ML070320827: Difference between revisions

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{{#Wiki_filter:Definitions 1.1 1.1 Definitions (continued)
{{#Wiki_filter:Definitions 1.1 1.1 Definitions (continued)
MODE OPERABLE -OPERABILITY PHYSICS TESTS A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
MODE OPERABLE - OPERABILITY PHYSICS TESTS A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.
PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.
A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
These tests are: a. Described in Chapter 14, of the FSAR;b. Authorized under the provisions of 10 CFR 50.59; or c. Otherwise approved by the Nuclear Regulatory Commission.
PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:
The PTLR is the unit specific document that provides the reactor vessel pressure and temperature limits, including heatup and cooldown rates, the power operated relief valve (PORV) lift settings and the LTOP arming temperature associated with the Low Temperature Overpressurization Protection (LTOP) System, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.6.PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)(continued)
: a.
COMANCHE PEAK -UNITS 1 AND 2 1.1-5 Amendment No. 664, 132 Reporting Requirements 5.6 5.6 Reporting Requirements (continued)
Described in Chapter 14, of the FSAR;
: b.
Authorized under the provisions of 10 CFR 50.59; or
: c.
Otherwise approved by the Nuclear Regulatory Commission.
The PTLR is the unit specific document that provides the reactor vessel pressure and temperature limits, including heatup and cooldown rates, the power operated relief valve (PORV) lift settings and the LTOP arming temperature associated with the Low Temperature Overpressurization Protection (LTOP) System, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.6.
PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
(continued)
COMANCHE PEAK - UNITS 1 AND 2 1.1-5 Amendment No. 664, 132


====5.6.6 Reactor====
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic testing, and PORV lift settings as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:
: a.
: 1. Specification 3.4.3, "RCS Pressure and Temperature (P/T) Limits," and 2. Specification 3.4.12, "Low Temperature Overpressure Protection (LTOP) System." b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic testing, and PORV lift settings as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:
* WCAP-14040-NP-A; "Methodology used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves." c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.(continued)
: 1.
COMANCHE PEAK -UNITS 1 AND 2 5.0-35 Amendment No. 94, 132}}
Specification 3.4.3, "RCS Pressure and Temperature (P/T) Limits,"
and
: 2.
Specification 3.4.12, "Low Temperature Overpressure Protection (LTOP) System."
: b.
The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
WCAP-14040-NP-A; "Methodology used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves."
: c.
The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
(continued)
COMANCHE PEAK - UNITS 1 AND 2 5.0-35 Amendment No. 94, 132}}

Latest revision as of 03:29, 15 January 2025

Technical Specification Pages Re Reactor Coolant System Pressure & Temperature Limits Report
ML070320827
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 02/22/2007
From:
NRC/NRR/ADRO/DORL/LPLIV
To:
Donohew J N, NRR/DORL/LP4, 415-1307
Shared Package
ML070320823 List:
References
TAC MC9500, TAC MC9501
Download: ML070320827 (2)


Text

Definitions 1.1 1.1 Definitions (continued)

MODE OPERABLE - OPERABILITY PHYSICS TESTS A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

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

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, of the FSAR;

b.

Authorized under the provisions of 10 CFR 50.59; or

c.

Otherwise approved by the Nuclear Regulatory Commission.

The PTLR is the unit specific document that provides the reactor vessel pressure and temperature limits, including heatup and cooldown rates, the power operated relief valve (PORV) lift settings and the LTOP arming temperature associated with the Low Temperature Overpressurization Protection (LTOP) System, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.6.

PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

(continued)

COMANCHE PEAK - UNITS 1 AND 2 1.1-5 Amendment No. 664, 132

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a.

RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic testing, and PORV lift settings as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

1.

Specification 3.4.3, "RCS Pressure and Temperature (P/T) Limits,"

and

2.

Specification 3.4.12, "Low Temperature Overpressure Protection (LTOP) System."

b.

The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

WCAP-14040-NP-A; "Methodology used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves."

c.

The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.

(continued)

COMANCHE PEAK - UNITS 1 AND 2 5.0-35 Amendment No. 94, 132