ML20007E344

GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 13 - Conduct of Operations

ML20007E344
Person / Time
Site:	05200001, 05200045
Issue date:	12/20/2019
From:	Michelle Catts GE-Hitachi Nuclear Energy Americas
To:	Office of Nuclear Reactor Regulation
Shea J
References
GEHITACHIABWR, GEHITACHIABWR.SUBMISSION.8, 25A5675.P, 25A5675.P.7
Download: ML20007E344 (21)

Text

25A5675AR Revision 7 October 2019 ABWR Design Control Document Tier 2 Chapter 13 Conduct of Operations Copyright 1994, 2010, 2016, 2019 GE-Hitachi Nuclear Energy Americas LLC All Rights Reserved

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 Chapter 13 Table of Contents 13.0 Conduct of Operations .................................................................................................................13.1-1 13.1 Organizational Structure of Applicant.........................................................................................13.1-1 13.2 Training........................................................................................................................................13.2-1 13.2.1 Reactor Operator Training...........................................................................................13.2-1 13.2.2 Training For Non-Licensed Plant Staff .......................................................................13.2-1 13.2.3 COL License Information............................................................................................13.2-1 13.3 Emergency Planning ....................................................................................................................13.3-1 13.3.1 COL License Information............................................................................................13.3-1 13.3.2 References ...................................................................................................................13.3-1 13.4 Review and Audit ........................................................................................................................13.4-1 13.4.1 COL License Information............................................................................................13.4-1 13.5 Plant Procedures ..........................................................................................................................13.5-1 13.5.1 Administrative Procedures ..........................................................................................13.5-1 13.5.2 Operating and Maintenance Procedures......................................................................13.5-1 13.5.3 COL License Information............................................................................................13.5-1 13.5.4 References ...................................................................................................................13.5-9 13.6 Physical Security..........................................................................................................................13.6-1 13.6.1 Preliminary Planning ...................................................................................................13.6-1 13.6.2 Security Plan................................................................................................................13.6-1 13.6.3 COL License Information............................................................................................13.6-1 Table of Contents 13.0 -i

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 Chapter 13 List of Tables Table 13.3-1 ABWR Design Considerations for Emergency Planning Requirements ....................13.3-2 13.0-ii List of Tables

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 13.0 Conduct of Operations 13.1 Organizational Structure of Applicant Out of ABWR Standard Plant scope.

Organizational Structure of Applicant 13.1-1

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 13.2 Training 13.2.1 Reactor Operator Training Out of ABWR Standard Plant scope.

13.2.2 Training For Non-Licensed Plant Staff Out of ABWR Standard Plant scope.

13.2.3 COL License Information 13.2.3.1 Incorporation of Operating Experience The results of reviews of operating experience shall be incorporated into training and retraining programs in accordance with the provisions of TMI Action Item I.C.5, Appendix 1A. The organizational responsibilities for accomplishing this shall be clearly identified.

Training 13.2-1

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 13.3 Emergency Planning Emergency planning is not within the scope of the ABWR design. However, there are design features, facilities, functions, and equipment necessary to support emergency planning. The design features in the ABWR Standard Plant scope include the technical support center (TSC) and the operational support center (OSC), which are described in Table 13.3-1. The emergency operations facility (EOF), also described in Table 13.3-1, is beyond the scope of the ABWR design and is addressed as COL license information in Subsection 19A.3.4 relative to the 50.34(f)(2)(XXV) requirement. Additional ABWR design considerations pertaining to emergency planning are contained in Table 13.3.-1. The COL applicant shall provide emergency plans in accordance with 10CFR50.33(g) and 52.79(d). See Subsection 13.3.1.1 for COL license information.

NEI 12-01 Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities (Reference 13.3-1) shall be used to assess staff and communications capabilities to respond to a beyond design basis event for Emergency Planning. The required assumptions for the event shall be:

all on-site unit(s) affected extended loss of AC power impeded access to the unit(s).

13.3.1 COL License Information 13.3.1.1 Emergency Plans The COL applicant shall provide emergency plans in accordance with 10CFR50.33(g) and 52.79(d). (See Section 13.3) 13.3.1.2 Staffing and Communications Capabilities Perform an assessment as described in NEI 12-01 (Reference 13.3-1) to assess staff and communications capabilities needed to respond to a beyond design basis event.

13.3.2 References 13.3-1 NEI 12-01, Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities, NEI, May 2012.

Emergency Planning 13.3-1

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 Table 13.3-1 ABWR Design Considerations for Emergency Planning Requirements Primary Document/ Emergency Planning Facility Section Requirements ABWR Design Consideration Technical Support NUREG-0696/ The TSC is an onsite facility The ABWR Standard Plant will Center (TSC) 1.3.1 located close to the control comply with all the TSC design room that shall provide plant requirements. Specifically, a TSC management and technical of sufficient size (at least 175 m2 support to the reactor of floor space) to support 25 operating personnel located in people is located in the service the control room during building adjacent to the control emergency conditions. It shall building. The TSC is non-safety-have technical data displays related and is not Seismic and plant records available to Category I. The necessary assist in the detailed analysis facilities and equipment are and diagnosis of abnormal called for in Section 2 of plant conditions and any NUREG-0696.

significant release of radioactivity to the The TSC has displays for the environment. The TSC shall be plant parameters which are the primary communications included in the fixed position center for the plant during an displays on the Main emergency. A senior official, Control Room Panels.

designated by the licensee, shall use the resources of the The TSC has voice TSC to assist the control room communication equipment for operators by handling the communication with the Main administrative items, technical Control Room, Emergency evaluations, and contact with Operations Facility, Operational offsite activities, relieving them Support Center (OSC), and NRC of these functions. The TSC Headquarters Operation Center.

facilities may also be used for performing normal functions, As shown on Figure 12.3-64, the such as shift technical TSC has an installed area supervisor and plant radiation monitor.

operations/ maintenance analysis functions, as well as for emergencies.

13.3-2 Emergency Planning

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 Table 13.3-1 ABWR Design Considerations for Emergency Planning Requirements (Continued)

Primary Document/ Emergency Planning Facility Section Requirements ABWR Design Consideration Operational NUREG-0696/ The OSC is an onsite The ABWR Standard Plant will Support Center 1.3.2 assembly area separate from comply with all the OSC design (OSC) the control room and the TSC requirements. Specifically, the where licensee operations lunch room adjacent to the TSC support personnel report in an in the service building which is emergency. There is direct adjacent to the control building communications between the will be identified as the OSC. The OSC and the control room and OSC is non-safety-related and is between the OSC and the TSC not seismic Category I. The OSC so that the personnel reporting has voice communication to the OSC can be assigned to equipment for communication duties in support of emergency with the main control room and operations. the TSC. The COL applicant is responsible for identifying the communication interfaces for inclusion in the detailed design of the control room and TSC. The detailed requirements are provided in Section 3 of NUREG-0696.

Emergency Planning 13.3-3

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 Table 13.3-1 ABWR Design Considerations for Emergency Planning Requirements (Continued)

Primary Document/ Emergency Planning Facility Section Requirements ABWR Design Consideration Emergency NUREG-0696/ The EOF is an offsite support The EOF is not within the scope Operations Facility 1.3.3 facility for the management of of the ABWR Standard Plant. It is (EOF) overall licensee emergency the responsibility of the COL response, coordination of applicant to identify his EOF and radiological and environmental the communication interfaces for assessments and inclusion in the detailed design of determination of recommended the TSC and control room. The public protective actions. The detailed requirements are EOF has appropriate technical provided in Section 4 of data displays and plant records NUREG-0696.

to assist in the diagnosis of plant conditions to evaluate the potential or actual release of radioactive materials to the environment. A senior licensee official in the EOF organizes and manages licensee offsite resources to support the TSC and the control room operators. Assembly area separate from the control room and the TSC, shall be provided for operations support personnel to report in an emergency. There shall be direct communications between the OSC and control room and between the OSC and the TSC so that the personnel reporting to the OSC can be assigned to duties in emergency operations.

Emergency NUREG-0654/ Each licensee shall make Not within the scope of the Operations Center II.H.6 provision to acquire data from ABWR Standard Plant. However, (EOC) or for emergency access to no impact on ABWR design.

offsite monitoring equipment including geophysical phenomena and radiological monitors.

Laboratory NUREG-0654/ Provisions to acquire data from Responsibility of COL applicant.

Facilities, Fixed or II.H.6.c or for emergency access to ABWR design allows applicant to Mobile offsite monitoring and analysis meet this requirement.

equipment for laboratory facilities, fixed or mobile.

13.3-4 Emergency Planning

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 Table 13.3-1 ABWR Design Considerations for Emergency Planning Requirements (Continued)

Primary Document/ Emergency Planning Facility Section Requirements ABWR Design Consideration Post-Accident NUREG-0737/ Post-accident sampling The counting room for analyzing Sampling System II.B.3 capability. post-accident samples is located in the Service Building. Post-accident sampling system of Subsection 9.3.2 meets requirements except as described in Section 1A.2.7 for the upper limit of activity in the samples at the time they are taken.

Onsite 10CFR50 Provisions shall be made and Decontamination of onsite Decontamination Appendix E/ described for facilities and individuals will be provided by the Facility IV.E.3 supplies at the site for COL applicant in the service decontamination of onsite building adjacent to the main individuals. change rooms (See Figure 1.2-20).

Emergency Planning 13.3-5

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 13.4 Review and Audit 13.4.1 COL License Information The COL applicant shall provide a plan for conducting reviews of operating phase activities that are important to safety. The provisions for the plant operations review of operational activities, for the independent review of plant operations and for the independent assessment of activities for safety enhancement should be provided in accordance with 10 CFR 50.40 (b), TMI Action Item I.B.1.2, and ANSI 18.7/ANS 3.2 or subsequent NRC-approved version of ANSI/ANS 3.2 elected by the COL applicant.

Review and Audit 13.4-1

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 13.5 Plant Procedures 13.5.1 Administrative Procedures Out of ABWR Standard Plant scope.

13.5.2 Operating and Maintenance Procedures Out of ABWR Standard Plant scope.

13.5.3 COL License Information 13.5.3.1 Plant Operating Procedures Development Plan A Plant Operating Procedures Development Plan shall be generated which establishes:

That the scope encompassed by the procedures development process includes those operating procedures defined in Subsection 13.5.3.4, which direct operator actions during normal, abnormal and emergency operations, including consideration of plant operations during periods when plant systems/equipment are undergoing test, maintenance or inspection.

The methods and criteria for the development, verification and validation, implementation, maintenance and revision of procedures. The methods and criteria shall be in accordance with TMI Items I.C.1 and I.C.9.

13.5.3.2 Emergency Procedures Development In addition to the above, for Emergency Procedures development, the plan shall establish:

That a writer's guide shall be developed and implemented which defines the process for developing emergency procedures. The writer's guide shall contain objective criteria which will require that the emergency procedures developed are consistent in organization, style, content and usage of terms.

The form and content of the documentation describing the emergency procedure development activity results which includes, but is not limited to: (1) the objectives of the emergency procedure development process, (2) the methods employed during emergency procedure development, (3) deviations from generic technical guidelines approved by the NRC and (4) discussion of any design change recommendations and/or negative implications that the current design may have on safe operation as a result of emergency procedures development plan implementation.

The procedure development will integrate the Emergency Operating Procedures (EOPs),

Severe Accident Management Guidelines (SAMGs), and Extensive Damage Mitigation Guidelines (EDMGs) by using the following guidance:

Plant Procedures 13.5-1

25A5675AR Revision 7 ABWR Design Control Document/Tier 2

- Industry (BWROG) guidance as endorsed by applicable NRC regulatory guides consistent with the Task Force recommendation as described in SECY-11-0124 (Reference 13.5-9).

- Plant Specific Technical Guidelines (PSTGs), EOPs and SAMGs development activities using as inputs the standard ABWR guidelines (DCD) and generic industry guidance per NEI 91-04, Revision 1, Severe Accident Issue Closure Guidelines (Reference 13.5-10), which includes the industry commitment to incorporate severe accident strategies into the overall accident management program.

- EDMGs development as described in NEI 06-12, Reference 13.5-11.

- The EOPs, EDMGs and SAMGs will be integrated in a cohesive, effective and useable manner as described in NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents (Reference 13.5-12).

13.5.3.3 Implementation of the Plan Implementation of the Plant Operating Procedures Development Plan shall establish:

Procedures which are consistent with the requirements of 10 CFR Part 50 and the TMI requirements described in NUREG-0737 and Supplement 1 to NUREG-0737.

Requirements that the procedures developed shall include, as necessary, the elements described in ANSI 18.7/ANS-3.2 or subsequent NRC-approved version of ANSI/ANS-3.2 elected by the COL applicant.

That the operator actions identified in the vendors task analysis and PRA efforts in support of the Standardized Design certification, Standardized Plant Design Emergency Procedure Guidelines and consideration of plant-specific equipment selection and site-specific elements such as the service water intake structure and the ultimate heat sink shall be used as a basis for specifying plant operating procedures.

The definition of the methods through which specific operator skills and training needs, as may be considered necessary for reliable execution of the procedures, will be identified and documented.

That the procedures specified in a., above, shall be made available for the purposes of the Human Factors V&V Implementation Plan described in Article VII of Table 18E-1.

Procedures for the incorporation of the results of operating experience and the feedback of pertinent information into plant procedures in accordance with the provisions of TMI I.C..5.

13.5-2 Plant Procedures

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 13.5.3.4 Procedures Included In Scope Of Plan The following procedures shall be included in the scope of the Plant Operating Procedures Development Plan described above:

System Procedures Procedures as delineated in Section A3 of ANSI/ANS-3.2 shall be prepared, as appropriate, for the following BWR systems:

Nuclear Boiler Control Rod Drive Reactor Water Cleanup Standby Liquid Control Residual Heat Removal High Pressure Core Flooder Reactor Core Isolation Cooling Reactor Building Cooling Water Containment

- Maintaining Integrity

- Containment Ventilation

- Inerting and Deinerting Fuel Pool Cooling & Cleanup Main Steam Turbine/Generator Condensate/Feedwater Makeup Water Reactor Service Water Turbine Service Water Reactor Building HVAC Plant Procedures 13.5-3

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 Control Room HVAC Radwaste Building HVAC Standby Gas Treatment Instrument Air Electrical

- Offsite: Circuits between offsite transmission network and the onsite Class 1E distribution system

- Onsite: Emergency Power Sources (e.g., Diesel generator, batteries)

AC System DC System Neutron Monitoring

- Source Range

- Intermediate Range

- Power Range

- TIP System Reactor Protection Rod Worth Minimizer Hydrogen Recombiners Procedures For Off-Normal Or Alarm Conditions.

Prepare all procedures for off-normal or alarm conditions that require operator action in the MCR and RSS. These correspond to the number of alarm annunciators. Each annunciator important to safety should have its own written procedure, which should normally contain (a) the meaning of the annunciator, (b) the source of the signal, (c) the immediate action that is to occur automatically, (d) the immediate operator action and (e) the long-range actions. If more than one annunciator applies to a given procedure, repetition of the procedure may not be required if the applicable annunciators are listed at the beginning of the procedure.

General Plant Operating Procedures.

As discussed in Section A5 of ANSI/ANS-3.2, procedures shall be prepared for the integrated operations of the plant. Typical general plant procedures are listed below:

13.5-4 Plant Procedures

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 Cold Shutdown to Hot Standby Hot Standby to Minimum Load (nuclear startup)

Recovery from Reactor Trip Operation at Hot Standby Turbine Startup and Synchronization of Generator Changing Load and Load Follow (if applicable)

Power Operation and Process Monitoring Power Operation with Less than Full Reactor Coolant Flow Plant Shutdown to Hot Standby Hot Standby to Cold Shutdown Preparation for Refueling and Refueling Equipment Operation Refueling and Core Alterations Procedures for Combating Emergencies and Other Significant Events.

As discussed in Section A10 of ANSI/ANS-3.2, procedures shall be provided to guide operations in emergencies and other significant events. Examples of such events are listed below. If symptomatic procedures are used, a single procedure may cover multiple events.

Loss of Coolant (inside and outside primary containment) (response to large and small breaks, including leak-rate determination),

Loss of Instrument Air Loss of Electrical Power or Degraded Power Sources, or both.

Loss of Core Coolant Flow Loss of Condenser Vacuum Loss of Containment Integrity Loss of Service Water Loss of Shutdown Cooling Loss of Component Cooling System and Cooling to Individual Components Plant Procedures 13.5-5

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 Loss of Feedwater or Feedwater System Failure (including verification of proper operation of the auxiliary feedwater system)

Loss of Protective System Channel Mispositioned Control Rod or Rods (and rod drops)

Inability to drive control rods Conditions Requiring Use of Standby Liquid Control System Fuel Cladding Failure or High Activity in Reactor Coolant or Offgas Fire in Control Room or Forced Evacuation of Control Room Turbine and Generator Trips Other Expected Transients That May Be Applicable Malfunction of Automatic Reactivity Control System Malfunction of Pressure Control System Reactor Trip Plant Fires Acts of Nature (e.g., tornado, flood, dam failure, earthquake)

Irradiated Fuel Damage While Refueling Abnormal Releases of Radioactivity Intrusion of Demineralizer Resin into Primary System Hydrogen Explosions Aircraft impact (see Section 19G)

Containment Isolation (including reopening of individual isolation valves following reset of safety injection or containment isolation valves).

Achievement and Maintenance of Natural Circulation.

Safe Shutdown and Cooldown of the reactor core under a degraded core condition, including sampling of the reactor coolant and containment atmosphere.

Loss of Annunciators 13.5-6 Plant Procedures

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 In addition, procedures shall be prepared for activation and implementation of the facility emergency plan. For example, a procedure should be prepared which describes the emergency action level classification system.

In addition, procedures shall be prepared for plant operations during plant systems/equipment and HSI (i.e., MCR and RSS) equipment testing, maintenance or inspection.

Procedures for Maintenance and Modification.

Prepare all maintenance and modification procedures that require operator actions to be taken in the MCR or RSS, including the following:

Exercise of equipment that is normally idle but that must operate when required.

Removal of Reactor Head.

Reactor Coolant System operation with loops partially drained.

Procedures for radiation control.

As discussed in Section A7(d) of ANSI/ANS-3.2, the following procedures shall be prepared:

Mechanical Vacuum Pump Operation Air Ejector Operation.

Packing Steam Exhauster Operation Sampling Air Ejection, Ventilation and Stack Monitor.

Area Radiation Monitoring System Operation Process Radiation Monitoring System Operation Meteorological Monitoring Discharge of Effluents Dose Calculations Procedures for Calibration, Inspection and Testing.

Prepare all calibration, inspection and testing procedures that require operator actions to be taken in the MCR or RSS, including the following:

Containment Isolation Tests Plant Procedures 13.5-7

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 Containment Vacuum Relief Valve Tests Containment Spray System Tests Standby Gas Treatment System Tests (including filter tests)

Emergency Service Water System Functional Tests Main Steam Isolation Valve Tests Fire Protector System Functional Tests Nitrogen Inerting System Tests Emergency Core Cooling System Tests Control Rod Operability and Scram Time Tests Reactor Protection System Tests and Calibrations Rod Block-Tests and Calibrations Liquid Poison System Tests Minimum Critical Heat Flux Checks and In Core Flux Monitor Calibrations Emergency Power Tests Isolation Condenser or Reactor Core Isolation Cooling (RCIC) Tests NSSS Pressurization and Leak Detection Control Rod Drive System Functional Tests Core Physics Surveillance, Including Heat Balance Axial and Radial Flux Pattern Determination Safety Valve Tests Turbine Overspeed Trip Test 13.5-8 Plant Procedures

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 13.5.4 References In addition to the sources cited previously, accepted methods and criteria for development of plant procedures are embodied in the following documents.

13.5-1 Gilmore, et al, User-Computer Interface in Process Control: A Human Factors Engineering Handbook, Academic Press, San Diego, Ca, 1989 13.5-2 IEC 964, Design for Control Rooms of Nuclear Power Plants, Bureau Central de la Commission Electrotechnique Internationale 13.5-3 MIL-H-46855B, Human Engineering Requirements for Military Systems, Equipment and Facilities, Dept. of Defense 13.5-4 MIL-STD-1472D, Human Engineering Design Criteria for Military Systems, Equipment and Facilities, Dept. of Defense 13.5-5 NUREG-0899, Guidelines for the Preparation of Emergency Operating Procedures, USNRC, 1982 13.5-6 NUREG-1358, Lessons Learned From the Special Inspection Program for Emergency Operating Procedures, USNRC, 1989 13.5-7 NUREG-1358, Supplement 1, Lessons Learned From the Special Inspection Program for Emergency Operating Procedures, USNRC, 1992 13.5-8 NUREG/CR-5228, Techniques for Preparing Flowchart Format Emergency Operating Procedures (Vols. 1 & 2), USNRC, 1989 13.5-9 SECY-11-0124, Recommended Actions to be Taken Without Delay from the Near-Term Task Force Report, USNRC, September 9, 2011.

13.5-10 NEI 91-04 Revision 1, Severe Accident Issue Closure Guidelines, NEI, 1994.

13.5-11 NEI 06-12 Revision 2, B.5.b Phase 2 & 3 Submittal Guideline, NEI, 2006.

13.5-12 NEI 14-01 Revision 0, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents, NEI, 2014.

Plant Procedures 13.5-9

25A5675AR Revision 7 ABWR Design Control Document/Tier 2 13.6 Physical Security 13.6.1 Preliminary Planning Not Required.

13.6.2 Security Plan The portion of the physical security plan, which is in the ABWR Standard Plant scope, is not included in DCD (Refer to SSAR Subsections 13.6.3.1, 13.6.3.2 and 13.6.3.3, Amendment 33).

13.6.3 COL License Information Safeguards Information not included in DCD (Refer to SSAR Subsection 13.6.3, Amendment 33).

Physical Security 13.6-1