operating licensee shall implement the specific items below, in the manner described in the I operating licensee's letter (PLA-1 621) dated April 15,1983, as modified by the operating I licensee's letter (PLA-1 750) dated July 22, 1983, the operating licensee's letter (PLA-1772) I dated August 3, 1983, the operating licensee's letter (PLA-1 966) dated November 23, 1983, the I operating licensee's letter (PLA-2059) dated February 1,1984, and the operating licensee's I letter (PLA-2131) dated March 14,1984 no later than the following specified dates:

(a) Safety Parameter Display System (SPDS)

SPDS full operational and operators trained July 1, 1984 (b) Detailed Control Room Design Review (DCRDR)

Submit a supplemental summary report to the March 1,1985 NRC including a proposed schedule for implementation.

(c) Regulatory Guide 1.97 - Application to Emergency Response Facilities (1) Submit a report to the NRC describing May 1984 how the requirements of Supplement 1 to NUREG-0737 have been or will be met.

(2) Implement (installation or upgrade) requirements June 1987 of R. G. 1.97 or provide justification acceptable to the NRC staff for suppression pool water temperature, drywell atmosphere temperature, neutron flux, primary containment isolation valve position, radiation level in circulating primary coolant, radiation exposure rate, and noble gas and vent rate.

(d) Upgrade Emergency Operating Procedures (1) Submit a Procedures Generation Package to June 1985 the NRC (2) Implement the upgraded EOP's December 1985 (e) Emergency Response Facilities (1) Technical Support Center fully functional June 1987 (2) Operational Support Center fully functional June 1987 (3) Emergency Operations Facility fully June 1987 functional Amendment No. 162 1 t 1,,4E C .::'

j INN'lo, I

TABLE OF CONTENTS (TECHNICAL SFECIFICATIONS) PPL Rev.

1.0 U SE AN D A PPLICAT IO N ............................................................................. 1.1-1 1.1 Definitions ......................................... 1.1-1 1.2 Logical Connectors ............................................................................. 1.2-1 1.3 Com pletion T im es ............................................................................... 1.3-1 1.4 F req ue n cy .................................................................. ......................... 1.4-1 2.0 SAFETY LIM ITS (SLs) ............................................................................. TS12.0-1 2 .1 S Ls ....................................................................................... ......... T S /2 .0-1 2.2 SL Violations ...................................... 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 Anom alies ........................................................................ 3.1-5 3.1.3 Control Rod OPERABILITY ..... ............................... 3.1-7 3.1.4 Control Rod Scram Times .... .......... .............. TS/3.1-12 3.1.5 Control Rod Scram Accumulators ........................ 3.1-15 3.1.6 Rod Pattern C ontrol ......................................................................... 3.1-18 311.7 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 POW ER 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 Instrumentation ...................... ............... 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)

Instrumentation ............................... .... 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)

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TABLE: OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.3 INSTRUMENTATION (continued) 3.3.8.1 Loss of Power (LOP) Instrumentation ......... ................. 3.3-72 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring......................................................................................... 3.3-75 3.4 REACTOR COOLANT SYSTEM (RCS) ............................................. TS/3.4-1 3.4.1 Recirculation Loops Operating ... ............................................ TS/3.4-1 3.4.2 Jet Pumps ............................................. 3.4-6 3.4.3 Safety/Relief Valves (S/RVs) ............................................. 3.4-8 3.4.4 RCS Operational LEAKAGE .................... ......................... 3.4-10 3.4.5 RCS Pressure Isolation Valve (PIV) Leakage ................................... 3.4-12 3.4.6 RCS Leakage Detection Instrumentation ..................................... TS/3.4-14 3.4.7 RCS Specific Activity............................................. TS/3.4-17 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ..... TS/3.4-19 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ................................ 3.4-22 3.4.10 RCS Pressure and Temperature (P/T) Limits ................................ 3.4-24 3.4.11 Reactor Steam Dome Pressure ................................ 3.4-31 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ................................. TS/3.5-1 3.5.1 ECCS - Operating ............................................... TS/3.5-1 3.5.2 ECCS - Shutdown ............................................. 3.5-8 3.5.3 RCIC System ............................................. TS/3.5-12 3.6 CONTAINMENT SYSTEMS ............................................. 3.6-1 3.6.1.1 Primary Containment ............................................. 3.6-1 3.6.1.2 Primary Containment Air Lock............................................. 3.6-L 3.6.1.3 Primary Containment Isolation Valves (PCIVs) ............................ TS/3.6-E.

3.6.1.4 Containment Pressure ............................................. 3.6-17 3.6.1.5 Drywell Air Temperature .............. ............................... 3.6-18 3.6.1.6 Suppression-Chamber-to-Drywell Vacuum Breakers ............. ........... 3.6-19 3.6.2.1 Suppression Pool Average Temperature ........................................... 3.6-22 3.6.2.2 Suppression Pool Water Level ........................ ..................... 3.6-2-5 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling ........... TS/3.6-26 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ................... 3.6-28 3.6.3.1 Not Used ............................................. TS/3.6-30 3.6.3.2 Drywell Air Flow System ....... TS/3.6-32 3.6.3.3 Primary Containment Oxygen Concentration .................................... 3.6-34 3.6.4.1 Secondary Containment ............................................. 3.6-35 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ............................. 3.6-38 3.6.4.3 Standby Gas Treatment (SGT) System ............................................. 3.6-L-2 (continied)

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TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) PPL Rev.

3.7 PLA NT SY ST EM S ............................................................................ TS/3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ................. I........................ TS/3.7-1 3.7.2 Emergency Service Water (ESW ) System ........................................ 3.7-4 3.7.3 Control Room Emergency Outside Air Supply (C REO AS) System ................................................................ TS/3*7-6 3.7.4 Control Room Floor Cooling System ................................................. 3.7-10 3.7.5 Main Condenser Offgas ............................... 3.7-13 3.7.6 Main Turbine Bypass System ....................................................... TS/3.7-15 3.7.7 Spent Fuel Storage Pool Water Level ...................... 3.7-17 3.8 ELECTRICAL POW ER SYSTEMS .................................................... TS/3.8-1 3.8.1 AC Sources - Operating .............................. ..... TS/3.8-1 3 8.2 AC Sources - Shutdown .......... ...... ............................................ TS/3.8-19 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ................ TS/3.8-23 3.8.4 DC Sources - Operating ........................ ....... 3.8-26 3.8.5 DC Sources - Shutdown................................................................... 3.8-34 3.8.6 Battery Parameters ..... .................................. TS/3.8-39 3.8.7 Distribution Systems - Operating ............................. TS/3.8-44 3.8.8 Distribution Systems - Shutdown ................................................... 3.8-50 3.9 REFUELING O PERATIO NS .............................. ............ .... .................. 3.9-1 3.9.1 Refueling Equipm ent Interlocks ........................................................ 3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock ..................... 3.9-3 3.9.3 Control Rod Position ........................................ 3.9-5 3.9.4 Control Rod Position Indication ........... .. . .......................... 3.9-6 3.9.5 Control Rod OPERABILITY-Refueling ............................................ 3.9-8 3.9.6 Reactor Pressure Vessel (RPV) Water Level ................. 3.9-9 3.9.7 Residual Heat Removal (RHR) - High Water Level .......................... 3.9-10 3.9.8 Residual Heat Removal (RHR) - Low Water Level ........................... 3.9-13 3.10 SPECIAL OPERATIONS ............. ................... ............................... TS/3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation .......... ...... TS/3.10-1 3.10.2 Reactor Mode Switch Interlock Testing .......... ......... .. . 3.10-4 3.10.3 Single Control Rod Withdrawal - Hot Shutdown ....... ......... 3.10-6 3.10.4 Single Control Rod Withdrawal - Cold Shutdown ......... ..... 3.10-9 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling ...................... 3.10-13 3.10.6 Multiple Control Rod Withdrawal - Refueling.................. 3.10-16 3.10.7 Control Rod Testing -Operating........................... 10-18 310.8 SHUTDOWN MARGIN (SDM) Test - Refueling ............... 3.10-20 4.0 DESIGN FEATURES, ..................................... TS/4.0-1 4.1 Site Location ....................................... TS/4.0-1 4.2 Reactor Core .... .............. I........ .................. TS/4.0-1 4.3 Fuel Storage....... ..................... ............ TS/4.0 1 (continued)

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TABLE: OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 ADMINISTRATIVE CONTROLS ...................... 5.0-1 5.1 Responsibility....................................................................................... 5.0-1 5.2 Organization ...................... 5.0-2 5.3 Unit Staff Qualifications ...................... 5.0-5 5.4 Procedures ...................... 5.0-i3 5.5 Programs and Manuals ...................... 5.0-7 5.6 Reporting Requirements ...................... TS/5.0-- 9 I 5.7 High Radiation Area ...................... TSt5.0-24 TS2 TOC 3/23/06 SUSQUE.HANNA - UNIT 2 TSITOC - 4 Amendment 1/1 ,1 i, 1f12,210

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

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

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

AVERAGE PLANAR LINEAR The APLHGR shall be applicable to a specific HEAT GENERATION RATE planar height and is equal to the sum of the (APLHGR) LHGRs for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an in place qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential. overlapping, or total channel steps so that the entire channel is calibrated.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

(continued)

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PPL Rev.

Definitions 1.1 Definitions (continued) 1.1 CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS:

a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and

b. Control rod movement, provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING The COLR is the unit specific document that provides LIMITS REPORT (COLR) cycle specific parameter limits for the current reload cycle.

These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT 1--131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries per gram) which alone would produce the same total effective dose equivalent (sum of committed effective dose equivalent {CEDE} from inhalation plus deep dose equivalent {DDE} or nominally equivalent to the effective dose equivalent {EDE) from external exposure {submersion}) as the quantity and isotopic mixture of I-131, 1-132,1-133,1-134, and 1-135 actually present. The conversion factors that are used (continued)

SUSQUEHANNA - UNIT 2 1.1-2 Amendment 1 1, 2 ý6

PPL Rev.

Definitions 1.1 1.1 Definitions DOSE for this calculation of committed effective dose equivalent (CEDE) from EQUIVALENT 1-131 inhalation shall be those listed in Table 2.1 of Federal Guidelines Report (continued) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion,"

EPA, 1988, as described in Regulatory Guide 1.183. The factors in the column headed "effective" yield doses corresponding to the CEDE. The conversion factors that are used for the calculation of EDE (or DDE) from external exposure (submersion) shall be those listed in Table 111.1 of Federal Guidance Report 12, "External Exposure to Radionuclides in Air, Water, and Soil," EPA, 1993, as described in Regulatory Guide 1.183. The factors in the column headed "effective" yield doses corresponding to the EDE.

EMERGENCY The ECCS RESPONSE TIME shall be that time interval from whien the CORE COOLING monitored parameter exceeds its ECCS initiation setpoint at the channel SYSTEM (ECCS) sensor until the ECCS equipment is capable of performing its safety RESPONSE TIME function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

END OF CYCLE The EOC RPT SYSTEM RESPONSE TIME shall be that time interval RECIRCULATION from initial signal generation by the associated turbine stop valve limit PUMP TRIP switch or from when the turbine control valve hydraulic oil control oil (EOC RPT) pressure drops e-V, , pressureo sw,*tch setpoint to compl ete SYSTEM suppression of the electric arc between the fully open contacts of the RESPONSE TIME recirculation pump circuit breaker. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

ISOLATION The ISOLATION SYSTEM RESPONSE TIME shall be that time interval SYSTEM from when the monitored parameter exceeds its isolation initiation setpoint RESPONSE TIME at the channel sensor until the isolation valves travel to their required positions. Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

(continued)

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216

Definitions 1.1 1.1 Definitions (continued)

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE into the drywell, such as that from pump seals or valve packing. that is captured and conducted to a collecting tank: or

2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE:

b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;

c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE:

d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body.

pipe wall. or vessel wall.

LINEAR HEAT GENERATION The LHGR shall be the heat generation rate per RATE (LHGR) unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test TEST of all required logic components (i.e., all required relays and contacts. trip units, solid state logic elements. etc.) of a logic circuit.

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.

(continued)

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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)

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PPL Rev.

Definitions

.1.1 1.1 Definitions (continued)

RATED THERMAL RTP shall be a total reactor core heat transfer rate to the reactor coolant POWER (RTP) of 3952 MWt.

REACTOR The RPS RESPONSE TIME shall be that time interval from when the PROTECTION monitored parameter exceeds its RPS trip setpoint at the channel sensor SYSTEM .(RPS) until de-energization of the scram pilot valve solenoids. The response RESPONSE TIME time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

.SDM shall be the amount of reactivity by which the reactor is subcritical or SHUTDOWN MARGIN (SDM). would be subcritical assuming that:.

.a. The reactor is xenon free;

b. The moderator temperature is 680F; and

c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

STAGGERED A STAGGERED TEST BASIS shall consist of the testing of one of the TEST BASIS systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

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

TURBINE BYPASS The TURBINE BYPASS SYSTEM RESPONSE TIME consists of the time SYSTEM from when the turbine bypass control unit generates a turbine bypass RESPONSE TIME valve flow signal (continued)

SUSQUEHANNA - UNIT 2 1.1-6 2,24 Amendment 224

Definitions 1.1 1.1 Definitions TURBINE BYPASS SYSTEM until the turbine bypass valves travel to their RESPONSE TIME required positions. The response time may be (continued) measured by means of any series of sequential.

overlapping. or total steps so that the entire response time is measured.

SUSQUEHANNA - UNIT 2 1.1-7 Amendment 151

Definitions 1.1 Table 1.1-1 (page 1 of 1)

MODES REACTOR MODE AVERAGE REACTOR MODE TITLE SWITCH POSITION COOLANT TEMPERATURE (OF) 1 Power Operation Run NA 2 Startup Refuel(a) or Startup/Hot NA Standby 3 Hot Shutdown(a) Shutdown > 200 4 Cold Shutdown(a) Shutdown < 200 5 Refueling(b) Shutdown or Refuel NA (a) Al 1 reactor vessel head closure bolts fully tensioned.

(b) One or more reactor vessel head closure bolts less than fully tensioned.

SUSQUEHANNA - UNIT 2 1 .1-8 Amendment 151

Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions. Required Actions, Completion Times.

Surveillances, and Frequencies. The only logical connectors that appear in TS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentions of the logical connectors.

When logical connectors are used to state a Condition.

Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition. Completion Time, Surveillance, or Frequency.

EXAMPLES The following examples illustrate the use of logical connectors.

(continued)

SUSQUEHANNA - UNIT 2 1 .2-1 Amendment 151

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-1 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Verify . . .

AND A.2 Restore . . .

In this example the logical connector AND is used to indicate that when in Condition A. both Required Actions A.1 and A.2 must be completed.

(continued)

SUSQUEHANNA - UNIT 2 1.2-2 Amendment 151

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Trip . . .

OR A.2.1 Verify . . .

AND A.2.2.1 Reduce . . .

OR A.2.2.2 Perform . . .

OR A.3 Align . . .

This example represents a more complicated use of logical connectors. Required Actions A.1. A.2, and A.3 are alternative choices. only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen. then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND.

Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

SUSQUEHANNA - UNIT 2 1.2-3 Amendment 151

Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Times(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g.. inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified. providing the unit is in a MODE or specified condition stated in the Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the LCO Applicability.

If situations are discovered that require entry into more than one Condition at a time within a single LCO (multiple Conditions). the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions. separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.

Once a Condition has been entered, subsequent divisions.

subsystems. components. or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

(continued)

SUSQUEHANNA - UNIT 2 1 .3-1 Amendment 151

Completion Times 1.3 1.3 Completion Times DESCRIPTION However, when a subsequent division, subsystem, component, (continued) or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a. Must exist-concurrent with the first inoperability; and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extensions do not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each division.

subsystem, component or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.

The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e.

"once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ." where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery . . ." Example 1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Condition A and B in Example 1.3-3 may not be extended.

(continued)

SUSQUEHANNA - UNIT 2 1.3-2 Amendment 151

Completion Times 1.3 1.3 Completion Times (continued)

EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

EXAMPLE 1.3-1 ACTIONS Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

The Required Actions of Condition B are to be in MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . AND in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) is allowed for reaching MODE 4 from the time that Condition B was entered. If MODE 3 is reached within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the time allowed for reaching MODE 4 is the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months because the total time allowed for reaching MODE 4 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

If Condition B is entered while in MODE 3. the time allowed for reaching MODE 4 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

(continued)

SUSQUEHANNA - UNIT 2 1.3-3 Amendment 151

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

ACTIONS .

CONDITION REQUIRED ACTION COMPLETION TIME A. One pump A.1 Restore pump to 7 days inoperable. OPERABLE status.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

When a pump is declared inoperable, Condition A is entered.

If the pump is not restored to OPERABLE status within 7 days. Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered. Conditions A and B are exited. and therefore, the Required Actions of Condition B may be terminated.

When a second pump is declared inoperable while the first pump is still inoperable, Condition A is not re-entered for the second pump. LCO 3.0.3 is entered. since the ACTIONS do not include a Condition for more than one inoperable pump.

The Completion Time clock for Condition A does not stop after LCO 3.0.3 is entered, but continues to be tracked from the time Condition A was initially entered.

While in LCO 3.0.3, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has not expired. LCO 3.0.3 may be exited and operation continued in accordance with Condition A.

(continued)

SUSQUEHANNA - UNIT 2 1.3-4 Amendment 151

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

While in LCO 3.0.3. if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has expired. LCO 3.0.3 may be exited and operation continued in accordance with Condition B. The Completion Time for Condition B is tracked from the time the Condition A Completion Time expired.

On restoring one of the pumps to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first pump was declared inoperable. This Completion Time may be extended if the pump restored to OPERABLE status was the first inoperable pump. A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension to the stated 7 days is allowed, provided this does not result in the second pump being inoperable for

> 7 days.

(continued)

SUSQUEHANNA - UNIT 2 1.3-5 Amendment 151

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore 7 days Function X Function X subsystem subsystem to AND inoperable. OPERABLE status.

10 days from discovery of failure to meet the LCO B. One B.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y -Function Y subsystem subsystem to AND inoperable. OPERABLE status.

10 days from discovery of failure to meet the LCO C. One C.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function X Function X subsystem subsystem to inoperable. OPERABLE status.

AND OR One C.2 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y Function Y subsystem subsystem to inoperable. OPERABLE status.

(continued)

SUSQUEHANNA - UNIT 2 1.3-6 Amendment 151

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each subsystem.

starting from the time each subsystem was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A).

The Completion Times of Conditions A and B are modified by a logical connector, with a separate 10 day Completion Time measured from the time it was discovered the LCO was not met. In this example, without the separate Completion Time, it would be possible to alternate between Conditions A. B.

and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO.

The separate Completion Time modified by the phrase "from discovery of failure to meet the LCO" is designed to prevent indefinite continued operation while not meeting the LCO.

This Completion Time a'llows for an exception to the normal "time zero" for beginning the Completion Time "clock". In this instance, the Completion Time "time zero" is specified as commencing at the time the LCO was initially not met.

instead of at the time the associated Condition was entered.

(continued)

SUSQUEHANNA - UNIT 2 1.3-7 Amendment 151

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-4 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves to OPERABLE inoperable. status.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis.

Declaring subsequent valves inoperable. while Condition A is still in effect. does not trigger the tracking of separate Completion Times.

Once one of the valves has been restored to OPERABLE status.

the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (plus the extension) expires while one, or more valves are still inoperable, Condition B is entered.

(continued)

SUSQUEHANNA - UNIT 2 1.3-8 Amendment 151

Completion Times 1.3 1.3 Completion Times EXAMPLE EXAMPLE 1.3-5 (continued)

ACTIONS

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

Separate Condition entry is allowed for each inoperable valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.1 -Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable.

Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable, Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.

(continued)

SUSQUEHANNA - UNIT 2 1.3-9 Amendment 151

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)

If the Completion Time associated with a valve in Condition A expires. Condition B is entered for that valve.

If the Completion Times associated with subsequent valves in Condition A expire. Condition B is entered separately for each valve and separate Completion Times start and are tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status. Condition B is exited for that valve.

Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times. Completion Time extensions do not apply.

EXAMPLE 1.3-6 ACTIONS CONDITION -REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform Once per inoperable. SR 3.x.x.x. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months OR A.2 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months POWER to

' 50% RTP.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated Completion Time not met.

(continued)

-SUSQUEHANNA - UNIT 2 1 .3-10 Amendment 151

Completion Times.

1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-6 (continued)

Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "once per" Completion Time, which qualifies for the 25% extension. per SR 3.0.2. to each performance after the initial performance.

The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be complete within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Action A.1 is followed and the Required Action is not met within the Completion Time (plus the extension allowed by SR 3.0.2). Condition B is entered.

If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met. Condition B is entered.

If after entry into Condition B. Required Action A.1 or A.2 is met. Condition B is exited and operation may then continue in Condition A.

(continued)

SUSQUEHANNA - UNIT 2 1. 3-11 Amendment 151

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem subsystem inoperable. isolated. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore subsystem 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE

.status.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Required Action A.1.

If after Condition A is entered. Required Action A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by SR 3.0.2). Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered. but continues from the time Condition A was initially entered. If Required Action A.1 (continued)

SUSQUEHANNA - UNIT 2 1.3-12 Amendment 151

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued) is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired.

IMMEDIATE When "Immediately" is used as a Completion Time, the COMPLETION TIME Required Action should be pursued without delay and in a controlled manner.

SUSQUEHANNA - UNIT 2 1.3-13 Amendment 151

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0.

Surveillance Requirement (SR) Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each SR. as well as certain Notes in the Surveillance column that modify performance requirements.

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by SR 3.0.1. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance, or both. Example 1.4-4 discusses these special situations.

Situations where a Surveillance could be required (i.e., its Frequency could expire). but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e.. the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.

The use of "met" or "performed" in these instances conveys specific meanings. A Surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance (continued)

SUSQUEHANNA - UNIT 2 1.4-1 Amendment 151

Frequency 1.4 1.4 Frequency DESCRIPTION criteria. SR 3.0.4 restrictions would not apply if both the (continued) following conditions are satisfied:

a. The Surveillance is not required to be performed: and

b. The Surveillance is not required to be met or. even if required to be met. is not known to be failed.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples. the Applicability of the LCO (LCO not shown) is MODES 1. 2.

and 3.

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time.

Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times. even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits. or the unit is outside the Applicability of -he LCO). If the interval specified by SR 3.0.2 is en eded while the unit is in a MODE or other specified condit-. in the Applicability of the LCO. and the performance of t., Surveillance is not (continued)

SUSQUEHANNA - UNIT 2 1.4-2 Amendment 151

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued) otherwise modified (refer to Examples 1.4-3 and 1.4-4). then SR 3.0.3 becomes applicable.

If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required. the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of SR 3.0.4.

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after a 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level < 25% RTP to 2 25% RTP. the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND"). This type of Frequency does not qualify for the extension allowed by SR 3.0.2.

(continued)

SUSQUEHANNA - UNIT 2 1.4-3 Amendment 151

PPL Rev.

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)

"Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (Le., the "once" performance in this example). If reactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after ~ 25% RTP.

Perform channel adjustment. 7 days The interval continues whether or not the unit operation is < 25% RTP between performances.

As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after power reaches ~ 25% RTP to perform the Surveillance. The Surveillance is still considered to be within the "specified Frequency." Therefore, if the Surveillance were not performed within the 7 day interval (plus the extension allowed by SR 3.0.2), but operation was < 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (plus the extension allowed by SR 3.0.2) with power ~ 25% RTP.

(continued)

SUSQUEHANNA - UNIT 2 TS / 1.4-4 Amendment -+M, 229

PPL Rev.

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-3 (continued)

Once the unit reaches 25% RTP, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval (plus the extension allowed by SR 3.0.2), there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Only required to be met in MODE 1.

Verify leakage rates are within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2), but the unit was not in MODE 1, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), SR 3.0.4 would require satisfying the SR.

SUSQUEHANNA - UNIT 2 TS / 1.4-5 Amendment 4-a+,229

PPL Rev.

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow

< 10 million Ibm/hr:

THERMAL POWER shall be s 23% RTP.

2.1.1.2 With the reactor steam dome pressure ~ 785 psig and core flow

~ 10 million Ibm/hr:

MCPR shall be ~ 1.08 for two recirculation loop operation or ~ 1.11 for single recirculation loop operation.

2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.

2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be s 1325 psig.

2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.

SUSUQUEHANNA - UNIT 2 TS 12.0-1 Amendment +5-1-, 94,

+84, +9+, +94, ~, ~, m

SLs 2.0

~...........~ ( .......

ig r SUSQUEHANNA - UNIT 2 TS / 2.0-2 Amendment %b. 1i4 F-~ n , -^-.

I'T' - ' '.

V-D Q.C'Mpl 4mLIoof St'itbt 4~\) LAL~LQa (6iRfl) I CJ

SLs 2.0

i:-E:. i -- E)Dt ; 0-: 0-- 0 An: ---.;T:-E -- .... . g-.. .. -. .... ..

(Figure 2.1.1.2-2)

THIS PAGE INTENTIONALLY LEFT BLANK I

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SUSQUEHANNA - UNIT 2 TS / 2.0-3 Amendment N. irA

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PPL Rev. 2 LCO Applicability 3.0 3.0 LIMITING CONDITIONS FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2, LCO 3.0.7 and LCO 3.0.8.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Acti6n shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

a. MODE 2 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ;

b. MODE 3 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and

c. MODE 4 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, and 3.

(continued)

SUSQUEHANNA - UNIT 2 TS / 3.0-1 Amendment 15/I, 1h5 213,

PPL Rev. 1 LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made: I

a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;

b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or

c. When an allowance is stated in the individual value, parameter, or other Specification. I This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered.

Only the support system LCO ACTIONS are required to be entered.

This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.11, Safety Function Determination Program (SFDP).* If a loss of safety function is determined to exist by this (continued)

SUSQUEHANNA - UNIT 2 TS / 3.0-2 Amendment 1i1, 195

PPL Rev. 2 LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.6 program, the appropriate Conditions and Required Actions of the (continued) LCO in which the loss of safety function exists are required to be entered. When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance witlh LCO 3.0.2.

LCO 3.0.7 Special Operations LCOs in Section 3.10 allow specified Technical Specifications (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Special Operations LCOs is optional. When a Special Operations LCO is desired to be met but is not met, the ACTIONS of the Special Operations LCO shall be met. When a Special Operations LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with the other applicable Specifications.

LCO 3.0.8 When one or more required snubbers are unable to perform their associated support function(s), any affected supported LCO(s) are not required to be declared not met solely for this reason if risk is assessed and managed, and:

a. The snubbers not able to perform their associated support function(s) are associated with only one train or subsystem of a multiple train or subsystem supported system or are associated with a single train or subsystem supported system and are able to perform their associated support function within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; or

b. The snubbers not able to perform their associated support function(s) are associated with more than one train or subsystem of a multiple train or subsystem supported system and are able to perform their associated support function within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

At the end of the specified period, the required snubbers must be able to perform their associated support function(s), or the affected supported system LCO(s) shall be declared not met.

(continued)

SUSQUEHANNA - UNIT 2 TS / 3.0-3 Amendment 15f, 145 213

SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENTS (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO.

Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3.

Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply.

If a Completion Time requires periodic performance on a "once per..." basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be (continued)

SUSQUEHANNA- UNIT 2 TS / 3.0-4 Amendment 179 AUG 1 2 2

PPL Rev. 1 SR Applicability 3.0 3.0 SR APPLICABILITY

' SR 3.0.3 declared not met, and the applicable Condition(s) must be entered.

(continued)

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCOs Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

SUSQUEHANNA - UNIT 2 TS I 3.0-5 Amendment -4, 195

SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.1 SDM shall be within the limits provided in the COLR.

APPLICABILITY: MODES 1. 2. 3. 4. and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limits A.1 Restore SDM to within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months in MODE 1 or 2. limits.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not met.

C. SDM not within limits C.1 Initiate action to Immediately in MODE 3. fully insert all insertable control rods.

D. SDM not within limits D.1 Initiate action to Immediately in MODE 4. fully insert all insertable control rods.

AND (continued)

SUSQUEHANNA - UNIT 2 3.1-1 Amendment 151

SDM 3.1.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued) D.2 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore secondary containment to OPERABLE status.

AND D.3 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore one standby gas treatment (SGT) subsystem to OPERABLE status.

AND D.4 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore isolation capability in each required secondary containment penetration flow path not isolated.

E. SDM not within limits E.1 Suspend CORE Immediately in MODE 5. ALTERATIONS except for control rod insertion and fuel assembly removal.

AND E.2 Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.

AND (continued)

SUSQUEHANNA - UNIT 2 3.1-2 Amendment 151

SDM 3.1.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. (continued) E.3 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore secondary containment to OPERABLE status.

AND E.4 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore one SGT subsystem to OPERABLE status.

AND E.5 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore isolation capability in each required secondary containment penetration flow path not isolated.

SUSQUEHANNA - UNIT 2 3.1-3 Amendment 151

SDM 3.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 4.

SR 3.1.1.1 Verify SDM to be within limits Prior to each in vessel fuel movement during fuel loading sequence-AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after criticality following fuel movement within the reactor pressure vessel or control rod replacement SUSQUEHANNA - UNIT 2 3.1-4 Amendment 151

Reactivity Anomalies 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Reactivity Anomalies LCO 3.1.2 The reactivity difference between the monitored core Keff and the predicted Keff shall be within +/- 1% Ak/k.

APPLICABILITY: MODE 1 and 2 ACTIONS -

CONDITION REQUIRED ACTION COMPLETION TIME A. Core reactivity A.1 Restore core 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months difference not within reactivity difference limit. to within limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

SUSQUEHANNA - UNIT 2 3.1-5 Amendment 151

Reactivity Anomalies 3.1.2 SURVEILLANCE REQUIREMENTS

.7 SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify core reactivity difference between Once within the monitored core Keff and the predicted Keff 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after is within +/- 1% Ak/k. reaching equilibrium conditions following startup after fuel movement within the reactor pressure vessel or control rod replacement AND 1000 MWD/MT thereafter during operations in MODE 1 SUSQUEHANNA - UNIT 2 3.1-6 Amendment 151

Control Rod OPERABILITY 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Control Rod OPERABILITY LCO 3.1.3 Each control rod shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

Separate Condition entry is allowed for each control rod.

CONDITION REQUIRED ACTION COMPLETION TIME A. One withdrawn control ------------NOTE------------

rod stuck. Rod worth minimizer (RWM) may be bypassed as allowed by LCO 3.3.2.1. "Control Rod Block Instrumentation," if required, to allow continued operation.

A.1 Verify stuck control Immediately rod separation criteria are met.

AND A.2 Disarm the associated 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months control rod drive (CRD).

AND (continued)

SUSQUEHANNA - UNIT 2 3.1-7 Amendment 151

PPL Rev.

Control Rod OPERABILITY 3.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Perform SR 3.1.3.3 for each 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from withdrawn OPERABLE control discovery of rod. Condition A concurrent with THERMAL POWER greater than the low power setpoint (LPSP) of the RWM.

AND A.4 Perform SR 3.1.1.1. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Two or more withdrawn B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months control rods stuck.

C. One or more control rods C.1 ---------------NOTE--------------

inoperable for reasons RWM may be bypassed as other than Condition A allowed by LCO 3.3.2.1, if or B. required, to allow insertion of inoperable control rod and continued operation.

Fully insert inoperable control 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months rod.

AND (continued)

SUSQUEHANNA - UNIT 2 TS / 3.1-8 Amendment +a-+,229

Control Rod OPERABILITY 3.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2 Disarm the associated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months CRD.

D.- NOTE--------- D.1 Restore compliance 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Not applicable when with BPWS.

THERMAL POWER

> 10% RTP. OR D.2 Restore control rod 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Two or more inoperable to OPERABLE status.

control rods not in compliance with banked position withdrawal sequence (BPWS) and not separated by two or more OPERABLE control rods.

E. ---------NOTE--------- E.1 Restore control rod 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Not applicable when to OPERABLE status.

THERMAL POWER

> 10% RTP.

One or more BPWS groups with four or more inoperable control rods.

F. Required Action and F.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A.

C. D. or E not met.

OR Nine or more control rods inoperable.

SUSQUEHANNA - UNIT 2 3.1-9 Amendment 151

PPL Rev.

Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Determine the position of each control rod. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.1.3.2 NOT USED SR 3.1.3.3 ----------------------------NOTE---------------------------

Not required to be performed until 31 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of the RWM.

Insert each withdrawn control rod at least one 31 days notch.

SR 3.1.3.4 Verify each control rod scram time from fully In accordance with withdrawn to notch position 05 is < 7 seconds. SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 (continued)

SUSQUEHANNA - UNIT 2 TS/3.1-10 Amendment -ta-+, 229

Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.3.5 Verify each control rod does not go to the Each time the withdrawn overtravel position. control rod is withdrawn to "full out" position AND Prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect coupling SUSQUEHANNA - UNIT 2 3.1-11 Amendment 151

PPL Rev. 1 Control Rod Scram Times 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO 3.1.4

a. No more than 13 OPERABLE control rods shall be "slow," in accordance with Table 3.1.4-1; and

b. No more than 2 OPERABLE control rods that are "slow" shall occupy adjacent locations.

APPLICABILITY: MODES 1 AND 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months LCO not met.

SURVEILLANCE REQUIREMENTS L ~~IY

\jI JJ ------------------------------------------------------

During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.

SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is within the Prior to exceeding 40% RTP limits of Table 3.1.4-1 with reactor steam dome after each reactor shutdown pressure > 800 psig. > 120 days (continued)

SUSQUEHANNA - UNIT 2 TS / 3.1-12 Amendment 1&1, 214

PPL Rev.

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify, for a representative sample, each tested 200 days cumulative control rod scram time is within the limits of operation in MODE 1 Table 3.1.4-1 with reactor steam dome pressure

~ 800 psig.

SR 3.1.4.3 Verify each affected control rod scram time is Prior to declaring control rod within the limits of Table 3.1.4-1 with any reactor OPERABLE after work on steam dome pressure. control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is Prior to exceeding 40% RTP within the limits of Table 3.1.4-1 with reactor after fuel movement within steam dome pressure ~ 800 psig. the affected core cell Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time SUSQUEHANNA - UNIT 2 TS /3.1-13 Amendment 4&1-, ~,228

Control Rod Scram Times 3.1.4 Table 3.1.4-1 (page 1 of 1)

Control Rod Scram Times

NOTES------------------------------------

1. OPERABLE control rods with scram times not within the limits of this Table are considered "slow."

2. Enter applicable Conditions and Required Actions of LCO 3.1.3. "Control Rod OPERABILITY," for control rods with scram times > 7 seconds to notch position 05. These control rods are inoperable, in accordance with SR 3.1.3.4. and are not considered "slow."

SCRAM TIMES(a)(b) (seconds) when REACTOR STEAM DOME NOTCH POSITION PRESSURE 2 800 psig 45 0.52 39 0.86 25 1.91 05 3.44 (a) Maximum scram time from fully withdrawn position. based on de-energization of scram pilot valve solenoids at time zero.

(b) Scram times as a function of reactor steam dome pressure, when

< 800 psig are within established limits.

SUSQUEHANNA - UNIT 2 3.1-14 Amendment 151

Control Rod Scram Accumulators 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Control Rod Scram Accumulators LCO 3.1.5 Each control rod scram accumulator shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

Separate Condition entry is allowed for each contrQl rod scram accumulator.

CONDITION REQUIRED ACTION COMPLETION TIME A. One control rod scram A.1 -------- NOTE---------

accumulator inoperable Only.applicable if with reactor steam the associated dome pressure control rod scram

> 900 psig. time was within the limits of Table 3.1.4-1 during the last scram time Surveillance.

Declare the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated control rod scram time "slow.

OR A.2 Declare the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated control rod inoperable.

(continued)

SUSQUEHANNA - UNIT 2 3.1-15 Amendment 151

Control Rod Scram Accumulators 3.1.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Two or more control B.1 Restore charging 20 minutes from rod scram accumulators water header pressure discovery of inoperable with to 2 940 psig. Condition B reactor steam dome concurrent with pressure 2 900 psig. charging water header pressure

< 940 psig AND B.2.1 -------- NOTE---------

Only applicable if the associated control rod scram time was within the limits of Table 3.1.4-1 during the last scram time Surveillance.

Declare the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated control rod scram time "slow."

OR B.2.2 Declare the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated control rod inoperable.

(continued)

SUSQUEHANNA - UNIT 2 3.1-16 Amendment 151

Control Rod Scram Accumulators 3.1.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more control C.1 Verify all control Immediately upon rod scram accumulators rods associated with discovery of inoperable with inoperable charging water reactor steam dome accumulators are header pressure pressure < 900 psig. fully inserted. < 940 psig AND C.2 Declare the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated control rod inoperable.

D. Required Action and D.1 -------- NOTE---------

associated Completion Not applicable if all Time of Required inoperable control Action B.1 or C.1 not rod scram met. accumulators are associated with fully inserted control rods.

Place the reactor Immediately mode switch in the shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each control rod scram accumulator 7 days nitrogen pressure is 2 940 psig.

SUSQUEHANNA - UNIT 2 3.1-17 Amendment 151

Rod Pattern Control 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control LCO 3.1.6 OPERABLE control rods shall comply with the requirements of the banked position withdrawal sequence (BPWS).

APPLICABILITY: MODES 1 and 2 with THERMAL POWER S 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more OPERABLE A.1 -------- NOTE---------

control rod(s) 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 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months control rod(s) to correct position.

OR A.2 Declare associated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months control rod(s) inoperable.

(continued)

SUSQUEHANNA - UNIT 2 3.1-18 Amendment 151

Rod Pattern Control 3.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Nine or more OPERABLE B.1 -------- NOTE---------

control rods not in Rod worth minimizer compliance with BPWS. (RWM) may be bypassed as allowed by LCO 3.3.2.1.

Suspend withdrawal of Immediately control rods.

AND B.2 Place the reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months mode switch in the shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify all OPERABLE control rods comply 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months with BPWS.

SUSQUEHANNA - UNIT 2 3.1-19 Amendment 151

PPL Rev.

SLC System 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCO 3.1.7 Two SLC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of sodium A.1 Restore concentration of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months pentaborate in solution is sodium pentaborate in solution not within limits of to within limits of Figure 3.1.7-1. Figure 3.1.7-1.

B. One SLC subsystem B.1 Restore SLC subsystem to 7 days inoperable for reasons OPERABLE status. I other than Condition A.

C. Two SLC subsystems C.1 Restore one SLC subsystem to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable for reasons OPERABLE status.

other than Condition A.

D. Required Action and D.1 Be in MODE 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND D.2 Be in MODE 4 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SUSQUEHANNA - UNIT 2 3.1-20 Amendment 1 /1, 2#217 Pevise ly letter dated March 19, 2)07

PPL Rev.

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify available volume of sodium pentaborate 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months solution is within the limits of Figure 3.1.7-1.

SR 3.1.7.2 Verify temperature of sodium pentaborate solution 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is within the limits of Figure 3.1.7-2.

SR 3.1.7.3 Verify temperature of pump suction piping is within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the limits of Figure 3.1.7-2.

SR 3.1.7.4 Verify continuity of explosive charge. 31 days SR 3.1.7.5 Verify the concentration of sodium pentaborate in 31 days solution is within the limits of Figure 3.1.7-1.

AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after water or sodium pentaborate is added to solution AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored within the limits of Figure 3.1.7-2 (continued)

SUSQUEHANNA - UNIT 2 3.1-21 Amendment 171 217

PPL Rev.

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify each SLC subsystem manuai and power 31 days operated valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position, or can be aligned to the correct position.

SR 3.1.7.7 Verify each pump develops a flow rate >_40.0 gpm In accordance with the at a discharge pressure > 1250 psig. Inservice Testing Program SR 3.1.7.8 Verify flow through one SLC subsystem pump into 24 months on a reactor pressure vessel. STAGGERED TEST BASIS SR 3.1.7.9 Verify all heat traced piping between storage tank 24 months and pump suction is unblocked.

AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored within the limits of Figure 3.1.7-2 SR 3.1.7.10 Verify sodium pentaborate enrichment is Ž88 Prior to addition to SLC tank.

atom percent B-1 0.

SUSQUEHANNA - UNIT 2 TS / 3.1-22 Amendment 1<51-, 1CI 217

PPL Rev.

SLC System 3.1.7 FIGURE 3.1.7-1 Sodium Pentaborate Solution Volume Versus Sodium Pentaborate Solution Volume Versus Concentration Requirements 12-0-

o 11 4-) Region of Approved 0=0 (1350, (5

10) Volume/Concentration 0 '9 0..

(1965, 7) 1200 1300 1400 1500 1600 1700 1800 1900 2000 2100 2200 Net Storage Tank Volume (gallons)

SUSQUEHANNA - UNiT 2 3. 1-23 Amendment 1'61 217

SLC System 3.1.7 FiGURE 3.1.7-2 Sodium Pentaborale Solution Temperature Verus Concectratio Requirements 120 0 OCEPTABL OPE ATING RA GE

.100

_ _ _UNACCE TABLE 40 0 6 10 15 20 . 25 30 Sodium Pentaborate Concentration, WeIgM Percern SUSQUEHANNA - UNIT 2 3.1-24 Amendment 151

PPL Rev. 1 SDV Vent and Drain Valves 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves LCO 3.1.8 Each SDV vent and drain valve shall be OPERABLE and open.

APPLICABILITY: MODES 1 and 2.

ACTIONS A------------------NOTES -----------------

1. Separate Condition entry is allowed for the SDV vent line and drain line.

2. An isolated line may be unisolated under administrative control to allow draining and venting of the SDV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SDV vent or A.1 Isolate the associated line. 7 days drain lines with one valve inoperable.

B. One or more SDV vent or B.1 Isolate the associated line. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months drain lines with both valves inoperable.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

SUSQUEHANNA - UNIT 2 TS / 3.1-25 Amendment W, 199

SDV Vent and Drain Valves 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 ------------ NOTE--------------------

Not required to be met on vent and drain valves closed during performance of SR 3.1.8.2.

Verify each SDV vent and drain valve is 31 days open.

SR 3.1.8.2 Cycle each SDV vent and drain valve to the 92 days fully closed and fully open position.

SR 3.1.8.3 Verify each SDV vent and drain valve: 24 months

a. Closes in s 30 seconds after receipt of an actual or simulated scram signal: and

b. Opens when the actual or simulated scram signal is reset.

SUSQUEHANNA - UNIT 2 3.1-26 Amendment 151

PPL Rev.

APLHGR 3.2.1 3.2. POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

LCO 3.2.1 All APLHGRs shall be less than or equal to the limits specified in the COLR.

APPL ICABILITY: THERMAL POWER Ž 23% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any APLHGR not within A.1 Restore APLHGR(s) to within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits, limits.

B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 23% RTP.

Time not met.

SUSQUEHANNA - UNIT 2 3.2-1 Amendment I.,it.,224

PPL Rev.

APLHGR

3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY after Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.2.1.1 Verify all APLHGRs are less than or equal to the Once within 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s* after limits specified in the COLR. Ž23% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter AND Prior to exceeding 44% RTP SUSQUEHANNA - UNIT 2 3.2-2 Amendment 4ý31,224

PPL Rev.

MCPR 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)

LCO 3.2.2 All MCPRs shall be greater than or equal to the MCPR operating limits specified in the COLR.

APPLICABILITY: THERMAL POWER _Ž23% RTP.

ACTIONS_

CONDITION REQUIRED ACTION COMPLETION TIME A. Any MCPR not within A. 1 Restore MCPR(s) to within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits, limits.

B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 23% RTP.

Time not met.

SUSQUEHANNA - UNIT 2 3.2-3 Amendment W,224

PPL Rev.

MCPR 3.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify all MCPRs are greater than or equal to the Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after limits specified in the COLR. 2!23% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter AND Prior to exceeding 44% RTP SR 3.2.2.2 Determine the MCPR limits. Once within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each completion of SRs in 3.1.4 SUSQUEHANNA - UNIT 2 3.2-4 Amendment IW,224

PPL Rev.

LHGR 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)

LCO 3.2.3 All LHGRs shall be less than or equal to the limits specified in the COLR.

APPLICABILITY: THERMAL POWER Ž23% RTP. I ACTIONS ..

CONDITION REQUIRED ACTION COMPLETION TIME A. Any LHGR not within A. 1 Restore LHGR(s) to within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits. limits.

B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 23% RTP.

Time not met.

SUSQUEHANNA - UNIT 2 3.2-5 Amendment j&%224

PPL Rev.

LHGR 3.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify all LHGRs are less than or equal to the Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after limits specified in the COLR. 'a 23% RTP I AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter AND Prior to exceeding 44% RTP SUSQUEHANNA-UNIT2 3.2-6 Amendment 1ý51,224

PPL Rev. 2 RFS Instrumentation 3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1 -1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.1-1.

ACTIONS

_________________-----------------------------------------MtI t- - --- --- -- -_--- --- -- ---_. -- --- -- _-- --

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in trip. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channels inoperable.

OR A.2 ------------------ NOTE---------------- 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Not applicable for Functions 2.a, 2.b, 2.c, 2.d, or 2.f.

Place associated trip system in trip.

B. ---------- NOTE------------ B.1 Place channel in one trip system 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Not applicable for in trip.

Functions 2.a, 2.b, 2.c, 2.d, or 2.f. OR One or more Functions B.2 Place one trip system in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with one or more required channels inoperable in both trip systems.

C. One or more Functions C.1 Restore RPS trip capability. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with RPS trip capability not maintained.

(continued)

SUSQUEHANNA - UNIT 2 TSq; / 3.3-1 Amendment l51, 20 7

PPL Rev.

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME.

D. Required Actionand D.1 Enter the Condition referenced Immediately associated Completion in Table 3.3.1 .1-1 for the Time of Condition A, B, channels.

or C not met.

E. As required by E.1 Reduce THERMAL POWER to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Action D.1 < 26% RTP.

and referenced in Table 3.3.1.1-1.

F. As required by F.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

G. As required by G.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

H. As required by H.1 Initiate action to fully insert all Immediately Required- Action D.1 insertable control rods in core and referenced in cells containing one or more fuel Table 3.3.1.1-1. assemblies.

As required by 1.1 Initiate alternate method to detect 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 and suppress thermal hydraulic and referenced in instability oscillations.

Table 3.3.1.1-1. AND 1.2 Restore required channels to 120 days OPERABLE.

J. Required Action and J.1 Reduce THERMAL POWER to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion <23% RTP.

Time of Condition I not met.

SUSQUEHANNA - UNIT 2 3.3-2 Amendment 1.81, 2.97, 224

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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.1.2 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.3.1.1.3 NOTE Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER Ž23% 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_> 23% RTP.

SR 3.3.1.1.4 Not required to be performed whenentering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 7 days (continued)

SUSQUEHANNA-UNIT2 3.3-3 24edmnt I-1, -77, 220,

PPL Rev. 2 RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST. 7 days SR 3.3.1.1.6 Verify the source range monitor (SRM) and intermediate Prior to fully range monitor (IRM) channels overlap. withdrawing SRMs from the core.

SR 3.3.1.1.7 ---------------------------------NOTE---------------------------------

Only required to be met during entry into MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap. 7 days SR 3.3.1.1.8 Calibrate the local power range monitors. 1000 MWD/MT average core exposure SR 3.3.1.1.9 ---------------------------------NOTE---------------------------------

A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.1.1.10 Perform CHANNEL CALIBRATION. 92 days (continued)

SUSQUEHANNA - UNIT 2 3.3-4 Amendment 151, 224 Correction Letter Dated May 5, 2008

PPL Rev.

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE -FREQUENCY SR.3.3.1.1.11 - -NOTES

1. Neutron detectors are excluded.

2. For Function 1.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL CALIBRATION. 184 days SR 3.3.1.1.12 NOTES

1. For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

2. For Functions 2.b and 2.f, the CHANNEL FUNCTIONAL TEST includes the recirculation flow input processing, excluding the flow transmitters.

Perform CHANNEL FUNCTIONAL TEST 184 days SR 3.3.1.1.13 Perform CHANNEL CALIBRATION. 24 months SR 3.3.1.1.14 Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.1.1.15 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SR 3.3.1.1.16 Verify Turbine Stop Valve-Closure and Turbine Control 24 months Valve Fast Closure, Trip Oil Pressure-Low Functions are not bypassed when THERMAL POWER is

>26% RTP.

(continued)

SUSQUEHANNA - UNIT 2 3.3-5 Amendment 1-51, 2, 224

PPL Rev.

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.17 ---------------- -- NOTES--------

1. Neutron detectors are excluded.

2. For Function 5, "n" equals 4 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.

3. For Function 2.e, "n" equals 8 channels for them purpose of determining the STAGGERED TEST BASIS Frequency. Testing of APRM and OPRM outputs shall alternate.

Verify the RPS RESPONSE TIME is within limits. 24 months on a STAGGERED TEST BASIS SR 3.3.1.1.18 -NOTES

1. Neutron detectors are excluded.

2. For Functions 2b and 2f, the recirculation flow transmitters that feed the APRMs are included.

Perform CHANNEL CALIBRATION 24 months SR 3.3.1.1.19 Verify OPRM is not-bypassed when APRM Simulated 24 months Thermal Power is >_25% and recirculation drive flow is I

_<value equivalent to the core flow value defined in the COLR.

SR 3.3.1.1.20 Adjust recirculation drive, flow to conform to reactor core 24 months flow.

SUSQUEHANNA - UNIT 2 3.3-6 Amendment 1,66, 227,224

PPL Rev.

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page !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 _<122/125 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 :5 122/125 divisions SR 3.311.1.5 of full scale SR 3.3.1.1.111 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 < 0.55 W Thermal SR 3.3.1.1.3 + 60.7% RTP(b) and Power-High SR 3.3.1.1.8 s 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) 0.55 (W-AW) + 60.7% RTP when reset for single loop operation per LCO 3.4;1, "Recirculation Loops Operating." I (c) Each APRM channel provides inputs to both trip systems.

SUSQUEHANNA - UNIT 2 TS / 3.3-7 Amendment 1-51, 202, W7", 22*, 224

PPL Rev.

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 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

2. Average Power Range Monitors (continued)

c. Neutron 3 (c) F SR 3.3.1.1.2 _120% RTP Flux-High SR 3.3.1.1.3 SR 3.3.1.1.8 SR 3.3.1.1.12 SR 3.3.1.1.18

d. Inop 1,2 3(c) G SR 3.311.1.12 NA

e. 2-Out-Of-4 1,2 2 G SR 3.3.1.1.2 NA Voter SR 3.3.1.1.12 SR 3.3.1.1.15 SR 3.3.1.1.17 (d)

f. OPRM Trip _>23% RTP 3(c) SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.12 SR 3.3.1.1.18 SR 3.31.1.19 SR 3.3.1.1.20

3. Reactor Vessel 1,2 2 G SR 3.3.1.1.9 < 1093 psig Steam Dome SR 3.3.1.1.10 Pressure-High SR 3.3.1.1.15

4. Reactor Vessel 1,2 2 G SR 3.3.1.1.1 >11.5 inches Water Level-- SR 3.3.1.1.9 Low, Level 3 SR 3.3.1.1.10 SR 3.3.1.1.15

5. Main Steam 1* 8 F SR 3.3.1.1.9 _ 11% closed Isolation SR 3.3.1.1.13 Valve-Closure SR 3.3.1.1.15 SR 3.3.1.1.17

6. Drywell 1,2 2 G SR 3.3.1.1.9

1.88 psig Pressure-High SR 3.3.1.1.10 SR 3.3.1.1.15 (continued)

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

(d) See COLR for OPRM period based detection algorithm (PBDA) setpoint limits.

SUSQUEHANNA - UNIT 2 TS / 3.3-8 Amendment 1'ýg6, 2.o7,224

PPL Rev.

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 3 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

7. Scram Discharge Volume Water Level--High

a. Level 1,2 2 G SR 3.3.1.1.9 :5 66 gallons Transmitter SR 3.3.1.1.13 SR 3.3.1.1.15 5 (a) 2 H SR 3.3.1.1.9 !566 gallons SR 3.3.1.1.13 SR 3.3.1.1.15

b. Float Switch 1,2 2 G SR 3.3.1.1.9 < 62 gallons SR 3.3.1.1.13 SR 3.3.1.1.15 5 (a) 2 H SR 3.3.1.1.9. < 62 gallons SR 3.3.1.1.13 SR 3.3.1.1.15

8. Turbine Stop > 26% RTP 4 E SR 3.3.1.1.9 < 7% closed Valves-Closure SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.16 SR 3.3.1.1.17

9. Turbine Control >26% RTP 2 E SR 3.3.1.1.9 Z!460 psig Valve Fast SR 3.3.1.1.13 Closure, Trip SR 3.3.1.1.15 Oil Pressure- SR 3.3.1.1.16 Low SR 3.3.1.1.17

10. Reactor Mode 1,2 2 G SR 3.3.1.1.14 NA.

Switch- SR 3.3.1.1.15 Shutdown Position 5 (a) H SR 3.3.1.1.14 NA 2

SR 3.3.1.1.15

11. Manual Scram 1,2 2 G SR 3.3.1.1.5 NA SR 3.3.1.1.15 (a) 5 2 H SR 3.3.1.1.5 NA SR 3.3.1.1.15 (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

SUSQUEHANNA-UNIT2 3.3-9 Amendment e15, 2-?,

224

SRM Instrumentation 3.3.1.2 3.3 INSTRUMENTATION 3.3.1.2 Source Range Monitor (SRM) Instrumentation LCO 3.3.1.2 The SRM instrumentation in Table 3.3.1.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.2-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required SRMs 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SRMs inoperable in to OPERABLE status.

MODE 2 with intermediate range monitors (IRMs) on Range 2 or below.

B. Three required SRMs B.1 Suspend control rod Immediately inoperable in MODE 2 withdrawal.

with IRMs on Range 2 or below.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B not met.

(continued)

SUSQUEHANNA - UNIT 2 3.3-10 Amendment 151

SRM Instrumentation 3.3.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more required D.1 Fully insert all 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SRMs inoperable in insertable control MODE 3 or 4. rods.

AND D.2 Place reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

E. One or more required E.1 Suspend CORE Immediately SRMs inoperable in ALTERATIONS except MODE 5. for control rod insertion.

AND E.2 Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.

SUSQUEHANNA - UNIT 2 3.3-11 Amendment 151

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified conditions.

SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.2.2 ------------------NOTES------------------

1. Only required to be met during CORE ALTERATIONS.

2. One SRM may be used to satisfy more than one of the following.

Verify an OPERABLE SRM detector is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months located in:

a. The fueled region;

b. The core quadrant where CORE ALTERATIONS are being performed. when the associated SRM is included in the fueled region: and

c. A core quadrant adjacent to where CORE ALTERATIONS are being performed.

when the associated SRM is included in the fueled region.

SR 3.3.1.2.3 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

SUSQUEHANNA - UNIT 2 3.3-12 Amendment 151

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 4

SR 3.3.1.2.4 ------------------NOTE------------------

Not required to be met with less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant.

Verify count rate is: 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE

a. 2 3.0 cps if a signal to noise ratio ALTERATIONS a 2:1 AND or 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

b. Within the limits of Figure 3.3.1.2-1 SR 3.3.1.2.5 Perform CHANNEL FUNCTIONAL TEST and 7 days determination of signal to noise ratio.

SR 3.3.1.2.6 ------------------NOTE-------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

Perform CHANNEL FUNCTIONAL TEST and 31 days determination of signal to noise ratio.

SR 3.3.1.2.7 ------------------NOTES------------------

1. Neutron detectors are excluded.

2. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

Perform CHANNEL CALIBRATION. 24 months SUSQUEHANNA - UNIT 2 3.3-13 Amendment 151

SRM Instrumentation 3.3.1.2 Table 3.3.1.2-1 (page 1 of 1)

Source Range Monitor Instrumentation APPLICABLE MODES OR OTHER REQUIRED SURVEILLANCE FUNCTION SPECIFIED CONDITIONS CHANNELS REQUIREMENTS

1. Source Range Monitor 2(a) 3 SR 3.3.1.2.1 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 3,4 2 SR 3.3.1.2.3 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 5 2 (b)(c) SR 3.3.1.2.1 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 SR 3.3.1.2.7 (a) With any OPERABLE IRMs on Range 2 or below.

(b) Only one SRM channel is required to be OPERABLE during spiral offload or reload when the fueled region includes only that SRM detector.

(c) Special movable detectors may be used in place of SRMs if connected to normal SRM circuits.

SUSQUEHANNA - UNIT 2 3.3-14 Amendment 151

SRM Instrumentation 3.3.1.2 3

2.8 2.6 2.4 2.2 2

a0-.

1.8 0 1.

(4) 1.4 12 1

0.8 0.6 0.4 0.2 0

6 10 14 18 22 26 30 Signal-to-Noise Ratio Figure 3.3.1.2-1 (page 1 of 1)

Minimum SRM Count Rate Versus Signal to Noise Ratio SUSQUEHANNA - UNIT 2 3.3-15 Amendment 151

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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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

Control Rod Block Instrumentation 3.3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.2 Verify movement of During control control rods is in rod movement compliance with banked position withdrawal sequence (BPWS) by a second licensed operator or other qualified member of the technical staff.

D. RWM inoperable during D.1 Verify movement of During control reactor shutdown. control rods is in rod movement accordance with BPWS by a second licensed operator or other qualified member of the technical staff.

E. One or more Reactor Mode E.1 Suspend control Immediately Switch -Shutdown Position rod withdrawal.

channels inoperable.

AND E.2 Initiate action to Immediately

-fully insert all insertable control rods in core cells containing one or more fuel assemblies.

SUSQUEHANNA - UNIT 2 3.3-17 Amendment 151

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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 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. 1 Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS 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 > 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 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 / 3.3-19 Amendment 1X1, 220 Reviedby letter datedl *gri 9, 2007

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.

Feedwater - Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrumentation LCO 3.3.2.2 Three channels of feedwater - main turbine high water level trip instrumentation shall be OPERABLE.

APPLICABILITY: THERMAL POWER > 23% RTP.

ACTIONS Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One feedwater - main A. 1 Place channel in trip. 7 days turbine high water level trip channel inoperable.

B. Two or more feedwater B. 1 Restore feedwater - main turbine 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

- main turbine high high water level trip capability.

water level trip channels inoperable.

C. Required Action and C.1 Reduce THERMAL POWER to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion < 23% RTP.

Time of Conditions A or B not met.

SUSQUEHANNA - UNIT 2 3.3-21 Amendment IBI 224

Feedwater - Main Turbine High Water Level Trip Instrumentation 3.3.2.2 SURVEILLANCE REQUIREMENTS

NOTE--------

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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided feedwater - main turbine high water level trip capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.3.2.2.2 ----------------------------------------

1. A test of all required contacts does not have to be performed.

2. For the Feedwater - Main Turbine High Water Level Function, a test of all required relays does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.2.3 Perform CHANNEL CALIBRATION. The 24 months Allowable Value shall be s 55.5 inches.

SR 3.3.2.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months including valve actuation.

SUSQUEHANNA - UNIT 2 3.3-22 Amendment 151

PPL Rev. 1 PAM Instrumentation 3.3.3.1 3.3 INSTRUMENTATION 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3.1 The PAM instrumentation for each Function in Table 3.3.3.1-1 shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS SprtCoiinetysalwd O NTE-.

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required channel to 30 days with one required OPERABLE status.

channel inoperable.

B. Required Action and B.1 Initiate action in accordance with Immediately associated Completion Specification 5.6.7.

Time of Condition A not met.

C. One or more Functions C.1 Restore one required channel to 7 days with two required OPERABLE status.

channels inoperable.

(continued)

SUSQUEHANNA - UNIT 2 TS / 3.3-23 Amendment 11v1, 195

PAM Instrumentation 3.3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.3.1-1 for not met. the channel.

E. As required by E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 and referenced in Table 3.3.3.1-1.

F. As required by F.1 Initiate action in Immediately Required Action D.1 accordance with and referenced in Specification 5.6.7.

Table 3.3.3.1-1.

SURVEILLANCE REQUIREMENTS

NOTES------------------------------------

These SRs apply to each Function in Table 3.3.3.1-1.

SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK. 31 days (continued)

SUSQUEHANNA - UNIT 2 3.3-24 Amendment 151

PPL Rev. 2 PAM Instrumentation 3.3.3.1 SURVEILLANCE REQUIREMENTS (continued) _

SURVEILLANCE FREQUENCY SR 3.3.3.1.2 Not Used. I SR 3.3.3.1.3 Perform CHANNEL CALIBRATION for all Functions except 24 months PCIV Position. I SUSQUEHANNA - UNIT 2 TS / 3.3-25 Amendment 1 `

211,

PF'L Rev. 2 PAM Instrumentation 3.3.3.1 Table 3.3.3.1 -1 (page 1 of 1)

Post Accident Monitoring Instrumentation CONDITIONS REFERENCE D FROM FUNCTION REQUIRED CHANNELS REQUIRED ACTION 0.1

1. Reactor Steam Dome Pressure 2 E

2. Reactor Vessel Water Level

a. Wide Range 2 E

b. Extended Range 2 E

c. Fuel Zone Range 2 E

3. Suppression Chamber Water Level 2 E

4. Primary Containment Pressure E

a. Accident Range 2

b. LOCA Range 2 E

5. Primary Containment High Radiation 2 F

6. PCIV Position 2 per penetration flow path(a)(b) E

7. Neutron Flux 2 E

8. Not Used I

9. Drywell Atmosphere Temperature 2 E

10. Suppression Chamber Water Temperature 2 E (a) Not required for isolation valves whose associated penetration flow path is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indicatior channel.

SUS)QUEHANNA - UNIT 2 TS /3.3-26 Amendment 1#1, 211,

PPL Rev. 1 Remote Shutdown System 3.3.3.2 3.3 INSTRUMENTATION 3.3.3.2 Remote Shutdown System LCO 3.3.3.2 The Remote Shutdown System Function in Table 3.3.3.2-1 shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

___ _---- --- I__[mlN Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore required Function to 30 days required Functions OPERABLE status.

inoperable.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

SUSQUEHANNA - UNIT 2 TS I 3.3-27 Amendment 1,X1, 195

Remote Shutdown System 3.3.3.2 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.3.2-1 to determine which SRs apply for each Remote Shutdown System Function.

SURVEILLANCE FREQUENCY SR 3.3.3.2.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.3.2.2 Verify each required control circuit and 24 months transfer switch is capable of performing the intended function.

SR 3.3.3.2.3 Perform CHANNEL CALIBRATION for each 24 months required instrumentation channel.

SUSQUEHANNA - UNIT 2 3.3-28 Amendment 151

Remote Shutdown System 3.3.3.2 Table 3.3.3.2-1 (page 1 of 1)

Remote Shutdown System Instrumentation REQUIRED CHANNELS SURVEILLANCE FUNCTION PER Function REQUIREMENTS

1. Reactor Pressure Vessel Pressure

a. Reactor Steam Dome Pressure indication 1 SR 3.3.3.2.1 SR 3.3.3.2.3

b. Safety ReLief Valve Control 1 SR 3.3.3.2.2

2. Decay Heat Removal and Reactor Pressure Vessel Inventory Control

a. RCIC Turbine Speed or RCIC Pump Flow 1 SR 3.3.3.2.1 Indication SR 3.3.3.2.3

b. RCIC Controls 1 SR 3.3.3.2.2

c. RHR System Flow indication 1 SR 3.3.3.2.1 SR 3.3.3.2.3

d. RHR Controls 1 SR 3.3.3.2.2

e. RHR Service Water System Controls 1 SR 3.3.3.2.2

f. RHR Service Water System Flow 1 SR 3.3.3.2.1 indication SR 3.3.3.2.3

g. Suppression Pool Water Level 1 SR 3.3.3.2.1 indication SR 3.3.3.2.3

h. Suppression Pool Water Temperature 1 SR 3.3.3.2.1 indication SR 3.3.3.2.3

i. ESW System Controls 1 SR 3.3.3.2.2

j. Reactor Pressure Vessel Water Level 1 SR 3.3.3.2.1 indication SR 3.3.3.2.3 SUSQUEHANNA - UNIT 2 3.3-29 Amendment 151

PPL Rev.

EOC-RPT Instrumentation 3.3.4.1 3.3 INSTRUMENTATION 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation LCO 3.3.4.1 a. Two channels per trip system for each EOC-RPT instrumentation Function listed below shall be OPERABLE:

1. Turbine Stop Valve (TSV)-Closure; and

2. Turbine Control Valve (TCV) Fast Closure, Trip Oil Pressure Low.

OR

b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," limits for inoperable EOC-RPT as specified in the COLR are made applicable.

APPLICABILITY: THERMAL POWER > 26% RTP.

ACTIONS

NOTE-Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to OPERABLE 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable, status.

AND OR MCPR limit for A.2 ------- .. -- -NOTE inoperable EOC-RPT Not applicable if inoperable not made applicable, channel is the result of an inoperable breaker.

Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR (continued)

'SUSQUEHANNA - UNIT 2 3.3-30 Amendment IRf224

PPL Rev.

EOC-RPT Instrumentation 3.3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Apply the MCPR limit for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable EOC-RPT as specified in the COLR.

B. One or more Functions B.1 Restore EOC-RPT trip capability. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with EOC-RPT trip capability not maintained.

OR AND MCPR limit for B.2 Apply the MCPR limit for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable EOC-RPT inoperable EOC-RPT as specified not made applicable in the COLR.

C. Required Action and C.1 Remove the associated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion recirculation pump from service.

Time not met.

OR,

'C.2 Reduce THERMAL POWER to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

< 26% RTP.

SUSQUEHANNA - UNIT 2 3.3-31 Amendment 15ý224

PPL Rev.

EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS, i , .'--NOTE--

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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains EOC-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.4.1.2 Perform CHANNEL CALIBRATION. The Allowable 24 months Values shall be:

TSV--Closure: < 7% closed; and TCV Fast Closure, Trip Oil Pressure-Low: Ž460 psig.

SR 3.3.4.1.3 Perform LOGIC SYSTEM FUNCTIONAL TEST including 24 months breaker actuation.

SR 3.3.4.1.4 Verify TSV-Closure and TCV Fast Closure, Trip Oil 24 months Pressure-Low Functions are not bypassed when THERMAL POWER is Ž26% RTP.

(continued)

SUSQUEHANNA - UNIT 2 3.3-32 Amendment IF6 224

EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.1.5 ---------------- NOTE-------------------

Breaker arc suppression time may be assumed from the most recent performance of SR 3.3.4.1.6.

Verify the EOC-RPT SYSTEM RESPONSE TIME 24 months on a is within limits. STAGGERED TEST BASIS SR 3.3.4.1.6 Determine RPT breaker arc suppression 60 months time.

SUSQUEHANNA - UNIT 2 3.3-33 Amendment 151

ATWS-RPT Instrumentation 3.3.4.2 3.3 INSTRUMENTATION 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation LCO 3.3.4.2 Two channels per trip system for each ATWS-RPT instrumentation Function listed below shall be OPERABLE:

a. Reactor Vessel Water Level - Low Low, Level 2: and

b. Reactor Steam Dome Pressure- High.

APPLICABILITY: MODE 1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to 14 days inoperable. OPERABLE status.

OR A.2 -------- NOTE---------

Not applicable if inoperable channel is the result of an inoperable breaker.

Place channel in 14 days trip.

(continued)

SUSQUEHANNA - UNIT 2 3.3-34 Amendment 151

ATWS-RPT Instrumentation 3.3.4.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One Function with B.1 Restore ATWS-RPT trip 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ATWS-RPT trip capability.

capability not maintained.

C. Both Functions with C.1 Restore ATWS-RPT trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ATWS-RPT trip capability for one capability not Function.

maintained.

D. Required Action and D.1 Remove the associated 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion recirculation pump Time not met. from service.

OR D.2 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS

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

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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains ATWS-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.2.1 Perform CHANNEL CHECK of Reactor Vessel 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Water Level, Low Low, Level 2.

(continued)

SUSQUEHANNA - UNIT 2 3.3-35 Amendment 151

ATWS-RPT Instrumentation 3.3.4.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.2.2 ---------------------------------

A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.4.2.3 Perform CHANNEL CALIBRATION of the 92 days Reactor Steam Dome Pressure- High. The Allowable Values shall be - 1150 psig.

SR 3.3.4.2.4 Perform CHANNEL CALIBRATION of the 24 months Reactor Vessel Water Level Low Low, Level

2. The Allowable Values shall be

- 45 inches.

SR 3.3.4.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months including breaker actuation.

SUSQUEHANNA - UNIT 2 3.3-36 Amendment 151

ECCS Instrumentation 3.3.5.1 3.3 INSTRUMENTATION 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation LCO 3.3.5.1 The ECCS instrumentation for each Function in Table 3.3.5.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5.1-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable. referenced in Table 3.3.5.1-1 for the channel.

B. As required by B.1 --------NOTES-Required Action A.1 1. Only applicable and referenced in in MODES 1. 2.

Table 3.3.5.1-1. and 3.

2. Only applicable for Functions l.a. 1.b, 1.c.

2.a. 2.b. and 2.c Declare supported 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from feature(s) inoperable discovery of when its redundant loss of feature ECCS initiation initiation capability capability for is inoperable. feature(s) in both divisions AND (continued)

SUSQUEHANNA - UNIT 2 3.3-37 Amendment 151

ECCS Instrumentation 3.3.5.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 - -- NOTE---------

Only applicable for Functions 3.a and 3.b.

Declare High Pressure 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Coolant Injection discovery of (HPCI) System loss of HPCI inoperable. initiation capability AND B.3 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

C. As required by C.1 -------- NOTES--------

Required Action A.1 1. Only applicable and referenced in in MODES 1, 2.

Table 3.3.5.1-1. and 3.

2. Only applicable for Functions 1.d. 2.d. and 2.e.

Declare supported 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from feature(s) inoperable discovery of when its redundant loss of feature ECCS initiation initiation capability capability for is inoperable. feature(s) in both divisions AND C.2 Restore channel to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

(continued)

SUSQUEHANNA - UNIT 2 3.3-38 Amendment 151

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1 -NOTE-Required Action A.1 Only applicable if and referenced in HPCI pump suction is Table 3.3.5.1-1. not aligned to the suppression pool.

Declare HPCI System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from inoperable. discovery of loss of HPCI initiation capability AND D.2.1 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

OR D.2.2 Align the HPCI pump 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months suction to the suppression pool.

(continued)

SUSQUEHANNA - UNIT 2 3.3-39 Amendment 151

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by E.1 Declare Automatic 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Required Action A.1 Depressurization discovery of and referenced in System (ADS) valves loss of ADS Table 3.3.5.1-1. inoperable. initiation capability in both trip systems AND E.2 Place channel in 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from trip. discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling (RCIC) inoperable AND 8 days (continued)

SUSQUEHANNA - UNIT 2 3. 3-40 Amendment 151

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. As required by F.1 - --- NOTE---------

Required Action A.1 Only applicable for and referenced in Functions 4.c, 4.e, Table 3.3.5.1-1. 4.f. 4.g, 5.c, 5.e, 5.f, and 5.g.

Declare ADS valves 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from inoperable. discovery of loss of ADS initiation capability in both trip systems AND F.2 Restore channel to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from OPERABLE status. discovery of inoperable channel concurrent with HPCI or RCIC inoperable AND 8 days G. Required Action and G.1 Declare associated Immediately associated Completion supported feature(s)

Time of Condition B. inoperable.

C. D, E. or F not met.

SUSQUEHANNA - UNIT 2 3.3-41 Amendment 151

PPL Rev.

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS

-NOTES ---------

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS 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 as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 3.c and 3.e; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than 3.c and 3.e provided the associated Function or the redundant Function maintains ECCS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.5.1.2 _- _--

A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SUSQUEHANNA-UNIT2 TS /3.3-42 Amendment No. 1%1, 202

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 5)

K'- Emergency Core Cooling System Instrumentation APPLICABLE CON1DITIONS POMES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREIENTS VALUE

1. Core Spray System

a. Reactor Vessel Water 1,2,3, 4 (b) B SR 3.3.5.1.1 t -136 inches Level - Low Low Low, SR 3.3.5.1.2 Level I 4 (a) 5( SR 3.3.5.1.4 SR 3.3.5.1.5

b. Drywell 1,2,3 4 (b) B SR 3.3.5.1.2 i 1.88 psig Pressure -High SR 3.3.5.1.3 SR 3.3.5.1.5

c. Reactor Steam Dome 1,2.3 4 B SR 3.3.5.1.2 2 407 psig (lower)

Pressure - Low SR 3.3.5.1.3 s 433 psig (upper) I (initiation) 4 (a), 5 Ca) SR 3.3.5.1.5

d. Reactor Steam Dome 1,2,3 4 C SR 3.3.5.1.2 2 407 psig (lower)

Pressure - Low SR 3.3.5.1.3 s 433 jsig (upper) I (injection permissive) SR 3.3.5.1.5 4 B SR 3.3.5.1.2 2 407 psig (lower) 4 (a), 5 (a)

SR 3.3.5.1.3 s 433 psig (upper) I SR 3.3.5.1.5

e. ManuaL Initiation 1,2,3, 2 C SR 3.3.5.1.5 NA (a) 4 5(a) 1 per 4(s),5(a) subsystem

2. Low Pressure Coolant Injection (LPCI) System

a. Reactor Vessel Water 1,2,3, 4 (c) B SR 3.3.5.1.1 2 -136 inches Level-Low Low Low, SR 3.3.5.1.2 Level 1 4(a), 5 (a)

SR 3.3.5.1.4 SR 3.3.5.1.5 (continued)

(a) When associated subsystemts) are required to be OPERABLE.

tb) Also required to initiate the associated diesel generator COG), initiate Drywell Cooling Equipment Trip, and Emergency Service Water (ESW) Pump timer reset.

(c) Also required to initiate the associated DGs, ESW Pump timer reset and Turbine Building and Reactor Building Chillers trip.

SUSQUEHIANNA - UNIT 2 TS / 3.3-43 AmnendmentNo. 155

-4 b t 5 4 >}MAR ul4 1999 laS t ; Spe9 " qqq -W CXtv iJ-

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

2. LPCI System (continued)

b. Drywell 1,2,3 4(") B SR 3.3.5.1.2 1.88 psig Pressure - High SR 3.3.5.1.3 SR 3.3.5.1.5

c. Reactor Steam Dome 1,2.3 4 B SR 3.3.5.1.2 2 407 psio (Lower)

Pressure - Low SR 3.3.5.1.3 S 433 psig (upper) I (initiation) 4(a), 5(a) SR 3.3.5.1.5

d. Reactor Steam Dome 1,2,3 4 C SR 3.3.5.1.2 2 407 psig (Lower)

Pressure - Low SR 3.3.5.1.3 ! 433 psig (upper) I (injection permissive) SR 3.3.5.1.5 4(a), 5(a) 4 B SR 3.3.5.1.2 t 407 psig (lower)

SR 3.3.5.1.3 ! 433 psig (upper) I SR 3.3.5.1.5

e. Reactor Steam Dome 1(d), 2(d), 4 C SR 3.3.5.1.2 t 216 psig Pressure - Low SR 3.3.5.1.3 (Recirculation 3(d) SR 3.3.5.1.5 Discharge Valve Permissive)

f. Manual Initiation 1,2,3, 2 C SR 3.3.5.1.5 NA 4(a), 5 Ca) 1 per subsystem (continued)

(a) When associated subsystem(s) are required to be OPERABLE.

Cc) Also required to initiate the associated DGs, ESW pump timer reset and Turbine Building and Reactor Building Chiller trip.

(d) With either associated recirculation pump discharge or bypass valves open.

SUSQUEHANNA - UNIT 2 TS / 3.3-44 Amendment No. 15

_h I 2, 30 caq5 aoU SaFp 4 4 MAR L 41999 e 6 3-1j5 -q

PPL Rev. 3 ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTIONA.1 REQUIREMENTS VALUE

3. High Pressure Coolant Injection (HPCI)

System

a. Reactor Vessel 1, 4 B SR 3.3.5.1.1 :::-45 inches Water Level-Low 2(e),3(e) SR 3.3.5.1.2 Low, Level 2 SR 3.3.5.1.4 SR 3.3.5.1.5

b. Drywell Pressure- 1, 4 B SR 3.3.5.1.2 $1.88 psig High i e),3 (e) SR 3.3.5.1.3 SR 3.3.5.1.5

c. Reactor Vessel 1 2 C SR 3.3.5.1.2 s 55.5 inches Water Level- 2(e),3(e) SR 3.3.5.1.3 High, Level 8 SR 3.3.5.1.5

d. Condensate 1, 2 D SR 3.3.5.1.2 :::40.5 inches Storage Tank 2(e),3(e) SR 3.3.5.1.3 above tank bottom Level-Low SR 3.3.5.1.5

e. Manual Initiation 1, C SR 3.3.5.1.5 NA 2(e),3(e)

(continued)

(a) When the associated subsystem(s) are required to be OPERABLE.

(e) With reactor steam dome pressure> 150 psig.

SUSQUEHANNA - UNIT 2 TS /3.3-45 Amendment 4-78, 2-00, 234

PPL Rev. 1 ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 5)

Emergency Core Coaling System Instrumentation APPLICABLE CONDmONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDmONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

4. Automatic Depressurizatlon System (ADS) Trip System A

a. Reactor Vessel 1, 2 E SR 3.3.5.1.1 2-136 Inches Water Level-Low 2e), 3() SR 3.3.5.12 Low Low, Level 1 SR 3.3.5.tA SR 3.3.5.1.5

b. Drywell Pressure- 1, 2 E SR 3.3.5.1.2 s 1.88 psig High 21 ,3(a) SR 3.3.5.1.3 SR 3.3.5.1.5

c. Automatic 1, 1 F SR 3.3.5.12 s114 seconds Depressurkzatbon 23(),3e) SR 3.3.5.1.3 System Initiation SR 3.3.5.1.5 Timer

d. ReactorVessel 1, 1 E SR 3.3.5.1.1 21t.5hiches Water Level-ow, j.), d) SR 3.3.5.12 Level 3 SR 3.3.5.1.4 (Confirrnatoy) SR 3.3.5.1.5

e. Core Spray Pump 1, 2 F SR 3.3.5.12 2 125 psig Discharge 2(), 3() SR 3.3.5.1.3 and Pressure-High SR 3.3.5.1.5 < 165 psig

f. LowPressure 1, 4 F SR3.3.5.12 115psig Coolant Irnection 2(') 3(a) SR 3.3.5.1.3 and Pump Discharge SR 3.3.5.1.5 S 135 psig Pressure - High

g. Automatic 1, 2 F SR 3.3.5.1.2 < 450 seconds Depressurization 2 (e)3(1 SR 3.3.5.1.3 System Drywell SR 3.3.5.1.5 Pressure Bypass Actuation Tirner

h. Manual Initiation 1, 2 F SR 3.3.5.1.5 NA 2c'), 3(e)

(continued)

(e) Wfih reactor steam dome pressure> 150 psig.

SUSQUEHANNA- UNIT 2 TS / 3.3-46 Amendment ItoC 196 I

PPL Rev. I ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDmONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

5. ADS Trip System B

a. ReactorVessel 1, 2 E SR 3.3.5.1.1 2-136 Inches Water Level- Low 2(a),3(e) SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.4 SR 3.3.5.1.5

b. Drywell Pressure- 1, 2 E SR 3.3.5.12 s1.88psig High 2(S 3(0) SR 3.3.5.1.3 SR 3.3.5.1.5

c. Automatic 1, 1 F SR 3.3.5.12 5114sec Depressurization 2'). 3(6) SR 3.3.5.1.3 System Initiation SR 3.3.5.1.5 Timer

d. ReactorVessel 1, 1 E SR 3.3.5.1.1 211.5Inches Water Level-Low, 2",

' 3() SR 3.3.5.12 Level 3 SR 3.3.5.1.4 (Conrirmatory) SR 3.3.5.1.5

e. CoreSprayPump 1, 2 F SR 3.3.5.12 2125psig Discharge 2P)t SR 3.3.5.1.3 and Pressure-High SR 3.3.5.1.5 s 165 pslg

t. Low Pressure 1, 4 F SR 3.3.5.12 2115psig Coolant Injection 2(o),3(s) SR 3.3.5.1.3 and Pump Discharge SR 3.3.5.1.5 5135psig Pressure-High

g. Automatic 1, 2 F SR 3.3.5.12 s450seconds Depressurization 21),P3) SR 3.3.5.1.3 System Drywell SR 3.3.5.1.5 Pressure Bypass Actuation Timner

h. Manual Initiation 1, 2 F SR 3.3.5.1.5 NA 2(e), 3()

(e) WIth reactor steam dome pressure > 150 psig.

SUSQUEHANNA - UNIT 2 TS / 3.3-47 Amendment 1X5 196

RCIC System Instrumentation 3.3.5.2 3.3 INSTRUMENTATION 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation LCO 3.3.5.2 The RCIC System instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.

APPLICABILITY: MODE 1.

MODES 2 and 3 with reactor steam dome pressure > 150 psig.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable. referenced in Table 3.3.5.2-1 for the channel.

B. As required by B.1 Declare RCIC System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Required Action A.1 inoperable. discovery of and referenced in loss of RCIC Table 3.3.5.2-1. initiation capability AND B.2 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

C. As required by C.1 Restore channel to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Required Action A.1 OPERABLE status.

and referenced in Table 3.3.5.2-1.

(continued)

SUSQUEHANNA - UNIT 2 3.3-48 Amendment 151

RCIC System Instrumentation 3.3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1 -------- NOTE---------

Required Action A.1 Only applicable if and referenced in RCIC pump suction is Table 3.3.5.2-1. not aligned to the suppression pool.

Declare RCIC System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from inoperable. discovery of loss of RCIC initiation capability AND D.2.1 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

OR D.2.2 Align RCIC pump 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months suction to the suppression pool.

E. Required Action and E.1 Declare RCIC System Immediately associated Completion inoperable.

Time of Condition B.

C. or D not met.

SUSQUEHANNA - UNIT 2 3.3-49 Amendment 151

RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS

NOTES------------------------------------

1. Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC 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 as follows: (a)for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 2 and 4 and (b)for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than Functions 2 and 4 provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.5.2.2 -----------------------------------------

A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.5.2.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.5.2.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SUSQUEHANNA - UNIT 2 3.3-50 Amendment 151

RCIC System Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 1 of 1)

Reactor Core Isolation Cooling System Instrumentation CONDITIONS REQUIRED REFERENCED CHANNELS FROM-REQUIRED SURVEILLANCE ALLOWABLE FUNCTION PER FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Reactor Vessel Water 4 B SR 3.3.5.2.1 2 -45 inches Level -Low Low, Level 2 SR 3.3.5.2.2 SR 3.3.5.2.4 SR 3.3.5.2.5

2. Reactor Vessel Water 2 C SR 3.3.5.2.1 s 55.5 inches Level - High, Level 8 SR 3.3.5.2.2 SR 3.3.5.2.3 SR 3.3.5.2.5

3. Condensate Storage Tank 2 D SR 3.3.5.2.2 2 36.0 inches Level - Low SR 3.3.5.2.3 above the tank SR 3.3.5.2.5 bottom

4. Manual Initiation 1 C SR 3.3.5.2.5 NA SUSQUEHANNA - UNIT 2 3.3-51 Amendment 151

Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6.1-1.

ACTIONS kItfr IVI. J I I-e%

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in trip. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for channels inoperable. Functions 2.a, 2.d, 6.b, 7.a, and 7.b I AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions other than Functions 2.a, 2.d, 6.b, 7.a, and 7.b I B. One or more automatic B.1 Restore isolation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Functions with isolation capability.

capability not maintained.

(continued)

SUSQUEHANNA - UNIT 2 TS / 3.3-52 Amendment xA, 18R

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A Table 3.3.6.1-1 for or B not met. the channel.

D. As required by D.1 Isolate associated 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action C.1 main steam line and referenced in (MSL).

Table 3.3.6.1-1.

OR D.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND D.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. As required by E.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action C.1 and referenced in Table 3.3.6.1-1.

F. As required by F.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Required Action C.1 penetration flow and referenced in path(s).

Table 3.3.6.1-1.

G. As required by G.1 Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Required Action C.1 penetration flow and referenced in path(s).

Table 3.3.6.1-1.

(continued)

SUSQUEHANNA - UNIT 2 3.3-53 Amendment 151

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued) .

CONDITION REQUIRED ACTION COMPLETION TIME H. As required by H.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action C.1 and referenced in AND Table 3.3.6.1-1.

H.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Required Action and associated Completion Time for Condition F or G not met.

I. As required by I.1 Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Required Action C.1 standby liquid and referenced in control subsystem Table 3.3.6.1-1. (SLC) inoperable.

OR I.2 Isolate the Reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Water Cleanup System.

J. As required by J.1 Initiate action to Immediately Required Action C.1 restore channel to and referenced in OPERABLE status.

Table 3.3.6.1-1.

OR J.2 Initiate action to Immediately isolate the Residual Heat Removal (RHR)

Shutdown Cooling System.

SUSQUEHANNA - UNIT 2 3.3-54 Amendment 151

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS

NOTES----------------------------

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation 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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.6.1.2 ----------------------------------------

1. A test of all required contacts does not have to be performed.

2. For Functions 2.e. 3.a. and 4.a. a test of all required relays does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.1.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SUSQUEHANNA - UNIT 2 3.3-55 Amendment 151

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.1.6 J TE-----------------------------

I~LM

1. For Function 1.b. channel sensors are I excluded.

2. Response time testing of isolating relays is not required for Function 5.a.

Verify the ISOLATION SYSTEM RESPONSE 24 months on a TIME is within limits. STAGGERED TEST BASIS SUSQUEHANNA - UNIT 2 3.3-56 Amendment 141, 166-I..... P

PPL Rev.

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 of.6)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SPECIFIED PERTRIP REQUIRED SURVEILLANCE ALLOWABLE CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

1. Main Steam Line Isolation

a. Reactor Vessel 1,2,3 2 D SR 3.3.6.1.1 -136 inches Water Level - Low SR 3.3.6.1.2 Low Low, Level 1 SR 3.3.6.1.4 SR 3.3.6.1.5

b. Main Steam Line 1 2 SR 3.3.6.1.2 >841 psig Pressure - Low SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6

c. Main Steam Line 1,2,3 2 per MSL D SR 3.3.6.1.1 5 179 psid Flow- High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5

d. Condenser Vacuum 1 2 D SR 3.3.6.1.2 > 8.8 inches (a) (a) SR 3.3.6.1.3 Hg vacuum

-Low 21 3SR 3.3.6.1.5

e. Reactor Building 1,2,3 2 D SR 3.3.6.1.2 < 184°F Main Steam Tunnel SR 3.3.6.1.3 Temperature - High. SR 3.3.6.1.5

f. Manual Initiation 1,213 1 G SR 3.3.6.1.5 NA (continued)

(a) With any main turbine stop valve not closed.

SUSQUEHANNA - UNIT 2 TS / 3.3-57 Amendment 1fi6,224

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3 3.6.1-1 (page 2 of 6)

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

2. Primary Contairinment Isolation

a. Reactor Vessel Water 1,2,3 2 H SR 3.3.6.1.1 a 11.5 inches Level - Low, Level 3 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5

b. Reactor Vessel Water 1,2,3 2 H SR 3.3.6.1.1 a -45 inches Level - Low Low, SR 3.3.6.1.2 Level 2 SR 3.3.6.1.4 SR 3.3.6.1.5

c. Reactor Vessel Water 1,2,3 2 H SR 3.3.6.1.1 2 -136 inches Level - Low Low Low, SR 3.3.6.1.2 Level 1 SR 3.3.6.1.4 SR 3.3.6.1.5

d. Drywelt Pressure -High 1,2,3 2 H SR 3.3.6.1.2 < 1.88 psig SR 3.3.6.1.4 SR 3.3.6.1.5

e. SGTS 1,2,3 1 H SR 3.3.6.1.1 s 31 fR/hr Exhaust SR 3.3.6.1.2 Radiation - High SR 3.3.6.1.4 SR 3.3.6.1.5

f. Manual Initiation 1,2,3 1 C SR 3.3.6.1.5 NA (continued)

SUSQUEHANNA - UNIT 2 3.3-58 Amendment 151

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 6)

Primary Contaiinment 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

3. High Pressure Coolant Injection (HPCI) System Isolation

a. KPCI Steam Line A 1,2,3 1 F SR 3.3.6.1.2 s 383 inches Pressure - High SR 3.3.6.1.3 HO SR 3.3.6.1.5

b. HPCI Steam Supply Line 1,2,3 2 F SR 3.3.6.1.2 2 90 psig Pressure - Low SR 3.3.6.1.3 SR 3.3.6.1.5

c. HPCI Turbine 1,2,3 2 F SR 3.3.6.1.2 s 20 psig Exhaust Diaphragm SR 3.3.6.1.3 Pressure -High SR 3.3.6.1.5

d. Drywell Pressure-High 1,2,3 2 F SR 3.3.6.1.2 s 1.88 psig SR 3.3.6.1.3 SR 3.3.6.1.5

e. HPCI Pipe Routing Area 1,2,3 1 F SR 3.3.6.1.2 5 174"F Temperature - High SR 3.3.6.1.3 SR 3.3.6.1.5

f. HPCI Equipment Room 1,2,3 1 F SR 3.3.6.1.2 s 174°F Temperature - High SR 3.3.6.1.3 SR 3.3.6.1.5

g. NPCI Emergency Area 1,2,3 1 F SR 3.3.6.1.2 s 174OF Cooler SR 3.3.6.1.3 Temperature - High SR 3.3.6.1.5

h. Manual Initiation 1,2,3 1 G SR 3.3.6.1.5 NA (continued)

SUSQUEHANNA - UNIT 2 3.3-59 Amendment 151

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 4 of 6)

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

4. Reactor Core Isolation Cooling tRCIC) System Isolation

a. RCIC Steam Line A 1,2,3 1 F SR 3.3.6.1.2 s 143 inches H2O Pressure- High SR 3.3.6.1.3 SR 3.3.6.1.5

b. RCIC Steam Supply 1,2,3 2 F SR 3.3.6.1.2 2 53 psig Line Pressure - Low SR 3.3.6.1.3 SR 3.3.6.1.5

c. RCIC Turbine 1,2,3 2 F SR 3.3.6.1.2 s 20 psig Exhaust Diaphragm SR 3.3.6.1.3 Pressure - High SR 3.3.6.1.5

d. Drywetl 1,2,3 2 F SR 3.3.6.1.2 s 1.88 psig Pressure - High SR 3.3.6.1.3 SR 3.3.6.1.5

e. RCIC Pipe Routing 1,2,3 1 F SR 3.3.6.1.2 s 174°F Area SR 3.3.6.1.3 Temperature - High SR 3.3.6.1.5

f. RCIC Equipment Room 1,2,3 1 F SR 3.3.6.1.2 s 174*F Temperature - High SR 3.3.6.1.3 SR 3.3.6.1.5

g. RCIC Emergency 1,2,3 1 F SR 3.3.6.1.2 s 174*F Area Cooler SR 3.3.6.1.3 Temperature - High SR 3.3.6.1.5 (continued)

SUSQUEHANNA - UNIT 2 3.3-60 Amendment 151

PPL Rev.

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 5.of 6)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

h. Manual Initiation 1,2,3 1 G SR 3.3.6.1.5 NA

5. Reactor Water Cleanup (RWCU) System Isolation

a. RWCU Differential A 1,2,3 1 F SR 3.3.6.1.1 _<

67 gpm Flow - High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.6

b. RWCU Penetration 1,2,3 1 F SR 3.3.6.1.2 < 1371F Area Temperature - SR 3.3.6.1.3 High SR 3.3.6.1.5

c. RWCU Pump Area 1,2,3 1 F SR 3.3.6.1.2 < 154OF Temperature - High SR 3.3.6.1.3 SR 3.3.6.1.5

d. RWCU Heat 1,2,3 1 F SR 3.3.6.1.2 < 154oF Exchanger Area SR 3.3.6.1.3 Temperature - High SR 3.3.6.1.5

e. SLC System Initiation 1,2,3 2 (b) I SR 3.3.6.1.5 NA

f. Reactor Vessel Water 1,2,3 2 F SR 3.3.6.1.1 > -45 inches Level -Low Low, SR 3.3.6.1.2 Level 2 SR 3.3.6.1.4 SR 3.3.6.1.5

g. RWCU Flow - High 1,2,3 1 F SR 3.3.6.1.1 5 472 gpm SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5

h. Manual Initiation 1,2,3 1 G SR 3.3.6.1.5 NA (continued)

(b) SLC System Initiation only inputs into one of the two trip systems.

SUSQUEHANNA - UNIT 2 3.3-61 Amendment 15A, 216

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 6 of 6)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

6. Shutdown Cooling System Isolation

a. Reactor Steam Dome 1,2,3 1 F SR 3.3.6.1.2 s108psig Pressure - High SR 3.3.6.1.3 SR 3.3.6.1.5

b. ReactorVesselWater 3.4,5 2(c) J SR 3.3.6.1.1 211.5 inches Level - Low, Level 3 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5

c. Manual InitIation 3,4.5 1 G SR 3.3.6.1.5 NA

7. Traversing Incore Probe Isolation

a. Reactor Vessel Water 1.2,3 2 G SR 3.3.6.1.1 2 11.5 Inches Level - Low, Level 3 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5

b. Drywell Pressure- 1,2,3 2 G SR 3.3.6.1.2 s 1.88 psig High SR 3.3.6.1.4 SR 3.3.6.1.5 (c) Only one trip system required In MODES 4 and 5 when RHR Shutdown Cooling System Integrity maintained.

SUSQUEHANNA - UNIT 2 TS / 3.3-62 Amendment A*, 188

Secondary Containment Isolation Instrumentation 3.3.6.2 3.3 INSTRUMENTATION 3.3.6.2 Secondary Containment Isolation Instrumentation LCO 3.3.6.2 The secondary containment isolation instrumentation for each Function in Table 3.3.6.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6.2-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for inoperable. trip. Function 2 AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions other than Function 2 B. One or more automatic. B.1 Restore secondary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Functions with containment isolation secondary containment capability.

isolation capability not maintained.

(continued)

SUSQUEHANNA - UNIT 2 3.3-63 Amendment 151

Secondary Containment Isolation Instrumentation 3.3.6.2 ACTIONS (continued) .

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1.1 Isolate the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion associated zone(s)

Time of Condition A and place the or B not met. associated standby gas treatment subsystem(s) in emergency operations aligned to the associated zone(s).

OR C.2.1 Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months secondary containment isolation valves inoperable.

AND C.2.2 Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SGT subsystem(s) inoperable.

SUSQUEHANNA - UNIT 2 3.3-64 Amendment 151

Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS

NOTES---------------------------

1. Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation 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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains secondary containment isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.6.2.2 --------------------------------------

A test of all required contacts does not have to be performed. -

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.2.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.6.2.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SUSQUEHANNA - UNIT 2 3.3-65 Amendment 151

Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS VALUE

1. Reactor Vessel Water 1,2,3, 2 SR 3.3.6.2.1 a -45 inches Level - Low Low, Level 2 (a) SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5

2. Drywell Pressure-High 1,2,3 2 SR 3.3.6.2.2 S 1.88 psig SR 3.3.6.2.3 SR 3.3.6.2.5

3. Unit 1 Refuel Floor High (a),(b) 1 SR 3.3.6.2.1 s 25 mR/hr Exhaust Duct SR 3.3.6.2.2 Radiation- High SR 3.3.6.2.4 SR 3.3.6.2.5

4. Unit 2 Refuel Floor High (a),(b) 1 SR 3.3.6.2.1 s 25 mR/hr Exhaust Duct SR 3.3.6.2.2 Radiation - High SR 3.3.6.2.4 SR 3.3.6.2.5

5. Unit 1 Refuel Floor Wall (a),(b) 1. SR 3.3.6.2.1 s 28 mR/hr Exhaust Duct SR 3.3.6.2.2 Radiation - High SR 3.3.6.2.4 SR 3.3.6.2.5

6. Unit 2 Refuel Floor Wall (a),Cb) 1 SR 3.3.6.2.1 s 28 mR/hr Exhaust Duct SR 3.3.6.2.2 Radiation - High SR 3.3.6.2.4 SR 3.3.6.2.5

7. Railroad Access Shaft Cc) 1 SR 3.3.6.2.1 s 7 mR/hr Exhaust Duct SR 3.3.6.2.2 Radiation - High SR 3.3.6.2.4 SR 3.3.6.2.5

8. Manual Initiation 1,2,3, 1 SR 3.3.6.2.5 NA Ca),Cb)

Ca) During operations with a potential for draining the reactor vessel.

Cb) During CORE ALTERATIONS and during movement of Irradiated fuel assemblies in secondary containment.

Cc) During movement of irradiated fuel assemblies within the Railroad Access Shaft, and above the Railroad Access Shaft with the Railroad Access Shaft Equipment Hatch open.

SUSQUEHANNA - UNIT 2 3.3-66 Amendment 151

CREOAS System Instrumentation 3.3.7.1 3.3 INSTRUMENTATION 3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS) System Instrumentation LCO 3.3.7.1 The CREOAS System instrumentation for each Function in Table 3.3.7.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.7.1-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Enter the Condition Immediately channels inoperable. referenced in Table 3.3.7.1-1 for the channel.

(continued)

SUSQUEHANNA - UNIT 2 3.3-67 Amendment 151

CREOAS System Instrumentation 3.3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. As required by B.1.1 Declare CREOAS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Required Action A.1 subsystems discovery of and referenced in inoperable. loss of CREOAS Table 3.3.7.1-1. initiation capability in both trip systems OR B.1.2 Place the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from CREWAS subsystem(s) discovery of in the loss of CREOAS pressurization/ initiation filtration mode of capability in operation. both trip systems AND B.2.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for trip. Function 2 AND OR 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for all other Functions (continued)

SUSQUEHANNA - UNIT 2 3.3-68 Amendment 151

CREOAS System Instrumentation 3.3.7.1 ACTIONS (continued) ._.

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2.2 Place the associated 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for CREOAS subsystem(s) Function 2 in the pressurization/

filtration mode of AND operation.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for all other Functions C. As required by C.1.1 Place the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Required Action A.1 CREOAS subsystem(s) discovery of and referenced in in the loss of CREOAS Table 3.3.7.1-1. pressurization/ initiation filtration mode of capability in operation. both trip systems OR C.1.2 Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from CREOAS subsystem(s) discovery of inoperable. loss of CREOAS initiation capability in both trip systems AND C.2 Place channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months trip.

D. Required Action and D.1 Declare associated Immediately associated Completion CREOAS subsystem Time of Condition B inoperable.

or C not met.

SUSQUEHANNA - UNIT 2 3.3-69 Amendment 151

CREOAS System Instrumentation 3.3.7.1 ACTIONS SURVEILLANCE REQUIREMENTS

- ---------------------------- NOTES------------------------------------

1. Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREOAS 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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains CREOAS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.7.1.2 ----------------------------------------

1. A test of all required contacts does not have to be performed.

2. For Function 8. a test of all required relays does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.7.1.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.7.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SUSQUEHANNA - UNIT 2 3.3-70 Amendment 151

CREOAS System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (page I of 1)

Control Room Emergency Outside Air SuppLy System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION A.1 REQUIREMENTS VALUE

1. Reactor Vessel Water 1,2,3, 2 B SR 3.3.7.1.1 k -45 inches Level -Low Low, (a) SR 3.3.7.1.2 Level 2 SR 3.3.7.1.4 SR 3.3.7.1.5

2. Drywell Pressure -High 1,2,3 2 B SR 3.3.7.1.2 S 1.88 psig SR 3.3.7.1.3 SR 3.3.7.1.5

3. Unit 1 Refuel Floor (a), (b) 1 B SR 3.3.7.1.1 s 25 mR/hr High Exhaust Duct SR 3.3.7.1.2 Radiation - High SR 3.3.7.1.4 SR 3.3.7.1.5

4. Unit 2 Refuel Floor (a), Cb) 1 8 SR 3.3.7.1.1 s 25 mR/hr High Exhaust Duct SR 3.3.7.1.2 Radiation - High SR 3.3.7.1.4 SR 3.3.7.1.5

5. Unit 1 Refuel Floor (a),(b) B SR 3.3.7.1.1 s 28 mR/hr Wall Exhaust Duct SR 3.3.7.1.2 Radiation - High SR 3.3.7.1.4 SR 3.3.7.1.5

6. Unit 2 Refuel Floor (a), (b) B SR 3.3.7.1.1 s 28 mR/hr Wall Exhaust Duct SR 3.3.7.1.2 Radiation - High SR 3.3.7.1.4 SR 3.3.7.1.5

7. Railroad Access Shaft cc) B SR 3.3.7.1.1 S 7 mR/hr Exhaust Duct SR 3.3.7.1.2 Radiation - High SR 3.3.7.1.4 SR 3.3.7.1.5

8. Main Control Room 1,2,3, C SR 3.3.7.1.1 S 5 mR/hr Outside Air Intake SR 3.3.7.1.2 Radiation - High (a),(b) SR 3.3.7.1.4 SR 3.3.7.1.5

9. Manual Initiation 1,2,3 B SR 3.3.7.1.5 n/a (a),(b)

(a) During operations with a potential for draining the reactor vessel.

(b) During CORE ALTERATIONS and during movement of irradiated fuel assemblies In the secondary containment.

(c) During movement of irradiated fuel assemblies within the Railroad Access Shaft, and above the Railroad Access Shaft with the Railroad Access Shaft Equipment Hatch open.

SUSQUEHANNA - UNIT 2 3.3-71 Amendment 151

PPL Rev. 1 LOP Instrumentation l 3.3.8.1 3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation LCO 3.3.8.1 The LOP instrumentation for each Function in Table 3.3.8.1-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and When the associated diesel generator is required to be OPERABLE by LCO 3.8.2, "AC Sources-Shutdown."

ACTIONS Sare----y-l--------------------------

e-r---c

--- --- nU I c- -- -. - - - - - --- - - - - - - - - - - - - -

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Enter the Condition referenced in Immediately channels inoperable for Table 3.3.8.1-1 for the channel.

reasons other than Condition B.

B. One or more required B.1 Restore the inoperable channels 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months channels associated with Unit 1 4.16 kV ESS Buses in one Division inoperable for the performance of Unit 1 SR 3.8.1.19 C. As required by C.1 Place channel In trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Required Action A.1 I and referenced in Table 3.3.8.1-1.

(continued)

SUSQUEHANNA - UNIT 2 TS I 3.3-72 Amendment tS1, 1 208,

PPL Rev. 1 LOP Instrumentation l 3.3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1 Restore the inoperable Channel. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months I Required Action A.1 and referenced in Table 3.3.8.1-1.

E. Required Action E.1 Declare associated diesel generator Immediately I and associated (DG) inoperable.

Completion Time of Condition B, C, or D not met. I SURVEILLANCE REQUIREMENTS

--------------------- NOTES-------------------------------------------

1. Refer to Table 3.3.8.1-1 to determine which SRs apply for each LOP 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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains DG initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.8.1.2 Perform CHANNEL FUNCTIONAL TEST. 31 days SR 3.3.8.1.3 Perform CHANNEL CALIBRATION. 24 months SR 3.3.8.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SUSQUEHANNA- UNIT 2 TS / 3.3-73 Amendment 18 , l 208,

PPL Rev. 1 LOP Instrumentation l 3.3.8.1 Table 3.3.8.1 -t (page 1 of 1)

Loss of Power Instrumentation CONDITIONS REFERENCED REQUIRED FROM REQUIRED SURVEILLANCE FUNCTION CHANNELS PER BUS ACTION A.1 REQUIREMENTS ALLOWABLE VALUE

1. 4.16 kV Emergency Bus Undervoltage (Loss of Voltage < 20%)

a. Bus Undervoltage 1 D SR 3.3.8.1.3 2 780.4V I SR 3.3.8.1.4 and s 899.6V

b. Time Delay I D SR 3.3.8.1.3 2O.4sec I SR 3.3.8.1.4 and 50.6 sec

2. 4.16 kV Emergency Bus Undervoltage Low Setting (Degraded Voltage 65%)

a. Bus Undervoltage 2 C SR 3.3.8.1.1 2 2503V I SR 3.3.8.1.2 and SR 3.3.8.1.3 S 2886V SR 3.3.8.1.4

b. Time Delay 1 D SR 3.3.8.1.2 2 2.7sec I SR 3.3.8.1.3 and SR 3.3.8.1.4 S 3.3sec

3. 4.16 kV Emergency Bus Undervoltage LOCA (Degraded Voltage 93%)

a. Bus Undervoltage 2 C SR 3.3.8.1.1 2 3801V I SR 3.3.8.1.2 and SR 3.3.8.1.3 S 3935V SR 3.3.8.1.4

b. Time Delay (LOCA) 1 D SR 3.3.8.1.3 2 9sec I SR 3.3.8.1.4 and S 11 sec

c. Time Delay (Non 1 D SR 3.3.8.1.2 > 4 min I LOCA) SR 3.3.8.1.3 30 sec SR 3.3.8.1.4 and S 5min 30 sec SUSQUEHANNA - UNIT 2 TS / 3.3-74 Amendment Z1 , l 208,

RPS Electric Power Monitoring 3.3.8.2 3.3 INSTRUMENTATION 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring LCO 3.3.8.2 Two RPS electric power monitoring assemblies shall be OPERABLE for each inservice RPS motor generator set or alternate power supply.

APPLICABILITY: MODES 1. 2. 3. 4. and 5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or both inservice A.1 Remove associated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months power supplies with inservice power one electric power supply(s) from monitoring assembly service.

inoperable.

B. One or both inservice B.1 Remove associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months power supplies with inservice power both electric power supply(s) from monitoring assemblies service.

inoperable.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND or B not met in MODE 1, 2. or 3. C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

SUSQUEHANNA - UNIT 2 3.3-75 Amendment 151

RPS Electric Power Monitoring 3.3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to Immediately associated Completion fully insert all Time of Condition A insertable control or B not met in MODE 4 rods in core cells or 5. containing one or more fuel assemblies.

AND D.2.1 Initiate action to Immediately restore one electric power monitoring assembly to OPERABLE status for inservice power supply(s) supplying required instrumentation.

OR D.2.2 Initiate action to Immediately isolate the Residual Heat Removal Shutdown Cooling System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.2.1 ------------------NOTE-------------------

Only required to be performed prior to entering MODE 2 or 3 from MODE 4. when in MODE 4 for a 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Perform CHANNEL FUNCTIONAL TEST. 184 days (continued)

SUSQUEHANNA - UNIT 2 3.3-76 Amendment 151

RPS Electric Power Monitoring 3.3.8.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.8.2.2 Perform CHANNEL CALIBRATION. The 24 months Allowable Values shall be:

a. Overvoltage : 129.1 V for Division A and < 130.3 V for Division B.

b. Undervoltage > 112.0 V for Division A and a 112.5 V for Division B.

c. Underfrequency > 57 Hz.

SR 3.3.8.2.3 Perform a system functional test. 24 months SUSQUEHANNA - UNIT 2 3.3-77 Amendment 151

PPL Rev. 3 Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation.

OR One recirculation loop may be in operation provided the following limits are applied when the associated LCO is applicable:

a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," single loop operation limits specified in the COLR;

b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR),"

single loop operation limits specified in the COLR;

c. LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR),"

single loop operation limits specified in the COLR, and

d. LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation,"

Function 2.b (Average Power Range Monitors Simulated Thermal Power-High), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation.

e. Recirculation pump speed is < 80%.

ole --

Required limit and setpoint resets for single recirculation loop operation may be delayed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after transition from two recirculation loop operation to single recirculation loop operation.

APPLICABILITY: MC)DES 1 and 2.

SUSQUEHANNA - UNIT 2 TS.1 3.4-1 Amendment 1-51, 1tEB, A.9, t92, 20n7

PPL Rev.

Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No recirculation loops A.1 Place reactor mode Immediately operating while in switch in the shutdown MODE 1. position.

B. Recirculation loop flow B.1 Declare the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months mismatch not within recirculation loop with limits. lower flow to be "not in operation."

C. No recirculation loops C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in operation while in MODE 2.

OR Single Recirculation Loop required limits and setpoints not established within required time.

SUSQUEHANNA - UNIT 2 TS / 3.4-2 Amendment1St t58, "9, 192

PPL Rev.

Recirculation Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 -------- --------- NOTE-------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are in operation.

Verify recirculation loop Jet pump flow 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months mismatch with both recirculation loops in operation is:

a. < 10 million Ibm/hr when operating at

< 75 million Ibm/hr total core flow; and

b. < 5 million Ibm/hr when operating at 2 75 million Ibm/hr total core flow.

SR 3.4.1.2 --- ------NOTE T--

Only required to be met during single loop operations.

Verify recirculation pump speed is within the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months limit specified in the LCO.

SUSQUEHANNA - UNIT 2 TS/3.4-3 Amendment 15SI,

-ti, tO, 192

PPL Rev.

Recirculation Loops Operating 3.4.1 K>'

THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 TS /3.4-4 Amendment 15t, 1-t,5X, 192

PPL Rev.

Recirculation Loops Operating 3.4.1 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 TS / 3.4-5 Amendment 151, 1M5, 4 192

Jet Pumps 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 Jet Pumps LCO 3.4.2 All jet pumps shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS -

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more jet pumps A.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable.

SUSQUEHANNA - UNIT 2 3.4-6 Amendment 151

PPL Rev.

Jet Pumps 3.4.2 SURVEILLANCE REQUIREMENTS ._ .

SURVEILLANCE FREQUENCY SR 3.4.2.1 " ---- ---- NOTES---------"---

1. Not required to be completed until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after associated recirculation loop is in operation.

2. Not required to -be completed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after > 23% RTP.

Verify at least two of the following criteria (a, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months b,ý or c) are satisfied for each operating recirculation loop:

a. Recirculation loop drive flow versus Recirculation Pump speed differs by

< 10% from established patterns.

b. Recirculation loop drive flow versus total core flow differs by < 10% from established patterns.

c. Each-jet pump diffuser to lower plenum differential pressure differs by

<20% from established patterns, or each jet pump flow differs by _ 10%

from established patterns.

SUSQUEHANNA - UNIT 2 3.4-7 Amendment 1,5%224

PPL Rev.

S/RVs 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 Safety/Relief Valves (S/RVs)

LCO 3.4.3 The safety function of 14 S/RVs shall be OPERABLE.

APPLICABILITY: MODES. 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.1 One or more required A.1 Be in MODE 3.: 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months S/RVs inoperable..

AND A.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SUSQUEHANNA - UNIT 2 3.4-8 Amendment IZI 224

S/RVs 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoints of the In accordance with the required S/RVs are as follows: Inservice Testing Program

_ _I__

-__---_ - ---- NU IJ C Up to two inoperable required S/RVs may be replaced with spare OPERABLE S/RVs having lower setpoints until the next refueling outage.

Number of Setpoint S/RVs (PsiQ) 2 1175 (2 1140 and 5 1210) 6 1195 (2 1160 and < 1230) 8 1205 (2 1169 and c 1241)

Following testing, lift settings shall be within +/-1%. I SUSQUEHANNA - UNLIT 2 3.4-9 Amendment Aid, 175 MAR o 7 W~

RCS Operational LEAKAGE 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Operational LEAKAGE LCO 3.4.4 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE:

b. 5 5 gpm unidentified LEAKAGE:

c. 5 25 gpm total LEAKAGE averaged over the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period: and

d. s 2 gpm increase in unidentified LEAKAGE within the previous 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months period in MODE 1.

APPLICABILITY: MODES 1. 2. and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Unidentified LEAKAGE A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months not within limit. within limits.

OR Total LEAKAGE not within limit.

B. Unidentified LEAKAGE B.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months increase not within within limits.

limit.

OR (continued)

SUSQUEHANNA - UNIT 2 3.4-10 Amendment 151

RCS Operational LEAKAGE 3.4.4 ACTIONS .

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Verify source of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months unidentified LEAKAGE increase is not service sensitive type 304 or type 316 austenitic stainless steel.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND or B not met.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Pressure boundary LEAKAGE exists.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and unidentified LEAKAGE increases are within limits.

SUSQUEHANNA - UNIT 2 3.4-11 Amendment 151

RCS PIV Leakage 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.5 The leakage from each RCS PIV shall be within limit.

APPLICABILITY: MODES 1 and 2.

MODE 3. except valves in the residual heat removal (RHR) shutdown cooling flow path when in. or during the transition to or from, the shutdown cooling mode of operation.

ACTIONS

NOTES------------------------------------

1. Separate Condition entry is allowed for each flow path.

2. Enter applicable Conditions and Required Actions for systems made inoperable by PIVs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more flow paths ------------NOTE-------------

with leakage from one Each valve used to satisfy or more RCS PIVs not Required Action A.1 must have within limit. been verified to meet SR 3.4.5.1 and be in the reactor coolant ressure boundary or the high pressure portion of the system.

(continued)

SUSQUEHANNA - UNIT 2 3.4-12 Amendment 151

RCS PIV Leakage 3.4.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.1 Isolate the high 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months pressure portion of the affected system.

from the low pressure portion by use of one closed manual, de-activated automatic, or check valve.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 -------------------NOTE--------------------

Not required to be performed in MODE 3.

Verify equivalent leakage of each RCS PIV In accordance is s 0.5 gpm per nominal inch of valve size with the up to a maximum of 5 gpm, at an RCS Inservice pressure a 1025 and s 1045 psig. Testing Program SUSQUEHANNA - UNIT 2 3.4-13 Amendment 151

PPL Rev. 1 RCS Leakage Detection Instrumentation 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Leakage Detection Instrumentation LCO 3.4.6 The following RCS leakage detection instrumentation shall be OPERABLE:

a. Drywell floor drain sump monitoring system; and

b. One channel of either primary containment atmospheric particulate or atmospheric gaseous monitoring system.

APPLICABILITY: MODES I and 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell floor drain A.1 Restore drywell floor 30 days I sump monitoring drain sump monitoring system inoperable. system to OPERABLE status.

(continued)

SUSQUEHANNA - UNIT 2 TS /3.4-14 Amendmnent 1#1, 195

PPL Rev. 1 RCS Leakage Detection Instrumentation 3.4.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME, B. Required primary B.1 Analyze grab samples Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months containment of primary containment atmospheric monitoring atmosphere.

system inoperable.

AND B.2 Restore required 30 days primary containment atmospheric monitoring system to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or AND B not met.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. All required leakage D.1 Enter LCO 3.0.3. Immediately detection systems inoperable.

SUSQUEHANNA - UNIT 2 TS /3.4-15 Amendment illf1, 195

RCS Leakage Detection Instrumentation 3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Perform a CHANNEL CHECK of required primary 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months containment atmospheric monitoring system.

SR 3.4.6.2 Perform a CHANNEL FUNCTIONAL TEST of 31 days required leakage detection instrumentation.

SR 3.4.6.3 Perform a CHANNEL CALIBRATION of required 24 months leakage detection instrumentation.

SUSQUEHANNA - UNIT 2 3.4-16 Amend~ment 151

PPL Rev. 1 RCS Specific Activity 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Specific Activity LCO 3.4.7 The specific activity of the reactor coolant shall be limited to DOSE EQUIVALENT 1-131 specific activity S 0.2 puCVgm.

APPLICABILITY: Mode 1, MODES 2 and 3 with any main steam line not isolated.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor coolant specific ---- N OTE --

activity > 0.2 pCVgm and LCO 3.0.4.c is applicable. I

< 4.0 pCVgm DOSE ___

EQUIVALENT 1-131.

A.1 Determine DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT 1-131 AND A.2 Restore DOSE EQUIVALENT 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 1-131 to within limits.

B. Required Action and B.1 Determine DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion EQUIVALENT 1-131.

Time of Condition A not met. AND OR B.2.1 Isolate all main steam lines. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Reactor Coolant specific OR activity > 4.0,Cigm Dose EQUIVALENT 1-131.

(continued)

SUSQUEHANNA - UNIT 2 TS /3.4-17 Amendment 141, 195

RCS Specific Activity 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND B.2.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 -------------------NOTE--------------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 7 days I-131 specific activity is 5 0.2 pCi/gm.

SUSQUEHANNA - UNIT 2 3.4-18 Amendment 151

PPL Rev. 1 RHR Shutdown Cooling System - Hot Shutdown 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown LCO 3.4.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

NOTES-------------

1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

APPLICABILITY: Mode 3, with reactor steam dome pressure less than the RHR cut in permissive pressure.

ACTIONS LIO%*Ir-

- -~II~j

I - ----------- ----------- _- - -- ------

I Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required A.1 Initiate action to restore Immediately RHR shutdown cooling RHR shutdown cooling subsystems subsystem(s) to inoperable. OPERABLE status.

AND (continued)

SUSQUEHANNA - UNIT 2 TS /3.4-19 Amendment 1,X1, 195

RHR Shutdown Cooling System- Hot Shutdown 3.4.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

AND A.3 Be in MODE 4. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months B. No RHR shutdown B.1 Initiate action to Immediately cooling subsystem in restore one RHR operation. shutdown cooling subsystem or one AND recirculation pump to operation.

No recirculation pump in operation. AND B.2 Verify reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from coolant circulation discovery of no by an alternate reactor coolant method. circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.3 Monitor reactor Once per hour coolant temperature and pressure.

SUSQUEHANNA - UNIT 2 3.4-20 Amendment 151

RHR Shutdown Cooling System- Hot Shutdown 3.4.8 SURVEILLANCE REQUIREMENTS

- SURVEILLANCE FREQUENCY SR 3.4.8.1 -------------------NOTE--------------------

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR cut in permissive pressure.

Verify one RHR shutdown cooling subsystem 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or recirculation pump is operating.

SUSQUEHANNA - UNIT 2 3.4-21 Amendment 151

RHR Shutdown Cooling System -Cold Shutdown 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System- Cold Shutdown LCO 3.4.9 Two RHR shutdown cooling subsystems shall be OPERABLE. and.

with no recirculation pump in operation. at least one RHR shutdown cooling subsystem shall be in operation.

NOTES--------------------------

1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

APPLICABILITY: MODE 4.

ACTIONS

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

Separate Condition entry is allowed for each shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months RHR shutdown cooling method of decay heat subsystems inoperable. removal is available AND for each inoperable RHR shutdown cooling Once per subsystem. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

SUSQUEHANNA - UNIT 2 3.4-22 Amendment 151

RHR Shutdown Cooling System - Cold Shutdown

.3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR shutdown B.1 Verify reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from cooling subsystem in coolant circulating discovery of no operation. by an alternate reactor coolant method. circulation AND AND No recirculation pump in operation. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.2 Monitor reactor Once per hour coolant temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify one RHR shutdown cooling subsystem 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or recirculation pump is operating.

SUSQUEHANNA - UNIT 2 3.4-23 Amendment 151

RCS P/T Limits 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 RCS Pressure and Temperature (P/T) Limits LCO 3.4.10 RCS pressure, RCS temperature. RCS heatup and cooldown rates, and the recirculation pump starting temperature requirements shall be maintained within limits.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE--------- A.1 Restore parameter(s) 30 minutes Required Action A.2 to within limits.

shall be completed if this Condition is AND entered.

A.2 Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months acceptable for Requirements of the continued operation.

LCO not met in MODES 1, 2. and 3.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

SUSQUEHANNA - UNIT 2 3.4-24 Amendment 151

RCS P/T Limits 3.4.10 ACTIONS (continued) . _

CONDITION REQUIRED ACTION COMPLETION TIME C. ---------NOTE--------- C.1 Initiate action to Immediately Required Action C.2 restore parameter(s) shall be completed if to within limits.

this Condition is entered. AND C.2 Determine RCS is Prior to Requirements of the acceptable for entering MODE 2 LCO not met in other operation. or 3.

than MODES 1, 2.

and 3.

SUSQUEHANNA - UNIT 2 3.4-25 Amendment 151

3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 ----------------------------- NOTE--------------------------------

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify:

a. RCS pressure and RCS temperature are to 30 minutes the right of the most limiting curve specified in Figures 3.4.10-1 through 3.4.10-3; and

b. ---- ------- NOTE------ - --------------------

Only applicable when governed by Figure 3.4.10-2, Curve B, and Figure 3.4.10-3, Curve C.

RCS heatup and cooldown rates are

< IOOoF in any one hour period; and

c. ------------------------ NOTE--------------------------

Only applicable when governed by Figure 3.4.10-1, Curve A.

RCS heatup and cooldown rates are < 20 F in any one hour period.

SR 3.4.10.2 Verify RCS pressure and RCS temperature are to Once within 15 minutes the right of the criticality limit (Curve C) specified in prior to control rod Figure 3.4.10-3. withdrawal for the purpose of achieving criticality (continued)

SUSQUEHANNA - UNIT 2 3.4-26 Amendment 174 FEE5 .- ES

PPL Rev.

RCS PIT Limits 3.4.10 SURVEILLANCE REQUIREMENTS (continued) "_.._ ..

SURVEILLANCE FREQUENCY SR 3.4.10.3 * "- "- 'NOTE-.--------

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump start.

Once within 15 minutes Verify the difference between the bottom head prior to each startup of a coolant temperature and the reactor pressure vessel recirculation pump (RPV) coolant temperature is < 1450 F.

SR 3.4.10.4 ------ NOTE---

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump start.

Verify the difference between the reactor coolant Once within 15 minutes temperature in the recirculation loop to be started prior to each startup of a and the RPV coolant temperature is < 50 0 F. recirculation pump SR 3.4.10.5 ---. ..----

Only required to be met in single loop operation when:

a. THERMAL POWER *27% RTP; or

b. The operating recirculation loop flow

21,320 gpm.

Verify the difference between the bottom head Once within 15 minutes coolant temperature and the RPV coolant prior to an increase in temperature is:* 145,F. THERMAL POWER or an increase in loop flow (continued)

SUSQUEHANNA - UNIT 2 3.4-27 Amendment 1R1, 224

PPL Rev.

RCS P/T Limits 3.4.10 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.10.6 - .---------------- NOTE---------------

Only required to be met in single loop operation when the idle recirculation loop is not isolated from the RPV, and:

a. THERMAL POWER *27% RTP; or I

b. The operating recirculation loop flow

<_21,320 gpm.

Verify the difference between the reactor coolant Once within 15 minutes temperature in the recirculation loop not in prior to an increase in operation and the RPV coolant temperature is THERMAL POWER or

< 500 F. an increase in loop flow.

SR 3.4.10.7 ------------- NOTE----------

Only required to be performed when tensioning the reactor vessel head bolting studs.

Verify reactor vessel flange and head flange 30 minutes temperatures are?_700F. "_ _

SR 3.4.10.8 -------------- NOTE----- ----

Not required to be performed until 30 minutes after RCS temperature < 80°F in MODE 4.

Verify reactor vessel flange and head flange 30 minutes temperatures are__ 70 0F. ....

(continued)

SUSQUEHANNA - UNIT 2 3.4-28 Amendment2121, 224

RCS P/T Limits 3.4.10 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.10.9 -------------------NOTE-------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS temperature s 1000 F in MODE 4.

Verify reactor vessel flange and head 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months flange temperatures are a 700F.

SUSQUEHANNA - UNIT 2 3.4-29 Amendment 151

PPL Rev. 2 RCS P/T Limits 3.4.10

---nn.

1 ZVV . .. .- .. w

/ I,I.1 1100 = h/ a==

/I 1000 1_ 900 - -

-n

/

V)

U)

'a D

700 7-a, 600 - _ _ _

1) 0 0

50 0 - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

a, rK c

C 400 _ :

a, L_

-- Upper Vessel U)

U) 0~ 300 - _ _ __ _ _ _ -Beltline _

- - Bottom Head_

d-J' 100 JI Il Z 60 80 100 120 140 160 180 200 Minimum Reactor Vessel Metal Temperature (degrees F)

Figure 3.4.10-1 System Hydrotest Limit with Fuel in Vessel for 30.2 EFPY (Curve A) I SUSQUEHANNA - UNIT 2 TS / 3.4-30 Amendment 17 4, 1P,209

PPL Rev. 2 RCS P/T Limits 3.4.10 1300 1200 A 1100 _ _ _ _

Ir 900 0j o

= 000.l- U prVse 200 __ ____ * = = =_

L. 00 _ _ _

4 Fiur () 3.1 0-2 l Non Nula Htin itfo302EP 0

600 2 -I-0 40 10 1 0 Non-ucler HetingLimi fo 30e2tline

~- 400 ______ _ (Curve - -perVse SUSQUEHANNA - UNIT 2 TS / 3.4-30a Amendment 17/4, 19Y,209

PPL Rev. 2 RCS P/T Limits 3.4.10 0-0 C) 0 Q

I-to Co a)

V)

E Qa) 0 CC 0~

V}

Qt L._

0o . . l lL l l. l 60 80 100 120 140 160 180 200 Minimum Reactor Vessel Metal Temperature (degrees F)

FIGURE 3.4.10-3 Nuclear (Core Critical) Limit for 30.2 EFPY (Curve C)

I SUSQUEHANNA - UNIT 2 TS / 3.4-30b Amendment 17Z4, 19;/ 209

Reactor Steam Dome Pressure 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Reactor Steam Dome Pressure LCO 3.4.11 The reactor steam dome pressure shall be < 1050 psig.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor steam dome A.1 Restore reactor steam 15 minutes pressure not within dome pressure to limit. within limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS -

SURVEILLANCE FREQUENCY SR 3.4.11.1 Verify reactor steam dome pressure is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 5 1050 psig.

SUSQUEHANNA - UNIT 2 3.4-31 Amendment 151

PPL Rev. 1 ECCS - Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS-Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure S 150 psig.

ACTIONS OTI =-- - ------- - --

LCO 3.0.4.b is not applicable to HPCI.

CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS A.1 Restore low pressure ECCS 7 days injection/spray subsystem injection/spray subsystem to inoperable for reasons other OPERABLE status.

than Condition B.

B. One LPCI pump in one or B.1 Restore LPCI pump(s) to 7 days both LPCI subsystems OPERABLE status.

inoperable.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or Condition B AND not met.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

SUSQUEHANNA - UNIT 2 TS /3.5-1 Amendment 16, 195

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. HPCI System D.1 Verify by Immediately inoperable. administrative means RCIC System is OPERABLE.

AND D.2 Restore HPCI System 14 days to OPERABLE status.

E. HPCI System E.1 Restore HPCI System 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. to OPERABLE status.

AND OR Condition A or E.2 Restore low pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Condition B entered. ECCS injection/spray subsystem to OPERABLE status.

F. One ADS valve F.1 Restore ADS valve to 14 days inoperable. OPERABLE status.

G. One ADS valve G.1 Restore ADS valve to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

AND OR Condition A or G.2 Restore low pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Condition B entered. ECCS injection/spray subsystem to OPERABLE status.

(continued)

SUSQUEHANNA - UNIT 2 3.5-2 Amendment 151

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. Two or more ADS valves H.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable.

AND OR H.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action and dome pressure to associated Completion < 150 psig.

Time of Condition D.

E, F. or G not met.

I. Two Core Spray I.1 Enter LCO 3.0.3. Immediately subsystems inoperable.

OR One LPCI subsystem inoperable for reasons other than Condition B and One Core Spray subsystem inoperable.

OR Two LPCI subsystems inoperable for reasons other than Condition B.

OR HPCI System and one or more ADS valves inoperable.

SUSQUEHANNA - UNIT 2 3.5-3 Amendment 151

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray 31 days subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

SR 3.5.1.2 -------------------NOTE----------------

Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut in permissive pressure in MODE 3. if capable of being manually realigned and not otherwise inoperable.

Verify each ECCS injection/spray subsystem 31 days manual, power operated, and automatic valve in the flow path, that is not locked.

sealed, or otherwise secured in position.

and the HPCI flow controller are in the correct position.

SR 3.5.1.3 Verify ADS gas supply header pressure is 31 days 2 135 psig.

SR 3.5.1.4 Verify at least one RHR System cross tie 31 days valve is closed and power is removed from the valve operator.

SR 3.5.1.5 Verify each 480 volt AC swing bus transfers 31 days automatically from the normal source to the alternate source on loss of power.

(continued)

SUSQUEHANNA - UNIT 2 3.5-4 Amendment 151

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY I.

SR 3.5.1.6 -------------------NOTE--------------------

Not required to be performed if performed within the previous 31 days.

Verify each recirculation pump discharge Once each valve and bypass valve cycles through one startup prior complete cycle of full travel or is to exceeding de-energized in the closed position. 25% RTP SR 3.5.1.7 Verify the following ECCS pumps develop the In accordance specified flow rate against a system head with the corresponding to the specified reactor Inservice pressure. Testing Program SYSTEM HEAD NO.. CORRESPONDING OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF Core Spray a 6350 gpm 2 a 105 psig LPCI a 12.200 gpm 1 a 20 psig SR 3.5.1.8 -------------------NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure s 1060 and In accordance a 920 psig. the HPCI pump can develop a with the flow rate 2 5000 gpm against a system head Inservice corresponding to reactor pressure. Testing Program (continued)

SUSQUEHANNA - UNIT 2 3.5-5 Amendment 151

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued) -

SURVEILLANCE FREQUENCY SR 3.5.1.9 -------------------NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 5 165 psig. 24 months the HPCI pump can develop a flow rate a 5000 gpm against a system head corresponding to reactor pressure.

SR 3.5.1.10 ------------------- NOTE--------------------

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem 24 months actuates on an actual or simulated automatic initiation signal.

SR 3.5.1.11 -------------------NOTE--------------------

Valve actuation may be excluded.

Verify the ADS actuates on an actual or 24 months simulated automatic initiation signal.

SR 3.5.1.12 -------------------NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify each ADS valve opens when manually 24 months on a actuated. STAGGERED TEST BASIS for each valve solenoid kcontinueuj SUSQUEHANNA - UNIT 2 3.5-6 Amendment 151

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.13 -------------------NOTE--------------------

Instrumentation response time is based on historical response time data.

Verify the ECCS RESPONSE TIME for each ECCS 24 months injection/spray subsystem is within limit.

SUSQUEHANNA - UNIT 2 3.5-7 Amendment 151

ECCS- Shutdown 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.2 ECCS -Shutdown LCO 3.5.2 Two low pressure ECCS injection/spray subsystems shall be OPERABLE.

APPLICABILITY: MODE 4.

MODE 5. except with the spent fuel storage pool gates removed and water level a 22 feet over the top of the reactor pressure vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required ECCS A.1 Restore required ECCS 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months injection/spray injection/spray subsystem inoperable. subsystem to OPERABLE status.

B. Required Action and B.1 Initiate action to Immediately associated Completion suspend operations Time of Condition A with a potential for not met. draining the reactor vessel (OPDRVs).

C. Two required ECCS C.1 Initiate action to Immediately injection/spray suspend OPDRVs.

subsystems inoperable.

AND C.2 Restore one ECCS 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months injection/spray subsystem to OPERABLE status.

(continued)

SUSQUEHANNA - UNIT 2 3.5-8 Amendment 151

ECGS - Shutdown 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 D.1 Initiate action to Immediately and associated restore secondary Completion Time not containment to met. OPERABLE status.

AND D.2 Initiate action to Immediately restore one standby gas treatment subsystem to OPERABLE status.

AND D.3 Initiate action to Immediately restore isolation capability in each required secondary containment penetration flow path not isolated.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each required low pressure 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months coolant injection (LPCI) subsystem. the suppression pool water level is 2 20 ft 0 inches.

(continued)

SUSQUEHANNA - UNIT 2 3.5-9 Amendment 151

ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.2 Verify, for each required core spray (CS) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months subsystem, the:

a. Suppression pool water level is 2 20 ft 0 inches; or

b. -----------------NOTE-----------------

Only one required CS subsystem may take credit for this option during OPDRVs.

Condensate storage tank water level is a 49% of capacity.

SR 3.5.2.3 Verify, for each required-ECCS injection/ 31 days spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

SR 3.5.2.4 -------------------NOTE--------------------

LPCI subsystems may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.

Verify each required ECCS injection/spray 31 days subsystem manual, power operated. and automatic valve in the flow path. that is not locked, sealed, or otherwise secured in position. is in the correct position.

(continued)

SUSQUEHANNA - UNIT 2 3.5-10 Amendment 151

ECCS -Shutdown 3.5.2 SURVEILLANCE REOUTREMENTS (continued) 1 SURVEILLANCE FREQUENCY SR 3.5.2.5 Verify each required ECCS pump develops the In accordance specified flow rate against a system head with the corresponding to the specified reactor Inservice pressure. Testing SYSTEM HEAD Program I NO. CORRESPONDING OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF CS 2 6350 gpm 2 2 105 psig LPCI a 12.200 gpm 1 a 20 psig SR 3.5.2.6 -------------------NOTE--------------------

Vessel injection/spray may be excluded.

Verify each required ECCS injection/spray 24 months subsystem actuates on an actual or simulated automatic initiation signal.

SR 3.5.2.7 --- NOTE-Instrumentation response time may be assumed to be the historical instrumentation response time.

Verify the ECCS RESPONSE TIME for each ECCS 24 months injection/spray subsystem is within limit.

SUSQUEHANNA - UNIT 2 3.5-11 Amendment 151

PPL Rev. 1 RCIC System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.3 RCIC System LCO 3.5.3 The RCIC System shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.

ACTIONS

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

LCO 3.0.4.b is not applicable to RCIC.

CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System inoperable. A.1 Verify by administrative means Immediately High Pressure Coolant Injection System is OPERABLE.

AND A.2 Restore RCIC System to 14 days OPERABLE status B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

AND B.2 Reduce reactor steam dome 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months pressure to S 150 psig.

SUSQUEHANNA - UNIT 2 TS /3.5-12 Amendment ;1, 195

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled 31 days with water from the pump discharge valve to the injection valve.

SR 3.5.3.2 Verify each RCIC System manual, power 31 days operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, and the RCIC flow controller are in the correct position.

SR 3.5.3.3 -------------------NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 5 1060 psig In accordance and 2 920 psig, the RCIC pump can develop a with the flow rate a 600 gpm against a system head Inservice corresponding to reactor pressure. Testing Program SR 3.5.3.4 -------------------NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure s 165 psig. 24 months the RCIC pump can develop a flow rate 2 600 gpm against a system head corresponding to reactor pressure.

(continued)

SUSQUEHANNA - UNIT 2 3.5-13 Amendment 151

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.3.5 -------------------NOTE--------------------

Vessel injection may be excluded.

Verify the RCIC System actuates on an 24 months actual or simulated automatic initiation signal.

SUSQUEHANNA - UNIT 2 3.5-14 Amendment 151

Primary Containment 3.6.1.1 3.6 CONTAINMENT SYSTEMS 3.6.1.1 Primary Containment LCO 3.6.1.1 Primary containment shall be OPERABLE.

APPLICABILITY: MODES 1. 2. and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore primary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. containment to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SUSQUEHANNA - UNIT 2 3.6-1 Amendment 151

Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILANCE FREQUENCY I

SR 3.6.1.1.1 Perform required visual examinations and In accordance with the leakage rate testing except for primary Primary Containment containment air lock testing, in accordance Leakage Rate Testing with the Primary Containment Leakage Program.

Rate Testing Program.

SR 3.6.1.1.2 Verify that the drywell-to-suppression When performing 10 CFR chamber bypass leakage is less than 50 Appendix J, Type A 0.00535 ft2at an initial differential pressure testing, in accordance of 2 4.3 psi. with the Primary Containment Leakage Rate Testing Program.

AND

Note-------------

Only required after two consecutive tests fail and continues until two consecutive tests pass 24 months SUSQUEHANNA - UNIT 2 TSI3.6-2 Amendment h-o, 160, 171 OCT o c 2001

Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.1.3 --------------- Note-------------

Satisfied by the performance of SR 3.6.1.1.2.

Verify that the total drywell-to- 24 months suppression chamber vacuum breaker leakage is less than or equal to

.001605 ft2 and the leakage area for each set of vacuum breakers is less than or equal to .000642 ft2 at an initial differential pressure of a 4.3 psi.

SUSQUEHANNA - UNIT 2 3.6-3 Amendment 151

Primary Containment Air Lock 3.6.1.2 3.6 CONTAINMENT SYSTEMS 3.6.1.2 Primary Containment Air Lock LCO 3.6.1.2 The primary containment air lock shall be OPERABLE.

APPLICABILITY: MODES 1. 2. and 3.

ACTIONS

NOTES ------------------------------------

1. Entry and exit is permissible to perform repairs of the air lock components.

2. Enter applicable Conditions and Required Actions of LCO 3.6.1.1. "Primary Containment," when air lock leakage results in exceeding overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. One primary ------------NOTES------------

containment air lock 1. Required Actions A.1.

door inoperable. A.2, and A.3 are not applicable if both doors in the air lock are inoperable and Condition C is entered.

2. Entry and exit is permissible for 7 days under administrative controls.

A.1 Verify the OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed.

AND (continued)

SUSQUEHANNA - UNIT 2 3.6-4 Amendment 151

Primary Containment Air Lock 3.6.1.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Lock the OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months door closed.

AND A.3 -------- NOTE---------

Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.

Verify the OPERABLE Once per 31 days door. is locked closed.

B. Primary containment ------------ NOTES------------

air lock interlock 1. Required Actions B.1, mechanism inoperable. B.2. and B.3 are not applicable if both doors in the air lock are inoperable and Condition C is entered.

2. Entry into and exit from containment is permissible under the control of a dedicated individual.

B.1 Verify an OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed.

AND (continued)

SUSQUEHANNA - UNIT 2 3.6-5 Amendment 151

Primary Containment Air Lock 3.6.1.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Lock an OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed.

AND B.3 - -- NOTE---------

Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.

Verify an OPERABLE Once per 31 days door. is locked closed.

C. Primary containment C.1 Initiate action to Immediately air lock inoperable evaluate primary for reasons other than containment overall Condition A or B. leakage rate per LCO 3.6.1.1. using current air lock test results.

AND C.2 Verify a door is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months closed.

AND C.3 Restore air lock to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

(continued)

SUSQUEHANNA - UNIT 2 3.6-6 Amendment 151

Primary Containment Air Lock 3.6.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.2.1 ------------------NOTE------------------

1. An inoperable air lock door does not invalidate the previous successful erformance of the overall air lock eakage test.

2. Results shall be evaluated against acceptance criteria acceptable to SR 3.6.1.1.1.

Perform required primary containment air In accordance lock leakage rate testing in accordance with the with the Primary Containment Leakage Rate Primary Testing Program. Containment Leakage Rate Testing Program SR 3.6.1.2.2 Verify only one door in the primary 24 months containment air lock can be opened at a time.

SUSQUEHANNA - UNIT 2 3.6-7 Amendment 151

PCIVs 3.6.1.3 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)

LCO 3.6.1.3 Each PCIV shall be OPERABLE.

APPLICABILITY: MODES 1, 2. and 3.

When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1. "Primary Containment Isolation Instrumentation."

ACTIONS

NOTES ------------------------------------

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.

4. Enter applicable Conditions and I Required Actions of LCO 3.6.1.1. "Primary Containment." when PCIV leakage iresults in exceeding overall containment leakage rate acceptance criteria in MODES 1, 2. and 3.

CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE--------- A.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except Only applicable to penetration flow path for main steam penetration flow paths by use of at least line with two PCIVs except one closed and for the H2 02 Analyzer de-activated AND penetrations. automatic valve.

closed manual valve. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for main blind flange, or steam line One or more check valve with flow penetration flow paths through the valve with one PCIV secured.

inoperable except for purge valve leakage AND not within limit. (continued)

SUSQUEHANNA - UNIT 2 TS/3.6-8 Amendment 170

,,.., -, C.

2sa0I

PCIVs 3.6.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 -NOTE-Isolation devices in high radiation areas may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path for isolation is isolated. devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4. if primary containment was de-inerted while in MODE 4. if not performed within the previous 92 days. for isolation devices inside primary containment (continued)

SUSQUEHANNA - UNIT 2 3.6-9 Amendment 151

PCIVs 3.6.1.3 ACTIONS .

CONDITION REQUIRED ACTION COMPLETION TIME B --------- NOTE--------- B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path penetration flow paths by use of at least with two PCIVs except one closed and for the H2 02 Analyzer de-activated penetrations. automatic valve.

closed manual valve, or blind flange.

One or more penetration flow paths with two PCIVs inoperable except for purge valve leakage not within limit.

C --------- NOTE--------- C.1 Isolate the affected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months except Only applicable to penetration flow path for excess flow penetration flow paths by use of at least check valves with only one PCIV. one closed and (EFCVs) de-activated automatic valve. AND One or more closed manual valve, penetration flow paths or blind flange. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for with one PCIV EFCVs inoperable. AND C.2 --------NOTE---------

Isolation devices in high radiation areas may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

(continued)

SUSQUEHANNA - UNIT 2 TS/3.6-10 Amendment 170 SEP 2 8 2001

PCIVs a 3.6.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. --------- NOTE--------- D.1 Isolate the affected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Only applicable to penetration flow path the H2 02 Analyzer by the use of at penetrations. least one closed and de-activated One or more H 02 automatic valve.

Analyzer penetrations closed manual valve with one or two PCIVs or blind flange.

inoperable. AND D.2 Verify the affected Once per 31 penetration flow path days is isolated.

E. Secondary containment E.1 Restore leakage rate 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months bypass leakage rate to within limit.

not within limit.

F. One or more F.1 Restore the valve 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l penetration flow paths leakage to within with one or more valve leakage limit.

containment purge valves not within purge valve leakage limit.

G. Required Action and G.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A. AND B. C. D. E or F not met in MODE 1. 2. G.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months or 3.

H. Required Action and H.1 Initiate action to I associated Completion suspend OPDRVs. Immediately Time of Condition A.

B. C. D. E or F not OR I met for PCIV(s) required to be G.2 Initiate action to OPERABLE during restore valve(s) to MODE 4. 5 or OPERABLE status. Immediately Operations with the potential for draining the reactor vessel (OPDRVs).

SUSQUEHANNA - UNIT 2 TS/3.6-11 Amendment 170 SEP 2 8 2001

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1 ---------------- NOTES------------------

1. Only required to be met in MODES 1.

2. and 3.

2. Not required to be met when the 18 and 24 inch primary containment purge valves are open for inerting.

de-inerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.

Verify each 18 and 24 inch primary 31 days containment purge valve is closed.

4 SR 3.6.1.3.2 ------------------ NOTES-----------------7

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation 31 days manual valve and blind flange that is located outside primary containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.

(continued)

SUSQUEHANNA - UNIT 2 3.6-12 Amendment 151

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued) _

SURVEILLANCE FREQUENCY SR 3.6.1.3.3 ------------------ NOTES------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment manual Prior to isolation valve and blind flange that is entering MODE 2 located inside primary containment and or 3 from not locked, sealed, or otherwise secured MODE 4 if and is required to be closed during primary accident conditions is closed. containment was de-inerted while in MODE 4. if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity for each of the 31 days traversing incore probe (TIP) shear isolation valve explosive charge.

SR 3.6.1.3.5 Verify the isolation time of each power In operated and each automatic PCIV. except accordance for MSIVs, is within limits. with the Inservice Testing Program (continued)

SUSQUEHANNA - UNIT 2 3.6-13 Amendment 151

PPL Rev.

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.11 ----------------------------N()TES-------------------------

Only required to be met in M()DES 1, 2, and 3.

Verify the combined leakage rate for all In accordance secondary containment bypass leakage with the Primary paths is s 15 scfh when pressurized to Containment

>

Pa . Leakage Rate Testing Program.

SR 3.6.1.3.12 ----------------------------N()-rES-------------------------

Only required to be met in M()DES 1, 2, and 3.

In accordance Verify leakage rate through each MSIV is with the Primary

~1 00 scfh and 5. 300 scfh for the combined Containment leakage including the leakage from the MS Line Leakage Rate Drains when the MSIVs are tested at z 24.3 psig Testing Program.

or Pa and the MS Line Drains are tested at Pa .

(continued)

SUSQUEHANNA - UNIT 2 TS / 3.6-15 Amendment +ea, ~,231

PCIVs 3.6. 1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 1*

SR 3.6.1.3.13 -----------------NOTE------------------

Only required to be met in MODES 1. 2.

and 3.

Verify combined leakage rate through In accordance hydrostatically tested lines that with the penetrate the primary containment is Primary within limits. Containment Leakage Rate Testing Program.

SUSQUEHANNA - UNIT 2 3.6-16 Amendment 151

Containment Pressure 3.6.1.4 3.6 CONTAINMENT SYSTEMS 3.6.1.4 Containment Pressure LCO 3.6.1.4 Containment pressure shall be -1.0 to 2.0 psig.

APPLICABILITY: MODES 1. 2. and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment pressure A.1 Restore containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not within limit. pressure to within li mi t.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.4.1 Verify containment pressure is within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months limit.

SUSQUEHANNA - UNIT 2 3.6-17 Amendment 151

Drywell Air Temperature 3.6.1.5 3.6 CONTAINMENT SYSTEMS 3.6.1.5 Drywell Air Temperature LCO 3.6.1.5 Drywell average air temperature shall be < 135 0F.

APPLICABILITY: MODES 1. 2. and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell average air A.1 Restore drywell 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months temperature not within average air limit. temperature to within limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.5.1 Verify drywell average air temperature is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months within limit.

SUSQUEHANNA - UNIT 2 3.6-18 Amendment 151

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.6 3.6 CONTAINMENT SYSTEMS 3.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers LCO 3.6.1.6 Five suppression chamber-to-drywell vacuum breaker pairs shall be OPERABLE and closed, except when performing their intended function.

APPLICABILITY: MODES 1. 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One suppression A.1 Restore the vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months chamber-to-drywell breaker pair to vacuum breaker pair OPERABLE status.

inoperable for opening.

B. One suppression B.1 Verify the other 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months chamber-to-drywell vacuum break in the vacuum breaker not pair is closed.

closed.

AND B.2 Close the open vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months breaker.

C. Both Suppression C.1 Close one open vacuum 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Chamber-to-Drywell breaker in the vacuum breakers in one affected vacuum vacuum breaker pair breaker pair.

not closed.

(continued)

SUSQUEHANNA - UNIT 2 3.6-19 Amendment 151

Suppression Chamber-to-DrYwell vacuum Breakers 3.6.1.6 ACTIONS (continued)_________

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND D.2 Be inMODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCEREQUIREMENTS_________

SURVEILLANCE FREQUENCY SR 3.6.1.6.1 - --------- NOTE-7 --------

Not required to be met for vacuum breakers that are open during Surveillances.

Verify each vacuum breaker is closed. 14 days AND Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after discharge of steam to the suppression chamber from safety/relief valve (S/RV) operation.

(continued)

SUSQUEHANNA - UNIT 23620Aiden15 3.6-20 Amendment 151

1, - - :, - Z - - - - - - - I, . -

- f7 : ,- l'I

. . I SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.6.2 Perfor7 a functional tesz-c ean 3L CayVs required vacuum breaKer.

AND Aiithin 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after discharge of steam to the suppression chamber from S/RV operation AND Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months following an operation that causes any of the vacuum breakers to open SR 3.6.1.6.3 Verify :re openu .r-pirn I 24 months requirei .<\ i ._

SUSQUEHANNA - UNIT 2 TS,'3.6-2-1 Amendment 173

Suppression Pool Average Temperature 3.6.2.1 3.6 CONTAINMENT SYSTEMS 3.6.2.1 Suppression Pool Average Temperature LCO 3.6.2.1 Suppression pool average temperature shall be:

a. s 900F when any OPERABLE intermediate range monitor (IRM) channel is > 25/40 divisions of full scale on Range 7 and no testing that adds heat to the suppression ,

pool is being performed;

b. S 105OF when any OPERABLE IRM channel is > 25/40 divisions of full scale on Range 7 and testing that adds heat to the suppression pool is being performed; and

c. s 110'F when all OPERABLE IRM channels are s 25/40 divisions of full scale on Range 7.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool A.1 Verify suppression Once per hour average temperature pool average

> 900F but s 110 0F. temperature s 110 0F.

AND AND Any OPERABLE IRM A.2 Restore suppression 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months channel > 25/40 pool average divisions of full temperature to scale on Range 7. s 900F.

AND Not performing testing that adds heat to the suppression pool.

(continued)

SUSQUEHANNA - UNIT 2 3.6-22 Amendment 151

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Reduce THERMAL POWER 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion until all OPERABLE Time of Condition A IRM channels 5 25/40 not met. divisions of full scale on Range 7.

C. Suppression pool C.1 Suspend all testing Immediately average temperature that adds heat to the

> 105'F. suppression pool.

AND Any OPERABLE IRM channel > 25/40 divisions of full scale on Range 7.

AND Performing testing that adds heat to the suppression pool.

D. Suppression pool D.1 Place the reactor Immediately average temperature mode switch in the

> 110 0F. shutdown position.

AND D.2 Monitor suppression Once per pool average 30 minutes temperature.

AND D.3 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

SUSQUEHANNA - UNIT 2 3.6-23 Amendment 151

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Suppression pool E.1 Depressurize the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months average temperature reactor vessel to

> 120 0F. < 200 psig.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1.1 Verify suppression pool average 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months temperature is within the applicable limits. AND 5 minutes when performing testing that adds heat to the suppression pool SUSQUEHANNA - UNIT 2 3.6-24 Amendment 151

Suppression Pool Water Level 3.6.2.2 3.6 CONTAINMENT SYSTEMS 3.6.2.2 Suppression Pool Water Level LCO 3.6.2.2 Suppression pool water level shall be a 22 ft 0 inches and

< 24 ft 0 inches.

APPLICABILITY: MODES 1. 2. and 3.

ACTIONS _

CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool water A.1 Restore suppression 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months level not within pool water level to limits. within limits.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.2.1 Verify suppression pool water level is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months within limits.

SUSQUEHANNA - UNIT 2 3.6-25 Amendment 151

3.6.2.3 3.6 CONTAINMENT SYSTEMS 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling LCO 3.6.2.3 Two RHR suppression pool cooling subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression pool A.1 Restore RHR suppression 7 days cooling subsystem pool cooling subsystem to inoperable. OPERABLE status.

B. Two RHR suppression pool B.1 Restore one RHR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months cooling subsystems suppression pool cooling inoperable. subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SUSQUEHANNA - UNIT 2 TS / 3.6-26 Amendment No.

A-1-r, 181 JAN 1 7 2a3

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling 31 days subsystem manual. power operated, and automatic valve in the flow path that is not locked. sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.2.3.2 Verify each RHR pump develops a flow rate In accordance

> 9750 gpm through the associated heat with the exchanger while operating in the Inservice suppression pool cooling mode. Testing Program SUSQUEHANNA - UNIT 2 3.6-27 Amendment 151

RHR Suppression Pool Spray 3.6.2.4 3.6 CONTAINMENT SYSTEMS 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray LCO 3.6.2.4 Two RHR suppression pool spray subsystems shall be OPERABLE.

APPLICABILITY: MODES 1. 2. and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression A.1 Restore RHR 7 days pool spray subsystem suppression pool inoperable. spray subsystem to OPERABLE status.

B. Two RHR suppression B.1 Restore one RHR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months pool spray subsystems suppression pool inoperable. spray subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SUSQUEHANNA - UNIT 2 3.6-28 Amendment 151

RHR Suppression Pool Spray 3.6.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.4.1 Verify each RHR suppression pool spray 31 days subsystem manual. power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.2.4.2 Verify each suppression pool spray is 10 years unobstructed.

SUSQUEHANNA - UNIT 2 3.6-29 Amendment 151

PFPL Rev. 2 Not Used 3.6.3.1 3.6 CONTAINMENT SYSTEMS 3.6.3.1 NOT USED I K THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 TS / 3.6-30 Amendment 1 4F,19,<

211,

PPi_ Rev. 2 Not Used 3.6.3.1 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 TS / 3.6-31 Amendment 15@,

211,1

PPL Rev. 1 Drywell Air Flow System 3.6.3.2 3.6 CONTAINMENT SYSTEMS 3.6.3.2 Drywell Air Flow System LCO 3.6.3.2 Three required drywell cooling fan pairs shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required drywell cooling A.1 Restore required drywell 30 days fan in one or more pairs cooling fan to OPERABLE inoperable. status.

B. Two required drywell cooling B.1 Verify by administrative means 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months fans in one or more pairs that the alternate hydrogen inoperable. control function is maintained. AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND thereafter B.2 Restore one required drywell 7 days cooling fan in each required pair to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time not met.

SUSQUEHANNA - UNIT 2 TS / 3.6-32 Amendment 1 1, 195

Drywell Air Flow System 3.6.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.2.1 Operate each required drywell cooling 92 days fan at low spee for a 15 minutes.

SUSQUEHANNA - UNIT 2 3.6-33 Amendment 151

Primary Containment Oxygen Concentration 3.6.3.3 3.6 CONTAINMENT SYSTEMS 3.6.3.3 Primary Containment Oxygen Concentration LCO 3.6.3.3 The primary containment oxygen concentration shall be

< 4.0 volume percent.

APPLICABILITY: MODE 1 during the time period:

a. From 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is > 15% RTP following startup, to

b. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing THERMAL POWER to < 15% RTP prior to the next scheduled reactor shutdown.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore oxygen 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months oxygen concentration concentration to not within limit. within limit.

B. Required Action and B.1 Reduce THERMAL POWER 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated Completion to s 15% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.3.1 Verify primary containment oxygen 7 days concentration is within limits.

SUSQUEHANNA - UNIT 2 3.6-34 Amendment 151

PPL Rev. 2 Secondary Containment 3.6.4.1 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment A.1 Restore secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable in MODE 1, 2, containment to OPERABLE or 3. status. OR 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months for a one-time outage for replacement of the Reactor Building Recirculating Fan Damper Motors, to be completed by December 31, 2005.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not met.

AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SUSQUEHANNA - UNIT 2 TS / 3.6-35 Amendment 1X1, 203

PPL Rev. 2 Secondary Containment 3.6.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Secondary containment C.1 -- NOTE inoperable during movement LCO 3.0.3 is not applicable.

of irradiated fuel assemblies in the secondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuel assemblies in OPDRVs. the secondary containment.

AND C.2 Suspend CORE Immediately ALTERATIONS.

AND C.3 Initiate action to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 2 0.25 inch of vacuum water gauge.

SR 3.6.4.1.2 Verify all required secondary containment 31 days removable walls and equipment hatches required to be closed are closed and sealed.

SUSQUEHANNA - UNIT 2 TS /3.6-36 Amendment 1,%, 221, 203

PPL Rev. 2 Secondary Containment 3.6.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

NOTE----

Single door access openings between required zones within the secondary containment boundary may be opened for entry and exit.

SR 3.6.4.1.3 Verify one secondary containment access door in 31 days each access opening is closed.

SR 3.6.4.1.4 -------- NOTE--- -- ------ NOTE-----

The maximum time allowed for secondary Once every 60 months containment draw down is dependent on the testing will be performed in secondary containment configuration. three zone configuration.

Verify each standby gas treatment (SGT) 24 months on a subsystem will draw down the secondary STAGGERED TEST BASIS containment to 2 0.25 inch of vacuum water gauge in less than or equal to the maximum time allowed for the secondary containment configuration that is OPERABLE.

SR 3.6.4.1.5 ---- NOTE-----a----- ------- NOTE---

The maximum flow allowed for maintaining Once every 60 months secondary containment vacuum is dependent on testing will be performed in the secondary containment configuration. three zone configuration.

Verify each SGT subsystem can maintain 24 months on a

> 0.25 inch of vacuum water gauge in the STAGGERED TEST BASIS secondary containment for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at a flow rate less than or equal to the maximum flow rate permitted for the secondary containment configuration that is OPERABLE.

SUSQUEHANNA - UNIT 2 TS / 3.6-37 Amendment V,1, 203

SCIVs 3.6.4.2 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)

LCO 3.6.4.2 Each required SCIV shall be OPERABLE.

APPLICABILITY: MODES 1, 2. and 3.

During movement of irradiated fuel assemblies in the secondary containment.

During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS

NOTES------------------------------------

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.

CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE--------- A.1 Isolate the affected 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Only applicable to penetration flow path penetration flow paths by use of at least with two SCIVs. one closed and de-activated automatic valve.

One or more closed manual valve.

penetration flow paths or blind flange.

with one required SCIV inoperable. AND (continued)

SUSQUEHANNA - UNIT 2 3.6-38 Amend~ment 151

SCIVs 3.6.4.2 ACTIONS .

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 -------- NOTE---------

Isolation devices in high radiation areas may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

B. ---------NOTE--------- B.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to penetration flow path penetration flow paths by use of at least with two SCIVs. one closed and de-activated automatic valve.

One or more closed manual valve.

penetration flow paths or blind flange.

with two required SCIVs inoperable.

C. -------- NOTE-------- C.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to penetration flow path penetration flow paths by use of at least with only one SCIV. one closed and de-activated automatic valve.

One or more closed manual valve, penetration flow paths or blind flange.

with one required SCIV inoperable. AND (continued)

SUSQUEHANNA - UNIT 2 3.6-39 Amendment 151

SCIVs 3.6.4.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2 - - NOTE---------

Isolation devices in high radiation areas may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A. B AND or C not met in MODE 1. 2. or 3. D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. Required Action and E.1 -------- NOTE---------

associated Completion LCO 3.0.3 is not Time of Condition A. B applicable.

or C not met during movement of irradiated fuel assemblies in the Suspend movement of Immediately secondary containment, irradiated fuel during CORE assemblies in the ALTERATIONS. or during secondary OPDRVs. containment.

AND E.2 Suspend CORE Immediately ALTERATIONS.

AND E.3 Initiate action to Immediately suspend OPDRVs.

SUSQUEHANNA - UNIT 2 3.6-40 Amendment 151

SCIVs 3.6.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1 -------------- NOTES------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for SCIVs that are open under administrative controls.

Verify each required secondary 31 days containment isolation manual valve and blind flange that is required to be closed during accident conditions is closed.

SR 3.6.4.2.2 Verify the isolation time of each 92 days required automatic SCIV is within limits.

SR 3.6.4.2.3 Verify each required automatic SCIV 24 months actuates to the isolation position on an actual or simulated actuation signal.

SUSQUEHANNA - UNIT 2 3.6-41 Amendment 151

SGT System 3.6.4.3 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.

APPLICABILITY: MODES 1. 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem A.1 Restore SGT 7 days inoperable. subsystem to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND not met in MODE 1. 2, or 3. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. Required Action and ------------NOTE------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement of irradiated C.1 Place OPERABLE SGT Immediately fuel assemblies in the filter train in secondary containment. operation.

during CORE ALTERATIONS, or during QO OPDRVs.

(continued)

SUSQUEHANNA - UNIT 2 3.6-42 Amendment 151

PPL Rev. 1 SGT System 3.6.4.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1 Suspend movement of Immediately irradiated fuel assemblies in secondary containment.

AND C.2.2 Suspend CORE Immediately ALTERATIONS.

AND C.2.3 Initiate action to suspend Immediately OPDRVs.

D. Two SGT subsystems D.1 Restore one SGT subsystem 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable in MODE 1, 2, to OPERABLE status.

or 3. OR 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months for a one-time outage for replacement of the Reactor Building Recirculating Fan Damper Motors, to be completed by December 31, 2005, E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition D not met in MODE 1, 2, or 3. AND E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

SUSQUEHANNA - UNIT 2 TS / 3.6-43 Amendment 1(1, 203

PPL Rev. 1 SGT System 3.6.4.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two SGT subsystems F.A NOTE--

inoperable during movement LCO 3.0.3 is not applicable.

of irradiated fuel assemblies in the secondary containment, during CORE Suspend movement of irradiated fuel Immediately ALTERATIONS, or during assemblies in secondary OPDRVs. containment.

AND F.2 Suspend CORE Immediately ALTERATIONS.

AND F.3 Initiate action to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT filter train for > 10 continuous 31 days hours with heaters operating.

SR 3.6.4.3.2 Perform required SGT filter testing in accordance In accordance with the VFTP with the Ventilation Filter Testing Program (VFTP).

SR 3.6.4.3.3 Verify each SGT subsystem actuates on an actual 24 months or simulated initiation signal.

SR 3.6.4.3.4 Verify each SGT filter cooling bypass and outside 24 months air damper opens and the fan starts on high charcoal temperature.

SUSQUEHANNA - UNIT 2 TS I 3.6-44 Amendment l-1/, 203

PPL Rev.

RHRSW System and UHS 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW).System and the..

Ultimate Heat Sink (UHS)

LCO 3.7.1 Two RHRSW subsystems and the UHS shall be OPERABLE.

APPLICABILITY' MODES 1, 2, and 3.

ACTIONS k I/"*'lt

- - ------------------------ .l*it Enter applicable Conditions and Required Actions of LCO 3.4.8, "Residual Heat Removal (RHR)

Shutdown Cooling System-Hot Shutdown," for RHR ]

shutdown cooling made inoperable by RHRSW System.

CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE------- A.1 , Declare the associated. Immediately Separate Condition entry is RHRSW subsystems allowed for each valve. inoperable.

AND One valve in Table 3.7.1-1 A.2 Establish an open flow path to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable. the UHS.

I OR AND One valve in Table 3.7.1-2 A.3 Restore the inoperable valve(s) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months from the inoperable. to OPERABLE status. discovery of an inoperable RHRSW OR subsystem in the opposite loop from the One valve in Table 3.7.1-3 inoperable valve(s) inoperable.

AND OR 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Any combination of valves in Table 3.7.1-1, Table 3.7.1-2, or Table 3.7.1-3 in the same return loop inoperable.

(continued)

SUSQUEHANNA - UNIT 2 TS / 3.7-1 Amendment J-6i, tW, 224

RHRSW System and UHS 3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One Unit 2 RHRSW B.1 Restore the Unit 2 RHRSW 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from subsystem inoperable. subsystem to OPERABLE discovery of the status. associated Unit 1 RHRSW subsystem inoperable AND 7 days C. Both Unit 2 RHRSW C.1 Restore one Unit 2 RHRSW 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months from I subsystems inoperable. subsystem to OPERABLE discovery of one status. Unit 1 RHRSW subsystem not capable of supporting associated Unit 2 RHRSW subsystem AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I associated Completion Time not met.

AND OR D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months UHS inoperable.

SUSQUEHANNA - UNIT 2 TS/3.7-2 Amendment l-5, ., 18O DEC RD 2

PPL Rev.

RHRSW System and UHS 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY.

SR 3.7.1.1 Verify the water level is greater than or equal to 678 feet 1 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inch above Mean Sea Level.

SR 3.7.1.2 Verify the average water temperature of the UHS is: 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

a. NOTE---------- ---

Only applicable with both units in MODE 1 or 2, or with either unit in MODE 3 for less than twelve (12) hours.

< 850 F; or

b. NOTE-Only applicable when either unit has been in MODE 3 for at least twelve (12) hours but not more than twenty-four (24) hours.

< 87 0 F; or c.------------------- NOTE- -

Only applicable when either unit has been in MODE 3 for at least twenty-four (24) hours.

5 880 F.

SR 3.7.1.3 Verify each RHRSW manual, power operated, and 31 days automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.

SR 3.7.1.4 Verify that valves HV-01222A and B (the spray array bypass 92 days valves) close upon receipt of a closing signal and open upon receipt of an opening signal.

(continued) I SUSQUEHANNA - UNIT 2 TS / 3.7-3 Amendment W, 1.56 186,224

PPL Rev.

RHRSW System and UHS 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.5 Verify that valves HV-01224A1 and B1 (the large spray 92 days array valves) close upon receipt of a closing signal and open upon receipt of an opening signal.

SR. 3.7.1.6 Verify that valves HV-01224A2 and B2 (the small spray 92 days array valves) close upon receipt of a closing signal and open upon receipt of an opening signal.

SR 3.7.1.7 Verify that valves 012287A and 012287B (the spray array 92 days bypass manual valves) are capable of being opened and closed.

SUSQUEHANNA-UNIT2 TS / 3.7-3a Amendment IZO,224

PPL Rev.

RHRSW System and UHS

3.7.1 TABLE 3.7.1-1 I Ultimate Heat Sink Spray Array Valves VALVE NUMBER, VALVE DESCRIPTION HV-01224A1 Loop A large spray array valve HV-01224811 Loop B large spray array valve HV-01224A2 Loop A small spray array valve HV-01224B2 Loop B small spray array valve SUSQUEHANNA - UNIT 2 TS /3.7-3b Amendment 10,224

PPL Rev.

RHRSW System AND UHS 3.7.1 TABLE 3.7.1-2 Ultimate Heat Sink Spray Array Bypass Valves VALVE NUMBER VALVE DESCRIPTION HV-01222A Loop A spray array bypass valve .

HV-01222B Loop B spray array bypass valve SUSQUEHANNA - UNIT 2 TS / 3.7-3c Amendment 224

PPL Rev.

RHRSW System AND UHS 3.7.1 TABLE 3.7.1-3

.Ultimate Heat Sink Spray Array Bypass Manual Valves.

VALVE NUMBER VALVE DESCRIPTION 012287A Loop A spray array bypass manual valve 012287B Loop B spray array bypass manual valve SUSQUEHANNA - UNIT 2 TS / 3.7-3d Amendment 224

ESW System 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Emergency Service Water (ESW) System LCO 3.7.2 Two ESW subsystems shall be OPERABLE.

APPLICABILITY: MODES 1. 2. and 3.

ACTIONS

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

Enter applicable Conditions and Required Actions of LCO 3.8.1. "AC Sources."

for DGs made inoperable by ESW.

CONDITION REQUIRED ACTION COMPLETION TIME A. One ESW pump in each A.1 Restore both ESW 7 days subsystem inoperable. pumps to OPERABLE status.

B. One or two ESW subsystems B.1 Restore ESW flow 7 days not capable of supplying to the required ESW flow to at least three DGs to ensure required DGs. that each ESW subsystem is supplying at least three DGs.

C. One ESW subsystem C.1 Restore the ESW 7 days inoperable for reasons subsystem to other than Condition B. OPERABLE status.

(continued)

SUSQUEHANNA - UNIT 2 3.7-4 Amendment 151

ESW System 3.7.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A. B or C not AND met.

D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Both ESW subsystems inoperable for reasons other than Condition A and B.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 -------------------NOTE------------------

Isolation of flow to individual comronents does not render ESW System inoperable.

Verify each ESW subsystem manual, power 31 days operated. and automatic valve in the flow paths servicing safety related systems or components, that is not locked, sealed, or otherwise secured in position. is in the correct position.

SR 3.7.2.2 Verify each ESW subsystem actuates on an 24 months actual or simulated initiation signal.

SUSQUEHANNA - UNIT 2 3.7-5 Amendment 151

PPL Rev.

CREOAS System 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System LCO 3.7.3 Two CREOAS subsystems shall be OPERABLE.

NOTES----------------------------------------------

The control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A, One CREOAS subsystem A,1 Restore CREOAS subsystem to 7 days inoperable for reasons other OPERABLE status.

than Condition B.

B. One or more CREOAS B.1 Initiate action to implement Immediately subsystems inoperable due mitigating actions to inoperable CRE boundary in MODES 1, 2, and 3. AND B.2 Verify mitigating actions to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.

AND B.3 Restore CRE boundary to 90 days OPERABLE status.

(continued)

SUSQUEHANA - UNIT 2 TS'3.7-6 Amendment 4-7-7,232

PPL Rev.

CREOAS System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B not met AND in MODE 1,2, or3.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Required Action and --------------------NOTE--------------------

associated Completion Time LCO 3.0.3 is not applicable.

of Condition A not met during --------------------------------------------------

movement of irradiated fuel assemblies in the secondary containment, during CORE D.1 Place OPERABLE CREOAS Immediately ALTERATIONS, or during subsystem in pressurization!

OPDRVs. filtration mode.

OR D.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND D.2.2 Suspend CORE Immediately ALTERATIONS.

AND D.2.3 Initiate action to suspend Immediately OPDRVs.

E. Two CREOAS subsystems E.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, or 3 for reasons other than Condition B.

(continued)

SUSQUEHANA - UNIT 2 TS !3.7-7 Amendment +++,232

PPL Rev.

CREOAS System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREOAS subsystems --------------------NOTE--------------------

inoperable during movement LCO 3.0.3 is not applicable.

of irradiated fuel assemblies -------------------------------------------------

in the secondary containment, during CORE F.1 Suspend movement of Immediately ALTERATIONS, or during irradiated fuel assemblies in OPDRVs. the secondary containment.

OR AND One or more CREOAS F.2 Suspend CORE Immediately subsystems inoperable due ALTERATIONS.

to an inoperable CRE boundary during movement AND of irradiated fuel assemblies in the secondary F.3 Initiate action to suspend Immediately containment, during CORE OPDRVs.

ALTERATIONS, or during OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each CREOAS filter train for ~ 10 31 days continuous hours with the heaters operable.

SR 3.7.3.2 Perform required CREOAS filter testing in In accordance with the VFTP accordance with the Ventilation Filter Testing Program (VFTP).

SR 3.7.3.3 Verify each CREOAS subsystem actuates on an 24 months actual or simulated initiation signal.

(continued)

SUSQUEHANA - UNIT 2 TS / 3.7-8 Amendment -t7-7~32

PPL Rev.

CREOAS System 3.7.3 SURVEILLANCE FREQUENCY SR 3.7.3.4 Perform required CRE unfiltered air inleakage In accordance with the testing in accordance with the Control Room Control Room Envelope Envelope Habitability Program. Habitability Program SUSQUEHANA - UNIT 2 TS/3.7-9 Amendment +a-+,

232

S Control Room Floor Cooling System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Control Room Floor Cooling System LCO 3.7 4 Two control room floor cooling subsystems shall be OPERABLE.

APPLICABILITY: MODES 1. 2. and 3.

During movement of irradiated fuel assemblies in the secondary containment.

During CORE ALTERATIONS.

During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room floor A.1 Restore control room 30 days cooling subsystem floor cooling inoperable. subsystem to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND not met in MODE 1. 2.

or 3. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

SUSQUEHANNA - UNIT 2 3.7-10 Amendment 151

Control Room Floor Cooling System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and ------------ NOTE-------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A .........................

not met during movement of irradiated C.1 Place OPERABLE Immediately fuel assemblies in the control room floor secondary containment, cooling subsystem in during CORE operation.

ALTERATIONS. or during OPDRVs. O C.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND C.2.2 Suspend CORE Immediately ALTERATIONS.

AND C.2.3 Initiate action to Immediately suspend OPDRVs.

D. Two control room floor D.1 Enter LCO 3.0.3. Immediately cooling subsystems inoperable in MODE 1.

2, or 3.

(continued)

SUSQUEHANNA - UNIT 2 3.7-11 Amendment 151

Control Room Floor Cooling System 3..4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two control room floor -- NOTE-------------

cooling subsystems LCO 3.0.3 is not applicable.

inoperable during ,--

movement of irradiated fuel assemblies in the E.1 Suspend movement of Immediately secondary containment, irradiated fuel during CORE assemblies in the ALTERATIONS. or during secondary OPDRVs. containment.

AND E.2 Suspend CORE Immediately ALTERATIONS.

AND E.3 Initiate actions to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify each control room floor cooling 24 months subsystem has the capability to remove the assumed heat load.

SUSQUEHANNA UNIT 2 3.7-12 Amendment 151

Main Condenser Offgas 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Main Condenser Offgas LCO 3.7.5 The radioactivity rate of the specified noble gases measured at the motive steam jet condenser discharge shall be s 330 mCi/second.

APPLICABILITY: MODE 1.

MODES 2 and 3 with any main steam line not isolated.

ACTIONS _ _.

CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactivity rate of A.1 Restore radioactivity 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months the specified noble rate of the specified gases not within noble gases to within limit, limit.

B Required Action and B.1 Isolate all main 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion steam lines.

Time not met.

OR B.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND B.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SUSQUEHANNA - UNIT 2 3.7-13 Amendment 151

Main Condenser Offgas 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 -------------------NOTE--------------------

Not required to be performed until 31 days after any main steam line is not isolated Verify the radioactivity rate of the 31 days specified noble gases is ' 330 mCi/second. AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after a z 50% increase in the nominal steady state fission gas release after factoring out increases due to changes in THERMAL POWER level SUSQUEHANNA - UNIT 2 3.7-14 Amendment 151 U

PPL Rev.

Main Turbine Bypass System 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Main Turbine Bypass System LCO 3.7.6 The Main Turbine Bypass System shall be OPERABLE.

OR Apply the following limits for an inoperable Main Turbine Bypass System as specified in the COLR:

a. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," and

b. LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)."

APPLICABILITY: THERMAL POWER 23% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Main Turbine Bypass A.1 Satisfy the requirements of the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months System inoperable. LCO or restore Main Turbine Bypass System to OPERABLE status.

AND Requirements of LCO 3.2.2 not met.

OR Requirements of LCO 3.2.3 not met.

B. Required Action and B.1 Reduce THERMAL POWER to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion Time <ý23% RTP.

not met.

SUSQUEHANNA - UNIT 2 TS / 3.7-15 Amendment 1ZI 1.85, 1-83, 224

PPL Rev. 1 Main Turbine Bypass System 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify one complete cycle of each required main 31 days turbine bypass valve.

SR 3.7.6.2 Perform a system functional test. 24 months SR 3.7.6.3 Verify the TURBINE BYPASS SYSTEM 24 months RESPONSE TIME is within limits.

SUSQUEHANNA - UNIT 2 TS / 3.7-16 Amendment 1*1 193 193

Spent Fuel Storage Pool Water Level 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Spent Fuel Storage Pool Water Level LCO 3.7.7 The spent fuel storage pool water level shall be 2 22 ft over the top of irradiated fuel assemblies seated in the spent fuel storage pool racks.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel storage A.1 -- NOTE-.

pool water level not LCO 3.0.3 is not within limit. applicable.

Suspend movement of Immediately irradiated fuel assemblies in the spent fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify the spent fuel storage pool water 7 days level is a 22 ft over the top of irradiated fuel assemblies seated in the spent fuel storage pool racks.

SUSQUEHANNA - UNIT 2 3.7-17 Amendment 151

PPL Rev.

Main Turbine Pressure Regulation System 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Main Turbine Pressure Regulation System LCO 3.7.8 Both Main Turbine Pressure Regulators shall be OPERABLE.

OR Apply the following limits for an inoperable Main Turbine Pressure Regulator as specified in the COLR:

a. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)", and

b. LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)."

APPLICABILITY: THERMAL POWER >_23% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Main Turbine Pressure A.1 Satisfythe requirements of the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Regulator inoperable. LCO or restore Main Turbine Pressure Regulator to AND OPERABLE status.

Requirements of LCO 3.2.2 not met.

OR Requirements of LCO 3.2.3 not met.

B. Required Action and B.1 Reduce THERMAL POWER to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion Time < 23% RTP.

not met.

SUSQUEHANNA - UNIT 2 TS / 3.7-18 Amendment 224

PPL Rev.

Main Turbine Pressure Regulation System.

3.7.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify that both Main Turbine Pressure Regulators 92 days are each capable of controlling main steam pressure.

SR 3.7.8.2 Perform a system functional test. 24 months SUSQUEHANNA - UNIT 2 TS, / 3.7-19 Amendment 224

PPL Rev. AC Sources-Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE:

a. Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System; and

b. Four diesel generators (DGs).

c. Two qualified circuits between the offsite transmission network and the Unit 1 onsite Class 1 E AC electrical power distribution subsystem(s) required by LCO 3.8.7, Distribution Systems - Operating; and

d. The DG(s) capable of supplying the Unit 1 onsite Class 1 E electrical power distribution subsystem(s) required by LCO 3.8.7.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS J *VJ J *I-

1. LCO 3.0.4.b is not applicable to DGs.

2. When an OPERABLE diesel generator is placed in an inoperable status solely for the purpose of alignment of DG E to or from the Class 1E distribution system, entry into associated Conditions and Required Actions may be delayed for up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , provided both offsite circuits are OPERABLE and capable of supplying the affected 4.16 kV ESS Bus.

3. When Unit 1 is in Modes 4 or 5 and an OPERABLE Unit 1 4160V subsystem is placed in an inoperable status solely for the purpose of performing bus maintenance with both offsite circuits and four diesel generators otherwise OPERABLE, only entry into LCO 3.8.7 Condition C is required.

CONDITION REQUIRED ACTION COMPLETION TIME A. One offsite circuit A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. OPERABLE offsite circuit.

AND AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter (continued)

SUSQUEHANNA - UNIT 2 TS / 3.8-1 Amendment 15*, 1W,225

PPL Rev.

AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Declare required feature(s) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from with no offsite power available discovery of no offsite inoperable when the power to one 4.16 kV redundant required feature(s) ESS bus concurrent are inoperable. with inoperability of redundant required feature(s).

AND A.3 Restore offsite circuit to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

AND 6 days from discovery of failure to meet LCO (continued)

SUSQUEHANNA - UNIT 2 TS / 3.8-2 Amendment 131 129 202

AC S us - - -Gil- .

I . .

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 3 B. One required DG B.1 Perform SR 3.8.1.1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. for OPERABLE offsite circuits. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , thereafter AND B.2 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from feature(s). supported discovery of by the inoperable DG. Condition B inoperable when the concurrent with redundant required inoperability of feature(s) are redundant inoperable. required feature(s)

AND B.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DGs are not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.7 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for OPERABLE DGs.

OR 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to entering Condition B AND B.4 Restore required DG 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

AND 6 days from discovery of failure to meet LCO.

I I (continued)

SUSQUEHANNA - UNIT 2 3 .8-3 Amendment 151

A- C,Z)Li z: - --- = , =- - - -

1: . 1: -

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Two offsite circuits C.1 Restore one offsite 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable. circuit to OPERABLE status.

D. One offsite circuit -----------NOTE-------------

inoperable. Enter applicable Conditions and Required Actions of LCO AND 3.8.7. "Distribution Systems-Operating." when Condition D One required DG is entered with no AC power inoperable. source to any 4.16 kV ESS bus.

D.1 Restore offsite 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months circuit to OPERABLE status.

OR D.2 Restore required DG 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to OPERABLE status.

E. Two or more required E.1 Restore at least 3 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months DGs inoperable. required DGs to OPERABLE status.

F. Required Action and F.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time of Condition A. AND B. C. D. or E not met.

F.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

SUSQUEHANNA - UNIT 2 3.8-4 Amendment 151

oai s _ e .

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. One or more offsite G.1 Enter LCO 3.0.3. Immediately circuits and two or more required DGs inoperable.

OR One required DG and two offsite circuits inoperable.

SUSQUEHANNA - UNIT 2 3.8-5 Amendment 151

PC S'01'2:= t- er = -

SURVEILLANCE REOUIREMENTS

- NOTES -----------------------------------

1. Four DGs are required and a DG is only considered OPERABLE wher tne DG is aligned to the Class 1E distribution system. DG Surveillance Requirements have been modified to integrate the necessary testina to demonstrate tne availability of DG E and ensure its OPERABILITY wnen substituZed for anv other DG. Ifthe DG Surveillance Requirements. as modified by tne associated Notes. are met and performed. DG E can be considered available and OPERABLE when substituted for any other DG after performance of SR 3.8.1.3 and SR 3.8.1.7.

2. SR 3.8.1.21 establishes Surveillance Requirements for the Unit 1 AC sources required to support Unit 2.

SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and 7 days indicated power availability for each offsite circuit.

SR 3.8.1.2 Not Used.

(continued)

SUSQUEHANNA - UNIT 2 3.8-6 Amendment 151

-OU'2oi -. - -

SURVETLLANCE REOUIREMENTS (continued)

SURVEILLANCE FREQUE N

SR 3.8.1.3 -------------- NOTES-------------------

1. DG loading may include gradual loading as recommended by the manufacturer.

2. Momentary transients outside the load range do not invalidate this test.

3. This Surveillance shall be conducted on only one DG at a time.

4. This SR shall be preceded by and immediately follow. without shutdown. a successful performance of SR 3.8.1.7.

5. DG E. when not aligned to the Class lE distribution system. may satisfy this SR using the test facility.

6. A single test will-satisfy this Surveillance for both units if synchronization is to the 4.16 kV ESS bus for Unit 2 for one periodic test and synchronization is to the 4.16 kV ESS bus for Unit 1 for the next periodic test. However, if it is not possible to perform the test on Unit 1 or test performance is not required per SR 3.8.2.1. then the test shall be performed synchronized to the 4.16 kV ESS bus for Unit 2.

Verify each DG is synchronized and loaded 31 days and operates for a 60 minutes at a load 3600 kW and 5 4000 kW.

(continued)

SUSQUEHANNA - UNIT 2 3.8-7 Amendment 151

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.4 Verify each engine mounted day tank fuel oil 31 days level is 2 420 gallons for DG A-D and 2 425 gallons for DG E.

SR 3.8.1.5 Check for and remove accumulated water from 31 days each engine mounted day tank.

SR 3.8.1.6 Verify the fuel oil transfer system operates 31 days to automatically transfer fuel oil from the storage tanks to each engine mounted tank.

SR 3.8.1.7 ------------------- NOTES-------------------

1. All DG starts may be preceded by an engine prelube period.

2. A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG starts from standby condition 31 days and achieves. in 5 10 seconds, voltage 2 3793 V and frequency 2 58.8, and after steady state conditions are reached, maintains voltage 2 3793 V and 5 4400 V and frequency 2 58.8 Hz and 5 61.2 Hz.

SR 3.8.1.8 ----------------- NOTE---------------------

The automatic transfer of unit power supply shall not be performed in MODE 1 or 2.

Verify automatic and manual transfer of unit 24 months power supply from the normal offsite circuit to the alternate offsite circuit.

(continued)

SUSQUEHANNA - UNIT 2 TS / 3.8-8 Amendment No. 159 AUV 2 3 199

c lat -:e$

.Z-SURVEILLANCE REOUIREMENTS (continued)

SURVEILLANCE FR UE'IN SR 3.8.1.9 ------------- NOTE----------------------

A single test at the specified Freauencv will satisfy this Surveillance for ooth units.

Verify each DG rejects a load greater than 24 months or equal to its associated single largest post-accident load, and:

a.- Following load rejection. the frequency is 5 64.5 Hz:

b. Within 4.5 seconds following load rejection, the voltage is a 3760 V and s 4560 V. and after steady state conditions are reached. maintains voltage 2 3793 V and 5 4400 V: and

c. Within 6 seconds-following load rejection, the frequency is a 58.8 Hz and s 61.2 Hz.

SR 3.8.1.10 ------------------NOTE---------------------

A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG does not trip and voltage is 24 months maintained 5 4560 V during and following a load rejection of 2 4000 kW.

(continued)

SUSQUEHANNA - UNIT 2 3.8-9 Amendment 151

A: Scar -: - ae -

SURVEILLANCE REOUIREMENTS (continued)

SURVEILLANCE cREQUEN:'

SR 3.8.1.11 -------------------NOTES-------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not be performed in MODE 1. 2 or 3.

3. This SR shall be performed for each DG on a rotational test basis and for each 4.16 kV ESS bus at the specified FREQUENCY.

Verify on an actual or simulated loss of 24 months offsite power signal:

a. De-energization of 4.16 kV ESS buses:

b. Load shedding from 4.16 kV ESS buses:

and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in 5 10 seconds.

2. energizes auto-connected shutdown loads through individual load timers.

3. maintains steady state voltage 2 3793 V and s 4400 V.

4. maintains steady state frequency 2 58.8 Hz and s 61.2 Hz. and

5. supplies permanently connected loads for a 5 minutes.

(continued)

SUSQUEHANNA - UNIT 2 3.8-10 Amendment 151

SURVEILLANCE REOUIREMENTS (continued)

SURVEILLANCE . F2. OUEN '

SR 3.8.1.12 -------------------NOTES-------------------

1. All DG starts may be preceded by an engine prelube period.

2. DG E. when not aligned to the Class lE distribution system. may satisfy this SR for both units by performance of SR 3.8.1.12.a. b and c using the test facility to simulate a 4.16 kV ESS bus.

SR 3.8.'.12.d and e may be satisfied with either the normally aligned DG or DG E aligned to the Class IE distribution system.

Verify, on an actual or simulated Emergency 24 months Core Cooling System (ECCS) initiation signal, each DG auto-starts from standby condition and:

a. In s 10 seconds after auto-start achieves voltage 2 3793 V. and after steady state conditions are reached.

maintains voltage a 3793 V and 4400 V:

b. In 5 10 seconds after auto-start achieves frequency 2 58.8 Hz. and after steady state conditions are reached.

maintains frequency a 58.8 Hz and s 61.2 Hz:

c. Operates for a 5 minutes:

d. Permanently connected loads remain energized from the offsite power system: and

e. Emergency loads are energized or auto-connected through the individual load timers from the offsite power system.

(continued)

SUSQUEHANNA - UNIT 2 3. 8-11 Amendment 151

i#-,' - ~-.- -. z.

SURVEILLANCE REOUIREMENTS (continued)

SURVEILLANCE FREQU EN C SR 3.8.1.13 ------------------ NOTES--------------------

1. A single test at the specified Frequency will satisfy this Surveillance for both units.

2. DG E when not aligned to the Class lE distribution system may satisfy this SR by using a.simulated ECCS initiation signal.

Verify each DG's automatic trips are 24 months bypassed on actual or simulated loss of voltage signal on the 4.16 kV ESS bus concurrent with an actual or simulated ECCS initiation signal except:

a. Engine overspeed; and

b. Generator differential current; and

c. Low lube oil pressure.

(continued)

SUSQUEHANNA - UNIT 2 3.8-12 Amendment 151

SURVEILLANCE REOUIREMENTS (cont-Inued)

SURVEILLANCE FREQUENag SR 3.8.1.14 -------------------NOTES-------------------

1. Momentary transients outside the load ranges do not invalidate this test.

2. A single test at the specified Frequency will satisfy this Surveillance for both units.

3. DG E when not aligned to the Class 1E distribution system may satisfy this SR using the test facility.

Verify each DG operates for 2 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s: 24 months

a. For 2 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded a 4400 kW and s 4700 kW for DGs A through D and 2 5000 kW and s 5500 kW for DG E; and

b. For the remaining hours of the test loaded 2 3600 kW and s 4000 kW for DGs A through D and a 4500 kW and s 5000 kW for DG E.

(continued)

SUSQUEHANNA - UNIT 2 3.8-13 Amendment 151

o At-SC) Z - T I- .:Z.

[URVETILANCE REOUIREMENTS (continued)

SURVEILLANCE K 0 UE C@'

1' SR 3.8.1.15 - ---- NOTES-------------------

1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated 2 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 2 3800 kW.

Momentary transients outside of load range do not invalidate this test.

2. All DG starts may be preceded by an engine prelube period.

3. A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG starts and achieves, in 24 months s 10 seconds. voltage.?-3793 V and frequency a 58.8 and after steady state conditions are reached, maintains voltage a 3793 V and s 4400 V and frequency a 58.8 Hz and s 61.2 Hz.

(continued)

SUSQUEHANNA - UNIT 2 3.8-14 Amendment 151

I - - ,-.- -

SURVEILLANCE REOUIREMENTS (continued) 1*

SURVEILLANCE FRE Q'u r, 4.

SR 3.8.1.16 ------------------NOTE--------------------

This SR shall be performed for each DG on a rotational basis and for each 4.16 kV ESS bus at the specified FREQUENCY.

Verify each DG: 24 months

a. Synchronizes with offsite power source while loaded with emergency loads upon a simulated restoration of offsite power;

b. Transfers loads to offsite power source: and

c. Returns to ready-to-load operation.

(continued)

SUSQUEHANNA - UNIT 2 3 .8-15 Amendment 151

A,^ Souce - - -r

-ac-SURVEILLANCE REOUIREMENTS (continued)

SURVEILLANCE 1 FRE0UE N'N SR 3.8.1.17 ------------- NOTES--------------------

This SR shall be performed for each DG on a rotational basis and for each 4.16 kV ESS bus at the specified FREQUENCY.

Verify with a DG operating in test mode and 24 montns connected to its bus. an actual or simulated ECCS initiation signal overrides the test mode by:

a. Returning DG to ready-to-load operation: and

b. Automatically energizing the emergency load from offsite power.

SR 3.8.1.18 -------------------NOTE-------------------

Load timers associated with equipment that has automatic initiation capability disabled are not required to be OPERABLE.

Verify each sequenced load is within 24 months required limits of the design interval.

(continued)

SUSQUEHANNA - UNIT 2 3.8-16 Amendment 151

A SouzesZ -

- Z-SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQU' NC'

+

SR 3.8.1.19 ------------------ NOTES-------------------

1. All DG starts may be preceded by an engine prelube period.

2. This SR shall be performed for each DG on a rotational test basis and for each 4.16 kV ESS bus at the specified FREQUENCY.

3. This Surveillance shall not be performed in MODE 1. 2 or 3.

Verify on an actual or simulated loss of 24 months offsite power signal in conjunction with an actual or simulated ECCS initiation signal:

a. De-energization of 4.16 kV ESS buses:

b. Load shedding from emergency buses: and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in < 10 seconds.

2. energizes auto-connected emergency loads through individual load timers.

3. achieves steady state voltage k -3793 V and < 4400 V.

4. achieves steady state frequency

58.8 Hz and 5 61.2 Hz. and

5. supplies permanently connected and auto-connected emergency loads for

' 5 minutes.

(continued)

SUSQUEHANNA - UNIT 2 3.8-17 Amendment 151

A.: SOu' _ _ _ _ . _

.Z.

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQU'ENZ SR 3.8.1.20 ---------- NOTES---------------------

1. All DG starts may be preceded by an engine prelube period.

2. This SR must be met. but does not have to be performed with DG E substituted for any DG.

Verify, when started simultaneously from 10 years standby condition, each DG achieves, in

10 seconds, voltage a 3793 V and frequency

58.8 and after steady state conditions are reached, maintains voltage a 3793 V and s 4400 V and frequency 2 58.8 Hz and s 61.2 Hz.

SR 3.8.1.21 --------------- NOTE--------------------

When Unit 1 is in MODE 4 or 5, or moving irradiated fuel assemblies in the secondary containment, the Note to Unit 1 SR 3.8.2.1 is applicable.

For required Unit 1 AC sources, the In accordance following SRs of Unit 1 Specification 3.8.1 with are applicable: applicable SRs SR 3.8.1.1; SR 3.8.1.10; SR 3.8.1.3: SR 3.8.1.11:

SR 3.8.1.4: SR 3.8.1.14:

SR 3.8.1.5: SR 3.8.1.15:

SR 3.8.1.6: SR 3.8.1.16:

SR 3.8.1.7: SR 3.8.1.18:

SR 3.8.1.9: SR 3.8.1.19:

and SR 3.8.1.8 (when more than one Unit 1 offsite circuit is required)

SUSQUEHANNA - UNIT 2 3.8-18 Amendment 151

PPL Rev.

AC Sources-Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources-Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, Distribution Systems-Shutdown"; and

b. Two diesel generators (DGs) capable of supplying the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.

c. One qualified circuit between the offsite transmission network and the Unit 1 onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, Distribution Systems-Shutdown; and

d. The DG(s) capable of supplying the Unit 1 onsite Class 1E electrical power distribution subsystem(s) required by LCO 3.8.8.

APPLICABILITY: MODES 4 and 5 During movement of irradiated fuel assemblies in the secondary containment.

SUSQUEHANNA - UNIT 2 T S /3.8-19 Amendment ldl 2021

A'- S'ouraeS - - D ACTIONS

-LC- -i

- -a-p-p-l-i-c-a---------------------------

.0.3 NOTEe-.---

LCO 3.0.3 is notlapplicable.

CONDITION l REQUIRED ACTION COMPLETION TIME A. One or more required ------------NOTE-------------

AC Sources inoperable. Enter applicable Condition and Required Actions of LCO 3.8.8. with one required subsystem de-energized as a result of Condition A.

A.1 Declare affected Immediately required feature(s) inoperable.

AD VI%

A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND A.2.3 Initiate action to Immediately suspend operations with a potential for draining the reactor vessel (OPDRVs).

AND A.2.4 Initiate action to Immediately restore required AC Source to OPERABLE status.

J ___________________________________________________

SUSQUEHANNA - UNIT 2 3.8-20 Amendment 151

A:. S ' L - _ e z -_S r -:

z; -

I . _ . _

SURVEILLANCE REOUIREMENTS SURVEILLANCE FRcUEN2FZ SR 3.8.2.1 - ----- NOTE------

The following SRs must be met but are not required to be performed:

SR 3.8.1.3: SR 3.8.1.14:

SR 3.8.1.9: SR 3.8.1.15:

SR 3.8.1.10; SR 3.8.1.16:

SR 3.8.1.11: SR 3.8.1.18; and SR 3.8.1.13: SR 3.8.1.19.

For required Unit 2 AC sources, the In accordance following SRs of Unit 2 Specification 3.8.1 with applicable are applicable: SRs SR 3.8.1.1; SR 3.8.1.11:

SR 3.8.1.3; SR 3.8.1.12:

SR 3.8.1.4: SR 3.8.1.13:

SR 3.8.1.5: SR 3.8.1.14:

SR 3.8.1.6: SR 3.8.1.15:

SR 3.8.1.7: SR 3.8.1.16:

SR 3.8.1.9: SR 3.8.1.18: and SR 3.8.1.10: SR 3.8.1.19.

(continued)

SUSQUEHANNA - UNIT 2 3.8-21 Amendment 151

A,' S 0 U,es-' - Sen, -- z: ),%

n,. ':. . - -

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENC\

.9.

SR 3.8.2.2 ----------------NOTE------------------

When Unit 1 is in MODE 4 or 5. the Note to Unit 1 SR 3.8.2.1 is applicable for the performance of required Unit 1 SRs.

For required Unit 1 AC sources. the following SRs of Unit 1 Specification 3.8.1 are applicable:

SR 3.8.1.1; SR 3.8.1.10: In accordance SR 3.8.1.3: SR 3.8.1.11: with applicable SR 3.8.1.4: SR 3.8.1.14; SRs SR 3.8.1.5: SR 3.8.1.15:

SR 3.8.1.6: SR 3.8.1.16:

SR 3.8.1.7: SR 3.8.1.18:

SR 3.8.1.9 SR 3.8.1.19:

and SR 3.8.1.8 (when more than one Unit 1 offsite circuit is required).

.5. ____________________________

SUSQUEHANNA - UNIT 2 3.8-22 Amendment 151

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air LCO 3.8.3 The stored diesel fuel oil, lube oil, and starting air subsystems shall be within limits for each required diesel generator (DG).

APPLICABILITY: When associated DG is required to be OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each DG.

CONDITION REQUIRED ACTION COMPLETION TIME

.4 .4 A. One or more DGs with A.1 Restore fuel oil 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months fuel oil level in level to within associated storage limits.

tank < 47,570 gallons and > 41,018 gallons for DG A-D;

< 60,480 gallons and

> 52,340 gallons for DG E.

B. One or more DGs with B.1 Declare associated DG Immediately lube oil sump level inoperable.

not visible in the sight glass.

(continued)

SUSQUEHANNA - UNIT 2 TS / 3.8-23 Amendment TsT, 157 JUL 0 7 1999

Diesel Fuel Oil. Lube Oil, and Starting Air

.3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more DGs with C.1 Restore stored fuel 7 days stored fuel oil total oil total particulates not particulates to within limits. within limits.

D. One or more DGs with D.1 Restore stored fuel 30 days new fuel oil oil properties to properties not within within limits.

limits.

E. One or more DGs with E.1 Restore starting air 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months one or more starting receiver pressure to air receiver pressures 2 240 psig.

< 240 psig and

180 psig.

F. Required Action and F.1 Declare associated DG Immediately associated Completion inoperable.

Time of Condition A.

B. C. D or E not met.

OR One or more DGs with diesel fuel oil. lube oil, or starting air not within subsystem limits for reasons other than Condition A. B. C. D or E.

SUSQUEHANNA - UNIT 2 3.8-24 Amendment 151

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage tank contains 31 days

Ž 47,570 gallons for DG A-D; 2 60,480 gallons for DG E. I SR 3.8.3.2 Verify lube oil sump level is visible in the 31 days sight glass.

SR 3.8.3.3 Verify fuel oil properties of new and stored In accordance fuel oil are tested in accordance with, and with the maintained within the limits of, the Diesel Diesel Fuel Fuel Oil Testing Program. Oil Testing Program SR 3.8.3.4 -------------------- NOTE-------------------

Not required to be met when DG is operating.

Verify each DG air start receiver pressure 31 days is Ž 240 psig.

SR 3.8.3.5 Check for and remove accumulated water from 31 days each fuel oil storage tank.

SUSQUEHANNA - UNIT 2 TS / 3.8-25 Amendmenst,, 157 JUL 1S9

PPL Rev.

DC Sources-Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources-Operating LCO 3.8.4 The DC electrical power subsystems in Table 3.8.4-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE-----------

Not applicable to DG E DC electrical power system One Unit 2 battery A.1 Restore battery terminal 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months charger on one 125 VDC voltage to greater than or electrical power equal to the minimum subsystem inoperable. established float voltage.

One Unit 2 battery charger on 250 VDC Division II electrical power subsystem A.2 Verify battery float current s 2 Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable. amps.

AND Two Unit 2 battery A.3 Restore battery charger(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months chargers on 250 VDC OPERABLE Status.

Division 1 electrical power subsystem inoperable.

(conti nued)

SUSQUEHANNA - UNIT 2 TS / 3.8-26 Amendment +a+227

PPL Rev.

DC Sources-Operating 3.8.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. -------------NOTE-----------

Not applicable to DG E DC electrical power system One Unit 2 125 VDC B.1 Restore battery bank to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months battery bank inoperable. OPERABLE status.

OR One Unit 2 250 VDC battery bank inoperable.

C. ------------NOTE----------- C.1 Restore Unit 2 DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Not applicable to DG E power subsystem to DC electrical power OPERABLE status.

subsystem.

One Unit 2 DC electrical power subsystem inoperable for reasons other than Conditions A or B.

D. Two or more Unit 2 D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months subsystems inoperable.

OR AND Required Action and D.2 Be in MODE 4 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Associated Completion Time of Conditions A, B or C not met.

(continued)

SUSQUEHANNA - UNIT 2 TS / 3.8-26a Amendment 227

PPL Rev.

DC Sources-Operating 3.8.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Diesel Generator E DC E.1 Verify that all ESW 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power valves associated with subsystem inoperable, Diesel Generator E are when not aligned to the closed.

Class 1E distribution system.

F. Diesel Generator E DC F.1 Declare Diesel 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power Generator E inoperable.

subsystem inoperable, when aligned to the Class 1E distribution system.

G. One or more Unit 1 DC G.1 Transfer associated 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power Unit 1 and common subsystem(s) loads to corresponding inoperable. Unit 2 DC electrical power subsystem.

AND G.2 Restore Unit 1 and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after Unit 1 DC common loads to electrical power subsystem is corresponding Unit 1 restored to OPERABLE status.

DC electrical power subsystem.

H. Required Actions and H.1 Declare associated Immediately associated Completion common loads Times of Condition E not inoperable.

met.

SUSQUEHANNA - UNIT 2 TS / 3.8-27 Amendment +&+,227

PPL Rev. 2 DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater than or 7 days equal to the minimum established float voltage.

SR 3.8.4.2 Verify each required battery charger supplies its 24 months associated battery at the following rates for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at greater than or equal to the minimum established float voltages:

a) _ 100 amps for the 125V Battery b) _300 amps for the 250V Battery c) _200 amps for the125V Diesel Generator E Battery

. ...... _ _(continued)

SUSQUEHANNA - UNIT 2 TS /G.8-28 Amendment 10, 21ý, 21.5

PPL Rev. 2 DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.3 --------------- NOTES -------------

1. The modified performance discharge test in SR 3.8.6.6 may be performed in lieu of SR 3.8.4.3.

2. This Surveillance shall not be Performed in Mode 1, 2 or 3 except for the Diesel Generator E DC electrical power subsystem.

This Surveillance can be performed on the Diesel Generator E DC electrical power subsystem when the Diesel Generator E is not aligned to the Class 1E distribution system. However, credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, 24 months and maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.

SR 3.8.4.4 --------------------------- NOTE -------------- I When Unit 1 is in MODE 4 or 5, or moving irradiated fuel assemblies in the secondary containment, the Note to Unit 1 SR 3.8.5.1 is applicable.

For required Unit 1 DC electrical power In accordance with subsystems, the SRs for Unit 1 Specification applicable SRs 3.8.4 are applicable.

SUSQUEHANNA UNIT 2 TS / 3.8-29 Amendment 10, 2p, 215

PPL Rev.

DC Sources-Operating 3.8.4 Table 3.8.4-1 (page 1 of 1)

Unit 2 and DG E DC Electrical Power Subsystems VOLTAGE DIVISION I DIVISION II 250 V 2D650 (Battery Bank) 2D660 (Battery Bank) 2D653A (Charger) 2D663 (Charger) or 2D653B (Charger) 125 V Unit 1 Subsystem A Unit 1 Subsystem B 1D610 (Battery Bank A) 1D620 (Battery Bank B) 1D613 (Charger A) 1D623 (Charger B)

Unit 2 Subsystem A Unit 2 Subsystem B 2D610 (Battery Bank A) 2D620 (Battery Bank B) 2D613 (Charger A) 2D623 (Charger B)

Unit 1 Subsystem C Unit 1 Subsystem D 1D630 (Battery Bank C) 1D640 (Battery Bank D) 1D633 (Charger C) 1D643 (Charger D)

Unit 2 Subsystem C Unit 2 Subsystem D 2D630 (Battery Bank C) 2D640 (Battery Bank D) 2D633 (Charger C) 2D643 (Charger D) 125 V OD595 (Battery Bank E)

OD596 (Charger)

SUSQUEHANNA - UNIT 2 TS / 3.8-30 Amendment 1-61, 2-+a, 227

PPL Rev. 2 DC Sources-Operating 3.8.4 SUSQUEHANNA - UNIT 2 TS / 3.8-31 Amendment 1V, ZL5

PPL Rev. 2 DC Sources-Operating 3.8.4 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 TS / 3.8-32 Amendment 15/, 215 N

PPL Rev. 2 DC Sources-Operating 3.8.4 SUSQUEHANNA - UNIT 2 TS'/3.8-33 Amendment 15/, 215

DC Sources - Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources -Shutdown LCO 3.8.5 DC electrical power subsystems listed in Table 3.8.4-1 shall be OPERABLE as needed to support the DC electrical power distribution subsystem(s) required by LCO 3.8.8.

"Distribution Systems - Shutdown."

APPLICABILITY: MODES 4 and 5.

During movement of irradiated fuel assemblies in the secondary containment.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE--------- A.1 Declare affected Immediately Not applicable to DG E required feature(s)

DC electrical power inoperable.

subsystem.

OR One or more required A.2.1 Suspend CORE Immediately Unit 2 DC electrical ALTERATIONS.

power subsystems inoperable. AND (continued)

SUSQUEHANNA - UNIT 2 3.8-34 Amendment 151

DC Sources - Shutdown 3.8.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND A.2.3 Initiate action to Immediately suspend operations wit a potential for draining the reactor vessel.

AND A.2.4 Initiate action to Immediately restore required Unit 2 DC electrical power subsystems to OPERABLE status.

B. Diesel Generator E DC B.1 Verify that all ESW 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power valves associated subsystem inoperable, with Diesel Generator while not aligned to E are closed.

the Class lE distribution system.

C. Diesel Generator E DC C.1 Declare Diesel 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power Generator E subsystem inoperable, inoperable.

while aligned to the Class lE distribution system.

(continued)

SUSQUEHANNA - UNIT 2 3.8-35 Amendment 151

DC Sources - Shutdown 3.8.5 ACTIONS (continued)

CONDITION] REQUIRED ACTION COMPLETION TIME D. --------- NOTE--------- D.1 Declare affected Immediately Not applicable to DG E required feature(s)

DC electrical power inoperable subsystem.

OR One or more inoperable D.2.1 Suspend CORE Immediately required Unit 1 DC ALTERATIONS.

electrical power subsystem.

AND D.2.2 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND D.2.3 Initiate action to Immediately suspend operations with a potential for draining the vessel.

AND D.2.4 Initiate action to Immediately restore required DC electrical power subsystems to OPERABLE status.

IOR (continued)

SUSQUEHANNA - UNIT 2 3.8-36 Amendment 151

DC Sources - Shutdown 3.8.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (Continued) D.3.1 Initiate action to Immediately transfer Unit 1 and common loads to corresponding Unit 2 DC electrical power subsystem.

AND D.3.2.1 Restore Unit 1 and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after common loads to Unit 1 DC corresponding Unit 1 electrical power DC electrical power subsystem is subsystems. restored to OPERABLE status.

OR D.3.2.2 Declare associated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after Unit 1 and common Unit 1 DC loads inoperable. electrical power subsystem is restored to OPERABLE status.

SUSQUEHANNA - UNIT 2 3.8-37 Amendment 151

PPL Rev. 1 DC Sources-Shutdown 3.8.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 The following SRs must be met, but are not required to be performed: SR 3.8.4.2 and SR 3.8.4.3. I For DC sources required to be OPERABLE the In accordance with applicable following SRs are applicable: SRs SR 3.8.4.1 I SR 3.8.4.2 I SR 3.8.4.3 SR 3.8.5.2 NOTE-----------------------

When Unit 1 is in MODE 4 or 5, or moving irradiated fuel assemblies in the secondary containment, the Note to Unit 1 SR 3.8.5.1 is applicable.

For required Unit 1 DC electrical power In accordance with applicable subsystems, the SRs for Unit 1 Specification 3.8.4 SRs are applicable.

SUSQUEHANNA - UNIT 2 TS / 3.8-38 Amendment 1V, 215

PPL Rev. 1 Battery Parameters

.3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Parameters I I

LCO 3.8.6 Battery parameters for the Class 1 E 250 V batteries and Class 1E 125 V batteries shall be within limits.

APPLICABIL .ITY: When associated DC electrical power subsystems are required to be OPERABLE.

ACTIONS

---- NOT t--- -- -- -- -- ------- -- -- -- -- -- -- -- -- -- -- -- -- -- -- -- -- -- -- -- -- -- ----

Separate Condition entry is allowed for each batti CONDITION REQUIRED ACTION COMPLETION TIME A. One 125 VDC electrical A.1 Perform SR 3.8.4.1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months power subsystem or-one 250 VDC electrical power AND subsystem with one or more battery cells float voltage A.2 Perform SR 3.8.6.1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

< 2.07 V.

AND A.3 Restore affected cell voltage 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

> 2.07 V.

(continued)

SUSQUEHANNA - UNIT 2 TS / 3.8-39 Amendment 15/, a5

PPL Rev. 1 Battery Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One 125 VDC electrical B.1 Perform SR 3.8.4.1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months power subsystem or one.

250 VDC electrical power AND subsystem with float current

> 2 amps. B.2 Restore battery Iloat current to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

_< 2 amps C. ------ NOTE----- -------------------- NOTE ------------------

Required Action C.2 shall be Required Actions C.1 and C.2 are completed if electrolyte level only applicable if electrolyte level was below the top of plates. was below the top of plates.

One 125 VDC electrical C.1 Restore electrolyte level to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months power subsystem or one above top of plates.

250 VDC electrical power subsystem with one or more AND cells electrolyte level less than minimum established design limits.

C.2 Verify no evidence of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months leakage.

AND C.3 Restore electrolyte level to 31 days greater than or equal to minimum established design limits.

(continued)

SUSQUEHANNA - UNIT 2 TS / 3.8-40 Amendment 1ý 1 215

PPL Rev. 1 Battery Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One 125 VDC electrical D.1 Restore battery pilot cell 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months power subsystem or one temperature to greater 250 VDC electrical power than or equal to minimum subsystem with pilot cell established design limits.

electrolyte temperature less than minimum established design limits.

E. Two 125 VDC electrical E.1 Restore battery 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months power subsystems or both parameters for batteries in 250 VDC electrical power one 125 VDC electrical subsystems with battery power subsystem or one parameters not within limits. 250 VDC electrical power subsystem to within limits.

F. Required Action and F.1 Declare associated battery Immediately associated Completion inoperable.

Time of Condition A, B, C, D, or E not met.

OR One battery on one 125 VDC electrical power subsystem or on one 250 VDC electrical power subsystem with one or more battery cells float voltage

< 2.07 V and float current

> 2 amps.

SUSQUEHANNA- UNIT 2 TS / 3.8-41 Amendment 1ý 1215

PPL Rev. 1 Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1

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

Not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1.

Verify each battery float current is < 2 amps. 7 days SR 3.8.6.2 Verify each battery pilot cell voltage is Ž_2.07 V. 31 days SR 3.8.6.3 Verify each battery connected cell electrolyte 31 days level is greater than or equal to minimum established design limits.

SR 3.8.6.4 Verify each battery pilot cell temperature is 31 days greater than or equal to minimum established design limits.

(continued)

SUSQUEHANNA - UNIT 2 TS / 3.8-42 Amendment 4, 45

PPL Rev. 1 Battery Parameters I 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.5 Verify each battery connected cell voltage is 92 days

_2.07 V.

SR 3.8.6.6 ------------------------- NOTE ---------------

This Surveillance shall not be Performed in Mode 1, 2, or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is _>80% of the 60 months manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test. AND 12 months when battery shows degradation or has reached 85% of expected service life with capacity

<100% of manufacturer's rating AND 24 months when battery has reached 85% of the expected service life with capacity Ž_100% of manufacturer's rating SUSQUEHANNA - UNIT 2 TS / 3.8-43 Amendment 14,215

PPL Rev. 2 Distribution Systems-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 The electrical power distribution subsystems in Table 3.8.7-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------- NOTE --------------- ---------------- Note----------------

Not applicable to DG E DC Enter applicable Conditions and Bus OD597 Required Actions of LCO 3.8.4, "DC Sources - Operating," for DC source(s) made inoperable One or more Unit 2 AC by inoperable power distribution electrical power distribution subsystem(s).

subsystems inoperable.

A.1 Restore Unit 2 AC electrical 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months power distribution subsystem(s) to OPERABLE status. AND 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO 3.8.7 except for Condition ForG B. ---------------NOTE-------------- B.1 Restore Unit 2 DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Not applicable to DG E DC power distribution subsystem(s)

Bus OD597 to OPERABLE status. AND One or more Unit 2 DC 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from electrical power distribution discovery of failure to subsystems inoperable. meet LCO 3.8.7 except for Condition ForG C. One Unit 1 AC electrical C.1 Restore Unit 1 AC electrical 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months power distribution power distribution subsystem to subsystem inoperable. OPERABLE status.

(continued)

SUSQUEHANNA - UNIT 2 TS / 3.8-44 Amendment W, 28 l 208,

PPL Rev. 2 Distribution Systems-Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two Unit 1 AC electrical D.1 Restore at lease one Unit 1 AC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months power distribution electrical power distribution subsystems on one Division subsystems to OPERABLE inoperable for performance status.

of Unit 1 SR 3.8.1.19.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I Associated Completion Time of Condition A, B or C not AND met.

E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months I F. Diesel Generator E DC F.1 Verify that all ESW valves 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months I electrical power subsystem associated with Diesel inoperable, while not aligned Generator E are closed.

to the Class 1E distribution system.

G. Diesel Generator E DC G.1 Declare Diesel Generator E 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months I electrical power subsystem inoperable.

inoperable, while aligned to the Class 1E distribution system.

H. Two or more electrical H.1 Enter LCO 3.0.3. Immediately I power distribution subsystems inoperable that result in a loss of safety function.

(continued)

SUSQUEHANNA - UNIT 2 TS / 3.8-45 Amendment 1.51 I 208,

PPL Rev. 2 Distribution Systems-Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. ----------------NOTE------------ 1.1 Transfer associated Unit 1 and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months I Not applicable to DG E DC common loads to Bus OD597 corresponding Unit 2 DC

- ------ electrical power distribution subsystem.

One or more Unit 1 DC electrical power distribution subsystem(s) inoperable.

AND 1.2 Restore Unit 1 and common 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after Unit 1 l loads to corresponding Unit 1 DC electrical power DC electrical power subsystem is distribution subsystem. restored to OPERABLE status.

J. Required Actions and J.1 Declare associated common Immediately I associated Completion loads inoperable.

Times of Condition I not I met.

SUSQUEHANNA - UNIT 2 3.8-46 Amendment 151, 208

Distribution Systems -Operating 3.8.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct breaker alignments and 7 days voltage or indicated power availability to required AC and DC electrical power distribution subsystems.

SUSQUEHANNA - UNIT 2 3.8-47 Amendment 151

Distribution Systems - Operating 3.037 Table 3.8.7-1 (page 1 of 2)

Unit 2 AC and DC Electrical Power Distribution Subsystems TYPE VOLTAGE DIVISION I DIVISION II AC Buses 4160 V lA201 (Subsys. A) 1A202 (Subsys. 0)

Load Groups: IA203 (Subsys. C) 1A204 (Subsys. D) 2A201 (Subsys. A) 2A202 (Subsys. B) 2A203 (Subsys. C) 2A204 (Subsys. D) 480 V 18210 (Subsys. A) 18220 (Subsys. B)

Load Centers: 18230 (Subsys. C) 1240 (Subsys. D) 2B210 (Subsys. A) 28220 (Subsys. B) 2B230 (Subsys. C) 28240 (Subsys. D) 4B0 V 0B516 (Subsys. A) OB526 (Subsys. B)

Motor Control OBS17 (Subsys. A) 06527 (Subsys. B)

Centers: lB216 (Subsys. A) 18226 (Subsys. 0) 18217 (Subsys. A) 1B227 (Subsys. B)

OB536 (Subsys. C) OB546 (Subsys. 0)

OB136 (Subsys. C) 0B146 (Subsys. 0) 18236 (Subsys. C) 1B246 (Subsys. 0) 2B216 (Subsys. A) 28246 (Subsys. D) 2B236 (Subsys. C) 28247 (Subsys. D) 28237 (Subsys. C) 2B226 (Subsys. B) 2B217 (Subsys. A) 2B227 (Subsys. B) 208/120 V lY216 (Subsys. A) 1Y226 (Subsys, B)

Distribution 1Y236 (Subsys. C) 1Y246 (Subsys. D)

Panels: 2Y216 (Subsys. A) 2Y226 (Subsys. B) 2Y236 (Subsys. C) 2Y246 (Subsys. D)

(continued)

SUSQUEnANNA - UNIT 2 3.8-48 Amendment 151 CD1LOC Qftut&L0 to -zt -98

Distribution Systems -Operating 3.8.7 Table 3.8.7-1 (page 2 of 2)

Unit 2 AC and DC Electrical Power Distribution Subsystems TYPE VOLTAGE DIVISION I DIVISION II DC Buses 250 V Buses 2D652 2D662 2D254 2D264 2D274 125 V Buses 1D612 (Subsys. A) 1D622 (Subsys. B) 1D614 (Subsys. A) 1D624 (Subsys. B) 1D632 (Subsys. C) 1D642 (Subsys. D) 1D634 (Subsys. C) 1D644 (Subsys. D) 2D612 (Subsys. A) 2D622 (Subsys. B) 2D614 (Subsys. A) 2D624 (Subsys. B) 2D632 (Subsys. C) 2D642 (Subsys. D) 2D634 (Subsys. C) 2D644 (Subsys. D)

DG E DC Bus 125 V Bus 0D597 SUSQUEHANNA - UNIT 2 3.8-49 Amendment 151

Distribution Systems - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems - Shutdown LCO 3.8.8 The necessary portions of the AC and DC electrical power distribution subsystems listed in Table 3.8.7-1 shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY: MODES 4 and 5.

During movement of irradiated fuel assemblies in the secondary containment.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE--------- A.1 Declare associated Immediately Not applicable to DG E supported required DC electrical power feature(s) subsystem. inoperable.

OR One or more required AC or DC electrical power distribution subsystems inoperable. (continued)

SUSQUEHANNA - UNIT 2 3.8-50 Amendment 151

Distribution Systems - Shutdown 3.8.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

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

A. (continued) Enter applicable Conditions and Required Actions of LCO 3.5.2 "ECCS Shutdown" when Condition A renders an ECCS subsystem Inoperable.

A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend handling of Immediately irradiated fuel assemblies in the secondary containment.

AND A.2.3 Initiate action to Immediately suspend operations with a potential for draining the reactor vessel (OPDRVS).

AND A.2.4 Initiate actions to Immediately restore required AC and DC electrical power distribution subsystems to OPERABLE status.

AND A.2.5 Declare associated Immediately required shutdown cooling subsystem(s) inoperable and not in operation.

OR (continued)

SUSQUEHANNA - UNIT 2 3.8-51 Amendment 151

Distribution Systems - Shutdown 3.8.8 ACTIONS CONDITION IREQUIRED ACTION I COMPLETION TIME A. (continued) A.3.1 Transfer affected Immediately Unit 1 and common loads to corresponding Unit 2 electrical power distribution subsystem.

AND A.3.2 Declare all affected Immediately required feature(s) which are not transferred inoperable.

AND A.3.3.1 Restore Unit 1 and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after common loads to Unit 1 corresponding Unit 1 electrical power electrical power distribution distribution subsystem is subsystem. restored to OPERABLE status.

OR A.3.3.2 Declare associated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after Unit 1 and common Unit 1 loads inoperable. electrical power distribution subsystem is restored to OPERABLE status.

(continued)

SUSQUEHANNA - UNIT 2 3.8-52 Amendment 151

Distribution Systems - Shutdown 3.8.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Diesel Generator E DC B.1 Verify that all ESW 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power valves associated distribution subsystem with Diesel Generator inoperable. while not E are closed.

aligned to the Class lE distribution system.

C. Diesel Generator E DC C.1 Declare Diesel 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power Generator E distribution subsystem inoperable.

inoperable, while aligned to the Class 1E distribution system.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and 7 days voltage or indicated power availability to required AC and DC electrical power distribution subsystems.

SUSQUEHANNA - UNIT 2 3.8-53 Amendment 151

Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO 3.9.1 The refueling equipment interlocks shall be OPERABLE.

APPLICABILITY: During in-vessel fuel movement with equipment associated with the interlocks.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend in-vessel Immediately refueling equipment fuel movement with interlocks inoperable. equipment associated with the inoperable interlock(s).

SUSQUEHANNA - UNIT 2 3.9-1 Amendment 151

Refueling Equipment Interlocks 3.9.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each of 7 days the following required refueling equipment interlock inputs:

a. All-rods-in,

b. Refuel platform position.

c. Refuel platform fuel grapple, fuel loaded.

d. Refuel platform frame mounted hoist.

fuel loaded.

e. Refuel platform monorail mounted hoist, fuel loaded.

SUSQUEHANNA - UNIT 2 3.9-2 Amendment 151

Refuel Position One-Rod-Out Interlock 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Refuel Position One-Rod-Out Interlock LCO 3.9.2 The refuel position one-rod-out interlock shall be OPERABLE.

APPLICABILITY: MODE 5 with the reactor mode switch in the refuel position and any control rod withdrawn.

ACTIONS -

CONDITION REQUIRED ACTION COMPLETION TIME A. Refuel position one- A.1 Suspend control rod Immediately rod-out interlock withdrawal.

inoperable.

AND A.2 Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify reactor mode switch locked in Refuel 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months position.

(continued)

SUSQUEHANNA - UNIT 2 3.9-3 Amendment 151

Refuel Position One-Rod-Out Interlock 3.9.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.9.2.2 -------------------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.

Perform CHANNEL FUNCTIONAL TEST. 7 days SUSQUEHANNA - UNIT 2 3.9-4 Amendment 151

Control Rod Position 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Control Rod Position LCO 3.9.3 All control rods shall be fully inserted.

APPLICABILITY: When loading fuel assemblies into the core.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more control A.1 Suspend loading fuel Immediately rods not fully assemblies into the inserted. core.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify all control rods are fully inserted. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SUSQUEHANNA - UNIT 2 3.9-5 Amendment 151

Control Rod Position Indication 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Control Rod Position Indication LCO 3.9.4 The control rod "full-in" position indication channel for each control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS

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

Separate Condition entry is allowed for each required channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1.1 Suspend in vessel Immediately control rod position fuel movement.

indication channels inoperable. AND A.1.2 Suspend control rod Immediately withdrawal.

AND A.1.3 Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.

OR (continued)

SUSQUEHANNA - UNIT 2 3.9-6 Amendment 151

Control Rod Position Indication 3.9.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.1 Initiate action to Immediately fully insert the control rod associated with the inoperable position indicator.

AND A.2.2 Initiate action to Immediately disarm the control rod drive associated with the fully inserted control rod.

SURVEILLANCE REQUIREMENT SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify the required channel has no Each time the "full-in" indication on each control rod control rod is that is not "full-in." withdrawn from the "full-in' position SUSQUEHANNA - UNIT 2 3.9-7 Amendment 151

Control Rod OPERABILITY -Refueling 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Control Rod OPERABILITY -Refueling LCO 3.9.5 Each withdrawn control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more withdrawn A.1 Initiate action to Immediately control rods fully insert inoperable. inoperable withdrawn control rods.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 ----- NOTE------------------

Not required to be performed until 7 days after the control rod is withdrawn.

Insert each withdrawn control rod at least 7 days one notch.

SR 3.9.5.2 Verify each withdrawn control rod scram 7 days accumulator pressure is 2 940 psig.

SUSQUEHANNA - UNIT 2 3.9-8 Amendment 151

RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure Vessel (RPV) Water Level LCO 3.9.6 RPV water level shall be 2 22 ft above the top of the RPV flange.

APPLICABILITY: During movement of irradiated fuel assemblies within the RPV, '

During movement of new or irradiated fuel assemblies or handling of control rods within the RPV. when irradiated fuel assemblies are seated within the RPV.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RPV water level not A.1 Suspend movement of Immediately within limit. fuel assemblies and handling of control rods within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is 2 22 ft above the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months top of the RPV flange.

SUSQUEHANNA - UNIT 2 3.9-9 Amendment 151

RHR-High Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Residual Heat Removal (RHR) -High Water Level LCO 3.9.7 One RHR shutdown cooling subsystem shall be OPERABLE and in operation.

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

The required RHR shutdown cooling subsystem may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level 2 22 ft above the top of the RPV-flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required RHR shutdown A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months cooling subsystem method of decay heat inoperable. removal is available. AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B. Required Action and B.1 Suspend loading Immediately associated Completion irradiated fuel Time of Condition A assemblies into the not met. RPV.

AND (continued)

SUSQUEHANNA - UNIT 2 3 .9-10 Amendment 151

RHR-High Water Level 3.9.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Initiate action to Immediately restore secondary containment to OPERABLE status.

AND B.3 Initiate action to Immediately restore one standby gas treatment subsystem to OPERABLE status.

AND B.4 Initiate action to Immediately restore isolation capability in each required secondary containment penetration flow path not isolated.

C. No RHR shutdown C.1 Verify reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from cooling subsystem in coolant circulation discovery of no operation. by an alternate reactor coolant method. circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Monitor reactor Once per hour coolant temperature.

SUSQUEHANNA - UNIT 2 3 .9-11 Amendment 151

RHR-High Water Level 3.9.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify one RHR shutdown cooling subsystem 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is operating.

SUSQUEHANNA - UNIT 2 3.9-12 Amendment 151

RHR-Low Water Level 3.9.8 3.9 REFUELING OPERATIONS 3.9.8 Residual Heat Removal (RHR)-Low Water Level LCO 3.9.8 Two RHR shutdown cooling subsystems shall be OPERABLE. and one RHR shutdown cooling subsystem shall be in operation.

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

The required operating shutdown cooling subsystem may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level < 22 ft above the top of the RPV flange.

ACTIONS

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

Separate Condition entry is allowed for each Shutdown Cooling Subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months RHR shutdown cooling method of decay heat subsystems inoperable. removal is available AND for each inoperable required RHR shutdown Once per cooling subsystem. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B. Required Action and B.1 Initiate action Immediately associated Completion to restore Time of Condition A secondary not met. containment to OPERABLE status.

AND (continued)

SUSQUEHANNA - UNIT 2 3.9-13 Amendment 151

RHR-Low Water Level 3.9.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Initiate action to Immediately restore one standby gas treatment subsystem to OPERABLE status.

AND B.3 Initiate action to Immediately restore isolation capability in each required secondary containment penetration flow path not isolated.

C. No RHR shutdown C.1 Verify reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from cooling subsystem in coolant circulation discovery of no operation. by an alternate reactor coolant method. circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Monitor reactor Once per hour coolant temperature.

SUSQUEHANNA - UNIT 2 3.9-14 Amendment 151

RHR-Low Water Level 3.9.8 SURVEILLANCE REQUIREMENTS _

SURVEILLANCE FREQUENCY SR 3.9.8.1 Verify one RHR shutdown cooling subsystem 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is operating.

SUSQUEHANNA - UNIT 2 3.9-15 .Amendment 151

PPL Rev. 1 SDM Test - Refueling 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling LCO 3.10.8 The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are met

a. LCO 3.3.1.1, "Reactor Protection System Instrumentation," MODE 2 requirements for Functions 2.a, 2.d and 2.e of Table 3.3.1.1-1;

b. 1. LCO 3.3.2.1, "Control Rod Block Instrumentation," MODE 2 requirements for Function 2 of Table 3.3.2.1-1, with the banked position withdrawal sequence requirements of SR 3.3.2.1.8 changed to require the control rod sequence to conform to the SDM test sequence.

2. Conformance to the approved rod sequence for the SDM test is verified by a second licensed operator or other qualified member of the technical staff;

c. Each withdrawn control rod shall be coupled to the associated CRD;

d. All control rod withdrawals that are not in conformance with the BPWS shall be made in notch out mode;

e. No other CORE ALTERATIONS are in progress; and

f. CRD charging water header pressure :2: 940 psig.

APPLICABILITY: MODE 5 with the reactor mode switch in startup/hot standby position.

SUSQUEHANNA - UNIT 2 TS /3.10-20 Amendment 4-64-, 2-Q.7, 234

Inservice Leak and Hydrostatic Testing Operation 3.10.1 ACTIONS

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

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 --------NOTE---------

above requirements not Required Actions to met. be in MODE 4 include reducing average reactor coolant temperature to s 2000F.

Enter the applicable Immediately Condition of the affected LCO.

OR A.2.1 Suspend activities Immediately that could increase the average reactor coolant temperature or pressure.

AND A.2.2 Reduce average 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months reactor coolant temperature to 2000F.

SUSQUEHANNA - UNIT 2 3.10-2 Amendment 151

Inservice Leak and Hydrostatic Testing Operation 3.10.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.1.1 Perform the applicable SRs for the required According to MODE 3 LCOs. the applicable SRs SUSQUEHANNA - UNIT 2 3. 10-3 Amendment 151

Reactor Mode Switch Interlock Testing 3.10.2 3.10 SPECIAL OPERATIONS 3.10.2 Reactor Mode Switch Interlock Testing LCO 3.10.2 The reactor mode switch position specified in Table 1.1-1 for MODES 3. 4, and 5 may be changed to include the run, startup/hot standby. and refuel position. and operation considered not to be in MODE 1 or 2. to allow testing of instrumentation associated with the reactor mode switch interlock functions, provided:

a. All control rods remain fully inserted in core cells containing one or more fuel assemblies: and

b. No CORE ALTERATIONS are in progress.

APPLICABILITY: MODES 3 and 4 with the reactor mode switch in the run, startup/hot standby, or refuel position, MODE 5 with the reactor mode switch in the run or startup/hot standby. position.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Suspend CORE Immediately aboverequirements not ALTERATIONS except met. for control rod insertion.

AND A.2 Fully insert all 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months insertable control rods in core cells containing one or more fuel assemblies.

AND (continued)

SUSQUEHANNA - UNIT 2 3.10-4 Amendment 151

Reactor Mode Switch Interlock Testing 3.10.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3.1 Place the reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months mode switch in the shutdown position.

OR A.3.2 ---- NOTE---------

Only applicable in MODE 5.

Place the reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months mode switch in the refuel position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.2.1 Verify all control rods are fully inserted 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in core cells containing one or more fuel assemblies.

SR 3.10.2.2 Verify no CORE ALTERATIONS are in progress. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SUSQUEHANNA - UNIT 2 3.10-5 Amendment 151

Single Control Rod Withdrawal- Hot Shutdown 3.10.3 3.10 SPECIAL OPERATIONS 3.10.3 Single Control Rod Withdrawal -Hot Shutdown LCO 3.10.3 The reactor mode switch position specified in Table 1.1-1 for MODE 3 may be changed to include the refuel position, and operation considered not to be in MODE 2, to allow withdrawal of a single control rod, provided the following requirements are met:

a. LCO 3.9.2. "Refuel Position One-Rod-Out Interlock";

b. LCO 3.9.4. "Control Rod Position Indication";

c. All other control rods are fully inserted: and

d. 1. LCO 3.3.1.1. "Reactor Protection System (RPS)

Instrumentation," MODE 5 requirements for Functions 1.a, 1.b. 7.a. 7.b. 10, and 11 of Table 3.3.1.1-1. and LCO 3.9.5. "Control Rod OPERABILITY- Refueling,"

OR

2. All other control rods in a five by five array centered on the control rod being withdrawn are disarmed; at which time LCO 3.1.1. "SHUTDOWN MARGIN (SDM).' MODE 3 requirements. may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

APPLICABILITY: MODE 3 with the reactor mode switch in the refuel position.

SUSQUEHANNA - UNIT 2 3.10-6 Amendment 151

Single Control Rod Withdrawal -Hot Shutdown 3.10.3 ACTIONS

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

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 -------- NOTES--------

above requirements not 1. Required Actions met. to fully insert all insertable control rods include placing the reactor mode switch in the shutdown position.

2. Only applicable if the requirement not met is a required LCO.

Enter the applicable Immediately Condition of the affected LCO.

A.2.1 Initiate action to Immediately fully insert all insertable control rods.

AND A.2.2 Place the reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months mode switch in the shutdown position.

SUSQUEHANNA - UNIT 2 3.10-7 Amendment 151.

Single Control Rod Withdrawal -Hot Shutdown 3.10.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.3.1 Perform the applicable SRs for the required According to LCOs. the applicable SRs SR 3.10.3.2 --------------- NOTE--------------------

Not required to be met if SR 3.10.3.1 is satisfied for LCO.3.10.3.d.1 requirements.

Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed.

SR 3.10.3.3 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod being withdrawn. are fully inserted.

SUSQUEHANNA - UNIT 2 3.10-8 Amendment 151

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 3.10 SPECIAL OPERATIONS 3.10.4 Single Control Rod Withdrawal -Cold Shutdown LCO 3.10.4 The reactor mode switch position specified in Table 1.1-1 for MODE 4 may be changed to include the refuel position, and operation considered not to be in MODE 2, to allow withdrawal of a single control rod, and subsequent removal of the associated control rod drive (CRD) if desired, provided the following requirements are met:

a. All other control rods are fully inserted;

b. 1. LCO 3.9.2. "Refuel Position One-Rod-Out Interlock."

and LCO 3.9.4. "Control Rod Position Indication,"

OR

2. A control rod withdrawal block is inserted:

c. 1. LCO 3.3.1.1. "Reactor Protection System (RPS)

Instrumentation," MODE 5 requirements for Functions l.a. l.b. 7.a, 7.b. 10, and 11 of Table 3.3.1.1-1. and LCO 3.9.5. "Control Rod OPERABILITY -Refueling."

OR

2. All other control rods in a five by five array centered on the control rod being withdrawn are disarmed: at which time LCO 3.1.1. "SHUTDOWN MARGIN (SDM)." MODE 4 requirements. may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

APPLICABILITY: MODE 4 with the reactor mode switch in the refuel position.

SUSQUEHANNA - UNIT 2 3. 10-9 Amendment 151

Single Control Rod Withdrawal -Cold Shutdown 3.10.4 ACTIONS

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

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION I REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 -------- NOTES--------

above requirements not 1. Required Actions met with the affected to fully insert control rod all insertable insertable. control rods include placing the reactor mode switch in the shutdown position.

2. Only applicable if the requirement not met is a required LCO.

Enter the applicable Immediately Condition of the affected LCO.

OR A.2.1 Initiate action to Immediately fully insert all insertable control rods.

AND A.2.2 Place the reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months mode switch in the shutdown position.

(continued)

SUSQUEHANNA - UNIT 2 3. 10- 10 .Amendment 151

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more of the B.1 Suspend withdrawal of Immediately above requirements not the control rod and met with the affected removal of associated control rod not CRD.

insertable.

AND B.2.1 Initiate action to Immediately fully insert all control rods.

OR B.2.2 Initiate action to Immediately satisfy the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.4.1 Perform the applicable SRs for the required According to LCOs. the applicable SRs SR 3.10.4.2 ------------------- NOTE--------------------

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.c.1 requirements.

Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod being withdrawn. in a five by five array centered on the control rod being withdrawn. are disarmed.

(continued)

SUSQUEHANNA - UNIT 2 3. 10-11 Amendment 151

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.4.3 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod being withdrawn, are fully inserted.

SR 3.10.4.4 ------------------- NOTE--------------------

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.b.1 requirements.

Verify a control rod withdrawal block is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inserted.

SUSQUEHANNA - UNIT 2 3.10-12 Amendment 151

Single CRD Removal- Refueling 3.10.5 3.10 SPECIAL OPERATIONS 3.10.5 Single Control Rod Drive (CRD) Removal- Refueling LCO 3.10.5 The requirements of LCO 3.3.1.1. "Reactor Protection System (RPS) Instrumentation"; LCO 3.3.8.2. "Reactor Protection System (RPS) Electric Power Monitoring"; and LCO 3.9.5.

"Control Rod OPERABILITY- Refueling," may be suspended in MODE 5 to allow withdrawal of a single control rod. and subsequent removal of the associated CRD from a core cell containing one or more fuel assemblies, provided the following requirements are met:

a. All other control rods are fully inserted; and

b. All other control rods in a five by five array centered on the withdrawn control rod are disarmed: at which time LCO 3.1.1. "SHUTDOWN MARGIN (SDM)." MODE 5 requirements may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

AND In conjunction with a. and b. above. the requirements of LCO 3.9.1. "Refueling Equipment Interlocks": LCO 3.9.2.

"Refuel Position One Rod Out Interlock"; and LCO 3.9.4, "Control Rod Position Indication" may be suspended, provided the following requirements are met:

c. No other CORE ALTERATIONS are in progress: and

d. A control rod block is inserted.

APPLICABILITY: MODE 5 with LCO 3.9.5 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Suspend removal of Immediately above requirements not the CRD mechanism.

met.

AND (continued)

SUSQUEHANNA - UNIT 2 3.10-13 Amendment 151

Single CRD Removal -Refueling 3.10.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.1 Initiate action to Immediately fully insert all control rods.

OR A.2.2 Initiate action to Immediately satisfy the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod withdrawn for the removal of the associated CRD. are fully inserted.

SR 3.10.5.2 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod withdrawn for the removal of the associated CRD. in a five by five array centered on the control rod withdrawn for the removal of the associated CRD. are disarmed.

SR 3.10.5.3 Verify a control rod withdrawal block is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inserted.

SR 3.10.5.4 Perform SR 3.1.1.1. According to SR 3.1.1.1 (continued)

SUSQUEHANNA - UNIT 2 3.10-14 Amendment 151

Single CRD Removal- Refueling 3.10.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.5.5 Verify no CORE ALTERATIONS are in progress. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SUSQUEHANNA - UNIT 2 3.10-15 Amnendment 151

Multiple Control Rod Withdrawal-Refueling 3.10.6 3.10 SPECIAL OPERATIONS 3.10.6 Multiple Control Rod Withdrawal -Refueling LCO 3.10.6 The requirements of LCO 3.9.3, "Control Rod Position";

ICO 3.9.4, "Control Rod Position Indication"; and LCO 3.9.5, "Control Rod OPERABILITY-Refueling," may be suspended, and the "full in' position indicators may be bypassed for any number of control rods in MODE 5, to allow withdrawal of these control rods, removal of associated control rod drives (CRDs), or both, provided the following requirements are met:

a. The four fuel assemblies are removed from the core cells associated with each control rod or CRD to be removed;

b. All other control rods in core cells containing one or more fuel assemblies are fully inserted; and

c. Fuel assemblies shall only be loaded in compliance with an approved spiral reload sequence.

APPLICABILITY: MODE 5 with LCO 3.9.3, LCO 3.9.4, or LCO 3.9.5 not met.

ACTIONS -

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Suspend withdrawal of Immediately above requirements not control rods and met. removal of associated CRDs.

AND A.2 Suspend loading fuel Immediately assemblies.

AND (continued)

RIVER BEND 3. 10- 16 Amendment No. 81

Multiple Control Rod Withdrawal -Refueling 3.10.6 ACTIONS -

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3.1 Initiate action to Immediately fully insert all control rods in core cells containing one or more fuel assemblies.

OR A.3.2 Initiate action to Immediately satisfy the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.6.1 Verify the four fuel assemblies are removed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from core cells associated with each control rod or CRD removed.

SR 3.10.6.2 Verify all other control rods in core cells 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months containing one or more fuel assemblies are fully inserted.

SR 3.10.6.3 -------------------NOTE--------------------

Only required to be met during fuel loading.

Verify fuel assemblies being loaded are in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months compliance with an approved spiral reload sequence.

RIVER BEND 3.10-17 Amendment No. 81

Control Rod Testing- Operating 3.10.7 3.10 SPECIAL OPERATIONS 3.10.7 Control Rod Testing -Operating LCO 3.10.7 The requirements of LCO 3.1.6. "Rod Pattern Control." may be suspended to allow performance of SDM demonstrations.

control rod scram time testing, control rod friction testing and the Startup Test Program provided:

a. The banked position withdrawal sequence requirements of SR 3.3.2.1.8 are changed to require the control rod sequence to conform to the specified test sequence.

OR

b. The RWM is bypassed: the requirements of LCO 3.3.2.1.

"Control Rod Block Instrumentation." Function 2 are suspended; and conformance to the approved control rod sequence for the specified test is verified by a second licensed operator or other qualified member of the technical staff.

APPLICABILITY: MODES 1 and 2 with LCO 3.1.6 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Suspend performance Immediately LCO not met. of the test and exception to LCO 3.1.6.

SUSQUEHANNA - UNIT 2 3.10-18 Amendment 151

Control Rod Testing- Operating 3.10.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY t

SR 3.10.7.1 -------------------NOTE--------------------

Not required to be met if SR 3.10.7.2 satisfied.

Verify movement of control rods is in During control compliance with the approved control rod rod movement sequence for the specified test by a second licensed operator.or other qualified member of the technical staff.

SR 3.10.7.2 -------------------NOTE--------------------

Not required to be met if SR 3.10.7.1 satisfied.

Verify control rod sequence input to the Prior to RWM is in conformance with the approved control rod control rod sequence for the specified movement test.

SUSQUEHANNA - UNIT 2 3. 10-19 Amendment 151

PPL Rev. 1 SDM Test - Refueling 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling LCO 3.10.8 The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are met:

a. LCO 3.3.1.1, "Reactor Protection System Instrumentation,' MODE 2 requirements for Functions 2.a, 2.d and 2.e of Table 3.3.1.1-1; I

b. 1. LCO 3.3.2.1, "Control Rod Block Instrumentation," MODE 2 requirements for Function 2 oe Table 3.3.2.1-1, with the banked position withdrawal sequence requirements of SR 3.3.2.1.8 changed to require the control rod sequence to conform to the SDM test sequence.

OR

2. Conformance to the approved rod sequence for the SDM test is verified by a second licensed operator or other qualified member of the technical staff;

c. Each withdrawn control rod shall be coupled to the associated CRD;

d. All control rod withdrawals that are not in conformance with the BPWS shall be made in notch out mode;

e. No other CORE ALTERATIONS are in progress; and

f. CFD charging water header pressure Ž 940 psig.

APPLICABILITY: MODE 5 with the reactor mode switch in startup/hot standby position.

SUSQUEHANNA - UNIT 2 TS / 3.10-20 Amendmentts, 207

PPL Rev. 1 SDM Test - Refueling 3.10.8 ACTIONS _

CONDITION REQUIRED ACTION COMPLETION TIME A. -------------- NOTE- -----------------------NOTE---------------

Separate Condition entry Rod worth minimizer may be is allowed for each control bypassed as allowed by LCO rod. 3.3.2.1, "Control Rod Block

- -Instrumentation," if required, One or more control rods to allow insertion of not coupled to its inoperable control rod and associated CRD. continued operation.

A.1 Fully insert inoperable 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months control rod.

AND 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months A.2 Disarm the associated CRD.

B. One or more of the above B.1 Place the reactor mode Immediately requirements not met for switch in the shutdown reasons other than or refuel position.

Condition A.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.8.1 Perform the MODE 2 applicable SRs for According to the applicable LCO 3.3.1.1, Functions 2.a, 2.d and 2.e of SRs Table 3.3.1.1-1.

(continued)

SUSQUEHANNA - UNIT 2 TS /3.10-21 Amendment ItE1, 207

SDM Test - Refueling 3.10.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.8.2 ------------------- NOTE--------------------

Not required to be met if SR 3.10.8.3 satisfied.

Perform the MODE 2 applicable SRs for According to LCO 3.3.2.1. Function 2 of Table 3.3.2.1-1. the applicable SRs SR 3.10.8.3 -------------------NOTE--------------------

Not required to be met if SR 3.10.8.2 satisfied.

Verify movement of control rods is in During control compliance with the approved control rod rod movement sequence for the SDM test by a second licensed operator or other qualified member of the technical staff.

SR 3.10.8.4 Verify no other CORE ALTERATIONS are in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months progress.

(continued)

SUSQUEHANNA - UNIT 2 3.10-22 Amendment 151

SDM Test - Refueling 3.10.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.8.5 Verify each withdrawn control rod does not Each time the go to the withdrawn overtravel position. control rod is withdrawn to "full out" position AND Prior to satisfying LCO 3.10.8.c requirement after work on control rod or CRD System that could affect coupling SR 3.10.8.6 Verify CRD charging water header pressure 7 days 2 940 psig.

SUSQUEHANNA - UNIT 2 3.10-23 Amendment 151

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location 4.1.1 Exclusion Area Boundaries The exdusion area shall be as shown in Figure 4.1-1.

4.1.2 Low Population Zone The low population zone shall be as shown in Figure 4.1-2.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 764 fuel assemblies. Each assembly shall consist of a matrix of Zircalloy fuel rods with an initial composition of depleted, natural, or I slightly enriched uranium dioxide (UO2) as fuel material, and water rods or water channels. Limited substitutions of zirconium alloy filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used.

Fuel assemblies shall be limited to those fuel designs that have been analyzed with NRC staff approved codes and methods and have been shown by tests or analyses to comply with all safety design bases. A limited number of lead use assemblies that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Control Rod Assemblies The reactor core shall contain 185 cruciform shaped control rod assemblies.

The control material shall be boron carbide and/or hafnium metal as approved by the NRC.

4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

(continued)

SUSQUEHANNA - UNIT 2 TS / 4.0-1 Amendment A*, 184

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued)

a. k f s 0.95 if fully flooded with unborated water.

which includes an allowance for uncertainties as described in Section 9.1.2 of the FSAR: and

b. A nominal 6.625 inch center to center distance between fuel assemblies placed in the storage racks.

4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a. keff " 0.95 dry or fully flooded conditions, which includes an allowance for uncertainties as described in Section 9.1.1 of the FSAR; and

b. A nominal 7.0 inch center to center distance between fuel assemblies placed in storage racks.

4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 816 ft 9 inches.

4.3.3 Capacity 4.3.3.1 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 2840 fuel assemblies.

4.3.3.2 A multi-purpose storage rack may be used to store up to 10 sound and/or defective fuel assemblies and/or other reactor internals.

SUSQUEHANNA - UNIT 2 4.0-2 Amendment 151

Design Features 4.0 WEST BUILDNG Exclusion Area Boundaries Figure 4.1-1 SUSQUEHANNA - UNIT 2 4.0-3 Amen dment 151

PPL Rev.

Design Features 4.0 Low Population Zone Figure 4.1-2 SUSQUEHANNA - UNIT 2 TS / 4.0-4 Amendment 11 221

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The plant manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affect nuclear safety.

5.1.2 The Shift Supervisor (SS) shall be responsible for the control room command function. During any absence of the SS from the control room while the unit is in MODE 1. 2. or 3. an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the SS from the control room while the unit is in MODE 4 or 5, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

SUSQUEHANNA - UNIT 2 5.0-1 Amendment 151

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Oroanizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or inequivalent forms of documentation. These requirements including the plant specific titles of those personnel fulfilling the responsibilities of the positions delineated inthese Technical Specifications shall be documented inthe FSAR,

b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant:

c. A specified corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and

d. The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.

5.2.2 Unit Staff The unit staff organization shall include the following:

a. A total of three non-licensed operators shall be assigned to SSES Units 1 and 2 .at all times.

(continued)

SUSQUEHANNA - UNIT 2 5.0-2 Amendment 151

PPL Rev.

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

b. At least one licensed Reactor Operator (RO) shall be present in the control room of each unit which has fuel in the reactor. In addition, while the unit is in MODE 1, 2, or 3, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room. This individual may be qualified on both Units and serving in this capacity for both Units.

c. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.g for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

d. A radiation protection technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

e. Deleted (continued)

SUSQUEHANNA - UNIT 2 TS /5.0-3 Amendment ~,

233

PPL Rev.

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

f. The operations manager or assistant operations manager shall hold an SRO license.

g. The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Supervisor (SS) in the areas of thermal hydraulics. reactor engineering, and plant analysis with regard to the safe operation of the unit. In addition, the STA shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

SUSQUEHANNA - UNIT 2 TS / 5.0-4 Amendment +a+,

233

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions except licensed operators and Shift Technical Advisors who shall meet the supplemental requirements in Reg Guide 1.8 Rev. 2 and the supervisor-health physics who shall meet or exceed the qualification of Regulatory Guide 1.8 September 1975.

SUSQUEHANNA - UNIT 2 5.0-5 Amendment 151

Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities:

a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2. Appendix A. February 1978;

b. The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737. Supplement 1, as stated in Generic Letter 82-33:

c. Quality assurance for effluent and environmental monitoring:

d. Fire Protection Program implementation: and

e. All programs specified in Specification 5.5.

SUSQUEHANNA - UNIT 2 5.0-6 Amendment 151

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented and maintained.

5.5.1 Offsite Dose Calculation Manual (ODCM)

A. 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 and trip setpoints. and in the conduct of the radiological environmental monitoring program; and B. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release reports required by Specification 5.6.2 and Specification 5.6.3.

C. Licensee initiated changes to the ODCM:

1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

a. sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s). and

b. a determination that the change(s) maintain the levels of radioactive effluent control required pursuant to 10 CFR 20.1302, 40 CFR 190.

10 CFR 50.36a. and 10 CFR 50. Appendix I. and not adversely impact the accuracy or reliability of effluent. dose, or setpoint calculations:

2. Shall become effective after the approval of the plant manager: and

3. Shall be submitted to the NRC in the form of a complete.

legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages. clearly indicating the area of the page that was changed. and (continued)

SUSQUEHANNA - UNIT 2 5.0-7 Amendment 151

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 ODCM (continued) shall indicate the date (i.e., month and year) the change was implemented.

5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, Reactor Water Cleanup, Standby Gas Treatment, Scram Discharge, Post Accident Sampling (until such time as a modification eliminates the PASS penetration as a potential leakage path) and Containment Air Monitoring Systems. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements; and

b. Integrated leak test requirements for each system at least once per 24 months.

The provisions of SR 3.0.2 are applicable.

5.5.3 Not Used 5.5.4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably (continued)

SUSQUEHANNA - UNIT 2 TS/5.0-8 Amendment No.

4 1+5-3, 187

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued) achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents from the site to unrestricted areas, conforming to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents pursuant to 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from the site to unrestricted areas, conforming to 10 CFR Part 50, Appendix l;

e. Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days.

netermination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days.

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2 percent of the guidelines for the annual dose or dose commitment, conforming to 10 CFR Part 50, Appendix l;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be limited to the following:

(continued)

SUSQUEHANNA - UNIT 2 TS / 5.0-9 AmendmeSA,5, 183

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

1. For noble gases: Less than or equal to a dose rate of 500 mrem/yr to the total body and less than or equal to a dose rate of 3000 mrem/yr to the skin, and

2. For iodine-131. iodine-133. tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem/yr to any organ:

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas at or beyond the site boundary, conforming to 10 CFR Part 50, Appendix I;

i. Limitations on the annual and quarterly doses to a member of the public from iodine--131, iodine--133. tritium. and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas at or beyond the site boundary, conforming to 10 CFR Part 50. Appendix I:

j. Limitations on the annual dose or dose commitment to any member of the public, beyond the SITE BOUNDARY. due to releases of radioactivity and to radiation from uranium fuel cycle sources. conforming to 40 CFR 190.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the FSAR Section 3.9.

Table 3.9-1. cyclic and transient occurrences to ensure that components are maintained within the design limits.

(continued)

SUSQUEHANNA - UNIT 2 5.0-10 Amendment 151

PPL Rev. 3 Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.6 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:

a. Testing frequencies specified in the ASME Operation and Maintenance Code and applicable Addenda are as follows:

ASME Operation and Maintenance Code and applicable Addenda Required Frequencies for terminology for inservice testing performing inservice activities testina activitips Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days

b. The provisions of SR 3.0.2 are applicable to the above required Frequencies and other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities;

c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and

d. Nothing in the ASME Operation and Maintenance Code shall be construed to supersede the requirements of any TS.

(continued)

SUSQUEHrANNA - UNiT 2 TS / 5.0-i i Amendment 91, 1m, 2V'4, 219

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.7 Ventilation Filter Testina Program (VFTP)

The VFTP shall establish the required testing of Engineered Safety Feature (ESF) filter ventilation systems.

Tests described in Specification 5.5.7.a and 5.5.7.b shall be performed:

Once per 24 months; and.

After each complete or partial replacement of the HEPA filter train or charcoal adsorber filter; and.

After any structural maintenance on the HEPA filter or charcoal adsorber housing; and.

Following significant painting, fire, or chemical release in any ventilation zone communicating with the subsystem while it is in operation.

Tests described in Specification 5.5.7.c shall be performed:

Once per 24 months; and.

After 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation; and.

After any structural maintenance on the HEPA filter or charcoal adsorber housing; and, Following significant painting, fire, or chemical release in any ventilation zone communicating with the subsystem while it is in operation.

Tests described in Specification 5.5.7.d. 5.5.7.e and 5.5.7.f shall be performed once per 24 months.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test Frequencies.

(continued)

SUSQUEHANNA - UNIT 2 5.0-12 Amendment 151

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Ventilation Filter Test Program (continued)

a. Demonstrate for each of the ESF systems that an inplace test of the HEPA filters shows a penetration and system bypass

< 0.05% when tested in accordance with Sections C.5.a and C.5.c of Regulatory Guide 1.52, Revision 2. at the system flowrate specified below:

ESF Ventilation System Flowrate (cfm)

Standby Gas 9.090 to 11.110 Treatment System Control Room Emergency 5.229 to 6.391 Outside Air Supply System

b. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < 0.05% when tested in accordance with Sections C.5.a and C.5.d of Regulatory Guide 1.52. Revision 2. at the system flowrate specified below:

ESF Ventilation System Flowrate (cfm)

Standby Gas 9.090 to 11.110 Treatment System Control Room Emergency 5.229 to 6.391 Outside Air Supply System

c. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber. when obtained as described in Section C.6.b of Regulatory Guide 1.52.

Revision 2. shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 5 300C and greater than or equal to the relative humidity specified below.

ESF Ventilation System Penetration (%) R.H.

Standby Gas < 0.175 70 Treatment System Control Room Emergency < 0.175 70 Outside Air Supply System (continued)

SUSQUEHANNA - UNIT 2 5.0-13 Amendment 151

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Ventilation Filter Test Program (continued)

d. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested at the system flowrate specified below:

ESF Ventilation System Delta P (inches wg) Flowrate (cfm)

Standby Gas < 13 9,090 to11,110 Treatment System Control Room Emergency <7.3 5,229 to 6,391 I Outside Air Supply System

e. Demonstrate that the temperature differential in the air flow across the heating coils for each of the ESF system is greater than or equal to the value specified below when tested in accordance with ASME N510-1975:

ESF Ventilation System Delta T (OF) Flowrate (cfm)

Standby Gas 2 17 9,090 to 11,110 Treatment System

f. Demonstrate that the heaters for each of the ESF system dissipate the value specified below when tested in accordance with ANSI N510-1975:

ESF Ventilation System Wattage (kW)

Control Room Emergency 27 to 33 Outside Air Supply System 5.5.8 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Main Condenser Offgas Treatment System and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks. The liquid radwaste quantities shall be determined in accordance with Standard Review Plan, Section 15.7.3, "Postulated Radioactive Release due to Tank Failures".

The program shall include:

a. The limits for concentrations of hydrogen in the Main Condenser Offgas Treatment System and a (continued)

SUSQUEHANNA - UNIT 2 TS / 5.0-14 Amendment -184, 186

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued) surveillance program to ensure the limits are maintained.

Such limits shall be appropriate to the system's design criteria (i.e.. whether or not the system is designed to withstand a hydrogen explosion);

b. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste System is less than or equal to 10 curies.

excluding tritium and dissolved or entrained noble gases.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

5.5.9 Diesel Fuel Oil Testing Program A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements. and acceptance criteria, following the guidelines of the applicable ASTM Standards. The purpose of the program is to establish the following:

a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

1. an API gravity or an absolute specific gravity within limits,

2. a flash point and kinematic viscosity within limits for ASTM 2D fuel oil requirements, and

3. a clear and bright appearance or water and sediment content within limits:

b. Within 31 days following addition of the new fuel oil to storage tanks, verify that the properties of the new fuel oil, other than those addressed in (a) above. are within the limits for ASTM 2D.fuel oil, and (continued)

SUSQUEHANNA - UNIT 2 5.0-15 Amendment 151

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Diesel Fuel Oil Testing Program (continued)

c. Total particulate concentration of stored fuel oil is < 10 mgAiter when tested every 31 days by laboratory filtration.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program Testing Frequency.

5.5.10 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following: I

1. a change in the TS incorporated in the license; or

2. a change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59. I

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.

d. Proposed changes that meet the criteria of Specification 5.5.10b above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71 (e).

(continued)

SUSQUEHANNA - UNIT 2 TS /5.0-16 Amendment,<-3, 183

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.11 Safety Function Determination Program (SFDP)

This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6. The SFDP shall contain the following:

a. Provisions for cross division checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

b. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

c. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

d. Other appropriate limitations and remedial or compensatory actions.

A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power, or no concurrent loss of onsite diesel generator(s),

a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a. A required system redundant to system(s) supported by the inoperable support system is also inoperable; or

b. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or

c. A required system redundant to support system(s) for the supported systems (a) and (b) above is also inoperable.

(continued)

SUSQUEHANNA - UNIT 2 TS /5.0-17 Amendrient~,< 183

PPL Rev.

Programs and Manuals

. 5.5 5.5 Programs and Manuals 5.5.11 Safety Function Determination Program (SFDP) (continued)

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and

.Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

5.5.12 Primary Containment Leakage Rate Testinq Progqram A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exceptions:

a. The visual examination of containment concrete surfaces intended to fulfill the.

requirements of 10CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified.by the ASME Section XI Code, Subsection IWL, except where relief has been authorized by the NRC.

b. The visual examination of the steel liner plate inside containment intended to fulfill the requirements of 10 CFR 50, AppendixJ, Option B,. will be performed in accordance with the requirements of and frequency specified by the ASME Section XI Code, Subsection IWE, except where relief has been authorized by the NRC.

c. NEI 94-01-1995, Section 9.2.3: The first Type A test performed after the October 31, 1992 Type A test shall be performed no later than October 30, 2007..

The peak calculated containment internal pressure.for the design basis loss of coolant accident, Pa, is 48.6 psig.

The maximum allowable primary containment leakage rate, La, at Pa, shall be 1% of the primary containment air weight per day.

(continued)

SUSQUEHANNA - UNIT 2 TS /5.0-18 Amendment 1 1.,

76, 1283, 2,n, 224

PPL Rev. 3 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued)

Leakage Rate Acceptance Criteria are:

a. Primary Containment leakage rate acceptance criterion is < 1.0 La. During each unit startup following testing in accordance with this program, the leakage rate acceptance criteria are *0.60 La for Type B and Type C tests and

0.75 La for Type A tests:

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is 5 0.05 La when tested at > Pa.

2) For each door, leakage rate is < 5 scfh when pressurized to > 10 psig.

The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.

The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

5.5.13 Battery Monitoring and Maintenance Program This program provides for battery restoration and maintenance, which includes the following:

a. Actions to restore battery cells with float voltage < 2.13 V; and

b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates; and

c. Actions to verify that the remaining cells are _> 2.07 V when a cell or cells have been found to be < 2.13 V.

SUSQUEHANNA - UNIT 2 TS / 5.0-18A Amendment 2;1,5, 219

PPL Rev.

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.14 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Outside Air Supply (CREOAS) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem whole body or its equivalent to any part of the body for the duration of the accident.

The program shall include the following elements:

a. The definition of the CRE and the CRE boundary.

b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.

c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Section C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision O.

d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one subsystem of the CREOAS System, operating at the flow rate required by the VFTP, at a Frequency of 24 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 24 month assessment of the CRE boundary.

SUSQUEHANNA - UNIT 2 TS / 5.0-18B Amendment 232

PPL Rev.

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Control Room Envelope Habitability Program (continued)

e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

SUSQUEHANNA - UNIT 2 TS /5.0-18C Amendment 232

PP[. Rev. 4 Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6:. Not Used I 5.6.2 Annual Radiological Environmental Operating Report

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

A single submittal may be made for both SSES units. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (continued)

SUSQUEHANNA - UNIT 2 TS /5.0-19 Amendment 1,d1,210

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2 Annual Radiological Environmental Operating Report (continued)

(ODCM), and in 10 CFR Part 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release Report

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

A single submittal may be made for both SSES units. The submittal shall combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.

(continued)

SUSQUEHANNA - UNIT 2 TS / 5.0-20 Amendment 183

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.

(continued)

SUSQUEHANNA - UNIT 2 TS / 5.0-21 Amendment 1.69, 1W, 1192, 2v7, 224

PPL Rev.

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

The approved analytical methods are described in the following documents, the approved version(s) of which are specified in the COLR.

1. XN-NF-81-58(P)(A), "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company.

2. XN-NF-85-67(P)(A), "Generic Mechanical Design for Exxon Nuclear Jet pump BWR Reload Fuel," Exxon Nuclear Company.

3. EMF-85-74(P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Siemens Power Corporation.

4' ANF-89-98(P)(A), "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation.

5. XN-NF-80-19(P)(A), "Exxon Nuclear Methodology for Boiling Water Reactors," Exxon Nuclear Company.

6. EMF-2158(P)(A), "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2," Siemens Power Corporation.

-7. EMF-2361(P)(A), "EXEM BWR-2000 ECCS Evaluation Model," Framatome ANP.

8. EMF-2292(P)(A), "ATRIUMTm-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation.

9. XN-NF-84-105(P)(A), "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," Exxon Nuclear Company.

(continued)

SUSQUEHANNA - UNIT 2 TS / 5.0-22 Amendment 1XI 2249, 6 3, 1,,4, 1V4, 224.

PPL Rev.

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

10. ANF-524(P)(A), "ANF Critical Power Methodology for Boiling Water Reactors," Advanced Nuclear Fuels Corporation.

11. ANF-913(P)(A), "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation.

12. ANF-1358(P)(A), "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Advanced Nuclear Fuels Corporation.

13. EMF-2209(P)(A), "SPCB Critical Power Correlation," Siemens Power Corporation.

14. EMF-CC-074(P)(A), "BWR Stability Analysis - Assessment of STAIF with Input from MICROBURN-B2," Siemens Power Corporation.

15. NE-092-001A, "Licensing Topical Report for Power Uprate with Increased Core Flow," Pennsylvania Power & Light Company.

16. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress, Solutions Licensing Basis Methodology for Reload Applications."

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

continued SUSQUEHANNA - UNIT 2 TS / 5.0-23 Amendment 1-9 182241.84,29,

PPL Rev. 2 Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.6 EDG Failures Report If an individual emergency diesel generator (EDG) experiences four or more valid failures in the last 25 demands, these failures and any nonvalid failures experienced by that EDG in that time period shall be reported within 30 days.

Reports on EDG failures shall include the information recommended in Regulatory Guide 1.9, Revision 3, Regulatory Position C.4.

5.6.7 PAM Report When a report is required by Condition B or F of LCO 3.3.3.1, 'Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

SUSQUEHANNA - UNIT 2 TS / 5.0-23a Amendme nt 1 06,1 ;4, 1Z,

High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area 5.7 High Radiation Areas As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601 (a) and (b) of 10 CFR Part 20:

5.7.1 High Radiation Areas with Dose Rates Less than or equal to 1.0 rem/hour at 30 Centimeters from the Radiation Source or from Any Surface Penetrated by the Radiation:

a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b. Access to, and activities in, each such area shall be controlled by means of a Radiation Work Permit (RWP) or equivalent that includes specification of radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures (e.g., radiation protection technicians) and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess:

(i) A radiation monitoring device that continuously displays radiation dose rates in the area; or (ii) A radiation monitoring device, with an appropriate alarm setpoint, that continuously integrates the radiation dose rates in the area and alarms when the devices's dose alarm setpoint is reached or (iii) A radiation monitoring device that continuously transmits dose rate and cumulative dose to a remote receiver monitored by radiation protection (continued)

SUSQUEHANNA - UNIT 2 TS / 5.0-24 Amendment 4S, 469-, 184

High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 (continued) personnel responsible for controlling personnel radiation exposure within the area, or (iv) A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area.

e. Except for individuals qualified in radiation protection procedures, or individuals escorted by personnel qualified in radiation protection procedures, entry into such areas shall be made only after dose rates in the area have been evaluated and entry personnel are knowledgeable of them.

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Source or from Any Surface Penetrated by the Radiation, but Less Than 500 rads/hour at 1 Meter from the Radiation Source or from Any Surface Penetrated by the Radiation:

a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked door or gate that prevents unauthorized entry, and, in addition:

(i) All such door and gate keys shall be maintained under administrative control of the shift supervisor, radiation protection manager, or his designee.

(ii) Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

(continued)

SUSQUEHANNA - UNIT 2 TS / 5.0-25 Amendment i,

+, 184

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 (continued)

c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual (whether alone or in a group) entering such an area shall possess:

(i) A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or (ii) A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or (iii) A self reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (a) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (b) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area, or, (continued)

SUSQUEHANNA - UNIT 2 TS 1 5.0-26 Amendment 45, 184

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 (continued)

(iv) In those cases where options (ii) and (iii), above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable principle, a radiation monitoring device that continuously displays radiation dose rates in the area may be used.

e. Except for individuals qualified in radiation protection procedures, or individuals escorted by personnel qualified in radiation protection procedures entry into such areas shall be made only after dose rates in the area have been evaluated and entry personnel are knowledgeable of them.

f. Such individual areas that are within a larger area that is controlled as a high radiation area, where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, but shall be barricaded and conspicuously posted as a high radiation area, and a conspicuous, and clearly visible flashing light shall be activated at the area as a warning device.

SUSQUEHANNA - UNIT 2 TS/5.0-27 Amendment

-415;-, 184

ZCEMSS AUIijciw:.ly FILE COify -P Nl'0 l..O'kiE APPENDIX B TO FACILITY OPERATING LICENSE NO. NPF-22 SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 PPL Susquehanna, LLC DOCKET NOS. 50-387 AND 50-388 ENVIRONMENTAL PROTECTION-PLAN (NON-RADIOLOGICAL)

March, 1984 Amendment No. 459, Amendment No. 162 1 JUL 0 1 2000

SUSQUEHAN4NA STEAM ELECTRIC STATION ENVIRONMENTAL PROTECTION PLAN (NON-RADIO LOGICAL)

TABLE OF CONTENTS Section Page 1.0 Objectives of the Environmental Protection Plan . . . . . . . 1-2.0 Environmental Protection Issues . . . . . . . . . . . . . .. 2-1 Aquatic Issues . .. .. .. .. .. .. .. 2-1 Z. _ ..

2.2 ' Terrestrial Issues. .. . . . . .. . . . . . . . . . . 2-2 Consistency Requirements . .. .. .. .. .. .. .. ... 3-.

3.1 Plant Desion and Operation .. .. . ... .. .. .. .. . 3-1 Reporting Related to the NPOES Permits and State Certification. 3-2 3.2 3.3 Changes Required for Compliance with Other Environmental Regulations . . . . . . . . . . . . . . . . . . . . . . . . 3-3 4.0 Environmental Conditions . . . . . . . . . . . . . . . . . . .-

UnusUal or i'moortant Environmental Events . . . . . . . . . . -

A I 4.12 Environmental Monitoring . .. .. ... . ... .. .. . 4-1 Z. 0 Administrative Procedures . . . . . . . . . . . . . . . . . .

Review and Audit . . . . . . . . . . . . . . . . . . . . . .-

5.2 Records Retention . . . . . . . . . . . . . ... . . . . . . .-

S. O Chances in Environmental Protec:ion Plan. ..

S. ;';

lcnt Reoor.inc Recuiremens .. .. ... .. .. ... . . -2

- . .1.0. Objectives of the Environmental Protection Plan 1.0 The Environmental Protection Plan (EPP) is to provide for protection of environmental values during additional construction and operation of the nuclear facility. The principal objectives of the EPP are as follows:

(1) Verify that the station is operated in an environmentally acceptable manner, as established by the FES and other NRC environmental impact assessments.

(2) Coordinate NRC requirements and maintain consistency with other Federal, State and local requirements for environmental protection.

(.) Keep NRC informed of the environmental effects of facility construction and operation and of actions taken to control those effects.

Environmental concerns identified in the FES which relate to water quality m~at64ers are regulated by'way of the licensee's NPOES perm.it.

2.0 Environmental Protection Issues In the FES-OL dated June 1981, the staff considered the environmental impacts C associated with the operation of the Susquehanna Steam Electric Station.

Certain environmental issues were identified which required study or license conditions to resolve environmental concerns and to assure adequate protection of the environment.

2.1 Aquatic Issues Specific aquatic issues raised by the staff in the FES-OL were:

1. The need for aquatic monitoring programs to confirm that thermal mixing occurs as predicted, that chlorine releases are controlled within those.

discharge concentrations evaluated, and that effects on aquatic biota and water quality due to plant operation are no greater than predicted.

2. The need for special studies to document levels of intake entrainment and impingement.

(FES-OL: Summary and Conclusions and Sections 5.2 and 5.3)

Aquatic issues are addressed by the effluent limitations, monitoring requirements and the effective NPDES permit issued and implemented by the Pennsylvania Department of Environmental Resources, Bureau of Water Quality Management. The NRC wqill rely on this agency for regulation of matters involving water quality and aquatic biota.

2-1 C--

2.2 Terrestrial Issues

~.Tnose issues requiring monitoring programs identified previously and not yet completely resolved are listed below.

1. General monitoring for bird impingement on cooling towers. (FEStOL Sections 5.2.5 and 5.3.5)

2. The applicant will conduct short duration operational sound level surveys when each unit reaches its full operational level. Daytime as well as nighttime measurements will be taken to determine ambient day-night equivalent sound levels.

(FES-OL Sections 5.2.5 and 5.3.5)

3. Maintenance of transmission lines. (Section 5.3.5)

NRC requirements with regard to remaining terrestrial issues are specified in Subsections 4.1 and 4.2 of this EPP. -

2.3 Cultural Resources Issues The need to protect the archeological sites identified in the flcodplain survey which may possibly be eligible for the National Register of Hist.ric Places. NRC requirements with regard to the cultural resources issue are specified in Subsection 4.2.4 of this EPP.

2-2 I

3.0 Consistency Requirements 3.1 Plant Design and Operation The licensee may make changes in station design or operation or perform tests or experiments affecting the environment provided such changes,-tests or experiments do not involve an unreviewed environmental question, and do not involve a change in the Environmental Protection Plan. Changes in plant design or operation or performance of tests or experiments which do not affect the environment are not subject to the requirements of this EPP. Activities governed by Section 3.3 are not subject to the requirements of this section.

Before engaging in additional construction or operational activities which may affect the environment, the licensee shall prepare and record an environmental evaluation of such activity. When the evaluation indicates that such activity 1 ,involves an unreviewed environmental question, the licensee shall provide a written evaluation of such activities and obtain prior approval from the Director, -Office of Nuclear Reactor Regulation. When such activity involves a chance in the Environmental Protection Plan, such activity and change to the Environmental Protection Plan may be implemented only in accordance with an appropriate license amendment as set forth in Section 5.3.

A proposed change, test or experiment shall be deemed to involve an unreviewed environmental question if it concerns (1) a matter which may result in a sicnificant increase in any adverse environmental impact previcusly evaluated

-_ a

in the final environmental statement (FES) as modified by staff's testimony to the Atomic Safety and Licensing Board, supplements to the FES, environmental impact appraisals, or in any. decisions of the Atomic Safety and Licensing

, card; or.(2) a significant change in effluents or power level [in ac:ordance with 10 CFR Part 51.5(b)(2)] or (3) a matter not previously reviewed and evaluated in the documents specified in (1) of this Subsection, which may have a sicnificant adverse environmental impact.

Before engaging In additional construction or operational activities that may result in a significant adverse environmental impact that was not evaluated or that is sig-nificantly greater than that evaluated in the environmental statement (NUREG-0564),

the applicant shall provide written notification to the Director, Division of Licensing, Office of Nuclear Reactor Regulation.

The licensee shall maintain records of changes in facility desicn or operation aId of tests and experiments carried out pursuant to this Subsection. These K-~records shall include a written evaluation which provide bases for the detea-mination that 'he change, test, or experiment does not involve an unreviewed environmental question nor constitute a decrease in the effectiveness of this pp to meet the objectives specified in Section 1.0. The licensee shall include as part of his Annual Environmental Operating Report (per Subsec-tion 5.4.1) brief descriptions, analyses, interpretations, and evaluations ox spuc cha nges, tests and experiments.

3-2 I/

.; . 4. ,%=;JWV6j I lW MI-, IC 6CI.L 6U 61 it: itrtizz rurink %.b dnu ztz;,;e ter-6i i -icar-ions iiola-ions of tle NPOES Permit or the State certification (pursuant 6o

-ct.on 'O1 of the Cle-n Water Act) shall be reported to the flRC by sutmittal of cocies of the reports required by the NPOES ?ermit or cErti1iction. The licar.see shall also provide the NRC with copies of the results of ctudies at

. tesame time they are submitted to the permitting acency.

Chances and additions to the NP5ES Permit or the State certification shall be reported to the NRC within 30 days following the date the change is approved.

f a permit or certification, in part or in its entirety, is appealed and stayed, the NRC shall be notified within 30 days following the date the stay is granted.

The NRC shall be notified of chances to the effective NPDES Permit proposed by

.hfe licensee by providing NRC with a copy of the proposed change at the same ime it.is submitted to the permitting agency. The notif-cation of a licensee-initiatad change shall include a copy of the requested revision submitted to the permitting agency. The licensee shall provide the NRC a copy of the application for renewal of the NPOES permit at the same tfime the acplication is submitted to the permitting agency.

3.3 Changes Required for Compliance with Other Environmental Regulations Changes in plant design or cperation and performance of tess or exceriments which are required to achieve czmpliance with other Federal, S.ate, or lotal

environmental regulations -re not subject tothe requirements of Sectioh 3.1.

3-3 I

4.0 Environmental Conditions 4.1 Unusual or Important Environmental Events Any occurrence of an unusual or important event that indicates or could result in significant environmental impact causally related to plant operation shall be recorded and promptly reported to the NRC within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone, telegraph, or facsimile transmissions followed by a written report per Sub-section 5.4.2. The following are examples: excessive bird impaction events, onsite plant or animal disease outbreaks, mortality or unusual occurrence of any species protected by the Endangered Species Act of 1973, fish kills, increase in nuisance organisms or conditions and unanticipated or emergency discharge of waste water or chemical substances.

No routine monitoring programs are required to implement this condition.

4.2 Environmental Monitoring 4.2.1 General Monitoring Program for Bird Impingement (refer to Section 4.1) 4.2.2 Maintenance of Transmission Line Corridors The use of herbicides within the Susquehanna Steam Electric Station transmission line corridors shall conform to the approved use of selected herbicides as registered by the Environmental Protection Agency and approved by State authorities and applied as directed by said authorities.

Records shall be maintained in the acorocriate division office concerning herbicide use. Such records shall include the flollowino information:

4-1

commercial and chemical names of materials used; concentration of active material in formulations diluted for field use; diluting substances other than

-,--/water; rates of application; method and frequency of application; location; and the date of application. Such records shall be maintained for a period of 5 years and be made readily available to the NRC upon request. There shall be no routine reporting requirement associated with this condition.

4.2.3 Sound Level Surveys Surveys shall be conducted to quantify the sound levels that exist at various locations around the site during operation of the Susquehanna Steam Electric Station. Surveys shall be conducted during one unit and during two unit operation -at the-site. The operational phase s..ound level surveys shall be conducted as soon as practicable during the operational phase of the facility, when each unit's cooling tower is operating with its design water flow rate. The one unit operation survey shall be scheduled to the extent practicable, such that measured sound levels are not significantly affected by onsite activities associa-ted with the construction of the second unit.

For each of the surveys, sound level data shall be collected at several sites, the exact number and location to be selected by the licensee after consid=raton of (1) existing on-site and nearby off-site noise sourc-s arad barriers, and (2) noise sensitive land uses in the site vicinity (e.g., residences, schools, churches, cemeteries, hospitals, parks).

4-2

< OData collected from each sampling site shall encompass both the daytime and the nighttime periods. Sampling shall include the identification of pure tones, if any, emanating from plant equipment during the operational phase.

The selection, calibration and use of equipment, conduct of the surveys, and the-analysis and reporting of data shall conform to the provisions of the applicable American National Standards Ins-titute Standards. The conduct of the surveys for both operational conditions shall be similar such that the results are comparable.

The results of the surveys conducted under this program sha2l be surmarized,

- interpreted and reported in accordance with Section 5.4.1 of this EPP. The results shall include, for each sampling location for each survey, the dayti~me and nighttime equivalent sound levels, the background and intrUsion sound levels (i.e., the L., and L10, respectivel.y), and the range of sound levels recorded. A description of the pure tones found, if any, and their sources shall also be included in the results.

The final report of t.his program shall present a brier assessment by the licensee of the environmental impact of plant operation on the off-site acCustic environment, and shall describe the proposed miticative measures, j, any, to e taken to reduce the impact of plant noise levels on :he off-site environment. This report shall also contain a list cf ail ncise related cmoiaints or Incuiries received by ?ennsyivania Power & L _nh 4-3

Co.-any (PP&L) concerning the Susquehanna Steam Electric Station subsequent to issuance of the operating license along with a description of the action taken by PP&L to resolve these complaints or inquiries.

This program shall terminate upon completion of the collection of the specified sound level data for each phase and submission of an acceptable final report.

4.2.4 Cultural Resources On March 26, 1981, the Pennsylvania Power & Light Company submitted a report to NRC, entitled, "Archeological Investigations at The Susquehanna SES: The Susqukhanna SES Floodplain", prepared by Cotmmonwealth Associates for Pennsylvania Power & Light Company. The report identified three sites as significant and one s.ite as potentially significant with the sites being possibly eligible for the National Register of Historic Places.

In order for the NRC to proceed with the submission of a determination of eligibility request to the Keeper of the National Register- the applicant shall be required to provide the NRC with the information necessary to initiate a determination of eligibility request with regard to sites SES-3, SES-6, SES-8 and SES-ll. The U.S. Department of Interior forrm entitled,

"'ational Register of Historic Places Inventory - Nomination Form" should be filled out in detail with appropriate maps and other materials for each of -he four sites and returned to the NRC. Item 12 of the form need nc; be filled Out. The licensee should refer to the Federal *egiszer, 4-4

September 21, 1977, Part 11, for detailed guidance. The NRC requests the licensee to take appropriate measures to protect the sites during the determination of eligibility process. Upon receipt and review of the information, the NRC will forward the materials to the Keeper for action.

If the Keeper rules the sites are not eligible, the finding will be filed and this section of the EPP is fully satisfied with no further action required.

If the Keeper rules that any of the sites are eligible for the National Register, the licensee is required to provide the NRC with information with regard to completing a determination of effect which the operation and maintenance activities of the plant may have on the eligible sites.

The licensee should follow the steps presented in 36 CFR 800.3 and 36 CFR 800.4 in developing the information. Upon receipt of the informa-

.xion, the NRC, in consultation with the SHPO, will complete the determination of effect process. If the determination results in a no effect determination as provided in 36 CFR 800.4(4)(B)(1), the documentation will be filed and this section of the EPP i-s fully satisfied with no further action required.

If the determination results in an effect determination, the licensee will be required to provide the NRC with information adequate to document the effect det.ermination and an appropriate action program which the licensee has developed in consultation with the SHPO and concurred in by the SHPO. Upon review of the program the NRC will forward the documentation to the Advisory Council on Historic Preservation (ACHP) for comment.

Ir 4-;

After ACHP comment is received by NRC, the program will be revised, if necessary, to incorporate any comments provided by the ACHP. The licensee shall then proceed, in consultation with the SHPO, to implement the proposed program. Upon completion of the program, a report shall be submitted to the NRC which will include a description of the results of the program and the disposition of data recovered (if applicable). Upon submittal of this report, this section of the EPP is fully satisfied with no further action required.

4-6

5.0 Administrative Procedures 5.1 Review and Audit The licensee shall provide for review and audit of. compliance with the Environmental Protection Plan. The audits shall be conducted independently of the individual or groups responsible for performing the specific activity. A description of the organization structure utilized to achieve the independent review and audit function and results of the audit activities shall be maintained and made available for inspection.

5.2 Records Retention Records and loas relative to the environmental aspects of plant operation shall be made and retained in a manner convenient for review and inspection.

These records and logs shall be made available to NRC on request.

Records of modifications to plant structures, systems and components determined to potentially Affect the continued protection of the environment shall be retained for the life of the plant. All other records, data and logs

relating to this EP shall be retained for five years or,.where applicable, in c:Orcance with the requirements of other acencies.

Chances in Environmental Protection Plan

-eq-esz 'or c;iance in the Eivironmental Protection Plan shail nc'-u e an 2sas-sment of lwne environmental impact of the pr-posec chance a a szuccrt-.4c

'on.

"ssifica Tmoie.mentat'on of sucn chances. in Viie ? s -o c ncs

prior .to NRC approval of the proposed changes in the form of a license amendment incorporating the appropriate revision to the Environmental K.,Protection Plan.

5.4 Plant Reporting Requirements 5.4.1 Routine Reports An Annual Environmental Operating Report describing implementaticn of this EP?

for the previous year shall be submitted to the NRC prior to May 1 of each year. The initial report shall be submitted prior to May 1.of the year following issuance of the operating licenses. The period of the first report shall begin with the date of issuance of the operating license for the first operational unit.

The report shall include summaries and analyses of the results of the environmental protection activities required by Subsection 4.2 of this Environmental Protecton Plan for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous nonradiological environmental monitorihg reports, and an assess ent of the observed impacts of the plant operation on the environment. If harmful effects Or evidence of trends towards irreversible damace to t.e environment are observed, the licensee shall provide a detailed analysis of the data and a proposed course of action to alleviate the-problen.

The Annual Environmental Operating Report shall also include:

\s_/4a) A list of EP noncompliances and the corrective actions taken to remedy them.

(b) A-list of all changes in station design or operation, tests, and experiments made in accordance with -Subsection 3.1 which involved a potentially significant unreviewed environmental issue.

(c) A list of nonroutine reports submitted in accordance with Subsection 5.4.2.

In the event that some results are not available -by the report due date, the report shall be submitted noting and-explaining the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

5.4.2 Nonroutine Reports A written report shall be submitted to the NRC within 30 days of occurrence of nonroutine event. The report shall (a) describe, analyze, and evaluate the event, including extent and magnitude of the impact and plant operating c.haracteristics, (b) describe the probable cause of the event, (c) indicate le action taken to correct, the reported event, (d) indic-te the corrective acicn taken to preclude repetition of the event and to -revent simil.lar occurrences Involving similar component*s or systems, anc (e) indicae the

_cenc-es notified and their preliminary res.onses.

__ - ___ . - . I . . . . . . I. . .

Events reportable under this subsection which also require reports to other Federal, State or local agencies shall be reported in accordance with those go freporting requirements in lieu of the requirements.of this subsection. The NRC shall be provided a copy of such report at the same time it is submitted to the other agency.

I v

11

Appendix C Additional Conditions Facility Operating License No. NPF-22 Docket No. 50-388 Amendment l odl I Number lAdditionalConditions J Implementation Date 151 The operating licensee is authorized to relocate This amendment is effective I certain requirements included in Appendix A to immediately and shall be operating licensee-controlled documents. implemented within 90 days Implementation of this amendment shall of the date of this include the relocation of these requirements to amendment.

the appropriate documents, as described in the Dated: July 30,1998 operating licensee's letters dated August 1, 1996, as supplemented by letters dated November 26, 1997, January 6, March 2, April 24, and June 18, 1998, evaluated in the NRC staff's Safety Evaluation enclosed with this amendment.

162 PPL Susquehanna shall not take any action This amendment shall be that would cause PPL Corporation or any other issued and made effective direct or indirect parent of PPL Susquehanna to at the time the license void, cancel, or diminish any applicable transfer to PPL commitment to fund an extended plant Susquehanna is completed shutdown as represented in the application for and shall be implemented approval of the transfer of the license for within 30 days of issuance.

Susquehanna SES, Unit 2.

For purposes of ensuring public health and This amendment shall be 162 safety, PPL Susquehanna shall provide issued and made effective decommissioning funding assurance, to be at the time the license held in a decommissioning trust for transfer to PPL Susquehanna SES, Unit 2, upon transfer of the Susquehanna is completed license to PPL Susquehanna, in the amount and shall be implemented specified in PP&L, Inc.'s, March 29, 1999, within 30 days of issuance.

Decommissioning Report of Financial Assurance" as Owner's Decommissioning Fund Totals at December 31, 1998, plus any additional funds added to the account since the filing of that report, on the date of transfer. In addition, PPL Susquehanna will ensure that its contractual arrangements with PPL EnergyPlus, LLC, and the contractual arrangements of PPL EnergyPlus, LLC with PPL Electric Utilities Corporation to obtain necessary decommissioning funds for Susquehanna SES through a non-bypassable charge will be maintained until the decommissioning trust is fully funded, or will ensure that other mechanisms that provide equivalent assurance of decommissioning funding in accordance with the Commission's regulations are maintained.

Amendment No. 162 I JUL 0 1 2000

V The decommissioning trust agreement for This amendment shall be 162 Susquehanna SES, Unit 2, is subject to the issued and made effective following: at the time the license a) The trust agreement must be in a form transfer to PPL acceptable to the NRC. Susquehanna is completed b) With respect to the decommissioning trust and shall be implemented fund, investments in the securities or within 30 days of issuance.

other obligations of PPL Corporation or its affiliates, successors, or assigns shall be prohibited. Except for investments tied to market indexes or other non-nuclear-sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

c) The decommissioning trust agreement for Susquehanna SES, Unit 2, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the NRC 30-days prior written notice of payment.

The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the Director, Office of Nuclear Reactor Regulation.

d) The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30-days prior written notification to the Director, Office of Nuclear Reactor Regulation.

e) The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a "prudent investor" standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commission's regulations.

Amendment No. 162 1 Just1 C: ore ti

ML093290177

Text

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