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| number = ML17033B585
| number = ML17033B585
| issue date = 09/29/2016
| issue date = 09/29/2016
| title = North Anna Power Station, Units 1 and 2 - Redacted Updated Final Safety Analysis Report Chapter 16
| title = Redacted Updated Final Safety Analysis Report Chapter 16
| author name = Sreenivas V
| author name = Sreenivas V
| author affiliation = NRC/NRR/DORL/LPLII-1
| author affiliation = NRC/NRR/DORL/LPLII-1
| addressee name = Heacock D A
| addressee name = Heacock D
| addressee affiliation = Virginia Electric & Power Co (VEPCO)
| addressee affiliation = Virginia Electric & Power Co (VEPCO)
| docket = 05000338, 05000339
| docket = 05000338, 05000339
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{{#Wiki_filter:North Anna Power Station Updated Final Safety Analysis Report Chapter 16 Intentionally Blank
{{#Wiki_filter:North Anna Power Station Updated Final Safety Analysis Report Chapter 16


Intentionally Blank Revision 52-09/29/2016 NAPS UFSAR 16-i16.1SAFETY AND ENVIRONMENTAL TECHNICA L SPECIFICATIONS . . . . . .16.1-116.2TECHNICAL REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Intentionally Blank Revision 5209/29/2016                                 NAPS UFSAR                                         16-i Chapter 16: Technical Specifications and Requirements Table of Contents Section                              Title                                                                Page 16.1  SAFETY AND ENVIRONMENTAL TECHNICAL SPECIFICATIONS . . . . . .                                     16.1-1 16.2    TECHNICAL REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16.2-1
16.2-1Chapter 16: Technical Specifications and RequirementsTable of ContentsSectionTitlePage Revision 52-09/29/2016 NAPS UFSAR 16-iiIntentionally Blank Revision 52-09/29/2016 NAPS UFSAR 16.1-1CHAPTER 16TECHNICAL SPECIFICATIONS AND REQUIREMENTS 16.1 SAFETY AND ENVIRONMENTAL TECHNICAL SPECIFICATIONSTechnical Specifications define plant va riables, operating co nditions, surveillance requirements, and administrative c ontrols that are considered necessary to en sure the health and safety of the public.
 
The scope of these specifications is as set forth in Section 50.36 of 10 CFR 50 for Final Safety Analysis Report Technica l Specifications. Items in six broad categories are included:  
Revision 5209/29/2016                   NAPS UFSAR 16-ii Intentionally Blank
 
Revision 5209/29/2016                                     NAPS UFSAR                       16.1-1 CHAPTER 16            TECHNICAL SPECIFICATIONS AND REQUIREMENTS 16.1   SAFETY AND ENVIRONMENTAL TECHNICAL SPECIFICATIONS Technical Specifications define plant variables, operating conditions, surveillance requirements, and administrative controls that are considered necessary to ensure the health and safety of the public.
The scope of these specifications is as set forth in Section 50.36 of 10 CFR 50 for Final Safety Analysis Report Technical Specifications. Items in six broad categories are included:
(1) safety limits, (2) limiting safety system settings, (3) limiting conditions for operation, (4) surveillance requirements, (5) design features, and (6) administrative controls.
(1) safety limits, (2) limiting safety system settings, (3) limiting conditions for operation, (4) surveillance requirements, (5) design features, and (6) administrative controls.
Safety limits are limits upon meas urable plant variables, such as thermal power, neutron flux, flow rates, pressures, and temperatures, which ensure fuel cla dding and reactor coolant system integrity.
Safety limits are limits upon measurable plant variables, such as thermal power, neutron flux, flow rates, pressures, and temperatures, which ensure fuel cladding and reactor coolant system integrity.
Limiting safety system se ttings are settings for automatic pr otective devices that ensure that even under the most adverse situ ation anticipated, a safety limit will not be exceeded. Prime examples are the reactor trip settings. Instrument inaccuracies, calibration errors, and circuit response times, as well as calculat ional uncertainties, are considered.
Limiting safety system settings are settings for automatic protective devices that ensure that even under the most adverse situation anticipated, a safety limit will not be exceeded. Prime examples are the reactor trip settings. Instrument inaccuracies, calibration errors, and circuit response times, as well as calculational uncertainties, are considered.
Limiting conditions for operati on primarily establish the conditions of the various safety-related components and syst ems necessary to either begin r eactor operation or to continue operation. The reactor coolant sy stem, Chemical and Volume Control System, steam and power conversion system, instrumentation systems, containment system, auxiliary electrical systems, and the systems making up the engineered safety features have minimum acceptable capabilities.
Limiting conditions for operation primarily establish the conditions of the various safety-related components and systems necessary to either begin reactor operation or to continue operation. The reactor coolant system, Chemical and Volume Control System, steam and power conversion system, instrumentation systems, containment system, auxiliary electrical systems, and the systems making up the engineered safety features have minimum acceptable capabilities.
Specifications on pumps, valves, tanks, fluid levels, ch emical constituents in certain fluids, radioactivity levels, etc., ensure that the above syst ems meet their minimum acceptable performance levels.Surveillance requirements are imposed on pl ant conditions, system s, and components to ensure that the limiting conditi ons for operation are being met.
Specifications on pumps, valves, tanks, fluid levels, chemical constituents in certain fluids, radioactivity levels, etc., ensure that the above systems meet their minimum acceptable performance levels.
Tests, checks, calibrations, inspections, and samplings at ap propriate intervals verify the required plant conditions and performance capability of systems and components.
Surveillance requirements are imposed on plant conditions, systems, and components to ensure that the limiting conditions for operation are being met. Tests, checks, calibrations, inspections, and samplings at appropriate intervals verify the required plant conditions and performance capability of systems and components.
Design features include a descri ption of the plant' s site, reac tor containment, reactor core, reactor coolant system, and fuel storage facilities. The purpose of this section is to delineate the features of a plant not cove red in other specifications.
Design features include a description of the plants site, reactor containment, reactor core, reactor coolant system, and fuel storage facilities. The purpose of this section is to delineate the features of a plant not covered in other specifications.
Revision 52-09/29/2016 NAPS UFSAR 16.1-2Administrative controls are meant to preven t the existence or development of an unsafe condition in connec tion with the operation of the reactor. They also de fine the administrative action to be taken in the event a safety limit or allowed condi tion for operation is exceeded.Requirements concerning the facility's or ganization and management, procedures, record-keeping, review and audi t, and reporting are specified.The Configuration Risk Management Prog ram (CRMP) provides a proceduralized risk-informed assessment to manage risks associated with equi pment inoperability
 
. The program applies to technical specification structures, systems, and components for which a risk-informed allowed outage time has been granted. The program includes the following elements:1.Provisions for the control and implementation of a Level 1, at power, internal events, PRA-informed methodology
Revision 5209/29/2016                                     NAPS UFSAR                       16.1-2 Administrative controls are meant to prevent the existence or development of an unsafe condition in connection with the operation of the reactor. They also define the administrative action to be taken in the event a safety limit or allowed condition for operation is exceeded.
. The assessment shall be capable of evalua ting the applicable plant configuration.2.Provisions for performing an assessment prior to entering an LCO Actions Table for planned activities.3.Provisions for performing an assessment after entering the LCO Actions Table for unplanned entry into the LCO Condition(s).4.Provisions for assessing the need for additi on actions after the di scovery of additional equipment out of service conditions while in the LCO Actions Table.5.Provisions for considering other applicable risk significant contri butors such as Level 2 issue and external events, qualitatively or quantitatively.The Technical Specifications originally in this chapter have been de leted, since they are no longer applicable. References to this chapter have be en amended as appropriate.The Technical Specificati ons (issued as Appendix A to the Operating Li cense) and changes thereto are contained in a separately bound document to facili tate updating independently of the FSAR.Environmental Technical SpecificationsThe Environmental Technical Specifications (ETS) define plant variables, operating conditions, monitoring requirements, and administrative controls that are considered necessary to ensure that the station will be operated within limits of acceptable environmental impact.
Requirements concerning the facilitys organization and management, procedures, record-keeping, review and audit, and reporting are specified.
VEPCO submitted proposed E nvironmental T echnical Spec ifications as Chapter 16A of the FSAR during September 1976. The NRC staff issued on November 16, 1976, a working edition of the ETS.
The Configuration Risk Management Program (CRMP) provides a proceduralized risk-informed assessment to manage risks associated with equipment inoperability. The program applies to technical specification structures, systems, and components for which a risk-informed allowed outage time has been granted. The program includes the following elements:
Revision 52-09/29/2016 NAPS UFSAR 16.1-3The ETS underwent an iterative process of review and developmen t between VEPCO and the NRC. The finalized version of the ETS was issued by the NRC as Appendix B to the Operating License.
: 1. Provisions for the control and implementation of a Level 1, at power, internal events, PRA-informed methodology. The assessment shall be capable of evaluating the applicable plant configuration.
The ETS originally in this chap ter have been deleted since th ey are no longer applicable.
: 2. Provisions for performing an assessment prior to entering an LCO Actions Table for planned activities.
References to this chapter have been amended as appropriate.The Environmental Technical Specifications and changes thereto are contained in a separately bound document to facilitat e updating independently of the FSAR.The Environmental Technical Specifications have subsequently be en replaced by the Environmental Protection Plan, Appendix B of the Facility Operating License.
: 3. Provisions for performing an assessment after entering the LCO Actions Table for unplanned entry into the LCO Condition(s).
Revision 52-09/29/2016 NAPS UFSAR 16.1-4Intentionally Blank Revision 52-09/29/2016 NAPS UFSAR 16.2-116.2 TECHNICAL REQUIREMENTSThe Technical Requirements Manual (TRM) cont ains requirements for plant operation and surveillance of systems formerly contained in the T echnical Specifications, along with other selected items. Some requirements were removed from the Technical Specifications as part of NRC and industry efforts to simplify Technical Specifications.
: 4. Provisions for assessing the need for addition actions after the discovery of additional equipment out of service conditions while in the LCO Actions Table.
The TRM is controlled by st ation procedure, and a 10 CFR 50.59 review is required to change the TRM. Changes to th e TRM may be made wi thout prior NRC approval, provided that the changes do not involve a license amendment as defined in 10 CFR 50.59. Changes to the TRM that are implemented without prior NRC a pproval are reported to the NRC in accordance with 10 CFR 50.59. Proposed changes that involve a license amendment are reviewed and approved by the NRC prior to implementation.
: 5. Provisions for considering other applicable risk significant contributors such as Level 2 issue and external events, qualitatively or quantitatively.
Revision 52-09/29/2016 NAPS UFSAR 16.2-2Intentionally Blank}}
The Technical Specifications originally in this chapter have been deleted, since they are no longer applicable. References to this chapter have been amended as appropriate.
The Technical Specifications (issued as Appendix A to the Operating License) and changes thereto are contained in a separately bound document to facilitate updating independently of the FSAR.
Environmental Technical Specifications The Environmental Technical Specifications (ETS) define plant variables, operating conditions, monitoring requirements, and administrative controls that are considered necessary to ensure that the station will be operated within limits of acceptable environmental impact.
VEPCO submitted proposed Environmental Technical Specifications as Chapter 16A of the FSAR during September 1976. The NRC staff issued on November 16, 1976, a working edition of the ETS.
 
Revision 5209/29/2016                                 NAPS UFSAR                     16.1-3 The ETS underwent an iterative process of review and development between VEPCO and the NRC. The finalized version of the ETS was issued by the NRC as Appendix B to the Operating License.
The ETS originally in this chapter have been deleted since they are no longer applicable.
References to this chapter have been amended as appropriate.
The Environmental Technical Specifications and changes thereto are contained in a separately bound document to facilitate updating independently of the FSAR.
The Environmental Technical Specifications have subsequently been replaced by the Environmental Protection Plan, Appendix B of the Facility Operating License.
 
Revision 5209/29/2016                   NAPS UFSAR 16.1-4 Intentionally Blank
 
Revision 5209/29/2016                                   NAPS UFSAR                   16.2-1 16.2 TECHNICAL REQUIREMENTS The Technical Requirements Manual (TRM) contains requirements for plant operation and surveillance of systems formerly contained in the Technical Specifications, along with other selected items. Some requirements were removed from the Technical Specifications as part of NRC and industry efforts to simplify Technical Specifications.
The TRM is controlled by station procedure, and a 10 CFR 50.59 review is required to change the TRM. Changes to the TRM may be made without prior NRC approval, provided that the changes do not involve a license amendment as defined in 10 CFR 50.59. Changes to the TRM that are implemented without prior NRC approval are reported to the NRC in accordance with 10 CFR 50.59. Proposed changes that involve a license amendment are reviewed and approved by the NRC prior to implementation.
 
Revision 5209/29/2016                   NAPS UFSAR 16.2-2 Intentionally Blank}}

Latest revision as of 08:53, 30 October 2019

Redacted Updated Final Safety Analysis Report Chapter 16
ML17033B585
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 09/29/2016
From: V Sreenivas
Plant Licensing Branch II
To: Heacock D
Virginia Electric & Power Co (VEPCO)
Sreenivas V, NRR/DORL/LPL2-1, 415-2597
Shared Package
ML17033B477 List:
References
Download: ML17033B585 (10)


Text

North Anna Power Station Updated Final Safety Analysis Report Chapter 16

Intentionally Blank Revision 5209/29/2016 NAPS UFSAR 16-i Chapter 16: Technical Specifications and Requirements Table of Contents Section Title Page 16.1 SAFETY AND ENVIRONMENTAL TECHNICAL SPECIFICATIONS . . . . . . 16.1-1 16.2 TECHNICAL REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16.2-1

Revision 5209/29/2016 NAPS UFSAR 16-ii Intentionally Blank

Revision 5209/29/2016 NAPS UFSAR 16.1-1 CHAPTER 16 TECHNICAL SPECIFICATIONS AND REQUIREMENTS 16.1 SAFETY AND ENVIRONMENTAL TECHNICAL SPECIFICATIONS Technical Specifications define plant variables, operating conditions, surveillance requirements, and administrative controls that are considered necessary to ensure the health and safety of the public.

The scope of these specifications is as set forth in Section 50.36 of 10 CFR 50 for Final Safety Analysis Report Technical Specifications. Items in six broad categories are included:

(1) safety limits, (2) limiting safety system settings, (3) limiting conditions for operation, (4) surveillance requirements, (5) design features, and (6) administrative controls.

Safety limits are limits upon measurable plant variables, such as thermal power, neutron flux, flow rates, pressures, and temperatures, which ensure fuel cladding and reactor coolant system integrity.

Limiting safety system settings are settings for automatic protective devices that ensure that even under the most adverse situation anticipated, a safety limit will not be exceeded. Prime examples are the reactor trip settings. Instrument inaccuracies, calibration errors, and circuit response times, as well as calculational uncertainties, are considered.

Limiting conditions for operation primarily establish the conditions of the various safety-related components and systems necessary to either begin reactor operation or to continue operation. The reactor coolant system, Chemical and Volume Control System, steam and power conversion system, instrumentation systems, containment system, auxiliary electrical systems, and the systems making up the engineered safety features have minimum acceptable capabilities.

Specifications on pumps, valves, tanks, fluid levels, chemical constituents in certain fluids, radioactivity levels, etc., ensure that the above systems meet their minimum acceptable performance levels.

Surveillance requirements are imposed on plant conditions, systems, and components to ensure that the limiting conditions for operation are being met. Tests, checks, calibrations, inspections, and samplings at appropriate intervals verify the required plant conditions and performance capability of systems and components.

Design features include a description of the plants site, reactor containment, reactor core, reactor coolant system, and fuel storage facilities. The purpose of this section is to delineate the features of a plant not covered in other specifications.

Revision 5209/29/2016 NAPS UFSAR 16.1-2 Administrative controls are meant to prevent the existence or development of an unsafe condition in connection with the operation of the reactor. They also define the administrative action to be taken in the event a safety limit or allowed condition for operation is exceeded.

Requirements concerning the facilitys organization and management, procedures, record-keeping, review and audit, and reporting are specified.

The Configuration Risk Management Program (CRMP) provides a proceduralized risk-informed assessment to manage risks associated with equipment inoperability. The program applies to technical specification structures, systems, and components for which a risk-informed allowed outage time has been granted. The program includes the following elements:

1. Provisions for the control and implementation of a Level 1, at power, internal events, PRA-informed methodology. The assessment shall be capable of evaluating the applicable plant configuration.
2. Provisions for performing an assessment prior to entering an LCO Actions Table for planned activities.
3. Provisions for performing an assessment after entering the LCO Actions Table for unplanned entry into the LCO Condition(s).
4. Provisions for assessing the need for addition actions after the discovery of additional equipment out of service conditions while in the LCO Actions Table.
5. Provisions for considering other applicable risk significant contributors such as Level 2 issue and external events, qualitatively or quantitatively.

The Technical Specifications originally in this chapter have been deleted, since they are no longer applicable. References to this chapter have been amended as appropriate.

The Technical Specifications (issued as Appendix A to the Operating License) and changes thereto are contained in a separately bound document to facilitate updating independently of the FSAR.

Environmental Technical Specifications The Environmental Technical Specifications (ETS) define plant variables, operating conditions, monitoring requirements, and administrative controls that are considered necessary to ensure that the station will be operated within limits of acceptable environmental impact.

VEPCO submitted proposed Environmental Technical Specifications as Chapter 16A of the FSAR during September 1976. The NRC staff issued on November 16, 1976, a working edition of the ETS.

Revision 5209/29/2016 NAPS UFSAR 16.1-3 The ETS underwent an iterative process of review and development between VEPCO and the NRC. The finalized version of the ETS was issued by the NRC as Appendix B to the Operating License.

The ETS originally in this chapter have been deleted since they are no longer applicable.

References to this chapter have been amended as appropriate.

The Environmental Technical Specifications and changes thereto are contained in a separately bound document to facilitate updating independently of the FSAR.

The Environmental Technical Specifications have subsequently been replaced by the Environmental Protection Plan, Appendix B of the Facility Operating License.

Revision 5209/29/2016 NAPS UFSAR 16.1-4 Intentionally Blank

Revision 5209/29/2016 NAPS UFSAR 16.2-1 16.2 TECHNICAL REQUIREMENTS The Technical Requirements Manual (TRM) contains requirements for plant operation and surveillance of systems formerly contained in the Technical Specifications, along with other selected items. Some requirements were removed from the Technical Specifications as part of NRC and industry efforts to simplify Technical Specifications.

The TRM is controlled by station procedure, and a 10 CFR 50.59 review is required to change the TRM. Changes to the TRM may be made without prior NRC approval, provided that the changes do not involve a license amendment as defined in 10 CFR 50.59. Changes to the TRM that are implemented without prior NRC approval are reported to the NRC in accordance with 10 CFR 50.59. Proposed changes that involve a license amendment are reviewed and approved by the NRC prior to implementation.

Revision 5209/29/2016 NAPS UFSAR 16.2-2 Intentionally Blank