ML070320479

Technical Specifications, Implementation of Alternative Radiological Source Term

ML070320479
Person / Time
Site:	Susquehanna
Issue date:	01/31/2007
From:	NRC/NRR/ADRO/DORL/LPLI-1
To:
References
Download: ML070320479 (46)

Text

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

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

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

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 239, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

For Surveillance Requirements (SRs) that are new in Amendment 178 to Facility Operating License No. NPF-1 4, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 178. For SRs that existed prior to Amendment 178, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval-that begins on the date the Surveillance was last performed prior to implementation of Amendment 178.

(3) Conduct of Work Activities During Fuel Load and Initial Startup The operating licensee shall review by committee all facility construction, Preoperational Testing, and System Demonstration activities performed concurrently with facility initial fuel loading or with the facility Startup Test Amendment No. 5, +43, +78, +88, +88, +94, £-35, 286, £3-7,-38,239

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 LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) 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 1-131, 1-132,1-133,1-134, and 1-135 actually present. The conversion factors that are used for this calculation of committed effective dose equivalent (CEDE) from inhalation shall be those listed in Table 2.1 of Federal Guidelines Report 11, "Limiting Values of Radionuclide Intake and Air (continued)

SUSQUEHANNA - UNIT 1 1.1-2 Amendment i17, 239

PPL Rev.

Definitions 1.1 1 .1 Definitions DOSE EQUIVALENT 1-131 Values of Radionuclide Intake and Air Concentration and (continued) 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 CORE COOLING The ECCS RESPONSE TIME shall be that time interval SYSTEM (ECCS) RESPONSE from when the monitored parameter exceeds its ECCS TIME initiation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety 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 RECIRCULATION PUMP TRIP time interval from initial signal generation by the (EOC RPT) SYSTEM associated turbuine stop valve limit switch or from when the RESPONSE TIME turbine control valve hydraulic oil control oil pressure drops below the pressure switch setpoint to complete suppression of the electric arc between the fully open contacts of the 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 SYSTEM The ISOLATION SYSTEM RESPONSE TIME shall be that RESPONSE TIME time interval from when the monitored parameter exceeds its isolation initiation setpoint 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.

(contin! ed)

SUSQUEHANNA - UNIT 1 1.1 -3 Amendment 138, 239

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 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> pentaborate in solution sodium pentaborate in solution

< 13.6 weight percent but to within limits >13.6 weight AND within limits of percent.

Figure 3.1.7-1. 10 days from discovery of failure to meet the LCO B. One SLC subsystem B.1 Restore SLC subsystem to 7 days inoperable for reasons OPERABLE status.

other than Condition A. AND 10 days from discovery of failure to meet the LCO.

C. Two SLC subsystems C.1 Restore one SLC subsystem to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

inoperable for reasons OPERABLE status.

other than Condition A.

D. Required Action and D.1 Be in MODE 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met. AND D.2 Be in MODE 4 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SUSQUEHANNA - UNIT 1 3.1-20 Amendment 1/8, 239

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

5. Reactor Water Cleanup (RWCU) System Isolation

a. RWCU Differential A 1,2,3 1 F SR 3.3.6.1.1 f- 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 F SR 3.3.6.1.2 _5137°F Area Temperature - SR 3.3.6.1.3 High SR 3.3.6.1.5

c. RWCU Pump Area 1,2,3 F SR 3.3.6.1.2 5 154°F 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 5 154°F 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 F SR 3.3.6.1.1 < 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 (b) SLC System Initiation only inputs into one of the two trip systems. (continued)

SUSQUEHANNA - UNIT 1 3.3-61 Amendment 17h 236

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

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

(1) Maximum Power Level PPL Susquehanna, LLC is authorized to operate the facility at reactor core power levels not in excess of 3489 megawatts thermal (100% power) in accordance with the conditions specified herein and in Attachment 1 to this license. The preoperational test, startup tests and other items identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 2216, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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

2.C.(3) PPL Susquehanna, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Fire Protection Review Report for the facility and as approved in Fire Protection Program, Section 9.5, SER, SSER#1, SSER#2, SSER#3, SSER#4, SSER#6, Safety Evaluation of Fire Protection Report dated August 9, 1989, Safety Evaluation Amendment No. 1-, 2, +05, -150, 1-5+, +-53, +62, +69, 2-+2, 2+3, 2-+-4, 2-t-5, 216

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)

SUSQUEHANNA - UNIT 2 1.1-3 Amendment 15/,

216

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 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> pentaborate in solution sodium pentaborate in solution

< 13.6 weight percent to within limits > 13.6 weight AND but within limits of percent.

Figure 3.1.7-1. 10 days from discovery of failure to meet the LCO B. One SLC subsystem B.1 Restore SLC subsystem to 7 days inoperable for reasons OPERABLE status.

other than Condition A. AND 10 days from discovery of failure to meet the LCO C. Two SLC subsystems C.1 Restore one SLC subsystem to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable for reasons OPERABLE status.

other than Condition A.

D. Required Action and D.1 Be in MODE 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met. AND D.2 Be in MODE 4 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SUSQUEHANNA - UNIT 2 3.1-20 Amendment 17i1, 216

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