ML20116A442

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Westinghouse AP600 Chapter 14,Initial Test Program
ML20116A442
Person / Time
Site: 05200003
Issue date: 07/31/1996
From:
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20116A409 List:
References
PROC-960731, NUDOCS 9607260094
Download: ML20116A442 (127)
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Text

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DRAFT 1

Enclosure to Westinghouse Letter NSD-NRC-%-4772 Westinghouse AP600 Chapter 14, Initial Test Program 9

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4 9607260094 960716 PDR ADOCK 05200003 A PDR

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14. Initial Test Program TABLE OF CONTENTS  ;

l 14.1 Specific Information to be Included in Preliminary / Final Safety Analysis Reports 14-1 ,

l 14.2 Specific Information to be Included in Standard Safety Analysis Reports ... . 14-1 14.2.1 Summary of Test Program and Objectives . ...... ... .. 14-1 14.2.1.1 Construction and Installation Test Program Objectives . .. ... . .. 14-2 14.2.1.2 Preoperational Test Program Objectives .. . . . . . . . 14-3 14.2.1.3 Startup Test Program Objectives . . . . . . . .. .. .. ... ... 14-3 14.2.2 Organization, Staffing, and Responsibilities . . ... . . 14-4 14.2.3 Test Procedures . .... . . .. . ..... . . . 14-4  !

14.2.3.1 Conduct of Test Program . ...... ... .. . . ... . . 14-5 1 14.2.3.2 Review of Test Results . . ... . . . ... . ......... 14-6 14.2.3.3 Test Records . .... ....... .. ...... . . ... . ... 14-6 14.2.4 Compliance of Test Program with Regulatory Guides . .. .. .. ..... 14-6 14.2.5 Utilization of Reactor Operating and Testing Experience in the Development of Test Program . .. .. .. ...... .. . .. .. . .... ..... 14-6 l 14-7 l 14.2.6 Use of Plant Operating and Emergency Procedures . . . ..... . . ... .

14.2.7 Initial Fuel Loading and Initial Criticality . . . . ... . . . . .. 14-7 j 14.2.7.1 Initial Fuel Loading . . ... .... . .. .. . .... . . 14-7 14.2.7.2 Initial Criticality .. . . . .. .. . . . . ..... ... .. ... 14-9*

14.2.7.3 Power Ascension .... ... . . . . . . . . 14-9  ;

14.2.8 Test Program Schedule .. . . . . . ... ... .. 14-10 '

14.2.9 Preoperational Test Descriptions . .. . . ... .. .14-10 14.2.9.1 Preoperational Tests of Systems with Safety-Related Functions . . . . .

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14.2.9.1.1 Reactor Coolant System Testing .. .. .. . ... . . . . . . . . . . . 14- 1 1 l 14.2.9.1.2 Steam Generator System Testing . . . . . . . . ... 14-14 14.2.9.1.3 Passive Core Cooling System Testing ......... . .... ... . .. 14-16 i 14.2.9.1.4 Passive Containment Cooling System Testing .. . . ... .. . . 14-19 l 14.2.9.1.5 Chemical and Volume Control System Isolation Testing . .. . . .. . 14-21 14.2.9.1.6 Main Control Room Emergency Habitability System Testing ... . . 14-22 14.2.9.1.7 Expansion, Vibration and Dynamic Effects Testing . . . . .. . .. 14-23 14.2.9.1.8 Control Rod Drive System . .. ... . .. . .. . .. 14-25 14.2.9.1.9 Reactor Vessel Internals Vibration Testing (First Plant Only) . .. . .14-26 )

14.2.9.1.10 Containment Isolation and Leak Rate Testing . .. . . .... . . .. 14-27 14.2.9.1.11 Containment Hydrogen Control System Testing . . .. ... 14-29 j 14.2.9.l.12 Protection and Safety Monitoring System Testing . . .. ... ... 14-30 14.2.9.1.13 Incore Instrumentation System Testing ..... ..... ....... . . .14-32 14.2.9.1.14 Class 1E DC Power and Uninterruptable Power Supply Testing . . ..... .14-33 14.2.9.1.15 Fuel Handling and Reactor Component Servicing Equipment Test . . . . . . 14-35 14.2.9.1.16 Long-Term Safety-Related System Support Testing . . . ...... . . . .14-37 14.2.9.2 Preoperational Testing of Defense in-Depth Systems . ....... . .. 14-39  ;

14.2.9.2.1 Main Steam System Testing . . ... . . . 14-39 l

i 14.2.9.2.2 Main and Startup Feedwater System . . . .. .. . . 14-39 l 14.2.9.2.3 Chemical and Volume Control System Testing . .. .. . .. 14-40

. 14.2.9.2.4 Normal Residual Heat Removal System Testing . . 14-41 l

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i TABLE OF CONTENTS (cont) i i

14.2.9.2.5 Component Cooling Water System Testing . . .. .... . 14-43 i 14.2.9.2.6 Service Water System Testing . . . ... .. .. . . . .. ... . 14-44 l 14.2.9.2.7 Spent Fuel Pool Cooling System Testing . . ...... . . 14-45 j 14.2.9.2.8 Fire Protection System Testing ...... ... . . ... . . . . 14-47 ,

14.2.9.2.9 Central Chilled Water System Testing .. . .. .. . ...... . . 14-47 l 14.2.9.2.10 Nuclear Island Nonradioactive Ventilation System Testing . .. .... . . . 14-48 14.2.9.2.11 Radiologically Controlled Area Ventilation System . .. . ... .... . . 14-50 14.2.9.2.12 Plant Control System Testing .. . . .. . .. ... . .. 14-51 ,

l 14.2.9.2.13 Data Display and Processing System Testing . . . . . .. .. ...... . . 14-52 14.2.9.2.14 Diverse Actuation System Testing . . . . ...... . .. .... . . . 14-54 14.2.9.2.15 Main AC Power System Testing . .. . .. ....... . .. .14-55 14.2.9.2.16 Non-Class IE de and Uninterruptable Power Supply System Testing .. .. . 14-56 14.2.9.2.17 Diesel Generator Testing . . . ......... . . ..... ... .14-57 14.2.9.2.18 Radiation Monitoring System Testing . .. . ... ... .. . . . . 14-59 14.2.9.2.19 Plant Lighting System Testing . . ......... . . .. .. .. . ... 14-59 14.2.9.2.20 Primary Sampling System Testing . ... . . . . ... .. .. . 14-60 14.2.9.3 Preoperational Testing of Nonsafety-Related Radioactive Systems . . . .. 14-61 14.2.9.3.1 Liquid Radwaste System Testing . . . .. ... ............... .. . 14-61 14.2.9.3.2 Gaseous Radwaste System Testing . . . . . . . . .... . .... ..... 14-62*-

14.2.9.3.3 Solid Radwaste System Testing . . . . . . .. .. .. ..... ...... 14-63 14.2.9.3.4 Radioactive Waste Drain System Testing . .. . .. .. .. . .. 14-64 14.2.9.3.5 Steam Generator Blowdown System Testing . ... . ... .. . .. 14-65 14.2.9.3.6 Waste Water System Testing . . ... . .... . ... . 14-66 14.2.9.4 Preoperational Tests of Additional Non-Safety-related Systems . .. . . 14-66 14.2.9.4.1 Condensate System Testing . . . . .. .. . . . . 14-66 14.2.9.4.2 Condenser Air Removal System Testing . . . . .. ... .. .. . 14-67 14.2.9.4.3 Main Turbine System and Auxiliaries Testing .... ... .... . ... . 14-68 14.2.9.4.4 Main Generator System and Auxiliaries Testing .... .... .. . ......I4-69 14.2.9.4.5 Turbine Building Clo. sed Cooling Water System Testing . .. . ... . . 14-70 14.2.9.4.6 Circulating Water System Testing . . . . . . . . . . . . ........ .. 14-70 14.2.9.4.7 Turbine Island Chemical Feed System Testing . . . ...... . .. ... 14-71 14.2.9.4.8 Condensate Polishing System Testing . ... . . .. .... ..... . . 14-72 14.2.9.4.9 Demineralized Water Transfer and Storage System Testing . . . .. . 14-72 14.2,.9.4.10 Compressed and Instrument Air System Testing ... .... . 14-73 14.2.9.4.11 Containment Recirculation Cooling System Testing . .. .. .. .. .. . 14-73 14.2.9.4.12 Containment Air Filtration System Testing . . . . ... . .... . 14-74 14.2.9.4.13 Plant Communications System Testing . . .. .. .. 14-75 14.2.9.4.14 Mechanical Handling System Crane Testing . . ...... 14-75 14.2.9.4.15 Seismic Monitoring System Testing . . .. . . ......... . 14-76 14.2.9.4.16 Special Monitoring System Testing . . .. .. . .... . ... .. ... 14-77 14.2.9.4.17 Secondary Sampling System Testing . .. .. .... .. 14-78 14.2.10 Startup Test Procedures . .. . . . . . . . . 14-78 14.2.10.1 Initial Fuel Loading and Precritical Tests . . ... . ...... . . . 14-79 Revision: 9 o w= moi 4 no9-07is*

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14. Initial Test Program TABLE OF CONTENTS (cont) 14.2.10.1.1 Fuel Loading Prerequisites and Periodic Checkoff .. ......... 14-79 14.2.10.1.2 Reactor Systems Sampling for Fuel Loading . . .. ... .... .. . .. 14-80 14.2.10.1.3 Fuel Loading Instrumentation and Ne tron Source Requirements . . . . 14-81 14.2.10.1.4 Inverse Count Rate Ratio Monitoring for Fuel Loading .. .. .... . I4-82 14.2.10.1.5 Initial Fuel Loading . . . .. . .... . . ... . ..... . 14-83 14.2.10.1.6 Post-Fuel Loading Precritical Test Sequence .. ... . ... . . .14-84 14.2.10.1.7 Incore Instrumentation System Precritical Verification . . . . . . .. . 14-84 14.2.10.1.8 Resistance Temperature Detectors-Incore Thermocouple Cross Calibntion . . 14-85 14.2.10.1.9 Nuclear Instrumentation System Precritical Verification ..... ... . . .14-86 14.2.10.1.10 Setpoint Precritical Verification . . ..... ... .. . .. .. ... .14-87 14.2.10.1.11 Rod Control System . .. .. .. . .. .... .. .... . 14-88 14.2.10.1.12 Rod Position Ind; cation System . ... . .... ... .. ........ .. .14-89 14.2.10.1.13 Control Rod Drive Mechanisms . .. . .... . . ..... ..... .... 14-89 14.2.10.1.14 Rod Drop Time Measurement . . . .. ... . . .. . . .. .. . . .14-90 14.2.10.1.15 Rapid Power Reduction System . . . .. . . . . ... .... .14-91 14.2.10.1.16 Process Instrumentation Alignment . . .. . . . . . .. . 14-92 ,

14.2.10.1.17 Reactor Coolant System Flow Measurement . ...... .. . . . . 14-92 14.2.10.1.18 Reactor Coolant System Flow Coastdown . . . . .... ...... .... .... 14-93 14.2.10.1.19 Pressurizer Spray Capability and Continuous Spray Flow Verification . ..... 14-93

  • 14.2.10.1.20 Feedwater Valve Stroke Test . . . . . . . .. . ..... .... .14-94 14.2.10.2 Initial Criticality Tests . . . . . ....... .. .. ... . . 14-95 14.2.10.2.1 Initial Criticality and Low-Power Test Sequence . . . ... . . . . . 14-95 14.2.10.2.2 Ir.itial Criticality .. .. .. ..... ... ...... .. ... . .. .14-95 14.2.10.2.3 Nuclear Instrumentation System Verification During Criiicality .... .... .. 14-96 14.2.10.2.4 Post-Critical Reactivity Computer Checkout .. . . ... .. . 14-97 14.2.10.3 Low Power Tests . . ... . . . ....... .. ..... .. . . . .14-98 14.2.10.3.1 Low-Power Test Sequence ... ... . ... .... .. .. . . .. 14-98 14.2.10.3.2 Determination of Physics Testing Range . .. ..... .. . ... 14-98 14.2.10.3.3 Boron Endpoint Determination . . ... . . . .. . . .. . 14-99 14.2.10.3.4 Isothermal Temperature Coefficient Measurement . ..... . . . ...14-100 .

14.2.10.3.5 Bank Worth Measurement . . . . . . .. . . ...... .. . .. . 14-101-14.2.10.3.6 Natural Circulation (First Plant Only) . . . . .... . .... .14-102 14.2.10.4 Power Ascension Tests . .. ....... .. .. . ....... . .. .14-103 14.2.10.4.1 Test Sequence . .......... . .. . . . .. ..14-103 14.2.10.4.2 Incore Instrumentation System . . . . ... . ....... . .14-103 14.2.10.4.3 Nuclear Instrumentation System . . . . .. .. . ..14-104 .

14.2.10.4.4 Setpoint Verification . . . .. . . .. . .. .. .14-105 14.2.10.4.5 Startup Adjustments of Reactor Control Systems . . ..... . . ..14-105 14.2.10.4.6 Rod Cluster Control Assembly Out of Bank Measurements . .. . . . .14-106 14.2.10.4.7 Axial Flux Difference Instrumentation Calibration . . .. ..14-107 14.2.10.4.8 Primary and Secondary Chemistry . . . . . .. ....... .14-108 14.2.10.4.9 Process Measurement Accuracy Verification . . . ...... ... ..14-109 14.2.10.4.10 Process Instrumentation Alignment at Power Conditions .. ..... .. . .14-110 o wmoi4 nou-o7is* Revision: 9 W W85tingt10US8 iii Draft July 31,1996

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14. Izitial Test ProgrEm 1

TABLE OF CONTENTS (cont) j 14.2.10.4.11 Reactor Coolant System Flow Measurement at Power Conditions .14-110 14.2.10.4.12 Steam Dump Control System . . ... . . . ... . .14-111 14.2.10.4.13 Steam Generator Level Control System .. . ...... . ..... .14-112 14.2.10.4.14 Radiation and Effluent Monitoring System . . . . . . ... .... ..14-113 14.2.10.4.15 Ventilation Capability .............. . . .. . ...14-114 14.2.10.4.16 Biological Shield Survey . . .. ..... . . ..... .. . .14-115 14.2.10.4.17 Thermal Power Measurement and Statepoint Data Collection .. . . .14-115 14.2.10.4.18 Dynamic Response . . . . . . . ........ .... ... . .. .. . .14-116 14.2.10.4.19 Reactor Power Control System ... . . .. . .. .14-117 14.2.10.4.20 Load Swing Test . . .... .. .. .. . . ... .14-117 14.2.10.4.21 100 Percent Load Rejection (First Plant Only) . . .. . .... . .14-118 14.2.10.4.22 Load Follow Demonstration (First Plant Only) . . . . . . .. ..14-119 14.2.10.4.23 Hot Full Power Boron Endpoint . . ... ....... ......... ...... ..14-120 14.2.10.4.24 Piant Trip from 100 Percent Power .. . .. ..... ............14-121 14.2.10.4.25 Thermal Expansion .......... . . ......... . . ... 14-122-l l

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14. Initial Test Program CHAPTER 14 INITIAL TEST PROGRAM 14.1 Specific Information to be Included in Preliminary / Final Safety Analysis Reports l Not applicable to the AP600.

14.2 Specific Information to be Included in Standard Safety Analysis Reports j i

14.2.1 Summary of Test Program and Objectives The purpose of this section is to describe the test program that is performed during initial startup of the AP600 plant.

i The overall objective of the test program is to demonstrate that the plant has been {

constructed as designed, that the systems perform consistent with the plant design, and that activities culminating in operation at full licensed power including initial fuel load, initial criticality, and power ascension; are performed in a controlled and safe manner. l Preoperational and/or stanup testing is performed on those systems that are:

a) Relied upon for safe shutdown and cooldown of the reactor under normal plant conditions and for maintaining the reactor in a safe condition for an extended shutdown period; b) Relied upon for safe shutdown and cooldown of the reactor under transient and postulated accident conditions and for maintaining the reactor in a safe condition for an extended shutdown period following such conditions; c) Relied upon for establishing conformance with safety limits or limiting conditions for operation that will be included in the facility technical specifications; d) Classified as engineered safety features actuation systems (ESFAS) or are relied upon to support or ensure operation of engineered safety features actuation systems within design limits; c) Assumed to function or for which credit is taken in the accident analysis of the AP600 as described in the SSAR; f) Used to process, store, control, or limit the release of radioactive materials.

g) Nonsafety-related systems identified in Regulatory Guide 1.68, Revision 2, Appendix A and are applicable to AP600.

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' 14. Initial Test Program The inspections, tests, analyses and acceptance criteria of 10 CFR 52.47 (a)(1)(vi) relating 4 to the AP600 design are found in the AP600 Inspections, Tests, Analyses and Acceptance Criteria (ITAAC) Document.

The initial plant test program consists of a series of tests categorized as constmetion and installation, preoperational, and startup tests. These tests are the responsibility of the combined operating license holder.

  • Construction and installation tests are performed to determine that plant structures, components, and systems have been constmeted or installed correctly and are operational.
  • Preoperational tests are performed after construction and installation tests, but prior to initial fuel loading to demonstrate the capability of plant systems to meet performance requirements.
  • Startup tests begin with the initial fuel loading and are performed to demonstrate the capability of individual systems, as well as the integrated plant, to meet performance requirements.

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14.2.1.1 Construction and Installation Test Program Objectives The adequacy of construction, installation, and preliminary operation of components and systems is verified by a construction and installation test program.

In this program, various electrical and mechanical tests are performed including the following:

  • Cleaning and flushing i
  • Checks of electrical wiring
  • Valve testing
  • Energization and operation of equipment
  • Calibration of mstrumentation  ;

On a system basis, completion of this program demonstrates that the system is ready for l preoperational testing.

Abstracts for tests constituting the constmetion and installation test program are not l provided in support of Design Certification. Development of the construction and installation tests is based on the engineering information for the equipment and systems installed.  !

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14. Initial Test Program 14.2.1.2 Preoperational Test Program Objectives Following construction and installation testing, preoperational tests are performed to demonstrate that equipment and systems perform in accordance with design criteria so that initial fuel loading, initial criticality, and subsequent power operation can be safely undertaken. Preoperational tests at elevated pressure and temperature are referred to as hot functional tests.

The general objectives of the preoperational test program are the following:

  • Demonstrate that essential plant components and systems, including alarms and indications, meet appropriate criteria based on the design  ;
  • Piovide documentation of the performance and condition of equipment and systems
  • Provide baseline test and operating data on equipment and systems for future use and reference

. Operate equipment for a sufficient period to demonstrate performance

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. Demonstrate that plant systems operate on an integrated basis Abstracts for the preoperational tests for portions of systems / components that perform safety-related functions; perform defense-in-depth (DID) functions; contain, transport, or isolate radioactive materiai; and for applicable systems that are specified in Regulatory l Guide 1.68, Appendix A. Revision 2 are provided in this section.

Plant operating, emergency, and surveillance procedures are incorporated into the initial test program procedures. These procedures are verified through use, to the extent practicable, )

during the preoperational test program and revised if necessary, prior to fuel loading.

Plant equipment used in the performance of preoperational tests is operated in accordance with appropriate operating procedures, thereby giving the plant operating staff an opportunity to gain expc rience in using these procedures and demonstrating their adequacy prior to plant initial enticality.

14.2.1.3 Startup Test Program Objectives The startup test program begins with initial fuel loading after the preoperational testing has been successfully completed.

Startup tests can be grouped into four broad categories:

. Tests related to initial fuel loading

= Tests performe'd after initial fuel loading but prior to initial criticality a wmv9ooi4 no947i6% Revision: 9 14-3 Draft July 31,1996

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= Tests related to initial criticality and those performed at low power (less than 5 percent) l

. Tests performed at power levels greater than 5 percent During performance of the startup test program, the plant operating staff has the opportunity to obtain practical experience in the use of normal and abnormal operating procedures while the plant progresses through heatup, criticality, and power operations. ,

I The general objectives of the startup test program are: )

Install the nuclear fuel in the reactor vessel in a controlled and safe manner.

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Verify that the reactor core and components, equipment, and systems required for control and shutdown have been assembled according to design and meet specified performance requirements.

  • Achieve initial criticality and operation at power in a controlled and safe manner. . I I

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Verify that the operating characteristics of the reactor core and associated control and,  !

protection equipment are consistent with design requirements and accident analysis assumptions. i i

  • Obtain the required data and calibrate equipment used to control and protect the plant.  !

= Verify that the plant is operating within the limits imposed by the technical specifications.  !

Abstracts of the startup tests are provided in this section.

14.2.2 Organization, Staffing, and Responsibilities The combined operating license holder is responsible for the establishment of a management' organization with overall responsibility for defining the responsibilities, requirements, and interfaces necessary to safely and efficiently test, operate, and maintain the AP600 plant.

'Ihe combined operating license holder is responsible for developing the specific plant organization and staffing level appropriate for the testing, operating and maintaining the AP600 plant.

14.2.3 Test Procedures l Preoperational and startup tests are performed using test procedures. For each test, the test l procedure specifies the following:

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  • Objectives for performing the test Revision: 9 .w.nevenoi4 no9-ovie96 Draft July 31,1996 14 4 [ W85tiflgh00S8 l

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14. Initial Test Program

- Prerequisites that must be completed before the test can be performed l

  • Initial conditions under which the test is staned
  • Special precautions required for the safety of personnel or equipment
  • Instructions delineating how the test is to be performed
  • Identification of the required data to be obtained and the methods for documentation
  • Data reduction analysis methods as appropriate
  • Criteria for test results evaluation i

l Available information on operating and testing experiences of operating reactors are factored I irito the test procedures as appropriate. l l

Copies of the test procedures for the startup tests are provided to NRC inspection personnel not less than 60 days prior to the scheduled fuel loading date.

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i Copies of the test proced. ires are available to NRC inspection personnel approximately 60 days prior to the scheduled performance of the following preoperational tests ,

. Tests of systems / components that perform safety-related functions a Tests of systems / components that are non-safety-related but perform defense-in-depth, I functions.

Submittal to the NRC of procedures for the preoperational tests of the plant systems /  ;

components which perform no safety or defense-in-depth functions is not required. l l

Tests of safety-related functions are performed with the quality assurance requirements as specified in Section 17.4.

14.2.3.1 Conduct of Test Program Administrative procedures and requirements that govern the activities of the conduct of the initial test program includes the following:

. Format and content of test procedures l

= Process for both initial issue and subsequent revisions of test procedures i

+ Review process for test results a Process for resolution of failures to meet performance criteria and of other operational problems or design deficiencies l

. Various phases of the initial test program and the requirements for progressing from one phase to the next as well as requirements for moving beyond selected hold points or milestones within a given phase o s== moi 4 no9 or:6% Revision: 9

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1 Controls to monitor the as-tested status of each system and modifications including retest requirements deemed necessary for systems undergoing or already having  !

completed testing I l

Qualifications and responsibilities of the positions within the stanup group  !

The stanup administrative procedures supplement normal plant administrative procedures by addressing those administrative issues that are unique to the stanup program.

14.2.3.2 Review of Test Results Final review of the individual tests is the responsibility of plant management which is also responsible for final review of overall test results and for review of selected milestones or hold points within the test phases.

14.2.3.3 Test Records i i

Test records demonstrating the adequacy of safety-related components, systems, and structures are retained for the life of the plant.

Retention periods for other test results are based on considerations of their usefulness in documenting initial plant performance characteristics.

14.2.4 Compliance of Test Program with Regulatory Guides Subsection 1.9.1 and Table 1.9-1 discuss compliance with the applicable NRC regulatory guides.

14.2.5 Utilization of Reactor Operating and Testing Experience in the Development of Test Program The design, testing, startup, and operating experience from previous pressurized water reactor plants is utilized in the development of the initial preoperational and startup test program for the AP600 plant. Other sources of experience reported and described in documents such as NRC repons including Inspection and Enforcement bulletins and Institute of Nuclear Power Operations (INPO) reports including Significant Operating Event Repons (SOER) are also utilized in the AP600 initial preoperational and stanup test program.

Special tests to establish a unique performance parameter of AP600 design features that will not change from plant to plant, are performed for the first plant only. Because of the standardization of the AP600 design, these special tests (designated as first plant only tests) are not required on follow plants. These first plant only tests are identified in the individual test descriptions. (See subsections 14.2.9 and 14.2.10.)

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14. Initial Test Program 14.2.6 Use of Plant Operating and Emergency Procedures As appropriate and to the extent practicable, plant normal, abnormal, and emergency operating procedures are used when performing preoperational startup tests.

He use of these procedures is intended:

  • To demonstrate the adequacy of the specific procedure or identify changes that may l be required
  • To increase the level of knowledge of plant personnel on the systems being tested i

1 A test procedure using a normal, abnormal, or emergency operating procedure references i the procedure directly or extracts a series of steps from the procedure in the way that l accomplishes the operator training goals while safely and efficiently performing the l specified testing.  ;

l 14.2.7 1sitial Fuel Loading and Initial Criticality l

i Initial fuel loading and subsequent initial criticality and power ascension to full licensed, power are performed during the startup test program. These operations are performed in a controlled and safe manner by using test procedures that specify:

  • Required prerequisite testing
  • Operational status of required systems ,
  • Step-by-step instructions l
  • Precautions which must be observed  ;
  • Actions to be taken in the event of unanticipated or abnormal response 14.2.7.1 Initial Fuel Loading The minimum conditions for initial core loading include:
  • The composition, duties, and eraergency procedure responsibilities of the fuel handling crew are established.
  • Radiation monitors, nuclear instrumentation, manual initiation controls, and other devices to actuate alarms and ventilation controls are tested and verified to be operable.
  • The status of systems required for fuel loading is established and verified.
  • The status of protection systems, interlocks, mode switch, alarms, and radiation protection equipment is established and verified for fuel loading.

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14. Initial Test Program j
  • Containment integrity has been established to the extent required by the Technical Specifications.

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  • The reactor vessel status has been established for fuel loading. Components are l verified to be in place or out of the vessel as required for fuel loading.

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  • Required fuel handling tools are available, operational, and calibrated to include indexing of the manipulator crane with a dummy fuel element. The fuel handling tools have been successfully tested.
  • The reactor vessel is filled with water to a level approximately equal to the center of the vessel outlet nozzles. The reactor coolant water is circulating at a rate which provides uniform mixing.
  • The boron concentration in the reactor coolant is verified to be equal to or greater than required by the plant Technical Specifications for refueling and is being maintained under a surveillance program.
  • Sources of unborated water to the reactor coolant system have been isolated and are under a surveillance program.
  • At least two neutron detectors are calibrated, operable, and located in such a way that changes in core reactivity can be detected and recorded. One detector is connected to an audible count rate indicator and a containment alarm.
  • A response check of nuclear instruments to a neutron source is required within eight hours prior to loading (or resumption of loading if delayed for eight hours or more).

Fuel assemblies together with inserted components (control rods, bumable poison assemblies, primary and secondary neutron sources) are placed in the reactor vessel, according to an established and approved sequence.

During and following the insertion of each fuel assembly, until the last fuel assembly has been loaded, the response of the neutron detectors is observed and compared with previous fuel loading data or calculations to verify that the observed changes in core reactivity are as expected. Specific instructions are provided it unexpected changes in reactivity are observed.

Because of the unique conditions that exist during initial fuel loading, temporary neutron l detectors may be used in the reactor vessel to provide additional reactivity monitoring.

Credit for the use of temporary detectors may be taken in meeting Technical Specifications' requirements on the number of operable source range channels.

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14. Initial Test Program 14.2.7.2 In!tial Criticality Following initial fuel loading, the reactor upper intemals and the pressure vessel head are installed. Additional mechanical and electrical tests are performed in preparation for critical and power operations. The following conditions exist prior to initial criticality:

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Tests are completed on the control rod drive system that demonstrate that the control rods have been latched, that the control and position indication system., are functioning properly, and that the rod drop time under hot full flow conditions is less than the Technical Specifications' limit.

Tests are completed that demonstrate that plant control and protection systems are operable and that the reactor trip breakers respond as designed to appropriate trip signals.

The reactor coolant system is at hot no-load temperature and pressure. The reactor .

coolant boron concentration is such that t% shutdown margin requirements of the i Technical Specifications are satisfied for the hot shutdown condition. .

Initial criticality is achieved in an orderly, controlled fashion by the combination of shutdown and control bank withdrawal and reactor coolant system boron concentration reduction.

m During the approach to initial criticality, the response of the source range nuclear instmments is used as an indication of the rate of reactivity addition and the proximity to a critical condition so that criticality is achieved in a controlled, predictable fashion.

Rates for rod withdrawal and boron reduction are specified in such a way that the startup rate is less than one decade per minute.

Following criticality and prior to operation at power levels greater than five perrent of rated d power, physics tests are performed to verify that the operating characteristics of the reactor l core are consistent with design predictions. During these tests, values are obtained for the reactivity worth of control and shutdown rod banks, isothermal temperature coefficient, and  ;

critical boron concentration for selected rod bank configurations.

\

Other tests at low power include verification of the response of the nuclear instrumenation system and radiation surveys.

14.2.7.3 Power Ascension l l

After the operating characteristics of the reactor have been verified by low-power testing, I a power level ascension program brings the unit to its full rated power level in successive I stages. At each successive stage, hold points are provided to evaluate and approve test i i

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14. Initial Test Program results prior to proceeding to the next stage. The minimum test requirements for each successive stage of power ascension are specified in the applicable startup test procedures.

During the power ascension program, tests are performed at various power levels as follows:

  • Statepoint data, including secondary system heat balance measurements, are obtained at various power levels up to full licensed power. This information is used to project plant performance during power escalation, provide calibration data for the various plant control and protection systems, and provide the bases for plant trip setpoints.
  • At prescribed power levels, the dynamic response characteristics of the primary and secondary systems are evaluated. System response characteristics are measured for design step load changes, rapid load reductions, and plant trips.

= Adequacy of the radiation shielding is verified by gamma and neutron radiation surveys. Periodic sampling is performed to verify the chemical and radiochemical analysis of the reactor coolant.

- Using the incore instrumentation as appropriate, the power distribution of the reactor core is measured to verify consistency with design predictions and technical, specifications limits on peaking factors.

14.2.8 Test Program Schedule The schedule for the initial fuel load and for each major phase of the initial test program includes the timetable for generation, review, and approval of procedures as well as the actual testing and analysis of results.

Preoperational testing is performed as system and equipment availability allows. The interdependence of systems is also considered so that common support systems (such as electrical power distribution, service and instrument air, and the various cooling systems) are tested as early as possible.

Sequencing of the startup tests depends on specified power and flow conditions and intersystem prerequisites. The startup test schedule establishes that, prior to core load, the test requirements are met for those plant structures, systems, and components that are relied upon to prevent, limit, or mitigate the consequences of postulated accidents. Testing is sequenced so that the safety of the plant is not dependent on untested systems, components, or features.

14.2.9 Preoperational Test Descriptions Test abstracts are provided for the preoperational testing of systems / components that perform safety-related functions; that are non-safety-related but perform functions designated to provide defense-in-depth; systems / components that may contain radioactive material; and other applicable nonsafety-related systems in accordance with Regulatory Guide 1.68, Revision: 9 owmv9eoi4 Rov-ot:6*

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14. Initial Test Program Revision 2, Appendix A. A limited number of these testing abstracts establish performance j parameters of AP600 design features that will not change from plant to plant. Because the I AP600 design is standardized, these tests need only be performed on the first AP600 plant.

These testing abstracts are clearly identified. l 14.2.9.1 Preoperational Tests of Systems with Safety Related Functions ,

l 14.2.9.1.1 Reactor Coolant System Testing I Purpose The purpose of the reactor coolant system testing is to verify that the as-installed reactor l coolant system properly performs the following safety-related functions:

  • Provide core cooling and boration in conjunction with the passive core cooling system as described in Sections 5.1 and 6.3.

Measure process parameters required for safety-related actuations as specified in, Sections 7.2,7.3 and 7.4.

  • Measure selected process parameters required for post-accident monitoring as specified in Section 7.5.
  • Vent the reactor vessel head as discussed in subsection 5.4.12.

Testing is also performed to verify that the system properly performs the following l

defense-in-depth functions described in Section 5.2:

  • Provide forced circulation cooling of the reactor core in conjunction with heat removal ,

by the steam generator (s) as described in Section 5.1. l

  • Provide core cooling by natural circulation of coolant in conjunction with heat removal by the steam generator (s) as described in Section 5.1.
  • Provide pressurizer pressure control during normal operation
  • Provide pressurizer level control in conjunction with the chemical and volume control system
  • Provide pressurizer spray o s m9eoi4 no9-07is* Revision: 9 Y W85tingh00S8 14-11 Draft July 31,1996

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14. Initial Test Program Prerequisites The construction testing of the reactor coolant system has been successfully completed. The pre-operational testing of the component cooling water system, service water system, )

chemical and volume control system, main AC power electrical power syste'n, and required interfacing systems must be completed to the extent sufficient to suppon the specified testing. The reactor coolant system is filled, vented, and pressurized above the minimum required pressure for reactor coolant pump operation; and component cooling water flow to the reactor coolant pumps is initiated prior to staning the pumps. I In preparation for the hydrostatic test of the reactor coolant system, the reactor vessel lower i and upper internals and the closure head are installed. The closure head studs are properly tensioned for the hydrostatic test pressure. The pressurizer safety valves and instmmentation j within the test boundary are either removed, recalibrated or verified to be able to withstand the hydrostatic test pressure. Welds within the test boundaries are verified as ready for i hydrostatic testing. A hydrostatic test pump is available for the pressure boundary mtegnty ,

I testing.

General Test Method and Acceptance Criteria I Reactor coolant system performance is observed and recorded during a series of individual' component and system tests. The following testing demonstrates that the reactor coolant system can perform the functions described above and in appropriate design specifications:

a) The integrity and leaktightness of the reactor coolant system and the high-pressure ponions of associated systems is verified by performing a cold hydrostatic pressure test in conformance with Section III of the American Society of Mechanical Engineers (ASME) Code. The reactor coolant system is pressurized in stages by operation of the temporary hydrostatic test pump, while monitoring system welds, piping, and components for leaks at each stage. The hydrostatic test verifies that there are no leaks at welds or piping within the test boundaries during the final inspection. Leaks at valves, flanges, or mechanical fittings are acceptable during the hydrostatic test, but they are repaired prior to the final inspection, or the leak may be isolated, repaired, and retested at a later date.

b) Proper operation of the safety-related reactor coolant system and reactor coolant pressure boundary valves is verified by the performance of baseline inservice tests as specified in subsection 3.9.6.

- c) The operability of the pressurizer safety valves is demonstrated by a bench test at temperature and pressure with steam as the pressurizing fluid or with a suitable in-situ test. This testing verifies that each pressurizer safety valve actuates at the required set pressure, with appropriate tolerance as specified in the technical specifications. The safety valve rated capacity as recorded on the valve vendor code plates is verified to be greater than or equal to that specified in Section 5.4.

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14. Initial Test Program d) During hot functional testing, reactor coolant system leakage is verified to be within the limits specified in the Technical Specifications. The pressurizer water level is set to the no-load level, the chemical and volume control system makeup pumps and letdown line do not operate, and no primary system samples are taken. During this test, the iden '.fied and unidentified reactor coolant system leakage rates are determined by monitoring the reactor coolant system water inventory over a specified period of time, e) The leakage across individual valves between high pressure and low pressure systems, as specified in the technical specifications, is verified to be less than design requirements.

f) The as-installed safety valve discharge chamber rupture disks are inspected to verify the manufacturer's stamped set pressure is within the limits specified in the appropriate design specifications.

g) Proper calibration and operation of safety-related instmmentation, controls, actuation-signals and interlocks is verified. This testing includes the following:

  • hot leg and cold leg resistance temperatu e detectors *

= cold leg flow instrumentation

= hot leg level instruments a pressurizer pressure and level instruments

= reactor coolant pump speed sensor instruments

= reactor vessel head vent valve controls This testing includes demonstration of proper actuation of safety-related functions from the main control room.

h) Automatic trip of the reactor coolant pumps following appropriate safety-related actuation signals is demonstrated.

i) Proper operation of the reactor vessel head vent valves is verified with the reactor coolant system pressurized.

The following testing demonstrates that the system properly performs e dense-in-depth functions described above and in appropriate design specifications:

j) The pressurizer spray valves are verified to operate properly over the range of reactor coolant system operating temperatures, and with the reactor coolant pumps : , erating.

k) Proper calibration and operation of defense-in-depth related instrumentation, controls, actuation signals and interlocks is verified. This testing includes actuation of the o Wanev90014 R094716% Revision: 9 14-13 Draft July 31,1996 T Westinghouse

14. Initial Test Program pressurizer spray valves on receipt of appropriate signals; and actuation from the main control room.
1) Reactor coolant pump performance and operating characteristics are verified with the reactor coolant system at cold conditions. All four RCPs are operated in various combinations as specified in the appropriate design specifications and operating procedures.

m) The reactor coolant system is heated from cold conditions to hot standby conditions by operating the reactor coolant pumps and the pressurizer heaters. The reactor coolant system is operated at full flow conditions for at least 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> prior to core loading.

The reactor coolant temperature is maintained at or above 515 'F for at least one-half

.of this operating time. In addition to facilitating the reactor coolant system tests that are required to be performed hot and pressurized, these hot functional testing conditions allow the plant operators to control the plant using the plant operating.

procedures for the reactor coolant system, secondary side systems, and auxiliary systems.

Other preoperational tests that require these hot and/or dynamic conditions are conducted during this hot functional testing period. ,

n) During hot functional testing, the reactor coolant pump operating characteristics are measured and recorded at various temperature plateaus during reactor coolant system j heatup to verify proper operation over the their operating temperature range.  ;

o) The pressurizer spray continuous flow rate is established and the proper spray line l temperature is verified for each pressurizer spray line. l p) The proper operation of the pressurizer heaters, pressudzer spray, and pressure control functions and alarms is verified during the heatup, operation at hot functional test conditions and cooldown of the reactor coolant system.

q) The proper operation of the pressurizer level control functions and alarms is verified i during the heatup, operation at hot functional test conditions and cooldown of the reactor coolant system.

Tests associated with the automatic depressurization functions of reactor coolant system components are described in subsection 14.2.9.1.3.

14.2.9.1.2 Steam Generator System Testing Purpose The purpose of the steam generator system testing is to verify that the as-installed components properly perform the following safety-related functions as described in Sections 5.4,10.3 and 10.4:

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14. Initial Test Program

. Provide steam generator isolation including isolation of the main steam lines, feedwater lines, and blowdown lines 1

l

  • Measure process parameters required for safety-related actuations as specified in ,

Sections 7.2, 7.3, r.nd 7.4. l

  • Measure process parameters required for post-accident monitoring as specified in Section 7.5.

1 This testing also verifies that the as-installed components properly perform the following defense-in-depth functions as described in Section 10.4:

  • Provide overpressure protection for the steam generators to minimize required actuations of the spring loaded safety valves
  • Measure process parameters and provide actuation signals for the diverse actuation
  • system.

Prerequisites The construction tests of the as-installed system have been completed. The reactor coolant l I

system as well as other systems used in power generation are to be functional since portions of the steam generator system testing is performed during the plant hot functional tests.

Prerequisite testing of required interfacing systems are to be completed to the extent sufficient to support the specified testing and the appropriate system configuration.

General Test Method and Acceptance Criteria ne performance of the steam generator system is observed and recorded during a series of individual component and integrated system testing that characterizes its modes of operation.

He following testing demonstrates that the steam generator system operates as specified in Sections 10.3 and 10.4, and appropriatr. design specifications:

a) Proper operation of the steam generator system safety-related valves is verified by the performance of baseline inservice tests as specified in subsection 3.9.6.

b) Proper operation of safety-related and defense-in-depth instrumentation, controls, actuation signals, and interlocks is verified. This testing includes actuation 'of equipment from the main control room.

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14. Initial Test Program l

l c) He proper operation of the steam generator safety valves is demonstrated in a bench i test at temperature and pressure with steam as the pressurizing fluid or with suitable in-situ testing. The safety valve rated capacity recorded on the valve vendor code plates i is verified to be greater than or equal to the required relief capacity.

Heat transfer performance of the steam generator system is verified by preoperational and startup testing of the reactor coolant system described in other sections.

14.2.9.1.3 Passive Core Cooling System Testing Purpose l

The purpose of the passive core cooling system testing is to verify that the as-installed i components and their associated piping and valves properly perfoun the following safety j functions, described in Section 6.3:

= Emergency core decay heat removal I

= Reactor coolant system emergency makeup and boration

= Safety injection j

= Containment pH control Prerequisites I De construction testing of the passive core cooling system, or of a specific portion of the system to be tested, is successfully completed. The preoperational testing of the reactor coolant system, normal residual heat removal system, chemical and volume control system, the refueling cavity, the Class IE de and uninterruptable power supply, the ac electrical power and distribution systems, and other interfacing systems required for operation of the above systems and data collection is completed as needed to support the specified testing l and system configurations. A source of water, of a quality acceptable for filling the passive core cooling system components and the reactor coolant system, is available.

General Test Method and Acceptance Criteria The performance of the passive core cooling system is observed and recorded during a series of individual component testing and testing with the reactor coolant system. The following testing demonstrates that the passive core cooling system operates as specified in Section 6.3 and appropriate design specifications.

a) Proper operation of safety-related valves is verified by the performance of baseline inservice tests as specified in subsection 3.9.6. Also, the proper operation of non-safety-related valves is verified including manual valve locking devices. This testing dces not include actuation of the squib valves, which is discussed in item t, below.

b) Proper calibration and operation of safety-related instrumentation, controls, actuation signals, and interlocks is verified. This testing includes the following:

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14. Initial Test Program

- Core makeup tank level

. In-containment refueling water storage tank level

- Containment floodup level

  • Core makeup tank inlet / outlet valve controls

= In-containment refueling water storage tank outlet valve controls

  • Containment recirculation valve controls
  • Automatic depressurization valve controls This testing includes demonstration of pper actuation of safety-related functions from the main control room.

c) Proper calibration and operation of instrumentation, controls, and interlocks required to demonstrate readiness of a safety-related component is verified. This testing includes the following:

= Accumulator pressure and level and alarms .

= Passive residual heat removal heat exchanger high point vent level ,,

  • Core makeup tank inlet line temperatures
  • Core makeup tank inlet line high point levels
  • Direct vessel injection line temperatures
  • In-containment refueling water storage tank temperatures The passive core cooling system emergency core decay heat removal function is verified by the following testing of the passive residual heat removal heat exchanger.

d) During hot functional testing of the reactor coolant system, the heat exchanger supply and retum line piping water temperatures are verified.

e) The heat transfer capability of the passive residual heat removal heat exchanger with~

natural circulation flow is verified. This testing is performed during reactor coolant system hot functional tests with the reactor coolant pumps not running.

f) 'Ihe proper operation of the passive residual heat removal heat exchanger and its heat transfer capability with forced flow is verified by initiating and operating the heat exchanger with al. four reactor coolant pumps running. This testing is performed during reactor coolant system hot functional testing.

g) The heatup characteristics of the IRWST water are verified by measuring the vertical water temperature gradient that occurs in the IRWST water at the passive residual heat removal heat exchanger tube bundle and at several distances from the tube bundle, during testing in Item (e), above. Note that this verification is required only for the first plant.

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14. Initial Test Program i n- I I

l l

l The passive core cooling system emergency makeup and boration function is verified by the following testing of the core makeup tanks.

h) The resistance of the core makeup tank cold leg balance lines is determined by filling the core makeup tanks with flow from the cold legs. This testing is performed by filling the cold, depressurized reactor coolant system using a constant, measured discharge flow from the normal residual heat removal pumps. The reactor coolant 1 system is maintained at a constant level above the top of the cold leg balance line(s). I The normal residual heat removal system flow rate and the differential pressure across  ;

_ the cold leg balance lines are used to determine the resistance of the balance imes.  !

l i) During hot functional testing of the reactor coolant system, the core makeup tank cold leg balance line piping water temperature at various locations is verified.

j) Proper operation of the core makeup tanks to perform their reactor water makeup and boration function is verified by initiating recirculation flow through the tanks during reactor coolant system hot functional testing. "Ihis testing is initiated by simulating a l safety signal which opens the tank discharge isolation valves, and stops reactor coolant pumps after the appropriate time delay. The proper tank recirculation flow after the pumps have coasted down is verified. Based on the cold leg temperature and temporary flow instmmentation, the net mass injection rate into the reactor is verified.'

Note that this verification is required only for the first plant.

The passive core cooling system safety injection function is verified by the following testing of the core makeup tanks, accumulators, in-containment refueling water storage tank, containment sump, automatic depressurization, and their associated piping and valves.

k) Proper flow resistance of each of the core makeup tank injection lines is verified by gravity draining each tank filled with cold water. Air enters the top of the draining tank from the reactor coolant system cold leg via the cold leg balance line. If necessary, the flow orifice in the core makeup tank discharge line is to be resized, and the core makeup tank retested to obtain the required line resistance.

1) The proper flow resistance of each of the accumulator injection lines is verified by performing a blowdown from a partially pressurized accumulator. If necessary, the flow orifice in the accumulator discharge line is to be resized and the accumulator retested to obtain the required discharge line resistance.

m) The proper flow resistance of each of the in-containment refueling water storage tank injection lines is verified by gravity draining water from the tank. If necessary, the flow orifice in the in-containment refueling water storage tank injection line is resized and retested, until the required line resistance is achieved.

n) The flow resistance.of each of the flow paths from the incontainment refueling water storage tank to each containment sump, and from each containment sump to the reactor Revision: 9 o warav9ooi4 Roo47i6%

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14. Initial Test Program is verified by a series of tests. These tests gravity drain water from the incontainment refueling water storage tank to the containment sump, and from the sump to the empty reactor coolant system. This testing is performed using temporary piping to prevent flooding of the containment. A spool piece with prototypical resistance may be used to simulate the squib valves in the flow paths tested.

o) The resistance of each automatic depressurization stage 1, 2, and 3 flowpath and flowpath combination is verified by pumping cold water from the in-containment refueling water storage enk into the cold, depressurized, water-filled reactor coolant system; and back to the 'n-containment refueling water storage tank using the normal residual heat removal pun.p(s). Temporary instrumentation may be used to measure the pressure drop across the flow paths tested.

p) The resistance of each automatic depressurization stage 4 flowpath and their flowpath combinations is verified by pumping cold water from the in-containment refueling.

water storage tank into the cold, depressurized, water-filled reactor coolant system using the normal residual heat removal pump (s). Temporary instrumentation may be used to measure the pressure drop across the flow paths tested. The automatic depressurization stage 4 squib valves are not required to be included in this test.

~

q) The proper operation of the vacuum breakers in the automatic depressurization discharge lines is verified.

r) During hot functional testing of the reactor coolant system, proper operation of automatic depressurization is verified by blowing down the reactor coolant system.

This testing verifies proper operation of the stage 1,2, and 3 components including the ability of the spargers to limit loads imposed on the incontainment refueling water storage tank by the blowdown. Proper operation of the stage 1,2 and 3 valves is demonstrated during blowdown conditions. Note that this veri 0 cation is required only for the first plant.

s) The proper operation of at least one of each squib valve size and type including a containment recirculation, in-containment refueling water storage tank injection, and a stage 4 automatic depressurization squib valve is demonstrated. The squib valve performance and the flow resistance of the actuated squib valves is compared to the squib valve qualification testing results.

t) The passive core cooling system containment pH control function is verified by inspections of the storage baskets.

14.2.9.1.4 Passive Containment Cooling System Testing Purpose The purpose of the passive containment cooling system testing is to verify that the as-installed components perform properly to accomplish their safety-related functions to otsarnv90014 R09 0716% Revision: 9 14-19 Draft July 31,1996

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14. InitSI Test Program l transfer heat from inside the containment to the environment, as described in Section 6.2.

The passive containment cooling water storage tank also provides a seismically qualified source of water for the fire protection system. Testing of this function is discussed m j subsection 14.2.9.2.11. l Prerequisites The construction testing of the passive containment cooling system is successfully completed. The preoperational testing of the IE de electrical power and uninterruptable power supply systems, the non-lE electrical power supply system, the compressed and instrument air system, and other interfacing systems required for operation of the above systems and data collection is available as needed to support the specified testing and  !

system configurations. Additionally, a sufficient quantity of acceptable quality water for l filling the passive containment cooling water storage tank and draining onto the containment  ;

is available, and a means of filling the tank is available.

General Test Acceptance Criteria and Methods Passive containment cooling system performance is observed and recorded during a series i of individual component testing that characterizes passive containment cooling system operation. The following testing demonstrates that the passive containment cooling system' operates as specified in Section 6.2 and appropriate design specifications:

a) Proper operation of safety-related valves is verified by the performance of baseline inservice tests as specified in subsection 3.9.6.

b) Proper calibration and operation of safety-related, defense-in-depth, and system readiness instrumentation, controls, actuation signals and interlocks is verified. This testing includes the following:

  • Normal range containment pressure
  • High range containment pressure a Passive containment cooling water flow rate
  • Passive containment cooling water storage tank level
  • Passive containment cooling water isolation valve instrumentation and controls
  • Diverse actuation system passive containment cooling initiation
  • Passive containment cooling water storage tank water temperature
  • Air inlet, shield plate, and exhaust heater controls This testing includes demonstration of proper actuation these functions from the main control room.

c) The resistance of each passive containment cooling water storage tank drain flowpath and flowpath combinations is verified by draining water from the water storage tank onto the containment surface, with the storage tank water initially at the different water levels just above and below each drain standpipe.

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14. Initial Test Program d) He proper operation of the passive containment cooling water distribution bucket and weirs is verified and proper wetting of the containment is observed and recorded i during draindown testing in item c, above.

e) The proper operation the drains in the upper containment / shield building annulus to each drain the containment cooling water from the annulus floor is verified.

f) The resistance of the passive containment cooling air flowpath is verified by measuring the wind induced driving head developed from the air inlet plenum region of the shield building to the air exhaust at several locations along the flow path and at several circumferential locations, and measurement of the induced air flow velocity. l Temporary instmmentation is used for this testing.

I 14.2.9.1.5 Chemical and Volume Control System Isolation Testing Purpose The purpose of the chemical and volume control system isolation testing is to verify that the as-installed components properly perform the following safety-related isolation functions, ,

described in Section 9.3: l

. i

  • Isolation of unborated water sources for reactor makeup
  • Isolation / termination of excessive makeup to the reactor j l

Prerequisites j The construction testing of the chemical and volume control system has been successfully completed. The required preoperational testing of appropriate support and interfacing j systems is completed Data collection is available as needed to suppoit the specified testing and system configuration:..

i General Test Acceptance Criteria and Methods i

Performance of the chemical and volume control system isolation functions is observed and recorded during a senes of individual component and integrated system testing.that characterizes the system isolation modes of operation. The following testing demonstrates i

that the chemical and volume control system properly performs the safety-related isolations as specified in Section 9.3 and appropriate design specifications:

a) Proper operation of the safety-related valves is verified by the performance of baseline inservice tests as specified in subsection 3.9.6, including:

  • Purification loop isolation valves I
  • Letdown' isolation valves o swtev90014 R00471696 Revision: 9 Draft July 31,1996

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14. Initial Test Program W-l l l l
  • Demineralized water isolation valves l
  • Makeup isolation valves j l
  • Auxiliary spray isolation valve i b) Proper calibration and operation of safety-related instrumentation, controls, actuation ,

j signals and interlocks is verified. This testing includes the following:

  • Purification isolation valve controls j

= Letdown isolation valve controls

  • Demineralized water isolation controls
  • Makeup isolation valve controls ,

l This testing includes demonstration of proper actuation of safety-related functions from l l

I the main control room.

14.2.9.1.6 Main Control Rcom Emergency Habitability System Testing l 1

1 Purpose .

l \

The purpose of the main control room emergency habitability system testing is to verify, I that the as-installed components properly perform the safety functions described in Section 6.4, including the following:

]

  • Provide sufficient breathable quality air to the main control room  :

l

  • Maintain the main control room at positive pressure i

l

  • Provide passive cooling of designated equipment
In addition, the following safety-related function performed by the nuclear island nonradioactive ventilation system described in subsection 9.4.1 is tested

l

  • Provide isolation of the main control room from the surrounding areas and outside i environment during a design basis accident if the nuclear island nonradioactive ventilation system becomes inoperable.
  • Monitor the radioactivity in the main control room normal air supply and provide j signals to isolate the incoming air and actuate the main control room emergency l habitability system.

Prerequisites The construction testing of the main control room habitability system has been successfully l l completed. The required preoperational testing of the compressed and instrument air system. .

Class IE electrical power and uninterruptable power supply systems, normal control room i ventilation system, and other interfacing systems required for operation of the above systems  !

and data collection is available as needed to support the specified testing and system configurations. The main control room air supply tanks are filled with air acceptable for Revision: 9 w.riev9ooi4 acnoti696 Draft July 31,1996 14-22 3 W85tingfl00S8 1

14. Initial Test Program breathing. The main control room constmetion is complete and its leak tight barriers are in place.

General Test Acceptance Criteria and Methods Performance of the main control room habitability system is observed and recorded during a series of individual component and integrated system testing. The following testing demonstrates that the habitability system operates as specified in Section 6.4 and as specified in the appropriate design specifications:

a) Proper operation of safety-related valves is verified by the performance of baseline inservice tests as specified in subsection 3.9.6.

b) Proper calibration and operation of safety-related and system readiness instrumentation, controls, retuation signals and interlocks is verified. This testing includes the following:

  • Air storage tank pressure
  • Refill line connection pressure a Main control room differential pressure ,
  • Air supply line flow rate
  • Contmls for the main control room pressure relief valves a Controls for the air supply isolation valves i
  • Controls for the main control room air inlet isolation valves i
  • Air intake radiation I c) The proper flow rate of emergency air to the main control room is verified, demonstrating proper sizing of each air flow limiting orifice and proper operation of each air supply pressure regulator.

d) The ability of the emergency air supply to maintain the main control room at the ,

proper positive pressure is demonstrated, verifying proper operation of the main control l room pressure relief dampers.

c) The ability of the habitability system to maintain the proper main control room

environment, and proper temperatures in the protection and safety monitoring system cabinet and emergency switchgear rooms during a long term loss of the nuclear island nonradioactive ventilation system is verified. This verification is on( required for  ;

the first plant.

14.2.9.1.7 Expansion, Vibration and Dynamic Effects Testing l Purpose The purpose of the expansion, vibration and dynamic effects testing is to verify that the safety-related, high energy piping and components are properly installed and supported such o Wanev90014 RD?.0715% Revision: 9 3 Westingh0058 14-23 Draft July 31,1996

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%at expected movement due to thermal expansion during normal heatup and cooldown, and as a result of transients; thermal stratification and thermal cycling; as well as vibrations or dynamic effects during steady-state and transients do not result in excessive stress or fatigue to safety-related plant systems and equipment, as described in Section 3.9.

Prerequisites The construction testing and preoperational testing of the reactor coolant system at cold coaditions has been successfully completed. Required ponions of the chemical and volume control system, passive core cooling system, normal residual heat removal system, main i feedwater system, stanup feedwater system, steam generator system, and steam generator blowdown system are operational Piping and components within the reactor coolant system  !

and steam generator system prersure boundaries and their associated supports and restraints I have been inspected and determined to be installed as designed. Permanently installed j support devices have been arified to be in their expected cold, static positions and l temporary restraining devic:.8 such as hanger locking pins have been removed. The j instmmentation required for this testing is installed.

General Test Method and Acceptance Criteria 1 i

During hot functional testing, verifications that ASME code class 1,2, and 3 high-energy

  • piping system components, piping, suppon, and restraint deflections are unobstmeted and j within design basis functional requirements. These tests verify that thermal movements for  !

safety-related piping suppons, with system operating temperature above 250 F are within design specifications. The high-temperature ponions of the following systems are considered for inclusion in this test:

= reactor coolant system .

= chemical and volume control system

= passive core cooling system 1

a steam generator system (including the safety-related ponions of mam steam system, main and stanup feedwater systems, and steam generator blowdown system)

= normal residual heat removal system 1

a) Thermal expansion testing during the preoperational testing phase consists of j displacement measurements on the above systems during heatup and cooldown of the reactor coolant system and associated systems (including heatup and cooldown of the passive core cooling system). The testing is performed in accordance ASME OM Standard, Pan 7 as discussed subsection 3.9.2.1.2 and consists of a combination of i visual inspections and local and remote displacement measuaments. This testing includes the inspection and measurement of deflection data associated with support thermal movements to verify suppon swing clearance at specified heatup and cooldown Revision: 9 o wmmoi4 no+47is96 Draft July 31,1996 14-24 W W8Stingt10US8

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14. Initial Test Program i

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intervals; that there is no evidence of blocking of the thermal expansion of any piping or components, other than by installed supports, restraints, and hangers; that spring l hanger movements remain within the hot and cold setpoints; that moveable suppons do not become fully retracted or extended; and that piping and components retum to l their approximate baseline cold positions.

b) Vibration testing is performed on safety-related and high-energy system piping and components during both cold and hot conditions to demonstrate that steady-state vibrations are within acceptable limits. This testing includes visual observation and local and remote monitoring in critical steady-state operating modes. Results are acceptable when visual observation show no signs of excessive vibration and when measured vibration amplitudes are within acceptable levels.

c) Testing for significant dynamic events is conducted during hot functional testing and may be performed as pan of other specified preoperational tests. This testing is conducted to verify that stress analyses of safety-related and high-energy system piping under transient conditions are acceptable. These tests are performed to verify that the dynamic effects are within expected values during transients such as pump starts and stops, valve stroking, and significant process flow changes.

Deflection measurements during various plant transients are recorded and compared to acceptance limits.

d) As specified in subsection 3.9.3, temperature sensors are installed on the pressurizer surge line and pressurizer spray line for monitoring thermal stratification and thermal cycling during power operation. Testing is performed to verify proper operation of these sensors. Note that this verification is required only for the first plant.

14.2.9.1.8 Control Rod Drive System Purpose

'Ihe purpose of the control rod drive system testing is to verify the proper operation of the control rod drive mechanisms, motor-generator sets and system components as specified in subsection 3.9.4 and Section 4.6, and in appropriate design specifications.

Prerequisites The construction tests of the control rod system have been successfully completed.

Required interfacing systems, as needed, are completed to the extent sufficient to support the specified testing and the appropriate system configuration. Required electrical power supplies are energized and operational.

For the control rod drive mechanism cooling test, the plant is at or near normal operating l

temperature and pressure, and hot functional testing is in progress. The integrated head and

! control rod drive mechanism cooling system are in their normal operational alignment.

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14. Initial Test Program For the control rod drive mechanism motor-generator sets tests, a three-phase load bank is available for motor generator set testing under loaded conditions.

General Test Methods and Acceptance Criteria Performance is observed and recorded during a series of individual component and integrated system tests. The following tests verify that the control rod drive system operates properly:

a) Tests are conducted to verify proper current command sequence, timing, and rod speed signal voltages by initiating control rod drive mechanism withdrawal and insertion.

Proper operation of the bank overlap unit to control rod bank sequence and movement is verified.

b) Tests are conducted to verify the adequacy of the integrated head and control rod drive mechanism cooling system for maintaining control rod drive mechanism temperature.

This test is conducted by measuring control rod drive mechanism coil resistances and calculating the coil temperatures.

c) Tests are conducted to verify control rod drive mechanirm motor-generator set and i

system component control circuits, including interlock and alarm functions.

d) Tests are conducted to verify generator phasing for parallel generator operation.

Operation of the control rod drive mechanism motor generator sets and control system during starting, running, and parallel operations is verified.

14.2.9.1.9 Reactor Vessel Internals Vibration Testing (First Plant Only)

Purpose The AP600 reactor internals testing is part of a comprehensive vibration assessment program performed in accordance with Regulatory Guide 1.20 as discussed in subsection 3.9.2.4.

This testing obtains data to verify the structural integrity of the AP600 reactor internals with regard to flow induced vibrations, as part of an internals vibration assessment program. This program also includes visual examination of the reactor internals after testing is completed, and analysis of the test data.

Prerequisites The construction testing of the reactor coolant system has been successfully completed.The testing and calibration of the required test instrumentation has been completed. The test instrumentation has been installed on the internals as specified in Table 3.9-4 and the mternals pre-test visual inspection has been completed. The intemali, test instrumentation.

l and instmmentation lead wires are installed in the reactor vessel. The reactor vessel head l

is installed in preparation for the cold hydrostatic test of the reactor coolant system and instrument leads have been properly sealed. The proper operation and calibration of the test Revision: 9 owvW0l4 R0447I5%

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14. Initial Test Program instmmentation and recording equipment is verified during the inydrostatic testing of the reactor coolant system.

General Test Method and Acceptance Criteria l The reactor vessel internals testing is performed by measuring and recording strains or  ;

accelerations of components in order to determine actual displacements that occur with the l reactor coolant pumps operating. This testing is performed at several reactor coolant system temperatures during the system hot functional test. The analysis of data obtained from this testing, combined with a pre-test ud post-test visual inspection of the internals, are intended to confirm that the stresses and wear on the AP600 internals, due to flow induced vibration l during plant operation, are acceptably low. The criteria fct evaluating testing results is '

l established in the AP600 reactor internals flow-induced vibration assessment program, and appropriate design specifications.

Data is recorded during the following reactor coolant system operating conditions:

a) Background noise in the instrumentation and recording equipment is recorded with no .

reactor coolant pumps running.

b) Data is recorded during the initial startup of the reactor coolant pumps and with all' four pumps operating, with the reactor coolant at cold temperature.

c) Data is recorded at several increasing coolant temperatures with the pumps operating.

d) Data is recorded at the hot functional testing temperature with all four pumps operating.  !

e) Data is recorded at the hot functional testing temperature with the appropriate combinations of reactor coolant pumps operating, including pump start and stop transients.

14.2.9.1.10 Containment Isolation and Leak Rate Testing Parpose The purpose of the containment isolation and leak rate testing is to demonstrate that the as installed containment isolation valves, piping and electrical containment penetrations, and hatches, and the containment vessel properly perform the following safety functions as described in Section 6.2:

  • Automatic isolation of the piping penetrating containment required to assure containment integrity
  • The containment vessel, penetration, and isciation valve leakage is less than the design basis leakage at or near the containment design pressure a wv9eoi4 no94ms% Revision: 9 W W85tingtt0058 14-27 Draft July 31,1996
14. Initial Test Program

. The containment vessel and penetrations can withstand elevated internal pressure consistent with 10 CFR50, Appendix J pressure test requirements Prerequisites The constmetion testing of the containment, containment hatches /airlocks and containment penetrations; plus the piping and isolation valves or electrical wiring through the penetrations has been successfully completed. . The instrumentation to be used in  !

performing the Type A, B, and C testing is properly calibrated and available, including their associated data processing equipment, as appropriate. The required preoperational testing of the protection and safety monitoring system, plant control system, the class IE electrical power uninterruptable power supply, and other interfacing systems required for operation I of the containment isolation devices and data collection is available as needed to support i the specified testing.

General Test Acceptance Criteria and Methods Containment isolation functions, leak rate, and structural integrity performance are observed and recorded during a series of individual component and integrated system testing. The i following testing demonstrates that the containment functions as specified in Section 6.2 and ~  !

the appropriate design specifications am achieved. The testing is in accordance with the American National Standard for Containment System Leakage Testing Requirements, ANSI /ANS-56.8-1994. l l

I a) Proper operation of safety-related containment isolation valves is verified by the performance of baseline inservice tests as specified in subsection 3.9.6.

b) Proper calibration and operation of safety-related containment isolation instrumentation, controls, actuation signals and interlocks is verified. This testing includes actuation of the containment isolation valves, listed in Table 6.2.3-1, on receipt of a containment isolation signal; actuation from the main control room.

c) The appropriate Type C leakage testing is performed for each piping path penetrating the containment boundary, verifying the leakage for each containment isolation valve (listed in Table 6.2.3-1) or set of isolation valves. His testing for individual isolation valves may be performed in conjunction with the associated system test.

d) The appropriate Type B leakage testing is performed for each containment penetration whose design incorporates seals, gaskets, scalants, or bellows. This testing includes door or hatch operating mechanisms and seals.

c) A baseline inservice test / inspection of the accessible interior and exterior surfaces of the containment structure and components is performed as specified in subsection

3.8.2. Revision

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14. Initial Test Program f) The stmetural integrity of the containment, including penetrations, is verified by pressurizing the containment to the pressure required by 10CFR50 Appendix J to verify their function at design pressure, g) A Type A integrated leak rate test is performed to verify that the actual containment leak rate does not exceed the design basis leak rate specified in the Technical Specifications.

14.2.9.1.11 Containment Hydrogen Control System Testing Purpose The purpose of the containment hydrogen control system safety-related testing is to verify that the system properly performs the following safety-related functions described in Section 6.2: .

= Prevent the concentration of hydrogen in containment from reaching the flammability limit

  • Monitor the containment hydrogen concentration as required by regulatory guide 1.97. ,

Prerequisites  !

The construction testing of the containment hydrogen control system is completed. The Class IE de electrical power and uninterruptable power supply systems, the non-lE electrical supply system, and other interfacing systems required for operation of the above systems and calibrated data collection instmmentation, are available as needed to support the specified testing.

General Test Acceptance Criteria and Methods Performance of the containment hydrogen control system is observed and recorded during a series of individual component testing. The following testing verifies that the system operates as specified in Section 6.2 and as spec med in the appropriate design specifications:

a) Proper operation of the safety-related containment hydrogen concentration instrumentation and alarms is verified.

b) The ability of the passive autocatalytic recombiners to achieve their specified plate temperature when exposed to a specified atmosphere containing hydrogen is verified by testing a portion of the installed recombiner plates ex-containment.

c) The proper actuation and operation of the hydrogen igniters is verified.

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R[ 14. Initial Test Program 14.2.9.1.12 Protection and Safety Monitoring System Testing Purpose The purpose of the protection and safety monitoring system preoperational testing is to verify that the as-installed components properly perform the following safety-related functions, described in Section 7.1:

  • Receive and analyze sensor inputs required for reactor trip and automatically initiate reactor trip signals when plant conditions reach the appropriate setpoints.
  • Provide actuation signals to the engineered safety features to limit the consequences of design basis accidents.
  • Provide instrumentation and display systems to monitor the safety-related functions of the plant during and following the occurrence of design basis accidents in accordance with Regulatory Guide 1.97.

Preoperational testing is also performed to verify proper operation of the following defense-in-depth functions, described in Section 7.1: ,

  • Provide data from the safety-related sensors to the plant control system.
  • Provide information to the data display and processing system.

- Provide data to the monitor bus for use by other systems within the plant.

Prerequisites Construction and in'tallation testing of the protection and safety monitoring system cabinets has been successfully completed. Related system interfaces are available or simulated as necessary to suypon the specified test configurations. Component testing and instrument calibrations have been completed. Programming has been completed and the initial software diagnostics tests have been completed. Required electrical power supplies and control circuits are energized and operational. Required cabinet Geld wiring is electrically isolated to prevent operation of components controlled by the protection and safety monitoring system. Exceptions are specifically identiGed in the preoperational test procedures if plant systems or components are to be operated during testing and these systems or components are to be properly aligned and have proper support systems operating prior to actuation of the particular sys. tem or component.

General Test Methods and Acceptance Criteria Performance of the protection and safety monitoring system is observed and recorded during a series of individual component and integrated tests designed to verify operation of the Revision: 9 o s umemoi4 Roootis96 Draft July 31,1996 14-30 3 Westingt10US8

l I

14. Initial Test Program N-system components. The following testing verifies that the system operates as specified in Section 7.1 and appropriate design specifications:  !

l a) Processing of the analog and digital signals is verified by injecting reference signals and verifying the outputs at various locations in the system.

b) Capability to process sensor data and main control room manual inputs resulting in the initiation of appropriate reactor trip signals is demonstrated by simulating inputs for each of the trip functions. Operation of the protection cabinet trip / normal / bypass switches and indicators for each of the reactor trip functions is demonstrated by verifying appropriate outputs. l c) Operation of the reactor trip breakers, including breaker interlock, alarm, and tripping functions and verification that reactor trip response times are less than the specified maximum allowable response times is performed by initiating a manual reactor trip from the main control room. The capability of the undervoltage coil and the shu'.2 trip coil functions to independently trip the reactor trip breakers is verified during this test using the test capabilities provided by the reactor trip switchgear interface.  ;

d) The capability to manually trip the reactor from the remote shutdown workstation is demonstrated by verifying actuation of the reactor trip breaker undervoltage and shunt '

trip attachments upon initiation of a manual reactor trip using the switches provided ,

at the remote shutdown workstation location. l l

e) The capability of the protection and safety monitoring system to process sensor data and manual inputs, resulting in appropriate engineered safety features actuation at design setpoints, is demonstrated by verifying that injection of simulated inputs for each of the engineered safety features actuation functions results in the proper output  ;

as indicated by contact operation, component actuation, or electrical test. Response times associated with the engineered safety features actuation functions are evaluated during these tests to provide verification that response times are less than the specified maximum allowable times. Operation of the manual actuation / bypass switches and j indicators for each of the engineered safety featues functions is verified by demonstrating appropriate system outputs. Correct input processing and calculational accuracy of the redundant actuation equipment and operator interface features is verified for each defined engineered safety features actuation function using simulated inputs.

f) Correct processing of inputs Oy redundant equipment and operation of the processing, permissive, interlock, display and operator interface features is verified by demonstrating that. simulated command inputs result in correct output or actuation functions as indicated by contact operation, component actuation, or electrical test.

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" 14. Initial Test Program l

g) Accurate processing of component-level manual actuation commands from the main  !

control room to the protection logic cabinets is verified by simulating main control l room commands. Processing of component status information is demonstrated by l simulating protect;on logic cabinet outputs to the main control room.

h) Processing of component-level manual actuation commands from the remote shutdown workstation to the protection logic cabinets is verified by simulating remote shutdown workstation commands. Processing of component status information is verified by simulating protection logic cabinet outputs to the remote shutdown workstation.

i) Operation of the automatic testing features provided in the protection and safety monitoring system is verified by observing the automatic test functions while l simulating component failures and utilizing provided man-machine interface l capabilities to evaluate system performance.

l l

j) The capability of the protection and safety monitoring system to provide the plant ,

I operator with correct equipment status, component position indication, component control modes and abnormal operating conditions is verified by evaluating system .

response to simulated inputs representing feedback from actuation devices and position 4 indicators. Communication of information from the protection and safety monitoring, i system to external systems is verified by injecting reference signals and evaluating the inputs to the respective external systems.

k) Operation of the qualified data processing equipment is verified by monitoring outputs and qualified display indications generated in response to simulated inputs representing  ;

data from the integrated protection cabinets and sensor inputs to the qualified data l processing I/O cabinets.

1) Operation of the isolated fiber-optic data links and redundant data highways used for j communication between the subsystems within the protection and safety monitoring system is verified.

m) Preoperational testing of plant sensors used to provide data related to plant equipment monitored by the protection and safety monitoring system is performed in conjunction with testing of the respective systems in which these sensors are located.

14.2.9.1.13 Incore Instrumentation System Testing Purpose The purpose of the incore instrumentation system preoperational testing is to verify that the as-installed components properly perform the following safety-related functions, described in Section 7.1: l Revision: 9 . wor =v9eoi4 nos-o7is96 Draft July 31,1996 14 32 W Westingt10US8

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14. Initial Test Program 1

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  • Provide reactor coolant system pressure boundary integrity for the incore instrumentation thimble assemblies which penetrate the upper head of the reactor vessel.
  • Provide the protection and safety monitoring system with the core exit temperature signals required for post-accident monitoring.

Testing is also performed to verify the following nonsafety-related defense-in-depth I functions, described in subsection 4.4.6:

1

  • Provide core exit temperature signals to the diverse actuation system dedicated display in the main control room Prerequisites Related system interfaces are available or simulated as necessary to support the specified test configurations. Component testing and instrument calibrations have been completed.-

Required electrical power supplies are energized and operational.

General Test Methods and Acceptance Criteria i

Performance of the incore instrumentation system is observed and recorded dunng a senes of individual component and integrated tests designed to confirm operation of the system components outside the reactor vessel. De following testing verifies that the system operates as specified in Section 7.1 and the appropriate design specifications:

l a) Reactor coolant system pressure boundary integrity at the incore instrumentation reactor vessel head penetrations is verified during hydrostatic testing of the reactor coolant system.

b) Processing of the incore thermocouple signals is verified by thermocouple signals at the incore instrumentation thimble assembly connectors and verifying the thermocouple signal paths.

14.2.9.1.14 CNs IE DC Power and Uninterruptable Power Supply Testing Purpose ne purpose of the Class IE de power and uninterruptable power supply testing is to verify that the as-installed components properly perform the following safety-related functions described in Section 8.3:

  • Provide the elect'ical power required for the operation of the plant safety-related equipment, equipment controls, and instrumentation.

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14. Initial Test Program Provide the required safety-related electrical power for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following a design basis event, independent of both off-site and on-site ac electrical power supplies.
  • Provide separation and independence of Class 1E power divisions from other Class 1E divisions and non-Class IE systems.

Testing is also performed to verify proper operation of the following defense-in-depth functions described in subsection 83.2:

. Be capable of being recharged / replenished from the on-site or off-site ac electrical sources; such that safety-related functions can be supponed for an indefinite time.

Prerequisites The construction testing of the Class IE de power and inte'rmptable power supply components has been successfully completed. The necessary permanently installed and test instrumentation is properly calibrated and operational. Adequate ventilation / cooling is available for the battery rooms and areas with operating components. The 480 V ac electrical power system is in operation and sqplying power to the battery chargers and regulating transformers. A test load is available for the performance of battery capacity

  • tests.

General Test Methods and Acceptance Criteria Performance of the Class IE de power and interruptable power supply is observed and recorded during a series of individual component and integrated system tests that characterize the operation of the system. The following testing verifies that this system operates as specified in Section 83 and appropriate design specifications:

a) The capability of each of the seven Class IE batteries to provide the required momentary and continuous load is verified by a battery service test performed in accordance with IEEE Standard 450. Following this discharge testing, the voltage of each cell is verified to be greater than or equal to the specified minimum cell voltage, b) The capacity of each of the seven Class IE batteries is verified to meet or exceed the required ampere-hour rating by a battery performance test performed in accordance with IEEE standard 450. Following this discharge testing, the voltage of each cell is i verified to be greater than or equal to the specified minimum cell voltage.

l c) The capability of each of the seven battery chargers to charge its associated battery at the required rate is verified. This testing includes verification that the individual voltage of each cell are within the specified limits for a charged battery, d) The capability of each of the six inverters to provide the required output current, frequency, and voltage is verified.

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14. Initial Test Program e) The capability of each of the four regulating transformers to provide the proper ac current to the Class IE ac distribution panels is verified.

f) The capability of each of the static transfer switches to automatically transfer the electrical loads supplied by each inverter to its associated regulating transformer is verified.

g) The separation and independence of each redundant division of the Class IE de power and interruptable power supply is verified by successively powering only one division at a time and verifying power to the proper loads and the absence of voltage at the base and loads not under test.

14.2.9.1.15 Fuel Handling and Reactor Component Servicing Equipment Test Purpose To verify proper operation of the fuel-handling and reactor component servicing equipment as described in Section 9.1. This includes the refueling machine, fuel handling machine, fuel transfer system, and refueling tools used to lift, transport, or otherwise manipulate fuel, control rods and other incore instruments. ,

Prerequisites The construction tests have been successfully completed. Prerequisites of the required interfacing systems must be completed to the extent sufficient to support the spec'ified testing. Required electrical power supplies are energized and operational. Compressed air, as required for tool operation, is available. The reactor vessel head has been removed, the reactor vessel and refueling cavity are drained, the refueling cavity gate is open, and the area in which the refueling machine moves is free of structures or components that could interfere with fuel handling operations.

The spent fuel pool and fuel transfer canal are drained, and the area in which the fuel handling machine moves is free of any structures or components that interfere with design fuel handling operations.

The fuel transfer system is operable and capable of transporting a dummy fuel assembly from the spent fuel pool to containment. A dummy fuel assembly resembling an actual fuel assembly in weight, envelope, and mating hardware, is available for use. The fuel transfer system and new fuel elevator are operable as required to permit testing of fuel handling machine functions.

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14. Initial Test Program General Test Methods and Acceptance Criteria The following tests are performed to verify that the refueling machine properly operates:

a) The refueling machine is operated to simulate actual refueling operations, using a dummy fuel assembly. This testing includes manual and automatic modes of operation, displays, interlocks, and limits. These tests verify:

The ability to move a fuel : embly from the fuel transfer system to the reactor vessel "nd back.

The consistency of measured trolley, bridge, and hoist speeds with each mode of operation.

He operability of interlocks limiting motion,. speed, and weight, including .

interlocks with other plant equipment.

  • The operability of displays indicating position, mode, alarm status, and load.

The adequacy of indexing (by placing the dummy fuel assembly in selected core ,

locations).

b) A known weight or a calibrated spring scale is used to calibrate and set the load limits l for the refueling machine load cells. A static load test or the manufacturer's test l results are used to verify the ability of the refueling machine hoists to support 125 percent of their rated loads.

l The following tests are performed to verify the proper operation of the fuel handling ma-chine:

c) The fuel handling machine is operated to simulate actual refueling operations, using a dummy fuel assembly. These tests verify:

  • The ability to transfer fuel assemblies between the new fuel elevator, fuel transfer system, fuel storage racks, and other areas of the pool where fuel is serviced or stored.
  • The consistency of measured trolley, bridge, and hoist speeds with each mode of operation.
  • The operability of interlocks limiting motion, speed, and weight, including interlocks with other plant equipment.
  • The operability of displays indicating position, mode, alarm status, and load.

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14. Initial Test Program i

l d) The fuel handling machine is operated to verify its capability to transfer fuel ' cetween the new fuel elevator, fuel transfer system, fuel storage racks, and other areas of the pool where fuel is serviced or stored.

e) A known weight or a calibrated spring scale is used to calibrate and set the load limits for the fuel handling machine load cells. A static load test or the manufacturer's test results are used to verify the ability of the refueling machine hoists to support 125 percent of their rated loads.

The following tests are performed to verify the proper operation of the fuel transfer system and refueling tools:

f) Using appropriate plant operating procedures, the operability of the new fuel elevator is verified. Testing is performed to demonstrate the proper operation of controls, displays, and limit switches including operation of the interlock that prevents raising the elevator when it contains a fuel assembly.

g) Using appropriate plant operating procedures, the fuel transfer system is operated to simulate actual refueling operations, using a dummy fuel assembly. During these operations, the following items are verified: ,

  • The ability to move ^2el assemblies between the fuel building and containment, including proper operation of upenders in both locations
  • The operability and setpoints of limit switches and of interlocks between stations and with other plant equipment
  • The operability of displays indicating mode of operation and status h) Tests are performed to verify that the refueling tools operate properly. Included are tools for handling new fuel assemblies; fuel assembly inserts; irradiation specimens, control rod drive shafts; and tools for such operations as control rod drive shaft latching and reactor vessel stud tensioning. As applicable, power is applied to each tool to verify proper operation of controls, limit switches, actuators, and indicators.

Stud tensioning equipment is checked when assembling the reactor for hot functional testing. The new fuel handling tool is tested with the dummy fuel assembly during the test of the new fuel elevator.

14.2.9.1.16 Long-Term Safety Related System Support Testing Purpose The purpose of this testing is verify the capability to perform the following functions for maintaining the extended operation of the safety-related systems and components as described in Section 1.9:

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14. Initial Test Program

. Supply makeup water to the inside of containment

= Supply makeup water to the spent fuel pool

= Provide electrical power for post-accident instrumentation

= Supply air to the main control room

  • Provide cooling to the Class 1E cabinets for post-accident instrumentation Prerequisites The construction tests of the safety-related systems and/or components designed for long-term actions have been successfully completed. The preoperational testing of these systems and/or components, including instrument calibrations, has been completed as required for the specified testing, system configurations, and coerations. Equipment required for data collection is available and operable. Water used in this testing shall be of a quality suitable for filling the specified components. Air used in this testing shall be of breathable quality.

Equipment used to provide the required long-term actions is available.

General Test Method and Acceptance Criteria The ability to perform the required long-term actions is observed and recorded during a series of individual component and integrated system testing. The following testing verifies, that the long-term actions can be performed as discussed in Section 1.9 and as specified in -

appropriate design specifications:

a) The ability to provide makeup water to containment via the piping connection on the normal residual heat removal system as described in Section 6.3 and subsection 5.4.7 is verified.

b) The ability to provide makeup water to the passive containment cooling water storage tank as described in subsection 6.2.2 is verified.

c) The ability to provide electrical power to the post-accident monitoring instrumentation by using a ponable, engine-driven ac generator as described in Section 8.3 is verified.

d) The ability to provide breathable, compressed air for the main control room air supply and pressurization system using portable compressed air bottles as described in Section 6.4 is verified.

e) The ability to provide main control room and air recirculation using a portable HVAC unit as described in Section 6.4 is verified.

f) The ability to provide ventilation cooling to post-accident monitoring instrumentation equipment rooms using portable fans as described in Section 6.4 is verified.

g) The ability to provide makeup water to the spent fuel pool via the safety-related makeup connection as described in subsection 9.1.3 is verified.

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14. Initial Test Program 14.2.9.2 Preoperational Testing of Defense In Depth Systems 14.2.9.2.1 Main Steam System Testing Purpose The purpose of the main steam system testing is to verify that the as-installed system properly performs the following defense-in-depth function, as described in Section 10.3 and appropriate design specifications:
  • Provide backup isolation of the steamlines to prevent blowdown of steam from the steam generators following an event where steamline isolation is required Prerequisites The construction tests of the as-installed main steam system have been successfully completed. Prerequisites of the required interfacing systems are completed to the extent sufficient to support the specified testing and the appropriate system configuration. ,

General Test Method and Acceptance Criteria Main steam system performance is observed and recorded during a series of individual component and integrated system testing. The following testing demonstrates that the system

  • operates as specified in Section 10.4 and appropriate design specifications.

Proper operation of the following system valves is verified.

  • Turbine steam stop valves
  • Auxiliary stem system supply header isolation valve
  • Extraction steam isolation and non-retum valves This testing includes actuation of these valves from the main control room. The ability of these valves to isolate steam flow is verified during hot functional testing.

14.2.9.2.2 Main and Startup Feedwater System Purpose The purpose of the main and startup feedwater system testing is to verify that the as-installed system properly performs the following nonsafety-related defense-in-depth function, as described in subsections 10.4.7 and 10.4.9:

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14. Initial Test Program l

1 l

Prercquisites i I

The construction tests have been successfully completed. The component testing of the main and stanup feedwater system components and instmments, or specific portion to be tested has been completed. Required interfacing systems are available. l I

l General Test Method and Acceptance Criteria The main and stanup feedwater system performance is observed and recorded during a l

. series of individual component and integrated system testing. The following defense-in- i depth testing demonstrates that the system operates as specified in subsections 10.4.7 and I

< 10.4.9 and appropriate design specifications: I a) Proper operation of defense-in-deoth instrumentation, controls, actuation signals and interlocks is verified. This testing includes actuation of star:up feedwater pumps and remotely-operated valves from the main control room.

b) The capability of the stanup feedwater pumps to operate properly when performing their defense-in-depth function is verified with the steam generator at normal operating l pressure.

c) The capability of the stanup feedwater pumps to operate properly with miniflow to the condensate storage tank is verified.

14.2.9.2.3 Chemical and Volume Cop': a. System Testing 4

Purpose The purpose of 6.e chemical and volume control system testing is to verify that the as-installed system properly performs the following defense-in-depth functions described in subsection 9.3.6 and appropriate design specifications:

  • Provide auxiliary pressurizer spray Prerequisites The construction testing of the as-installed chemical and volume control system is successfully completed. The following interfacing and suppon systems are available as necessary to suppon testing: component cooling water system; service water system; reactor coolant system; electrical power and distribution systems. Data collection is available as needed to suppon the specified testing and system configurations.

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14. Initial Test Program General Test Acceptance Criteria and Methods  !

\

Chemical and volume control system performance is observed and recorded during a series I of individual component and integrated system testing. The following testing verifies the  !

system properly performs the defense-in-depth functions described in subsection 9.3.6 and )

appropriate design specifications: j l

a) Proper operation of pumps and valves which perform defense-in-depth functions is  ;

verified, including: j

  • makeup pumps I
  • makeup flow control valve b) Proper calibration and operation of defense-in-depth related instrumentation, controls, actuation signals and interlocks is verified including: i e automatic makeup pump actuation and shutoff

. automatic alignment of the boric acid tank l

  • pressurizer auxiliary spray initiation and termination ,

This testing includes actuation of defense-in-depth pumps and remotely-operated valves j from the main control room. Note that pressurizer level control testing is described in subsection 14.2.9.1.1.

c) The capability of the makeup pumps to operate properly when performing their normal makeup and pressurizer spray functions is verified with the RCS at normal operating pressure.

d) The capability of the makeup pumps to operate properly at mini-flow and the proper operation of the miniflow heat exchanger is verified.

14.2.9.2.4 Normal Residual Heat Removal System Testing Purpose The purpose of the normal residual heat removal system testing is to verify that the as-installed components and associated piping, valves, and instrumentation properly perform the following defense-in-depth functions, as discussed in Section 5.4:

  • Remove reactor core decay heat and cool the reactor coolant system during shutdown operations at low pressure and temperature.

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14. Initial Test Program

= Following actuation of the automatic depressurization system, provide makeup to the reactor coolant system at low pressure

= Circulate and cool water from the containment after draindown of the in-containment war storage tank.

  • Provide low temperature overpressure protection for the - actor coolant system. I Prerequisites l The constmetion testing of the normal residual heat removal system is successfully )

completed. The required preoperational testing of the in-containment refueling water storage J tank, reactor coolant system, passive core cooling system, component cooling water system, I service water system, ac electrical power and distribution systems, and other interfacing systems required for operation of the above systems and data collection is available as needed to support the specified testing and system configurations. The reactor coolant j system and the incontainment refueling water storage tank have an adequate water inventory j to support testing. l

)

General Test Acceptance Criteria and Methods ,

l Normal residual heat removal system performance is observed and recorded during a series of individual component and system testing, that characterizes system operation. The i following testing verifies that the normal residual heat removal system performs its defense-I in-depth functions as specified in subsection 5.4.7 and appropriate design specifications:

a) Proper operation of valves to open, to close, or to control flow as required to perform ,

the above defense-in-depth functions is verified.

l b) Proper operation of system controls, alarms, instmmentation, and interlocks associated  ;

with performing the above defense-in-depth functions is verified. j c) The normal residue! heat removal system pumps testing includes verification of the proper pump flow rate corresponding to the expected system alignment, pump miniflow operation, and verification that adequate NPSH is available for the configurations tested. 'Ibe following system configurations are tested with each pump operating individually and with two pumps operating:

  • Makeup to the reactor from the in-containment refueling water storage tank with approximately 4 feet of water in the tank. )

i l

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14. Initial Test Program d) 'Ile capability of the normal residual heat removal heat exchangers to provide the required heat removal rate from the reactor coolant system by testing performed with flow from and to the heated reactor coolant system, with each normal residual heat removal pump / heat exchanger operating individually.

e) Proper operation of the normal residual heat removal system relief valve which provides low temperature overpressure protection for the reactor coolant system is verified by the performance of baseline inservice testing, as specified in subsection 3.9.6.

f) Proper operation of the system to facilitate draining the reactor coolant system water l level to near the centerline of the hot leg for reduced inventory operations is verified.

This test is performed in conjunction with the chemical and volume control system, and is used to demonstrate the performance of the reactor coolant system hot leg level 1 instruments as discussed in subsection 14.2.9.1.1. I 14.2.9.2.5 Component Cooling Water System Testing j l

Purpose l

. I The purpose of the component cooling water system testing is to verify that the as-installed "

system properly performs the following defense-in-depth functions as described in i

subsection 9.2.2:

  • Provide cooling water to defense-in depth components and transfer heat to the service  ;

water system. In addition, this system prcryides cooling water to other' nonsafety-  ;

related components for heat removal.

Prerequisites The construction testing of the component cooling water system is successfully completed.

Preoperational testing of the cooled components has been completed as necessary to support I testing of the component cooling water system. Required support systems are available l including applicable ponions of the service water system and electrical power and distribution systems. Data collection is available as needed to support the specified testing and system configurations. l 1

General Test Acceptance Criteria and Methods l l

Component cooling water system performance is observed and recorded during a series of individual component and integrated system testing that characterizes the various modes of system operation. The following testing demonstrates that the system operates as specified in subsection 9.2.2 and as specified in appropriate design specifications:

a) Proper operation of the component cooling water pumps is verified.

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'U-A b) Proper operation of defense-in-depth related instrumentation, controls, actuation signals and interlocks is verified, including:

  • automatic pump actuation if an operating pump stops a pump flow rate
  • pump discharge pressure e surge tank water level and control a surge tank pressure and control
  • water flow rate to defense-in-depth components This testing includes actuation of the system pumps and remotely-operated valves from the main control room as appropriate.

c) The capability to provide the expected cooling water flow rates to and from the required components with both pumps operating, and with either individual pump and heat exchanger operating as specified in the appropriate design specifications is verified. -

4 d) In conjunction with Item c above, the pump (s) runout flow rate is verified to be properly limited, and adequate NPSH is verified to be available during its operating

  • modes.

e) The capability of the heat exchanger (s) to transfer heat properly to the service water system is verified during the plant conditions simulated during plant hot functional testing; with both pumps / heat exchangers in operation and with either one of the pumps / heat exchangers operating.

14.2.9.2.6 Service Water System Testing Purpose The purpose of the service water system testing is to verify the capability of the as-installed system to perform the following defense-in-depth functions, as described in subsection 9.2.1:

  • Transfer heat from the component cooling water heat exchangers to the environment Prerequisites The construction testing of the service water system is successfully completed.

( ,

Preoperational testing of the component cooling water heat exchangers so that they can receive service water have been completed; as well as the electrical power and distribution systems, and other interfacing systems required for operation of the service water system.

Data collection is available as needed to support the specified testing and system configurations. The component cooling water system and components it cools are functional and hot pre-operational testing of the reactor coolant system is in progress in order to confirm the service water system heat removal and heat rejection capability.

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14. Initial Test Program l

General Test Acceptance Criteria and Methods Service water system performance is observed and recorded during a series of individual component and integrated system testing. The following testing demonstrates that the service water system properly performs its defense-in-depth functions, as described in subsection 9.2.1 and appropriate design specifications a) Proper operation of the service water pumps, valves, strainers, cooling tower fens, and l freeze protection provisions are verified.

b) Proper operation of the defense-in-depth related instrumentation, controls, actuation signals and interlocks is verified, including:

e automatic pump actuation if an operating pump stops e pump flow rate e pump discharge pressure e cooling tower water level and control e cooling tower basin water temperature and control

. water supply and retum temperature e cooling tower fan control ,

This testing includes actuation of defense-in-depth pumps and remotely-operated valves from the raain control room as appropriate.

c) The capability of the pumps to provide the expected cooling flow rates to and from the component cooling water heat exchangers is verified; with both pumps operating and with either individual pump operating.

d) In conjunction with item c above, the pump (s) runout flow rate is verified to be properly limited, and adequate NPSH is verified to be available during appropriate operating modes.

e) The heat removal and heat rejection capability of the service water system during the conditions of the plant hot functional testing is verified; with both pumps / cooling towers cells in operation and with either one of the pumps / cooling tower cells operating.

14.2.9.2.7 Spent Fuel Pool Cooling System Testing Purpose The purpose of the spent fuel pool cooling system testing is to verify that the system properly performs the following defense-in-depth functions described in subsection 9.1.3:

  • Remove heat from the spent fuel stored in the spent fuel pool o humv90014 RMI596 Revision: 9

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14. Initial Test Program Prerequisites The construction testing of the spent fuel pool cooling system has been successfully completed. The spent fuel pool is filled with water of acceptable quality and chemistry, and the ac electrical power and distribution systems and other interfacing systems required for operation of the pumps and for data collection are available as needed to support the specified testing and system configurations.

1 General Test Acceptance Criteria and Methods Spent fuel pool cooling system performance is observed and recorded during a series of individual component and integrated system testing. The following testing demonstrates that the system properly performs its defense-in-depth function as described in subsection 9.1.3 and appropriate design specifications:

a) Proper operation of the spent fuel pool cooling pumps, valves, and strainers is verified. i l

b) Proper operation of the instrumentation, controls. actuation signals and interlocks is

)

verified, including:  ;

l

  • automatic pump actuation if an operatmg pump stops i

= pump flow rate a

)

pump discharge pressure

- spent fuel pool water level and control

  • spent fuel pool water temperature

= water retum temperature This testing includes operation of the system pumps from the main control room.

c) The capability of the pumps to provide the expected cooling flow rates to and from the pool is verified; with both pumps operating, with either individual pump operating, and with either heat exchanger operating.

d) In conjunction with Item c above, the pump (s) runout flow rate is verified to be properly limited, and adequate NPSH is verified to be available during the appropriate operating modes.

e) The proper operation of the spent fuel pool siphon breakers is verified.

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14. Initial Test Program 14.2.9.2.8 Fire Protection System Testing Purpose The purpose of the fire protection system testing is to verify the system properly performs the following defense-in-depth functions as described in subsection 9.5.1:

= Provide equipment for manual fire fighting in areas containing safe shutdown equipment Prerequisites The construction tests of the fire protection system have been successfully completed.

Required preoperational testing of the ac power and distribution systems and other interfacing systems required for operation of the fire protection system. Data collection is available as needed to support the specified testing and system configurations.

General Test Method and Acceptance Criteria Fire protection. system performance is observed and recorded during a series of individual component and integrated system testing to verify the system performs its defense-in-depth *

, function. The following testing demonstrates that the system performs its defense-in-depth functions specified in subsection 9.5.1 and as specified in appropriate design specifications:

The capability of the seismic standpipes to supply the required fire water quantity and flow rate is verified.

14.2.9.2.9 Central Chilled Water System Testing Purpose The purpose of the central chilled water system testing is to verify that the as-installed low capacity portion of this system properly performs the following defense-in-depth functions, as described in subsection 9.2.7:

l = Provide chilled water to cool air used to cool safety-related or defense-in-depth equipment rooms Prerequisites The construction testing of the low capacity subsystem of the central chilled water system

> has been successfully completed. The required preoperational testing of the component cooling water system, service water system, ac electrical power and distribution systems, radiologically controlled ventilation system, non-radiologically controlled ventilation system, and other interfacing systems required for operation of the central chilled water system. Data collection is available as needed to support the specified testing and system configurations.

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l l

General Test Acceptance Criteria and Methods Central chilled water system performance is observed and recorded during a series of i individual component and integrated system testing. The following testing demonstrates that I the central chilled water system performs its defense-in-depth functions described in l subsection 9.2.7 and appropriate design specifications 1

a) Proper operation of the low capacity portion of the .:entral chilled water system equipment is verified; including chillers, pumps, and valves.

b) Proper calibration and operation of defense-in-depth related instrumentation, controls, actuation signals and interlocks is verified, including:

I

  • Temperature control of the chilled water
  • Chiller and chilled water pump actuation
  • Chilled water pump flow and discharge pressure

= Chilled water flow control to air handling units i

This testing includes actuation of the defense-in-depth pumps and remotely operated l valves from the main control room. ,

c) The proper chilled water flow rate to each of the nuclear island nonradioactive ventilation system air handling units is established, and the capability of each pump i to provide this chilled water flow rate is verified. i d) In conjunction with Item c above, the pump (s) runout flow rate is verified to be properly limited, and adequate NPSH is verified to be available during the appropriate 1 operating modes.

e) The heat removal capability of the air-cooled chillers is verified when the component areas cooled by the nuclear island nonradioactive ventilation system air handling units are operating.

14.2.9.2.10 Nuclear Island Nonradioactive Ventilation System Testing Purpose The purpose of the nuclear island nonradioactive ventilation system testing is to verify that the as-installed system properly performs the following defense-in-depth functions, as described in subsection 9.4.1:

- Protect the mc "'ml room from smoke infiltration

  • Provide the capability to remove smoke from the main control room and Class IE electrical equipment rooms Revision: 9 o wvwx>i4 no947:5*

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14. Initial Test Program
  • Provide heating, ventilation, and cooling for the main control room and Class IE electrical equipment rooms
  • Provide air filtration to limit radioactivity in the main control room

. Maintain passive heat sinks at acceptably low initial temperatures

  • Maintain the main control room at positive pressure The safety-related functions associated with this system are tested as part of the main control room emergency habitability testing described in subsection 14.2.9.1.6.

Prerequisites The construction testing of the nuclear island non-radioactive ventilation system has been successfully completed. The required preoperational testing of central chilled water system, the hot water heating system, the ac electrical power and distribution systems, and other interfacing systems required for operation of the above systems and data collection is ,

available as needed to support the specified testing and system configurations.

General Test Acceptance Criteria and Methods Nuclear island non-radioactive ventilation system performance is observed and recorded during a series of individual component and integrated system testing.to verify the system performs its defense-in-depth functions. The following testing demonstrates that the system performs its defense-in-depth functions as specified in subsection 9.4.1 and appropriate design specifications.

a) Proper function of the fans, filters, heaters, coolers, and dampers is verified.

b) Proper operation of instmmentation, controls, actuation signals, and alarms and interlocks is verified. This testing includes the following:

  • Smoke detectors and alarms
  • Air handling unit and fan flows, controls, and alarms
  • Differential air pressures and alarms
  • Air and air filtration unit charcoal temperatures, controls, and alarms
  • Air relative humidity measurements, controls, and alarms
  • Isolatiordshutoff damper controls
  • Fire / smoke damper controls This testing includes operation from the main control room.

c) The proper air Dows from/through each air handling unit; to/from the main control room and oth: equipment rooms is established for each mode of operation.

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14. Initial Test Program l d) The main control room is verified to be maintained at the proper positive pressure. l c) The main control room, class IE equipment rooms, and passive heat sink areas are ,

verified to be maintained at their proper temperature during hot functional testing.

14.2.9.2.11 Radiologically Controlled Area Ventilation System Purpose The purpose of the radiologically controlled area ventilation system testing is to verify that the as-installed system properly performs the following defense-in-depth function, as described in subsection 9.4.3:

  • In conjunction with the low capacity portion of the central chilled water system, maintain the normal residual heat removal system and chemical and volume control system pump rooms at proper temperature during pump operation Prerequisites The construction testing of the radiologically controlled area ventilation system has been successfully completed. The required preoperational testing of the central chilled water' system, the hot water heating system, the ac electrical power and distribution systems, and other interfacing systems required for operation of the radiologically controlled a.rea ventilation system. Data collection is available as needed to support the specified testing and system configurations.

\

l General Test Acceptance Criteria and Methods l l

Radiologically controlled area ventilation system performance is observed and recorded during a series of individual component and integrated system testing to verify the system performs its defense-in-depth function as described in subsection 9.4.3 and appropriate design specifications: ,

a) Proper function of the defense-in-depth fans, filters, heaters, and coolers is verified.

b) Proper operation of defense-in-depth instrumentation, controls, actuation signals, and alarms and interlocks is verified. This testing includes operation of the normal residual heat removal and chemical and volume control pump room cooler / fans from the main control room.

c) The proper air flow and cooling capability of the normal residual heat removal and chemical and volume control pump room cooler / fans is verified.

d) The proper actuation of the normal residual heat removal and chemical and volume control pump room cooler fans in response to pump operation or high room temperature is verified.-

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14. Initial Test Program 1

14.2.9.2.12 Plant Control System Testing l Purpose

]

The purpose of the plant control system testing is to verify that the as-installed components properly perform the following nonsafety-related defense-in-depth functions, described in i Section 7.1: l

  • Provide control and coordination of the plant during startup, ascent to power. power i operation and shutdown conditions by integrating the automatic and manual control of j the reactor, reactor coolant and reactor support processes required for normal and off- i nonnal conditions utilizing rod control, pressurizer pressure and level control, steam generator water level control, steam dump (turbine bypass) control and rapid power reduction.
  • Provide control of other defense-in-depth systems and comp'onents. j Prerequisites l

\

Construction and installation testing of the plant control system has been successfully completed. Related system interfaces are available or simulated as necessary to support all* l specified test configurations. Component testing and int.trument calibrations have been j completed. The reactor vessel integrated head package is in place, all control rod drive i mechanism cables are connected and the integrated head and control rod drive mechanism i cooling system is operational. Programming has been completed and the initial software diagnostics tests have been completed. Required electrical power supplies and control circuits are energized and operational. Required plant control system field wiring is electrically isolated to prevent operation of components controlled by the plant control I system. Exceptions are specifically identified in the preoperational test procedures if plant systems or components are to be operated during testing and these systems or components are to be properly aligned and have proper support systems operating prior to actuation of the particular system or component.

General Test Methods and Acceptance Criteria Performance of the plant control system hardware and software is c$ served and recorded during a series of individual component and integrated tests designed to verify operation of defense-in-depth functions. The following testing demonstrates that the system operates as specified in Section 7.1 and applicable design specifications:

a) Processing of analog and digital signals is verified by injecting reference signala and verifying the outputs of the plant control system.

l b) Interfaces with other applicable plant equipment and systems such as reactor power control, feedwater control and turbine control are verified by demonstrating that

{

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14. Initial Test n ram I

l control room results in the proper output as indicated by contact operation, component )

actuation, or electrical test.  !

c) Interfaces with applicable plant equipment and systems are verified by demonstrating that injection of simulated inpm.s for each of the control functions provided at the l remote shutdown workstation results in the proper output as indicated by contact oper-ation, component actuation, or electrical test. ]

d) Proper operation of deferse-in-depth processing, monitoring, display and operator  ;

interface features provided by the plant control system is demonstrated by monitoring system outputs in response to simulated inputs, including simulated device or data highway failures, and utilization of provided self-test functions.

e) Proper functioning of the rod control system is verified by evaluating response to simulated demands from the plant control system and protection and safety monitoring  !

system including group selection and interlocking fuactions.

f) Proper calibration and operation of the rod position indication system is demonstrated by evaluating system response, utilizing applicable displays, annunciators and alarms, to simulated rod control logic inputs.

g) Proper operation of logic and controls for the pressurizer level and pressure control functions, including interlocks and equipment protective devices, is demonstrated by injecting simulated input signals representing anticipated pressurizer level and pressure transients.

14.2.9.2.13 Data Display and Processing System Testing Purpose  ;

\

The purpose of the data display and processing system testing is to verify that the as-installed components properly perform the following nonsafety-related defense-in-depth functions, described in Section 7.1:  ;

  • Display plant parameters for normal and emergency operations
  • Provide plant alarm functions for normal and emergency plant operations. i
  • Provide operational support for plant personnel iacluding computerized, interactive plant procedures. l
  • Provide analysis, logging and historical storage and retrieval of plant data. I i
  • Provide a redundant communications network for transmission of plant parameters.

l plant status, displays, alarms and data files. )

i l

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14. Initial Test Program Prerequisites Constmetion and installation testing of the data display and processing system has been successfully completed. Related system interfaces are available or simulated as necessary to support the specified test configurations. Component testing and instrument calibrations have been completed. Programming has been completed and the initial software diagnostics tests have been determined acceptable. Required electrical power supplies are energized and operational. Required system interfaces are connected and available or simulated as necessary to support the specified test configurations.

General Test Methods and Acceptance Criteria Performance of the data display and processing system hardware and software is observed and recorded during a series of individual component and integrated tests designed to verify that the data display and processing system equipment operates as specified in Section 7.1 and the applicable design specifications:

a) Initial operation of installed devices is verified by completing the diagnostics tests provided for the components and equipment.

b) Proper operation of the data display and processing system software and hardware is*-  :

demonstrated by utilizing the data display and processing system to provide the i processing, monitoring, display and opera'or interface features required during l l

preoperational testing of associated plant instmmentation and control systems.

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14.2.9.2.14 Diverse Actuation System Testing Purpose The purpose of the diverse actuation system preoperational testing is to verify that the as-installed components properly perform the following nonsafety-related defense-in-depth functions, described in Section 7.7:

  • Provide diverse (from the safety-related protection and safety monitoring system) automatic actuation of the following:

= passive containment cooling

  • isolation of selected containment penetrations
  • Provide a diverse, attemate means for manual actuation of reacto: W and engineered ,

safety features functions.

  • Provide a diverse system for monitoring selected plant parameters used to provide
  • guidance for manual operation and confirmation of reactor trip and selected engineered safety features actuation.

Prerequisites Construction and installation testing of the diverse actuation system has been successfully completed to the extent necessary to suppon preoperational testing. Related system interfaces are available or simulated as necessary to support the specified test configurations.

Component testing and instrument calibrations have been completed. Programming has been completed and initial system diagnostics tests have been determined acceptable.

Required electrical power supplies and control circuits are energized and operational.

Required field wiring is electrically isolated to prevent operation of components controlled by the diverse actuation system. Exceptions are specifically identified in the preoperational test procedures if plant systems or components are to be operated during testing and these systems or components are to be properly aligned and have proper suppon systems i operating prior to actuation of the particular system or component.

General Test Methods and Acceptance Criteria Performance of the diverse actuation system is observed and recorded during a series of individual component and integrated tests designed to verify operation of the system Revision: 9 owwooi4no947:3%

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14. Initial Test Program  ;

components. The following testing demonstrates that the system operates as speciGed in Section 7.7 and applicable design specifications:

a) Processing of the analog and digital signals is verified by injecting reference signals and verifying the outputs at various locations in the system.

b) Correct outputs or actuation furyions, for the automatic actuation logic mode, is verified by demonstrating that inption of simulated inputs for each of the specified actuation functions results in the proper output as indicated by contact operation, component actuation, or electrical test. l c) Correct outputs or actuation functions, for the manual actuation logic mode, is verified by demonstrating that each manual actuation function results in the proper output as indicated by contact operation, component actuation, or electrical test.

d) Proper operation of indications and alarms, for the specified inputs, including those l which provide reactor trip or engineered safety features actuation status, is verified by-injecting simulated input signals.

14.2.9.2.15 Main AC Power System Testing ,

Purpose The purpose of the main ac power system testing is to verify that the as-installed components properly performs its nonsafety-related defense-in-depth function to provide ac electrical power to plant nonsafety-related loads as described in subsection 8.3.1. l Prerequisites l

l The constmetion tests for the individual components associated with the main ac power system have been successfully completed. The required test instrumentation is properly calibrated and operational. Additionally, the plant offsite grid connection is complete and available.

General Test Methods and Acceptance Criteria The capability of the main ac power system to provide power to plant loads under various plant operating conditions is verified. The system components to be tested include the j medium and low voltage power system, load centers, motor control centers, and instrumentation and controls appropriate to each portion of the system. The following tcsts verify that the main ac power system provides its defense-in-depth functions as specified in subsection 8.3.1 and appropriate design specifications:

a) Verify the operability of medium-voltage supply breakers for the diesel-backed buses.

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14. Initial Test Program b) Energize the diesel-backed buses from their associated onsite standby diesel-generator supplies. Verify the bus voltages are within design limits. This test can be performed in conjunction with the testing of the standby diesel generator.

c) Verify correct operation of the manual controls, annunciation, and instrumentation for the 480 V load centers powered from diesel-backed buses and their 4160 V feeder breakers.

d) Simulate fault conditions at the 480 V load centers powered from diesel-backed buses and verify alarms and operation of trip devices and protective relays.

e) Energize the 480 V load centers powered from diesel-backed buses. Verify the bus

. voltages are within design limits.

f) Verify the operability of motor control center supply breakers which supply defense in-depth loads.

g) Simulate fault conditions at the motor control centers which supply defense-in-depth loads and verify alarms and operation of trip devices and protective relays.

h) Energize the motor control centers which supply defense-in-depth loads. Verify the' bus voltages are within design limits.

14.2.9.2.16 Non-Class IE de and Uninterruptable Power Supply System Testing Purpose The purpose of the non-Class IE de and uninterruptable power sup-ly system testing is to verify the ability to provide continuous, reliable power for the non-Class 1E control and instrumentation defense-in-depth loads.

Prerequisites The construction tests for the individual components associated with the non-Class IE de and uninterruptable power supply system have been successfully completed. Permanently installed and test instrumentation are properly calibrated and operational. Adequate ventilation is available for the battery rooms. The 480 V ac system is in operation to supply power to the battery chargers. Additionally, a test load is available for the performance of battery capacity tests.

General Test Methods and Acceptance Criteria The non-Class IE de and uninterruptable power supply system consists of electrical equipment including batteries, battery chargers, inverters, static transfer switches, and associated instrumentation and alarms that is used to supply power for the non-Class IE control and instrumentation loads. Performance is observed and recorded during a series Revision: 9 o warrev9ooi4 no9-o7:3*

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14. Initial Test Program l

of indi Hual component and integrated system tests. These tests verify that the non-Class IE de and unintermptable power supply system operates properly as specified in subsection 8.3.2 and appropriate design specifications:

a) The capability of each of the three non-Class IE batteries serving defense-in-depth loads is verified to meet or exceed the required ampere-hour rating by a battery performance test in accordance with IEEE 450. Following this discharge, the voltage of each cell is verified to be greater than or equal to the specified minimum cell voltage.

l b) The capability of each of the three chargers serving defense-in-depth loads to meet the {

rating specified by Table 8.3.2-6 is verified. His testing includes a verification that the charger output voltage is within design limits.  !

i c) The capability of each inverter to meet the rating specified by Table 8.3.2-6 is verified.

His testing includes a verification that the output frequency and voltage to be within '

the limits specified in Table 8.3.2-6.

I 14.2.9.2.17 Diesel Generator Testing l l

Purpose l l

ne purpose of the diesel generator testing is to verify the capability to provide electrical power to plant nonsafety-related loads that enhance an orderly plant shutdown if off-site AC power is not available.

Prerequisites The construction tests have been successfully completed. The necessary permanently installed instrumentation is properly calibrated and operational. Appropriate electrical power sources and diesel generator building heating and rentilation system are available for use.

The plant control system is available for operation as applicable to the diesel generator under test. Additionally, sufficient diesel fuel is available, on site or readily accessible, to perform the tests.

General Test Methods and Acceptance Criteria Performance is observed and recorded during a series of individual component and integrated tests. These tests verify that the diesel generators operate properly as specified in Sections 8.3 and 9.5 through the following testing:

a) Verify the operability of generator protection features required by subsection 8.3.1.1.2.2.

b) Simulate the loss of ac voltage and verify proper operation of undervoltage relay.

Verify sequencer control logic meets the requirements of Tables 8.3.1-1 and 8.3.1-2.

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14. Initial Test Program c) Verify the diesel generators fuel transfer pumps stan and stop automatically in response to simulated day tank low level and high level signals.

d) Transfer fuel oil from the fuel oil storage tank to the diesel fuel oil day tanks by means of the transfer pumps. Verify flow parameters are within design limits.

e) Verify proper operation of diesel generators building heating and ventilation system fans and dampers, manual and automatic controls, alarms, and indicating instruments.

f) Verify the air flow in the diesel generator building heating and ventilation system is acceptable.

g) Verify the diesel generator lockout features, i.e., turning gear engaged, emergency stop.

h) Verify that the diesel generator air staning system has sufficient capacity for cranking the engine for prescribed number of automatic or manual stans without recharging.

i) Stan the diesel generators. Verify voltage and frequency control.

j) Verify the full load-carrying capability for a period of not less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, of which 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at are at a load equivalent to the 2-hour (Standby) rating of the diesel *-

generators and 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> at a load equivalent to the continuous rating of the diesel generators. Verify the voltage and frequency requirements are maintained. Verify that the diesel generator cooling system functions witnin design limits.

k) Following the full-load capability test (j), simulate loss of ac voltage and verify proper automatic stanup, sequencing, and operation of the diesel generators. Verify diesel generators bus de-energization and load shedding. Verify diesel generators attain frequency and voltage within design limits within the time specified in subsection 8.3.1.1.2.3. Verify sequencer control logic meets the requirements of Tables 8.3.1-1 and 8.3.1-2. Verify that the diesel generators continuous rating is not exceeded.

Verify voltage and frequency requirements are maintained.

1) Verify that the rate of fuel consumption and the operation of the fuel transfer pumps and associated components, while providing power to the load equivalent to those specified in Tables 8.3.1-1 or 8.3.1-2, are such that the design capacity of the fuel oil storage tanks meet the subsection 9.5.4 requirement for 7-day storage inventory, m) With each diesel generator bus supplied only by the diesel generator and supplying loads up to its continuous rating, trip a load equivalent to the largest single load in Table 8.3.1-1 or 8.3.1-2. Verify that the voltage and frequency values are maintained within design limits.

i n) With each diesel generator supplying loads up to its continuous rating, trip the j generator breaker that supplies power to the diesel generator bus. Verify that the diesel !

engine continues to run and does not trip on overspeed.  !

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14. Initial Test Program 14.2.9.2.18 Radiation Monitoring System Testing Purpose The purpose of the radiation monitoring system testing is to verify that the as-installed radiation monitors perform their defense-in-depth function as described in Section i1.5.

Prerequisites The constmction testing of the radiation monitoring system has been successfully completed.

The radiation monitors have been calibrated and the monitor check sources are installed, as appropriate. The required preoperational testing of the protection and safety monitoring system, plant control system, the electrical power and distribution systems, and other interfacing systems required for operation of the above systems and data collection is available as needed to support the specified testing.

General Test Acceptance Criteria and Methods -

Radiation monitoring system performance is observed and recorded during a series of individual component and integrated system testing to verify the system performs its defense-in-depth functions. The following testing demonstrates that the system operates as' specified in Section 11.5 and as specified in appropriate design specifications:

a) The proper calibration and operation of each radiation detector assembly and associated equipment using a standard radiation source or ponable calibration unit is verified.

b) Proper operation of the monitoring equipment and controls required for manually initiated operation of the monitor check sources is verified. l c) Proper operation of the local processors that process and transmit radiation monitoring data to the protecticn and safety monitoring system or plant control system as appropriate, is verified.

d) Proper actuation of alarms and signals for actuation of equipment responses following receipt of a high radiation signal is verified.

14.2.9.2.19 Plant Lighting System Testing Purpose The purpose of plant lighting system testing is to verify that the system can perform its defense- in-depth function of providing emergency lighting in the main control room and remote shutdown workstation area to illuminate these areas for emergency operations upon loss of normal lighting, as described in subsection 9.5.3.

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14. Initial Test Program Prerequisites The construction testing of the plant lighting system is completed. The required preoperational testing of the interfacing and support systems required for testing the emergency lighting function is available as needed to support the specified testing and system configurations including the Class IE de and uninterruptable power supply system, and the main ac power system.

General Test Acceptance Criteria and Methods Plant lighting system performance is observed during a series of individual component and integrated system testing to verify the system capability to perform its defense-in-depth functions. The following testing verifies that the system operates as specified in subsection 9.5.3 and in appropriate design specifications:

a) The proper operation of the plant lighting system emergency lighting is verified when powered from the Class IE de and unintermptable power supply system.

14.2.9.2.20 Primary Sampling System Testing Purpose The purpose of the primary sampling system testing is to verify that the as installed components properly perform the following nonsafety-related defense-in depth functions described in subsection 9.3.3:

  • Provide the capability to obtain samples of the reactor coolant, containment sump water, and containment atmosphere Prerequisites Construction testing of the primary sampling system has been successfully completed.

Component cooling water is being provided to the sample coolers when samples are taken ,

from the reactor coolant system when it is at elevated temperature. The systems / components i to be sampled are filled and at their normal pressure and temperature. The liquid radwaste system is available to receive discharged sample fluid. Electrical power is available for operation of the system components and a source of compressed gas is available for operation of the gas sample eductor.

General Test Method and Acceptance Criteria The performance of the primary sampling system is observed and recorded during a series of individual component tests and testing in conjunction with the reactor coolant system and passive core cooling system operation. The following testing demonstrates that the primary sampling system performs its defense-in-depth functions as described in subsection 9.3.3 and appropriate design specifications.

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14. Initial Test Program a) Proper operation of the system remotely-operated valves and eductor supply pump is verified.

b) Proper calibration and operation of instrumentation, controls, actuation signals, and interlocks is verified.

c) Verify the capability to properly obtain samples from the reactor coolant, containment sump, and containment atmosphere.

d) Verify the ability to return the sample stream fluid to the containment sump or liquid radwaste system, as appropriate.

e) . Verify the capability to route sample streams to the laboratory.

14.2.9.3 Preoperational Testing of Nonsafety Related Radioactive Syst. ems  ;

I 14.2.9.3.1 Liquid Radwaste System Testing Purpose The purpose of the liquid radwaste system testing is to verify that the as-installed' l components and associated piping, valves, and instmmentation properly perform the following safety-related functions described in subsection 11.2.1.1:

  • Drain the passive core cooling system compartments to the containment sump to prevent flooding of these compartments and possible immersion of safety-related components.
  • Prevent back flow through the drain lines from the containment sump to the chemical and volume control system compartment and the passive core cooling system compartments, in order to prevent cross flooding of these compartments.

l The liquid radwaste system testing is performed to verify that the as-installed components l and associated piping, valves, and instrumentation properly perform the nonsafety-related functions described in subsection i1.2.1.2, including receiving and processing reactor coolant system effluents, radioactive equipment and floor drains, and other radioactive liquid wastes from the plant.

Prerequisites The construction testing of the liquid radwaste system is successfully completed. The required preoperational testing of the interfacing and support systems required for testing and data collection is available as needed to support the specified testing and system configurations.

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14. Initial Test Program 1

I General Test Acceptance Criteria and Methods Liquid radwaste system performance is observed and recorded during a series of individual I component and system testing that characterizes system operation. This testing verifies that ,

the system operates as specified in Section 11.2 and appropriate design specifications.  ;

I a) The drain lines from the passive core cooling system compartments and the refueling I cavity are verified to provide a flow path to the reactor compartment. I l

b) Proper operation of the backflow prevention check valves is verified by the performance of baseline inservice tests as specified in subsection 3.9.6.

c) Proper operation of the system pumps and valves is verified, including:

  • effluent holdup tank pumps

= waste holdup tank pumps i

= degasifier separator pumps i e chemical waste tank pump

  • monitor tank pumps

1 d) Proper calibration and operation of the system instrumentation, controls, actuation I signals, and interlocks is verified, including: j l

  • Pump controls and alarms l

= Tank level control and alarms )

. Valve and pump responses to safeguards signals

  • Valve and pump responses to high radiation isolation signals e) In conjunction with the gaseous radwaste system testing in subsection 14.2.9.3.2, the proper operation of the degasifier is verified.

f) The proper operation of the liquid radwaste filters and ion exchangers is verified.

14.2.9.3.2 Gaseous Radwaste System Testing The purpose of the gaseous radwaste system testing is to verify that the as-installed components and associated piping, valves, and instrumentation properly perform the following nonsafety-related functions described in Section 11.3

- Collect waste gases that contain radioactivity or hydrogen

= Reduce the radioactivity of the waste gases as appropriate to enable its release 1

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14. Initial Test Program Prerequisites The construction testing of the gaseous radwaste system is successfully completed. The required preoperational testing of the interfacing and support systems required for testing is completed, and data collection is available as needed to support the specified testing and system configurations. In addition, a source of hydrogen and calibration gases is available.

General Test Acceptance Criteria and Methods I

The performance of the gaseous radwaste system is observed and recorded during a series I of individual component and system tests that characterizes the various modes of system operation. This testing verifies that the gaseous radwaste system operates as specified in i Section 11.3 and appropriate design specifications: )

a) System and component control circuits, including response to normal control, interlock, and alarm signals are verified. The gaseous radwaste system instrumentation, controls, valves, and interlocks are verified to respond to various inputs and calibration testing I and provide proper isolation and alarm signals. Appropriate automatic control l functions are verified in response to abnormal conditions inputs.

b) Nitrogen, hydrogen, and calibration gases are routed through the system. Performance' characteristics of the instrumentation and control systems are verified, and the delay ,

bed operation is verified.

c) Moist test gas is routed through the system to verify proper moisture removal and detection.

d) The degasifer vacuum pump is verified to operate properly. Manual override of the automatic control functions of the drainpot and moisture separator drain control valves is verified.

e) Sample pumps are operated and the sample flow meter indication is observed.

f) The proper operation of the degasifier moisture separator is demonstrated.

14.2.9.3.3 Solid Radwaste System Testing Purpose The purpose of the solid radwaste system testing is to verify that the as-installed components and associated piping, valves, and instrumentation operate properly to prepare waste generated during the normal operation of the plant for processing, packaging, and shipment as described in subsection 11.4.1.2.

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't 14. Initial Test Program I n- l Prerequisites 1

The constmetion testing of the solid radwaste system is successfuliy completed. The j interfacing and support systems required for testing and data collection are available as )

needed to support the specified testing and system configurations.

General Test Method and Acceptance Criteria  !

The performance of the solid radwaste system is observed and recorded during a series of i individual component and system tests that characterizes the various modes of system j operation. This testing verifies that the solid radwaste system operates as specified in l I

Section 11.4 and in appropriate design specifications:

a) Tests are performed to verify that manual and automatic system controls, alarms, indicating instruments and readouts are functional. The system instrumentation, controls, valves, and interlocks respond properly to various inputs and provide proper l isolation and alann signals. Appropriate automatic control functions occur in response to abnormal condition inputs. .

b) Tests are performed to verify proper system process rates as specified in Section 11.4. ,

c) The capability to properly transfer and retain spent resins is verified.

l 1

d) The capability to properly handle filter cartridges in a manner that minimizes personnel l radiation exposure is demonstrated.

14.2.9.3.4 Radioactive Waste Drain System Testing Purpose The purpose of the radioactive waste drain system testing is to verify that the as-installed components and associated piping, valves, and instrumentation properly perform the following functions described in Section 11.2: I

  • Drair door and equipment compartments l
  • Collect drainage and transfer drainage to the liquid radwaste system

]

Prerequisites The construction testing of the radioactive waste drain system is successfully completed The interfacing and support systems required for testing and data collection are available as needed to support the specified testing and system configurations, including the liquid radwaste system and compressed air supply.

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14. Initial Test Program General Test Method and Acceptance Criteria The performance of the radioactive drain system is observed and recorded during a series of individual component and system tests that characterizes the various modes of system operation. This testing verifies that the system operates as specified in Section 11.2 and in appropriate design specifications:

a) Proper operation of system instrumentation, controls, alarms, and interlocks is verified.

b) Proper operation of the system pumps and valves is verified.

c) Proper system and component flowpaths and flowrates, including pump capacities and sump tank volumes is verified.

14.2.9.3.5 Steam Generator Blowdown System Testing Purpose The purpose of the steam generator blowdown system testing is to verify that the as-installed components and associated piping, valves, and instrumentation operate properly to

, provide an isolatable flowpath for the controlled removal of water from the secondary side"

, of the steam generators as described in Section 10.4.

Prerequisites The construction testing of the steam generator blowdown system is successfully completed The interfacing and support systems required for testing and data collection are available as needed to support the specified testing and system configurations, including the liquid radwaste system. A portion of this testing is performed during the hot functional testing of the plant, when the steam generators are at or near normal operating pressure and temperature.

General Test Method and Acceptance Criteria The performance of the steam generator blowdown system is observed and recorded during a series of individual component and system tests that characterizes the various modes of system operation. This testing demonstrates that the system operates as specified in Section 10.4 and in appropriate design specifications:

a) Proper operation of system instrumentation, controls, alarms, and interlocks is verified.

b) Proper operation of the system pumps and valves is verified.

d) The proper operation of the electrodeionization units is verified.

e) The heat transfer capability of each blowdown heat exchanger is verified.

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14. Initial Test Program rip _

f) The automatic isolation of steam generator blowdown on low steam generator level is verified.

14.2.9.3.6 Waste Water System Testing Purpose The purpose of the waste water system testing is to verify that the as-installed components and associated piping, valves, and instrumentation operate properly to collect and perform appropriate processing of normally non-radioactive drains as described in Section 11.2.

Prerequisites The construction testing of the waste water system is completed. The interfacing and support systems required for testing and data collection are available as needed to support the sycified testing and system configurations, including the liquid radwaste system and a source of compressed air.

General Test Acceptance Criteria and Methods

~

Waste water system performance is observed and recorded during a series of individual component and system testing that characterizes system operation. This testing verifies that the system operates as specified in Section 11.2 and appropriate design specifications.

3 a) Proper operation of the system pumps and valves is verified.

1 b) Proper calibration and operation of the system instrumentation, controls, actuation  !

signals, and interlocks is verified.,

c) Proper system and component flowpths and flowrates, including pump capacities and ,

sump tank volumes is verified. l i

14.2.9.4 Preoperational Tests of Additional Non-Safeti-related Systems  !

14.2.9.4.1 Condensate System Testing Purpose The purpose of the condensate system testing is to verify that the as-installed components properly perform the system functions, described in subsection 10.4.7, to deliver the required flow of heated water from the condenser hotwell to the feedwater system.

Prerequisites

'Ile construction testing of the condensate system has been successfully completed. The construction testing of the condenser is completed and a source of water of appropriate Revision: 9 .s meooi4no9o7is96 Draft July 31,1996 14-66 3 Westinghouse

14. Initial Test Program quality is available for filling the condenser hotwell. The steam generator feedwater system is available to receive flow from the condensate system. Required electrical power supplies and control circuits are operational.

General Test Method and Acceptance Criteria 2

Condensate system performance is observed and recorded during a series of individual component and integrated system testing. The following testing verifies that the condensate system can perform its functions as described in subsection 10.4.7 and appropriate design specifications:

a) Proper operation of the condensate pumps and system valves is verified.

b) Proper calibration and operation of the system instmmentation, controls, actuation signals, and interlocks is verified.

, c) Verify proper operation of the heater drains.

d) During the plant hot functional testing, the integrated operation of the condensate system in conjunction with the feedwater system is verified with the condenser and circulation water system in operation.

14.2.9.4.2 Condenser Air Removal System Testing Purpose The purpose of the condenser air removal system testing is to verify that the as-installed components properly perform the system functions, described in subsection 10.4.2, to establish and maintain the required vacuum in the main condenser.

Prerequisites The construction testing of the condenser air removal system has been successfully completed. The construction testing of the condenser is completed and a source of water of  ;

appropriate quality is available for filling the condenser hotwell. The turbine gland sealing i system and exhaust blower shall be in operation. A source of steam such as the auxiliary boiler shall be available. Required support systems, electrical power supplies and control l circuits are operational. l General Test Method and Acceptance Criteria Condenser air removal system performance is observed and recorded during a series of individual component and integrated system testing. The following testing verifies that the l condensate system can perform its functions as described in subsection 10.4.2 and appropriate design specifications:

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14. Initial Test Program a) Proper operation of the vacuum pumps and system valves is verified.

b) Proper calibration and operation of the system instrumentation, controls, actuation signals, and interlocks is verified.

c) The ability of the vacuum pumps to establish the required vacuum in the main condenser is verified.

14.2.9.4.3 Main Turbine System and Auxiliaries Testing Purpose The purpose of the main turbine system testing is to verify that the as-installed main turbine and its auxiliary components properly perform their functions, described in Sections 10.2 and 10.4. This testing includes testing of the turbine gland sealing system, lube oil system, turning gear, turbine controls and protective functions, and moisture separator reheater.

Prerequisites The construction testing of the main turbine and its auxiliaries has been successfully, completed. The constmetion testing of the condenser is completed and a source of water of' appropriate quality is available for filling the condenser hotwell. The main turbine shall be on turning gear and the condenser air removal system shall be operable. A source of steam such as the auxiliary boiler shall be available. Required support systems, electrical power supplies and control circuits are operational.

General Test Method and Acceptance Criteria Because this testing is performed using a temporary steam source, the extent to which the turbine can be tested in preoperational testing is limited. However, the proper function of the turbine auxiliaries is verified to assure the turbine will operate properly when a greater amount of steam is provided by the nuclear steam supply system.

Main turbine system performance is observed and recorded during a series of individual component and integrated system testing. The following testing verifies that the turbine and its auxiliaries function as described in Sections 10.2 and 10.4 and in appropriate design specifications:

a) Proper operation of the turbine lube oil pump and turning gear motor, gland seal exhaust blower, and moisture separator and gland seal valves is verified.

b) Proper calibration and operation of the system instrumentation, controls, actuation signals, and interlocks is verified.

c) Proper turbine operation during the turning gear testing is verified. The turning gear engagement a6d disengagement functions are verified to operate properly.

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14. Initial Test Program l

d) Proper performance of the turbine trip functions are verified.

14.2.9.4.4 Main Generator System and Auxiliaries Testing i Purpose j The purpose of the main generator system testing is to verify that the as-installed main l generator and its auxiliary components properly perform their functions, described in i Sections 10.2 and 10.4. This testing includes testing of the generator cooling systems, lube oil system, controls and protective functions.

Prerequisites l

The construction testing of the main generator and its auxiliaries has been successfully j completed. The construction testing of the condenser is completed. The turbine cooling l water system is operable and any additional required support systems, electrical power supplies and control circuits are operational.

~

General Test Method and Acceptance Criteria  ;

Because this testing is performed when the turbine is tested using a temporary steam source,'

the extent to which the generator can be tested may be limited. However, the proper i function of the generator auxiliaries is verified to assure proper operation when the turbine l is operated when a greater amount of steam is provided by the nuclear steam supply system. j l

l Main generator system performance is observed and recorded during a series of individual  ;

component and integrated system testing. The following testing verifies that the generator and its auxiliaries function as described in Sections 10.2 and 10.4 and appropriate design specifications:

a) Proper operation of the seal oil and stator cooling water pumps and associated valves is verified.

b) Proper calibration and operation of the system instrumentation, controls, actuation signals, and interlocks is verified.

, c) Proper operation of the generator gas control in removing air and providing the generator with hydrogen gas is verified. The generator hydrogen purity, hydrogen pressure, and leakage are verified to meet appropriate design requirements.

d) Proper performance of the generator trip and runback functions are verified.

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14. Initial Test Program u-14.2.9.4.5 Turbine Building Closed Cooling Water System Testing Purpose The purpose of the turbine building closed cooling water system testing is to verify that the as-installed components properly perform its functions described in subsection 9.2.8, to supply adequate cooling water to the designated turbine building components.

Prerequisites The construction testing of the turbine building closed cooling water system has been successfully completed. The cooled components are operational and operating to the extent possible, especially for verifying the heat exchanger capability. Required support systems, electrical power supplies and control circuits are operational.

General Test Method and Acceptance Criteria Turbine building closed cooling water system performance is observed and recorded dering a series of individual component and integrated system testing. The following testing verifies that the system functions as described in subsection 9.2.8 and appropriate design

  • specifications:

a) Proper operation of the system pumps and valves is verified.

b) Proper operation of the system instrumentation, controls, actuation signals, and interlocks is verified.

14.2.9.4.6 Circulating Water System Testing Purpose The purpose of the circulating water system testing is to verify that the as-installed components properly perform the functions described in subsection 10.4.5, to cool and circulate adequate cooling water from the cooling tower basin to the main condenser and turbine building closed cooling water system heat exchangers. I Prerequisites The constmetion testing of the circulating water system and cooling tower has been successfully completed. The cooling tower water reservoir is filled with water of appropriate quality. The main condenser and turbine building closed cooling water heat exchangers shall be operational. Required support systems, electrical power supplies and control circuits are operational, i

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14. Initial Test Program i

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General Test Method and Acceptance Criteria Since their will be little, if any heat rejected to the circulating water system; verification of the heat removal capability of the ultimate heat sink is performed during the startup testing of the plant when the reactor is producing power.

Circulating water system performance is observed and recorded during a series of individual component and integrated system testing. The following testing verifies that the system functions as described in subsection 10.4.5 and appropriate design specifications:

l a) Proper operation of the system pumps and valves is verified.

b) . Proper calibration and operation of the system instrumentation, controls, actuation signals, and interlocks is verified.

l c) The proper operation of the system freeze protection equipment is verified, as )

applicable.

14.2.9.4.7 Turbine Island Chemical Feed System Testing l

Purpose l The purpose of the turbine island chemical feed system testing is to verify that the as-installed components properly perform the functions described in subsection 10.4.11, to add appropriate chemica's to the condensate, circulating water, service water, and auxiliary boiler; in a controlled manner, i

Prerequisites l The construction testing of the chemical feed system has been successfully completed. The ultimate heat sink water reservoir is filled with water of appropriate quality. Required l support systems, electrical power supplies and control circuits are operational.

General Test Method and Acceynoce Criteria Turbine island chemical feed system performance is observed and recorded during a series of individual component and integrated system testing. The following testing verifies that the system functions as described in subsection 10.4.11 and appropriate design specifications:

a) Proper operation of the system pumps and valves is verified.

b) Proper calibration and operation of the system instrumentation, controls, actuation signals, and interlocks is verified.

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l l 14.2.9.4.8 Condensate Polishing System Testing Purpose The purpose of the condensate polishing system testing is to verify that the as-installed components properly perform the functions described in subsection 10.4.6, to remove corrosion products, dissolved solids, and other impurities from the condensate system.

Prerequisites i

The construction testing of the condensate polishing system has been successfully  ;

completed. The ultimate heat sink water reservoir is filled with water of appropriate quality and the condensate and feedwater systems are operational. Required support systems, l electrical power supplies and control circuits are operational.

l General Test Method and Acceptance Criteria Condensate polishing system performance is observed and recorded during a series of individual component and integrated system testing. The following testing verifies that the system functions as described in subsection 10.4.6 and appropriate design specifications:

a) Proper operation of the system valves is verified.

I b) Proper calibration and operation of the system instrumentation, controls, actuation signals, and interlocks is verified.

14.2.9.4,9 Demineralized Water Transfer and Storage System Testing l Purpose The purpose of the demineralized water transfer and storage system testing is to verify that the as-installed components properly perform the function to provide reservoirs of demineralized water and deliver deoxygenated, demineralized water to various plant users as described in subsection 9.2.4. ]

Prerequisites The construction testing of the demineralized water transfer and storage system has been successfully completed. The demineralized water treatment system is operational and the equipment which uses demineralized water are able to accept water. Required support systems, electrical power supplies and control circuits are operational..

General Test Method and Acceptance Criteria Demineralized water transfer and storage system performance is observed and recorded during a series of individual component and integrated system testing. The following Revision: 9 o w.rrev9eoi4 Ro+47:596 Draft July 31,1996 14-72 3 W85tingt100S8

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14. Initial Test Program 1

I defense-in-depth testing verifies that the system functions as described in subsection 9.2.4 and appropriate design specifications:

l a) Proper opcration of the system pumps, valves, blower, and is verified. I I

b) Proper calibration and operation of the system instrumentation, controls, actuation )

signals, and interlocks is verified.

14.2.9.4.10 Compressed and Instrument Air System Testing Purpose l The purpose r 'he compressed and instmment air system testing is to verify that the as-installed corr _ aents properly perform the functions described in subsection 9.3.1,to i provide compressed air at the required pressures to various plant users.

Prerequisites i

The construction testing of the compressed and instrument air system has been successfully  !

completed. The component cooling water system is operational and providing cooling for,  !

the compressor units. Required support systems, electrical power supplies and control' l circuits are operational.

General Test Method and Acceptance Criteria l Compressed and instrument air system performance is observed and recorded du'ing r a series of individual component and integrated system testing. The following testing verifies that the system functions as described in Section 9.3 and appropriate design specifications:

a) Proper operation of the system compressors and valves is verified.

b) Proper calibration and operation of the system instrumentation, controls, actuation signals, and interlocks is verified.

14.2.9.4.11 Containment Recirculation Cooling System Testing Purpose The purpose of the containment recirculation cooling system testing is to verify that the as-installed components properly perform the functions described in subsection 9.4.6, to maintain the proper containment air temperature during normal plant operation and during refueling and maintenance operations.

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14. Initial Test Program Prerequisites The construction testing of the containment recirculation cooling system has been successfully completed. The central chilled water system and hot water heating system are operational. Required support systems, electrical power supplies and control circuits are operational.

General Test Method and Acceptance Criteria Containment recirculation cooling system performance is observed and recorded during a series of individual component and integrated system testing. 'Ihe following testing verifies that the system functions as described in subsection 9.4.6 and appropriate design specifications:

a) Proper operation of the system fans and dampers is verified.

b) Proper calibration and operation of the system instrumentation, controls, actuation signals, and interlocks is verified. .

4 14.2.9.4.12 Containment Air Filtration System Testing ,

, Purpose The purpose of the containment air filtration system testing is to verify that the as-installed components properly perform the functions described in subsection 9.4.7, to supply and exhaust air to maintain the proper containment air pressure, and filter exhaust air to minimize radiation release.

Prerequisites The construction testing of the containment air filtration system has been successfully completed. The portions of the radiologically controlled area ventilation system connected to the air filtration system are operational. The hot water heating and chilled water systems are required for verification of the air filtration heating and cooling functions. Required support systems, elec*rical power supplies and control circuits are operational.

General Test Method and Acceptance Criteria

~

Containment air filtration system performance is observed and recorded during a series of

- individual component and integrated system testing. The following testing verifies that the system functions as described in subsection 9.4.7 and appropriate design specifications:

a) Proper operation of the system fans and dampers is verified.

b) Proper calibration and operation of the system instrumentation, controls, Revision: 9 ow=v9eoi4 no947is96 Draft July 31,1996 14 74 [ W 85tlR gtt0 0S6

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14. Initial Test Program c) The capability to dilute the actuation signals, and interlocks is verified.

14.2.9.4.13 Plant Communications System Testing Purpose The purpose of the plant communications system testing is to verify that the as-installed components properly perform the functions described in Section 9.5, to verify the proper operation and adequacy of the plant communication systems used during normal and abnormal operations. I l

Prerequisites 1

The constmetion testing of the communication system has been successfully completed.

Required support systems, electrical power supplies and control circuits are operational.

I General Test Method and Acceptance Criteria Plant communications system performance is observed and recorded during a series of individual component and integrated system testing. The following testing verifies that the*

system functions as described in Section 9.5 and appropriate design specifications:

a) Transmitters and receivers are verified to operate without excessive interference.

b) Proper operation of controls, switches, and interfaces is verified.

l c) Proper operation of the public address, including the plant emergency alarms, is verified.

d) The proper operation of equipment expected to function under abnormal conditions such as a loss of electrical power, shutdown from outside the control room, or execution of the plant emergency plan is verified.

14.2.9.4.14 Mechanical Handling Sfstem Crane Testing Purpose The purpose of the mechanical handling system crane testing is to verify that the as-installed components properly perform the functions described in subsection 9.1.5, to verify the proper operation and adequacy of the reactor building polar crane which is used to lift and relocate components to provide access to the reactor fuel, vessel internals, and reactor components during refueling and servicing operations; as well as other heavy lift cranes located throughout the plant, including: the spent fuel shipping cask crane, the equipment hatch hoist, the maintenance hatch hoist, and the main steam isolation valve hoists.

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14. Initial Test Program i

Prerequisites The construction testing of the heavy lift cranes has been successfully completed. Required support systems, electrical power supplies and control circuits are operational. The heavy load analysis has been completed defining the load paths.

General Test Method and Acceptance Criteria Heavy load crane performance is observed and recorded during a series of individual component and integrated system testing. The following testing verifies that the crane systems function as described in subsection 9.1.5 and in appropriate design specifications:

a) . Proper operation and assembly of the various cables, grapples, and hoists including brakes, limit switches, load cells, and other equipment protective devices is verified.

b) Proper operation of control, instrumentation, interlocks, and alarms is verified.

c) Dynamic and static load testing of cranes and hoists, and associated lifting and rigging equipment is performed; including a static load test at 125% of rated load and full operational test at 100% of rated load. .

14.2.9.4.15 Seismic Monitoring System Testing Purpose The pugose of the seismic monitoring system testing is to verify that the as-installed components properly perform the functions described in Section 3.7, to verify proper operation in response to a seismic event.

Prerequisites ne construction testing of the seismic monitoring system has been successfully completed.

Required support systems, electrical power supplies and control circuits are operational. He system recording devices have sufficient recording. medium available.

General Test Method and Acceptance Criteria Seismic monitoring system instrumentation performance is observed and recorded during a series of individual component and integrated system testing. The following testing verifies that the system functions as described in Section 3.7 and appropriate design specifications:

a) Proper calibration and response of seismic instrumentation is verified, including verification of alarm and initiation setpoints.

b) Proper operation of internal calibration and test features is verified.

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14. Initial Test Program c) Proper integrated system response, including actuations, alarms, and annunciations is l verified. 1 14.2.9.4.16 Special Monitoring System Testing l l

Purpose  :

i l

The purpose of the special monitoring system testing is to verify that the as-installed components properly perform the following nonsafety-related functions, described in subsection 4.4.6:

  • Detect the presence of metallic debris in the reactor coolant system i Obtain baseline data for metal impact monitoring prior to power operations i l

Prerequisites 1

i Construction and installation testing of the special monitoring system has been successfully l completed to the extent necessary to support preoperational testing. Related system interfaces is available or simulated as necessary to support the specified test configurations.

Component testing and instrument calibrations have been completed. Programming has been completed and initial system diagnostics tests have been determined acceptable.*

Required electrical power supplies are energized and operational.

General Test Methods and Acceptance Criteria l

Performance of the special monitoring system is observed and recorded during a series of individual componcnt and integrated tests designed to verify system operation in response to specified input conditions. The following testing demonstrates that the system operates i as specified in subsection 4.4.6 and the applicable design specifications:

a) Proper calibration and response of digital metal impact monitoring instrumentation is verified.

b) Proper operation of the digital metal impact monitoring system is verified by evaluating system response to simulated input signals representing the anticipated signal range.

c) Baseline response data is obtained for the metal impact monitoring system to serve as a reference for monitoring degradation of sensor response.

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14. Initial Test Program 14.2.9.4.17 Secondary Sampling System Testing Purpose The purpose of the secondary sampling system testing is to verify that the as installed components properly perform the following nonsafety-related functions described in subsection 9.3.4:
  • Provide the capability to continuously monitor selected secondary water and steam process streams in order to establish e.nd maintam proper water chemistry during plant operation.
  • Provide the capability to manually analyze additional secondary water and steam process streams.

Prerequisites Construction testing of the secondary sampling system has been successfully completed.

Cooling water is being provided to the sample coolers when samples are taken from sample ,

points with fluid temperatures exceeding 125 F. The systems / components to be sampled are filled and operating at their normal pressure and temperature. Electrical power ist available for operation of the on-line chemistry analyzers. l l

4 General Test Method and Acceptance Criteria The performance of the secondary sampling system is observed and recorded during a series l of individual component tests and testing in conjunction with the plant in operation at )

normal pressure and temperature. The following testing verifies that the secondary sampling system operates as specified in subsection 9.3.4 and appropriate design specifications.

a) Prooer calibration and operation of on-line continuous analyzers, data collection and dispby, controls, and actuation signals to the turbine island chemical feed system is verified.

1 b) Proper calibration and operation of the portable analyzer is verified.

c) The proper operation of the sampie coolers is verified.

d) The capability to obtain grab samples from the sample points is verified. ,

14.2.10 Startup Test Procedures Those tests comprising the startup test phase are discussed in this subsection. For each test a general description is provided for test objective, test prerequisites, test description, and test performance criteria, where applicable. In describing a test, the operating and safety--

oriented characteristics of the plant to be tested and evaluated are identified.

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14. Initial Test Program Where applicable, the relevant performance criteria for the test are discussed. Some of the criteria relate to the value of process variables assigned in the design or analysis of the plant, component systems, and associated equipment. Other criteria may be associated with expectations relating to the performance of systems.

The specifics of the startup tests relating to test methodology, plant prerequisites, initial conditions, performance criteria, and analysis techniques are developed by the COL applicant / holder in the form of plant, system and component performance and testing specifications.

14.2.10.1 Initial Fuel Loading and Precritical Tests Tests to be performed after preoperational testing is complete but prior to initial criticality are described in this section. These tests include those performed prior to core load to verify the plant is ready for core loading, the loading of the core and the tests performed under hot conditions after the core has been loaded but prior to initial criticality.

Tests to be performed prior to and during initial core loading are described in ,

subsections 14.2.10.1.1 through 14.2.10.1.5. These tests verify the systems necessary to monitor the fuel loading process are operational and that the core loading is conducted properly.

After core load, tests are performed at hot conditions to bring the plant to a final state of readiness prior to initial criticality and to perform low power testing.

14.2.10.1.1 Fuel Loading Prerequisites and Periodic Checkoff Objectives

  • Specify the prerequisites for initial fuel loading, including the status of required i systems, plant conditions, and special equipment.
  • Provide a checklist for periodic verification that the conditions required for ; iel loading )

are being maintained.  ;

i Prerequisites I

= Plant systems required for initial fuel loading have been satisfactorily tested and turned over to the plant operating staff, and are in the status specified.

  • Plant conditions required for initial core loading are as specified.

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  • Special equipment required for initial fuel loading is available and operable.

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14. Initial Test Program i

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Test Method  ;

  • Prior to the beginning of fuel loading, verify and document the required status of test I prerequisites.  ;
  • Throughout fuel loading, verify through periodic checks that conditions required for safe fuel loading are being maintained.

Performance Criterion The required status of prerequisites for initial fuel loading is verified and documented prior to fuel loading and maintained throughout the loading process.

14.2.10.1.2 Reactor Systems Sampling for Fuel Loading Objective

= Verify that the dissolved boron concentration in the reactor coolant system and directly connected ponions of associated auxiliary systems is uniform and equals or exceeds the value required by the plant technical specifications for fuel loading. ,

Prerequisites

  • Plant technical specifications for fuel loading are complete and verified.
  • Boric acid storage tanks, transfer pumps, and associated piping and equipment are filled and operable.
  • The reactor vessel is filled with borated water to a level approximately equal to the centerline of the outlet nozzles.

= The water in the reactor vessel and reactor coolant system piping, including all directly connected auxiliary systems, is borated to a value that equals or exceeds the value specified in the plant technical specifications for fuel loading. That water is circulating through the normal residual heat removal system at a rate that provides reasonable assurance of a uniform concentration.

Test Method

. Obtain and analyze samples from at least one representative point in each system auxiliary and at four equidistant depths in the reactor vessel for boron concentration.

  • Periodically repeat sampling until the performance criteria are met.

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14. Initial Test Program Performance Criteria l
  • The minimum boron concentration of all samples equals or exceeds the value specified  !

in the plant technical specifications for fuel loading. l

. The boron concentrations of the samples obtained in the reactor vessel and operating l 1

residual heat removal loop are within 30 ppm of each other.

14.2.10.1.3 Fuel Loading Instrumentation and Neutron Source Requirements 1

Objectives i l

l

. Verify alignment, calibration, and neutron response of the temporary core loading l instrumentation prior to the start of fuel loading.

~

. Verify the neutron response of the nuclear instmmentation system source range channels prior to the start of fuel loading.

  • Verify the neutron response of the temporary and nuclear instmmentation system source range instrumentation prior to resumption of fuel loading following any delay

~

of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or more.

i Prerequisites

= The following special equipment is available: )

The temporary core loading package consisting of three complete counting l channels, including preshipment alignment and calibration data. l A portable neutron source with sufficient strength to verify detector response.

  • Preoperational testing of the nuclear instrumentation system source range channels is completed.

Test Method

. Prior to the start of fuel loading, verify the response of temporary and nuclear instrumentation system source range channels to neutrons by using a portable neutron source.

  • Verify proper alignment and calibration of the temporary channels by comparing the neutron response data to the data obtained during preshipment testing.
  • Prior to resumption of fuel loading following a delay of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or more, verify proper operation of the temporary and nuclear instrumentation system source range channels by performing a neutron response check (using the portable neutron source or by a wamv9 Wold R09-071596 Revision: 9 14-81 Draft July 31,1996

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14. Initial Test Program mcving a fuel assembly containing a primary neutron source) or by statistical analysis of the count rate data.

Performance Crit'erion Equipment used for neutron monitoring during fuel loading is operating correctly and is responsive to changes in neutron flux levels.

14.2.10.1.4 Inverse Count Rate Ratio Monitoring for Fuel Loading Objective Verify the neutron monitoring data obtained during initial fuel loading is consistent with calculations showing the predicted response and, for plants subsequent to the first plant, with data obtained during a previous similar fuel loading.

Prerequisites

  • Temporary and plant source range nuclear instmmentation has been operational for a minimum of 60 minutes to allow the equipment to attain stable operating conditions.
  • The plant is prepared for initial fuel loading.
  • Neutron monitoring data from a previous similar initial fuel loading or calculations showine the predicted response of monitoring channels are available for evalu'ating monitosing data.

Test Method 4

  • Prior to inserting the first fuel assembly into the reactor vessel, obtain background count rates for each temporary and plant source range channel.

l

. During the insertion of each fuel assembly, continuously observe the response of at least one channel for unexpected changes in count rate.

  • Construct a plot of inverse count rate ratio versus fuel loading step number from monitoring data obtained after each fuel assembly is loaded and is used to assess the safety with which fuel loading can continue.

Performance Criteria

  • Monitoring data are consistent with calculations showing the predicted response and, for plants subsequent to the first plant, with data obtained during a previous similar fuel loading.

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14. Initial Test Program 14.2.10.1.5 Initial Fuel Loading Objectives
  • Establish the conditions under which the initial fuel loading is to be accomplished.
  • Accomplish initial fuel loading in a safe manner.

Prerequisites

  • The nuclear design of the initial reactor core specifying the final core configuration of fuel assemblies and inserts is completed.
  • Preoperational testing is completed on systems specified as required for initial fuel loading.
  • Preoperational testir:g is completed on required fuel handling tools. Tools are avail-able, operational, and calibrated, including indexing of the manipulator crane with a dummy fuel element.
  • Containment integrity is established.
  • The reactor vessel is filled with water to a level approximately equal to the center of the vessel outlet nozzles. The water is being circulated at a rate to provide uniform mixing.
  • The boron concentration in the reactor coolant equals or exceeds the concentration re-quired by the plant technical specifications for refueling.

=

Temporary and, plant source range channels are operable as required to monitor changes in core reactivity.

  • A surveillance program will verify that the conditions for fuel loading will be maintained throughout the fuel loading program.
  • Auxiliary system status is in accordance with Technical Specification requirements.

Test Method

  • Place fuel assemblies, together with inserted components (control rods, burnable poison elements, primary and secondary neutron sources), in the reactor vessel one at a time according to an established and approved sequence.
  • During and following the insertion of each fuel assembly and until the last fuel assembly has been loaded, the response of the neutron detectors is observed and a wanev9eoi4 no947is* Revision: 9 Y W85tingh0US8 14-83 Draft July 31,1996
14. Initial Test Program compared to previous fuel loading data, or calculations, to verify that the observed changes in response are as expected.
  • Check sheets are completed at prescribed intervals verifying that the conditions required for initial fuel loading are being maintained.

Performance Criterion All fuel assemblies have been loaded into the vessel in the correct location and orientation consistent with the prespecified configuration for the initial reactor core. All fuel loading steps are documented, including the final core configuration.

14.2.10.1.6 Post Fuel Loading Precritical Test Sequence Objective Specify the sequence of events constituting the precritical test program.

Prerequisite Plant system conditions are established as required by the individual test instructions within*

the precritical test sequence as described in subsections 14.2.10,1.7 through 14.2.10.1.23.

Test Method The instructions establish the sequence for required testing after core loading, until the plant has completed precritical testing.

Performance Criteria Performance criteria are contained in the various individual tests conducted during this time (subsections 14.2.10.1.7 through 14.2.10.1.23).

14.2.10.1.7- Incore Instrumentation System Precritical Verification Objectives

  • Verify that the incore instrumentation thimbles have been installed correctly following initial fuel loading.
  • Verify proper operation of the incore thermocouples prior to plant heatu'p.

Prerequisites

. Initial fuel loading is completed, all incore instrumentation thimble assemblies are installed, and all mechanical and electrical connections are completed.

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14. Initial Test Program The plant is at ambient temperature and pressure prior to heatup for initial criticality.

Incore instrumentation system signal processing software is installed and operational.

Test Method With the plant at ambient conditions following initial fuel loading and prior to heatup for initial criticality, mrie electrical continuity checks at the incore instrumentation system panel to verify proper installation and connection of the incore sensor strings.

Obtain incore thermocouple data and compare with the measured reactor coolant system temperature to verify proper operation of the incore thermocouples and signal processirg.

Performance Criteria

  • Prior to plant heatup, proper connecticas to the incore instrumentation thimbles are

. verified and outputs from the incore thermocouple system are consistent with existing plant conditions.

~

  • Data required for calibration of other plant instrumentation are obtained.

14.2.10.1.8 Resistance Temperature Detectors Incore Thermocouple Cross Calibration i 1

Objectives i

a Verify calibration coefficients for the resistance temperature detectors installed in the reactor coolant system. ,

l

  • Determine calibration coefficients for resistance temperature detectors replaced in the reactor coolant system following hot functional testing as required.
  • Determine calibration coefficients for the incore thermocouples that are pan of the  ;

incore instrumentation system.

Prerequisites

  • . Initial fuel loading is completed and the reactor coolant system is filled and vented prior to heatup for initial criticality.
  • Reactor coolant system resistance temperature detectors that were replaced as a result of pre-operational testing are operational, and an initial alignment has been completed in according to the manufacturer's calibration data.
  • The incore instrumentation system, including signal processing software, is installed I and operational, and the preoperational testing is completed.

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14. Initial Test Program

. Instrumentation and data collection equipment is operational and available for logging plant data.

Test Method

= With the reactor coolant system at ambient temperature, and under isothermal conditions at specified temperature plateaus during heatup to normal operating temperature, measure the resistance of each resistance temperature detector installed in the reactor coolant system and the output from each installed incore thermocouple, along with supplemental plant data.

= Using the calibration coefficients determined during hot functional testing and the manufacturer's resistance versus temperature calibration data for the replaced resistance temperature detectors, determine the best-estimate temperature of each temperature plateau from the average of the derived resistance temperature detectors temperatures.

= On an iterative basis, recompute the best-estimate plateau temperature after removing from the average calculation the data from resistance temperature detectors whose temperature differs from the average by a predetermined amount.

= Verify or recompute calibration coefficients for each resistance temperature detector,'

as required, based on the final plateau average temperatures.

. Compute calibration coefficients for each incore thermocouple based on the final plateau average temperatures and supplemental data obtained during heatup.

Performance Criteria

= For each resistance temperature detector, the adegaacy of the final calibration coefficients is verified when the temperature derived from the resistance temperature detector resistance agrees with the plateau average temperatures within predetermined limits.

. For each incore thermocouple, the adequacy.of the final calibration coefficients is verified when the temperature derived from the thermocouple output agrees with the plateau average temperatures within predetermined limits.

14.2.10.1.9 Nuclear Instrumentation System Precritical Verification Objective Establish and determine voltage settings, trip settings, operational settings, alarm settings, and overlap of channels on source range instrumentation prior to initial criticality.

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14. Initial Test Program Prerequisite The nuclear instrumentation system is aligned according to the design requirements.

Test Method

. Calibrate, test, and verify functions using permanently installed controls and adjustment mechanisms.

= Set operational modes of the source range channels for their proper functions, in accordance with the test instructions.

Performance Criteria

. The nuclear instmmentation system demonstrates the ability to achieve the operational adjustments in accordance with the design basis functional requirements.

14.2.10.1.10 Setpoint Precritical Verification i Objectives ,

  • Prior to initial criticality, verify that initial values of instrumentation setpoints assumed in the design, operation, and safety analysis of the nuclear steam supply system have been in:talled correctly, and identify which of these are expected to be readjusted '

based on the results of startup testing and initial operations.

= Prior to initial criticality, to document final values of instrumentation setpoints assumed in the design, operation, and safety analysis of the plant and as modified by initial startup testing, operations, or reanalysis to serve as a basis for future plant operations.

Prerequisites f

= Initial alignment and calibration of plant instrumentation has been completed, and initial set points are installed per applicable design documentation.

  • Preoperational and startup testing of affected plant instrumentation has been completed,  ;

and test results are documented.

Test Method j i

  • Review applicable design .>cumentation and generate a list of the instrumentation l setpoints assumed in the design, operation, and safety analysis of the plant. Identify j setpoints expected to be modified based on the results of initial startup tests and operations.

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14. Initial Test Program l
  • Prior to initial criticality, the results of preoperational and startup tests, as applicable, are reviewed to verify that. initial setpoints have been installed correctly. Document the results of this review for future use.

= Prior to initial criticality, summarize and document the setpoint values for future plant operations.

Performance Criteria

= Prior to initial criticality, installed setpoint values are verified to be consistent with design documentation.

14.2.10.1.11 Rod Control System j Objective i Demonstrate and document that the rod control system performs the required control and indication functions just prior to initial criticality.

1 Prerequisites i

  • The nuclear instrumentation system source range channels are aligned and operable.  !

l Test Method  ;

  • With the reactor at no-load temperature and pressure, just prior to initial criticality, I verify the operation of the rod control system in various modes. I l

- Verify the operation of status lights, alarms, and indicators.

Performance Criteria 1

  • The rod control system withdraws and inserts each rod bank. )

1

= The rod position and indication system tracks each rod bank as it is being moved. l

= ' Die control banks overlap system starts and stops rod movement at the designated bank positions.

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14. Initial Test Program 14.2.10.1.12 Rod Position Indication System l

Objective i Verify that the rod position indication system satisfactorily performs required indication and ,

alarm functions for each individual rod and that each rod operates satisfactorily over its l entire range of travel. i I

Prerequisites j

= The reactor coolant system is at no-load operating temperature and pressure.

1 Test Method Individually withdraw rod banks from the core and reinsert them, according to the test procedure. Record rod position sensor output voltages, and rott position readouts and group

  • step counters in the Main Control Room.

Performance Criterion i

)

The rod position indication system performs the required indication and alarm functions, and I each rod operates over its entire range of travel. l 14.2.10.1.13 Control Rod Drive Mechanisms Objectives

  • Demonstrate operation of each control rod drive mechanism under both cold and hot standby conditions.
  • Provide verification of slave cycler timing.

Prerequisites

  • Rods are fully insened.
  • Nuclear instmmentation channels are available.
  • A fast-speed oscillograph or equivalent to monitor test parameters is available.

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14. Initial Test Program I

Test Method

. With the reactor core installed and the reactor in the cold shutdown condition, confirm that the slave cycler devices supply operating signals to the control rod drive mechanism stepping magnet coils. i 1

. Verify operation of all control rod drive mechanisms under both cold and hot standby conditions. Record the control rod drive mechanism magnet coil currents. j Performance Criterion i The control rod drive mechanisms conform to the requirements for proper mechanism operation and timing as described by the technical requirements.

14.2.10.1.14 Rod Drop Time Measurement l

Objectives I

- Determine the rod drop time of each rod cluster control assembly under cold no-flow and hot full-flow conditions, with the reactor at normal operating temperature and, )

pressure.

. Verify the operability of the control rod deceleration device.

Prerequisites l

= Initial core loading is completed.

  • Source range channels are in operation.
  • Rods are fully inserted.

Test Method

. Withdraw each rod cluster control assembly.

  • Interrupt the electrical power to the associated control rod drive mechanism.
  • Measure and record the rod drop time, and verify control rod deceleration.
  • Perform a minimum of three additional drops for each control rod whose drop time falls outside the two-sigma limit, as determined from the drop times obtained for each test condition.

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14. Initial Test Program Performance Criteria

. Measured rod drop times are consistent with the design basis functional requirements and the applicable plant technical specifications.

  • The control rod is slowed by the control rod deceleration device during rod drop testing. 1 14.2.10.1.15 Rapid Power Reduction System i

Ob,lective l

Verify proper operation of the rapid power reduction system prior to power operations.  !

Prerequisites .

- The following systems are operable to the extent necessary to suppon the test: rod control system, rod position indication system, reactor trip breakers, and reactor  ;

protection system. j l

  • The reactor is shut down, the reactor coolant system boron concentration is such that i technical specifications' requirements for shutdown margin will be met with required l rod withdrawal, and all control banks are near their fully inserted positions. l Test Method

. Input signals simulating operation at the full power condition to the reactor control and protection system. Close the reactor trip breakers.

  • Input signals simulating a rapid loss of load exceeding 50 percent power are input to j the rapid power reduction system. Verify the response of the system. 1 1
  • Demonstrate procedures for returning the plant to power following a partial trip.

Performance Criteria

. In response to the simulated loss of load, gripper power is interrupted to a preselected j grouping of control rods so that rods drop freely into the core.  ;

l

  • Gripper power to only those control rods selected for drop is interrupted. l I
  • Procedures for retuming the plant to power operations without a reactor trip are verified.

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14. Initial Test Program 14.2.10.1.16 Process Instrumentation Alignment Objective Align AT and Tavg Process instrumentation under isothermal conditions prior to initial criticality.

Prerequisites

Test Method

  • Align AT and T,,, according to test instmetions at isothermal conditions prior to criticality.

Performance CrPerion ,

The indicated values for reactor coolant system Tw, T , T.,,, and AT under isothermal conditions are within the limits of the applicable design requirements.

14.2.10.1.17 Reactor Coolant System Flow Measurement ,

Objectives

  • Prior to initial criticality, verify that the reactor coolant system flow rate is sufficient to permit operation at power.

Prerequisites

  • The core is insta!'ed and the plant is at normal operating temperature and pressure.
  • Special instrumentation is installed and calibrated for obtaining reactor coolant flow velocity head data.

Test Method

  • Prior to initial criticality, measure the reactor coolant flow velocity head with all four coolant pumps in operation. Estimate the reactor coolant flow rate using these data.

l i

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14. Initial Test Program Performance Criteria

. The estimated reactor coolant flow rate from data taken prior to initial criticality equals or exceeds 90 percent of the minimum value required by the plant technical specifications for full power operation.

14.2.10.1.18 Reactor Coolant System Flow Coastdown Objectives

. Measure the rate at which reactor coolant loop flow and pump r, peed changes, subsequent to tripping all reactor coolant pumps.

= Measure the rate at which reactor coolant loop flow and pump speed changes, subsequent to tripping two of four reactor coolant pumps.

Prerequisites

- Required component testing and instrument calibration are complete.

  • Required electrical power supplies and control circuits are operational.
  • The reactor core is installed, and the plant is at normal operating temperature and pressure with all reactor coolant pumps running.

Test Method

  • Record loop flow, pump speeds following the trip of all reactor coolant pumps.
  • Record loop flows, pump speeds following the trip of two of four reactor coolant pumps. .

Performance Criteria

- The loop flows and pump speed data are obtained for verification of the loss of flow analyses in subsections 15.3.1 and 15.3.2.

14.2.10.1.19 Pressurizer Spray Capability and Continuous Spray Flow Verification Objectives

  • Establish the optimum continuous spray flow rate.
  • Determine the effectiveness of the normal control spray.

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14. Initial Test Program Prerequisites

= All reactor coolant pumps are operating. .

1 1

Test Method I l

  • While maintaining constant pressurizer level, adjust spray bypass valves until a j minimum flow is achieved that maintains the temperature difference between the spray I line and the pressurizer within acceptable limits. l 1
  • With the pressurizer heaters de-energized, fully open both spray valves, and record the time to lower the pressurizer pressure a specified amount.

I Performance Criteria {

1

  • The spray bypass valves are throttled so that the minimum flow necessary to keep the spray line warm is achieved. .
  • The pressurizer pressure res;,onse to the opening of the pressurizer spray valves is
  • within design basis functional limits.

14.2.10.1.20 Feedwater Valve Stroke Test i

i Objective ,

1 Verify proper operation of the main and startup feedwater control valves prior to the start of power operations.

Prerequisites

  • Preoperational testing of the feedwater control systems is completed.
  • Initial fuel loading is completed prior to initial criticality.

Test Method For each main and startup feedwater flow control valve, the following tests are performed:

  • Using simulated signals for several valve demand positions covering the range from fully closed to fully open, verify the actual valve position to be consistent with the demand signal.

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- For selected valve position changes, measure the time required from the initiation of the demand signal until the valve reaches the final position. Typical demands changes are the following: fully closed to fully open, fully open to fully closed,25 percent open to 75 percent open, and 75 percent open to 25 percent open.

Performance Criteria

. The differences between the measured actual and demand valve positions, over the range of travel, are less than prespecified tolerances.

. The time between the initiation of the demand signal and the final valve position for each of the demand changes is within prespecified ranges. l

= For demand changes to intermediate valve positions, the amount of overshoot is less than prespecified limits. I 14.2.10.2 Initial Criticality Tests Initial criticality testing is described in this section. Following completion of the core loading and precriticality testing, the plant is brought to initial criticality according to the, test procedures in subsection 14.2.10.2.1.

14.2.10.2.1 Initial Criticality and Low Power Test Sequence Objective Define the sequence of tests and operations, to bring the core to initial criticality.

Prerequisite l i

Plant system conditions are established as required by the individual test instructions within i this sequence.

Test Method Individual test instruction will establish the plant conditions required for initial criticality.

Performance Criteria Relevant performance criteria are provided in each of the test procedure abstracts.

14.2.10.2.2 Initial Criticality Objective Achieve initial criticality in a controlled manner.

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14. Initial Test Program  !

m- l Prerequisites

  • Control rod banks are inserted, and shutdown rod banks are withdrawn.
  • The reactor coolant system boron concentration is sufficiently high so the reactor is shut down by at least 1000 pcm with all banks withdrawn.

1 Test Method

  • . Accomplish initial criticality by the controlled withdrawal of the rods, followed by the dilution of the reactor coolant system boron concentration.
  • At preselected points during rod withdrawal and/or boron dilution, gather data to plot the inverse count rate ratio to monitor the approach to critical evolution for reactivity monitoring.
  • As criticality is approached, slow or stop the dilution rate to allaw criticality to occur, during the mixing or by rod withdrawal.

Performance Criterion The reactor is critical.

1 14.2.10.2.3 Nuclear Instrumentation System Verification During Criticality I Objective Establish and determine voltage settings, trip settings, operational settings, alarm settings, and overlap of channels on source and intermediate range instrumentation from prior to initial criticality and during initial criticality.

Prerequisite The nuclear instrumentation system is aligned according to the design requirements.

Test Method

  • Calibrate, test, and verify functions using permanently installed controls and adjustment mechanisms.
  • Set operational modes of the source and intermediate range channels for their proper functions, in accordance with the test instructions.

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14. Initial Test Program u-I l

Performance Criteria l

  • The nuclear instrumentation system demonstrates the ability to achieve the operational j adjustments in accordance with the design basis functional requirements.
  • The nuclear instrumentation system demonstrates an overlap of indication between the l source and intermediate range instrumentation.

i 14.2.10.2.4 Post Critical Reactivity Computer Checkout Objective l

Demonstrate proper operation of the reactivity computer through a dynamic test using i neutron flux signals. l Prerequisites J

l

  • The reactor is critical with the neutron flux level within the range for low-power physics testing. I
  • The reactivity computer is installed, checked out, and operational, and input flux signals are representative of the core average neutron flux level.
  • 'Ihe controlling rod bank is positioned in such a way that the required reactivity insertion can be made by rod motion alone.

Test Method

  • By control rod motion, add positive reactivity to the core.
  • During the resultant increase in flux level, make two independent measurements of core reactivity: one using the reactivity computer, and one using an analysis of the rate of change of flux level (for example, reactor period or doubling time).

Performance Criterion Each measurement deviation between the two independent sources of reactivity is within design tolerances.

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14. Initial Test Program 14.2.10.3 Low Power Tests Following successful completion of the initial criticality tests, low power tests are conducted, typically at power levels less than 5%, to measure physics characteristics of the reactor system and to verify the operability of the plant systems at low power levels.

14.2.10.3.1 Low-Power Test Sequence Objective Define the sequence of tests and operations that constitutes the low-power testing program.

Prerequisite Plant system conditions are established as required by the individual test instructions within this sequence.

Test Method Individual test instmetion will establish the plant conditions required for and during the low-power testing program following initial criticality.

  • Performance Criteria  ;

Relevant performance criteria are provided in each of the test procedure abstracts.

14.2.10.3.2 Determination of Physics Testing Range Objectives a Determine the re. actor power level at which the effects from fuel heating are detectable.

- Establish the range of neutron flux in which zero power reactivity measurements are to be performed.

Prerequisites

  • The reactor is critical, and the neutron flux level is below the expected level of nuclear heating.

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. The reactivity computer is installed, checked out, and operational, and input flux l signals are representative of the core average neutron flux level.  ;

1

  • The controlling rod bank is positioned in such a way that the required reactivity insenion can be made by rod motion alone.

Test Method l

= Withdraw the control rod bank and allow the neutron flux level to increase until nuclear heating effects are indicated by the reactivity computer.

' Record the reactivity flux level and the corresponding intermediate range channel currents at which nuclear heating occurs. l 1

  • Multiply the measured reactivity flux level by 0.3 to determine the maximum value for l the zero power testing range. l Performance Criterion .

The zero power testing range is determined.

  • i 14.2.10.3.3 Boron Endpoint Determination 1

Objective 1

I Determine the critical reactor coolant system boron concentration appropriate to an endpoint ,

rod configuration. )

l Prerequisites  ;

= The reactor is critical, and the neutron flux level is within the range for low power physics testing.

l l

- The neutron flux level and reactor coolant system boron concentration are stable.

I

~

  • Instmmentation and equipment used to measure and compute reactivity is installed, checked out, and operational, with input flux signals representative of the core average neutron flux level.

- The controlling rod bank is positioned in such a way that limited reactivity insenion will be required to achieve the endpoint condition.

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14. Initial Test Program Test Method

- Move the rods to the desired endpoint configuration without boron concentration adjustment.

  • Directly measure the just-critical boron concentration by chemical analysis.

. Measure and convert the change in reactivity and the reactor coolant temperature difference from program to an equivalent change in boron concentration.

  • Add the changes to the just-critical boron concentration to yield the endpoint for the given rod configuration.

Performance Criterion The measured value for the boron endpoint is consistent with the design value within design limits.

14.2.10.3.4 Isothermal Temperature Coefficient Measurement Objectives

  • Measure the isothermal temperature coefficient.

Prerequisites

  • The reactor is critical, and the neutron flux level is within the range for low-power physics testing.
  • The reactor coclant system temperature and pressure are stable at the normal no-load values.
  • Instrumentation and equipment used to measure and compute reactivity is installed, checked out, and operational, with input flux signals representative of the core average neutron flux level.

= The controlling rod bank is positioned near fully withdrawn or near fully inserted.

Test Method

= Vary reactor coolant system temperature (heatup/cooldown) while maintaining rods and boron concentration constant.

  • Monitor reactivity results and determine the isothermal temperature coefficient.

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14. Initial Test Program Performance Criteria

. The measured value for the isothermal temperature coefficient is more negative than the technical specification limit.

14.2.10.3.5 Bank Worth Measurement Objective Validate design calculations of the reactivity wonh of the rod cluster control banks.

1 Prerequisites

= The reactor is critical and the neutron flux level is within the range for low-power physics testing. ,

  • 1r.strumentation and equipment used to measure and compute reactivity is installed and operational, with input flux signals representative of the core average neutron flux level.

i Test Method )

= One of the following methods will be used to measure the wonh of all of the individual control rod banks:

l

- A bank is stepwise inserted into the core from fully withdrawn and the wonh is measured using the reactivity computer.

- Er. change bank with another bank measured as above, with the wonh determined from the critical positions and the wonh of the reference bank.

Performance Criteria

  • 'Ihe measured value for the individual bank wonh is consistent with the design value within prespecified limits.
  • The sum of the measured bank wonh is consistent with the design value within the assumed uncertainty used in the shutdown margin calculation.

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14. Initial Test Program 14.2.10.3.6 Natural Circulation (First Plant Only)

Objective Demonstrate that core decay heat can be removed by the steam generators under the conditions of natural circulation (no reactor coolant pumps operating).

Prerequisites 1

  • The reactor is critical, and the neutron flux level is within the range for low-power I physics testing.
  • The neutron flux level and reactor coolant system boron concentration and temperature are stable, and the controlling rod bank is positioned in such a way that an increase in l l

core power level to approximately 3 percent can be achieved by rod motion alone.

i

  • The reactivity computer is installed, checked out, and operational, with input flux signals representative of the core average neutron flux level.

~.

  • Instrumentation and data collection equipment is operational and available for logging plant data.
  • Special instrumentation is available to measure vessel AT with high precision at low-power levels.

Test Method

  • Because this test is performed at beginning of life when the core fission product density is low, decay heat is simulated by reactor power.
  • By control rod motion, increase reactor power to approximately 3 percent of full power based on predictions of vessel AT at full power.
  • With reactor coolant pumps running, obtain data for correlating nuclear flux level and loop temperatures with power.
  • Trip all reactor coolant pumps. Maintain core power at approximately 3 percent by control rod motion while cold leg temperatures remain relatively constant.
  • Verify natural circulation by observing the response of the hot leg temperature in each loop. The plant is stable under natural circulation at this power level when hot leg temperature is constant.
  • Obtain data characterizing the plant under natural circulation conditions.

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. Restart reactor coolant pumps only after the reactor is shut down and isothermal conditions are re-established.

Performance Criterion The measured average vessel AT under natural circulation conditions is equal to or less than limiting design predictions for the measured reactor power level.

14.2.10.4 Power Ascension Tests After low power testing is completed, testing is performed at specified elevated power levels to demonstrate the facility operates in accordance with design during normal steady-state operations, and to the extent practical, during and following anticipated transients. During power ascension, tests are performed to obtain operational data and to demonstrate the operational capabilities of the plant.

14.2.10.4.1 Test Sequence -

Objective Define the sequence of operations, beginning at approximately 5 percent rated thermal ~

power, that constitutes the power ascension testing program.

Prerequisite Plant system conditions are established, as required, by the individual test instruction within this sequence.

Test Method Present the sequence of operations and tests, along with detailed instructions, specific plant conditions, and test procedures.

Performance Criteria Relevant performance criteria are provided in each of the test procedures.

14.2.10.4.2 Incore Instrumentation System Objectives

- Obtain data for incore thermocouple and flux maps at various power levels during ascension to full power.

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3 14. Initial Test Program Prerequisites

= Incore instrumentation system signal processing software is installed and operational.

  • For incore thermocouple and flux mapping, the plant is at various power levels greater than approximately 20 percent of rated thermal power.

Test Method

.. With the plant at approximate power levels of 25,50,75 and 100 percent of rated thermal power, obtain data from the incore instrumentation system and process to produce incore thermocouple and flux maps. (Actual power levels will be specified in the power ascension program test sequence.)

  • Use data from the incore maps to verify that core power peaking factors and axial distribution are consistent with design predictions and the limits imposed by the plant ]

technical specifications, and to calibrate other plant instrumentation. I Performance Criteria

= Core power peaking factors derived from the incore data are consistent with design-prediuions and the limitations of the plant technical specifications.

1 1

  • Data required for calibration of other plant instrumentation are obtained.  !

14.2.10.4.3 Nuclear Instrumentation System Objective l Establish and determine voltage settings, trip settings, operational settings, alarm settings, and overlap of channels on source range, intermediate range, and power range instrumentation from zero power to at or near full rated thermal power.

Prerequisite The nuclear instrumentation system is aligned according to the design requirements.

Test Method

. Calibrate, test, and verify functions using permanently installed controls and adjustment mechanisms.

  • Set operational modes of the source range, intermediate range, and power range channels for their proper func. ions, in accordance with the test instructions.

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14. Initial Test Program Performance Criteria
  • The nuclear instrumentation system demonstrates the ability to achieve the operational adjustments in accordance with the design basis functional requirements.  !
  • The nuclear instrumentation system demonstrates an overlap of indication between the j source and intermediate ranges and the intermediate and power range instrumentation.

14.2.10.4.4 Setpoint Verification Objectives l

.During power ascension, document final values of instrumentation setpoints as j modified by initial sta; tup testing, operations, or reanalysis to serve as a basis for j future plant operations. ,

l Prerequisites j l

= Initial alignment and calibration of plant instrumentation has been completed, and )

initial set points are installed per applicable design documentation.

  • Preoperational and startup testing of affected plant instrumentation has been completed, and test results are documented.
  • The results of the precritical verification of the instrument setpoints is completed and documented.

Test Method l

  • Identify setpoints modified based on the results of initial startup tests and operations. l I
  • During power ascension testing, readjust specific setpoints noted for readjustment on  ;

the data sheets if required. Record final setpoint values. ]

Performance Criteria

  • Setpoint changes based on initial startup testing and operations are documented for future reference.

14.2.10.4.5 Startup Adjustments of Reactor Control Systems Objectives

l i

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14. Initial Test Program

. Obtain plant data during power ascension which would provide the basis for any required changes to the T,,, program.

Prerequisites The reactor coolant system is at no-load operating temperature and pressure.

The reactor coolant system temperature is being control!cd by the steam dump valves.

Test Method

. Obtain system temperature and steam pressure data at steady-state conditions for zero rated thermal power and at hold points during power escalations.

At approximately 75 percent rated thermal power, modify the T,,, program as required to achieve design steam generator pressure at full power, based on extrapolation of the data to the full power condition.

Revaluate the T,,, program as above at approximately 90 and 100 percent rated thermal power making modifications to the T.,, program as required.

Performance Criterion The reactor coolant system T,,, program is established such that steam generator pressure at the full rated thermal power condition is within design functional requirements.

14.2.10.4.6 Rod Cluster Control Assembly Out of Bank Measurements Objectives

  • Demor: strate the sensitivity of the incore and excore instrumentation system to rod cluster control assembly (RCCA) misalignments.
  • Demonstrate the design conservatism for predicted power distributions with a fully misaligned rod cluster control assembly.

= Monitor the power distribution following the recovery of a misaligned rod cluster control assembly.

Prerequisites

. The reactor is operating between 30 and 50 percent of full licensed power and has been at that power for a sufficient time to reach xenon equilibrium.

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14. Initial Test Program l
  • The control and shutdown banks are positioned as required for the specific measurement: near fully withdrawn for rod cluster control assembly insertion and at their respective insenion limits for rod cluster control assembly withdrawal.

l Test Method  ;

1

= For the rod cluster control assembly insertion, insert a group of selected rod cluster l control assemblies, one at a time, first to the limit of misalignment specified in i subsection 15.0.5, then fully inserted, and finally restored to the bank position.

Compensate for reactivity changes by dilution and boration as required. i

= For the rod cluster control assembly withdrawal, withdraw one or more selected rod I cluster control assemblies, one at a time, to the fully withdrawn position. Compensate for reactivity changes by boration and dilution as required. l l

= Record incore and excore instrumentation signals to determine their response and to determine the power distribution and power peaking factors prior to rod cluster control l assembly misalignment, at partial misalignment, at full misalignment, and periodically l after restoration to normal.

1 i

Performance Criteria .

  • Measured power distributions and power peaking factors are within technical j specification limits and are consistent with the predictions. l 1

l

  • The sensitivity of the incore and excore instrumentation to rod cluster control asse:ably l misalignment is demonstrated by examination of the power distribution and powe i peaking factors measured for each misahgnment.

14.2.10.4.7 Axial Flur. Difference Instrumentation Calibration Objectives

= Calibrate the power range nuclear instrumentation signals used as axial flux difference (delta flux) input to the reactor protection system.

  • Calibrate instrumentation used to display and monitor axial flux difference.

Prerequisites

  • The reactor is at a power level greater than 50 percent of rated thermal power.
  • The incore instrumentation system is available for obtaining incore power distribution data.

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e A preliminary calibration of the axial flax difference indication instrumentation is completed.

Test Method

  • Using control rod movement, xenon redistribution, or a combination of both, vary the axial power distribution of the core over a specified range of interest. At selected values of indicated axial flux difference, obtain reactor thermal power data along with the otitputs from the nuclear instrumentation power range channels and the incore instrumentation system. (For the first plant, a minimum of three data sets will be taken; subsequent cores may require less.)
  • Calibrate signals from the nuclear instrumentation power range channels based on .

incore power distribution and thermal power data.

l Performance Criterion l I

Axial flux difference signals, derived from the nuclear instrumentation power range ,

I detectors and input to the reactor protection system, display, and monitoring instrumentation, reflect actual incore power distribution within prespecified limits.

~

l 14.2.10.4.8 Primary and Secondary Chemistry i Objective Verify proper water quality in the reactor coolant system and secondary coolant system.

Prerequisite The plant is at the steady-state condition at approximately 0,25,50,75, and 100 percent rated thermal power.

Test Method Analyze samples to determine the chemical and radiochemical concentrations.

Performance Criterion The chemical and radiochemical control systems maintain the water chemistry within limits listed in the technical specifications.

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14. Initial Test Program l

14.2.10.4.9 Process Measurement Accuracy Verification Objectives 1 1

  • Measure the temperature variation in the reactor coolant loops resulting from non- I uniform flow effects such as streaming. l

= Measure the sensitivity of the excore detectors to variations in control bank position )

and reactor coolant loop cold leg temperature. l Prerequisites

Special temperature measuring equipment, including recording and indicating instrumentation, is installed, as required, on the reactor coolant loops hot and cold leg piping and is checked out and operational.

The reactor is at a stable power level of approximately 0,50,75 and 100 percent of rated thermal power.

  • For the excore detector measurements:

- 'Ihe reactor is at a stable power level of approximately 25,50 and 100 percent of rated thermal power.

Test Method

  • For the reactor coolant loop temperature measurements, at each power level:

Measure reactor power level, using calorimetric data.

Simultaneously, measure the hot and cold leg temperatures, using normal plant instrumentation' and any other required instrumentation.

  • For the excore detector tests, and with the reactor at constant power level:

Measure the response of the excore detectors as selected control banks are moved over prescribed ranges of travel.

Measure excore detector response as the reactor coolant cold leg temperature is j varied over a prescribed range.

- Simultaneously, for each of the preceding measurements, obtain calorimetric data to verify reactor power level.

t I

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14. Initial Test Program Performance Criteria

. Uncertainties in reactor coolant loop temperature measurements resulting from non-uniform flow effects such as streaming are consistent with allowances used in the plant i safety analyses. ]

l

= Uncertainties in excore detector response resulting from control rod motion and reactor I coolant loop cold leg temperature changes are consistent with allowances used in the l plant safety analyses. l I

14.2.10.4.10 Process Instrumentation Alignment at Power Conditions Objective 1 Align AT and Tavg Process instrumentation at power conditions. ,

Prerequisites I

= Reactor coolant pumps are operating. )

  • The reactor system is operating at the required power level. ,

Test Method  !

l Align AT and T,,, according to test instmetions at approximately 75 percent rated thermal power. Extrapolate the 75 percent data to determine AT and T,,, values for l the 100 percent plateau.

At or near 100 percent rated thermal power, check the alignment of the AT and Tavg channels for agreement with the results of the thermal power measurement.

Performance Criterion The indicated values for reactor coolant system Tw, T , T,,,, and AT at or near full I thermal power are within the limits of the applicable design requirements.

14.2.10.4.11 Reactor Coolant System Flow Measurement at Power Conditions Objectives

  • At power, verify that the reactor coolant flow equals or exceeds the minimum value j required by the plant technical specifications.  !

Prerequisites

  • The reactor is at power levels greater than 75 percent and up to and including 100 l percent of rated thermal power. ]

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= Special instrumentation required for measuring reactor thermal power and reactor cool-ant inlet and outlet temperatures is installed and calibrated.

Test Method a With the reactor at steady-state power greater than 75 percent and up to and including 100 percent of rated thermal power, measure the reactor thermal power and coolant inlet and outlet temperatures. Determine the reactor coolant flow rate using the data.

Performance Criteria

  • The reactor coolant system flow determined from the measurements at approximately 100 percent rated thermal power equals or exceeds the minimum value required by the plant technical specifications.

14.2.10.4.12 Steam Dump Control System Objective Verify automatic operation of the Tavg steam dump control system, demonstrate controller' set-point adequacy, and obtain final settings from steam pressure control of the condenser dump valves.

Prerequisites

  • The steam dump control system is aligned and calibrated to initial settings.
  • The plant is at no-load temperature and pressure.
  • The condenser vacuum is established.
  • The reactor is critical.

Test Method

. Increase reactor power to less than 10 percent rated thermal power by r;.d withdrawal and steam dump to condenser to demonstrate setpoint adequacy.

  • Increase pressure controller setpoint prior to switching to T,, control, which rapidly modulates open condenser dump valves.
  • Simulate turbine operating conditions with reactor at power, then simulate a turbine trip resulting in the rapid opening of the steam dump valves.

Performance Criteria

=

The plant trip controller respnds to maintain a stable Tavg. After steady state power is achieved, no divergent oscillaions in temperature occur.

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14. Initial Test Program The loss of load controller responds properly to maintain a specified stable Tavg-After steady-state power is achieved, no divergent oscillations in temperature occur.

I

  • The steam header pressure controller responds to maintain a stable pressure at normal ]

no-load pressure. 1 14.2.10.4.13 Steam Generator Level Control System Objective Verify the stability of the automatic steam generator level control system by introducing I simulated transients at various power levels during escalation to full power.

Prerequisites

= The reactor is critical and stable at various power levels during the power escalation test program. (Typical power levels are 30,75 and 90 percent of full rated thermal power).

= The steam generator level control system is checked and calibrated.

- Steam generator alarm setpoints are set for each generator.

Test Method

= At each power level, with the steam generator control system in manual mode, simulate level transients by changing the level setpoint. Verify the steam generator level control response when the control system is returned to automatic control.

  • Verify the variable speed features of the main feedwater pumps by manipulating controllers and t,est input signals.

Performance Criteria

. During recovery from a simulated steam generator level transient, steam generator level control response is consistent with the design for the following: overshoot or under-shoot to the new level, time required to achieve the new level, and error between the actual level and control setpoint.

  • Feedwater pump discharge pressure oscillations are less than design test limits.
  • The main feedwater control valves open and stabilize in response to various steam flow conditions.

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14. Initial Test Program 14.2.10.4.14 Radiation and Emuent Monitoring System Objectives

- For monitors that:

Will be used for establishmg conformance with the safety limits or limiting conditions for operation that will be included in the facility technical specifications or Are classified as engineered safety features or will be relied on to support operation of the engineered safety features within design limits or Are assumed to function or for which credit is taken in the accident analysis of the facility and Will be used to process, store, control, or limit the release of radioactive materials, ,

  • The objectives are:

Verify the calibration of the process and effluent radiation monitor against an acceptable standard.

I Establish baseline activity and background levels. l I

Demonstrate that process and effluent radiation monitoring systems respond correctly by performing independent laboratory or other analyses, i I

Prerequisites I

  • The plant is stable at the desired power level.

= The sampling systems for the process ar.d effluent radiation monitoring systems are ,

l operable. i Test Method

  • Perform calibrations with the use of radioactive sources to verify proper operation of the monitors and detectors.

- Collect and analyze samples with laboratory instruments, and compare the results from the process and effluent monitor to verify proper monitor operation.

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14. Initial Test Program

. Establish background levels at low power (less than 5 percent rated thermal power).

Establish background levels and baseline activity levels determined by sampling at 100 percent rated thermal power to monitor the buildup of activity.

Performance Criteria

  • Radiation monitors are calibrated against radioactive standards.
  • Baseline activities are established.
  • Laboratory analyses agree, given sensitivity and energy response, with the process and effluent radiation monitors.

14.2.10.4.15 Ventilation Capability Objective Verify that various heating, ventilation, and air conditioning systems for the containment and areas housing engineered safety features continue to maintain design temperatures.

~

Prerequisite The plant is operating at or near the desired power (0,50, and 100 percent of rated power).

Test Method

  • Record temperature readings in specified areas while operating with normal ventilation lineups.
  • Record temperature readings in specified areas while operating the designed minimum number of heating ventilation and air conditioning components consistent with existing plant conditions.

Record surface concrete temperatures adjacent to the high temperature piping penetrations and at selected locations on the concrete shielding (at 100 percent rated thermal power only).

Performance Criterion The heating, ventilation and air conditioning systems for the containment and areas housing engineered safeguards features are acceptable when the test results are consistent with the applicable design basis functional requirements.

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14. Initial Test Program 14.2.10.4.16 Biological Shield Survey Objectives
  • Document the radiation levels in accessible locations of the plant outside of the biological shield while at power.
  • Obtain baseline radiation levels for comparison with future measurements of level buildup wah operation.

Prerequisites

  • Radiation survey instmments are calibrated.
  • Background radiation levels are measured in designated , locations prior to initial criticality.
  • The plant is stable at the applicable power level.

Test nhthod .

Measure gamma and neutron radiation dose rates at designated locations at approximately 25,50,75, and 100 percent rated thermal power.

Performance Criterion Radiation levels are demonstrated to be acceptable for full-power operation and consistent with design expectations.

14.2.10.4.17 Thermal Power Measurement and Statepoint Data Collection Objective Obtain thermal power measurement and statepoint data at selected power levels during the power ascension testing program, typically at 25,50,75, and 100% of rated thermal power.

Prerequisites

  • The following equipment is installed and is checked out and operational: sensors for measuring steam generator feedwater temperature, differential pressure measuring

~

devices for determining feedwater flow to each steam generator, and pressure gauges to measure steam pressure at steam generator outlets.

  • The following control systems are in automatic: pressurizer pressure and level, and steam generator level.

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14. Initial Test Program i

1

. Instrumentation and data collection equipment is available for logging supplemental plant data.

  • Reactor power is stable at the required level.

)

Test Method

  • The required data are obtained using installed plant equipment, special test equipment, and the plant data processing equipment. These data are subsequently used to determine reactor thermal power and assess the performance of the plant.

Performance Criterion Reactor thermal power is stable at each power level and at the rated level at full power conditions.

14.2.10.4.18 Dynamic Response Objectives 1

1

= Verify during power range testing that stress analysis of essential nuclear steam supply- 1 system and balance-of-plant components under transient conditions is within design j functional requirements.

. To test modifications made since hot functional testing (See subsection 14.2.8.f.67) i

- To test systems not tested during hot functional testing (For example, main feedwater) l Prerequisites a Temporary instrumentation is installed, as required, to monitor the deflections of components under test.

  • Points are monitored and baseline data are established.

Test Method Record deflection measurements during various plant transients.

Performance Criteria

. The movements due to flow-induced loads do not exceed the stress analysis of the j monitored points. ,

l 1

  • Flow-induced movements and loads do not cause malfunctions of plant equipment or instrumentation. l l

Revision: 9 owmv9eoinomis*

Draft July 31,1996 14-116 3 W96tingh00S8

I m

14. Initial Test Program 14.2.10.4.19 Reactor Power Control System Objective Demonstrate the capability of the reactor power control system to respond to input signals.

Prerequisites

=

The reactor is at equilibrium at the power level specified by the startup test program reference document.

= Setpoints and controls for the pressurizer, steam generator steam dump, and feedwater pump are checked and are set to proper values.

Test Method i l

Vary T ,, from the T,,, setpoint to verify the transient recovery capabilities of the automatic l reactor power control system.

Performance Criterion T,,, returns to the T,,, setpoint, within pre-specified limits, without manual intervention.

14.2.10.4.20 Load Swing Test Objective l

Verify nuclear plant transient response, including automatic control system performance, when 10 percent step-load changes are introduced to the turbine-generator at 30,75, and i 100 percent rated thermal power levels.

4 .

Prerequisite The plant is operating is a steady-state condition at the desired thermal power level.

Test Method Change the turbine-generator output as rapidly as possible to achieve a step 10 percent load increase or decrease. Monitor and record plant parameters of reactor pwer, reactor coolant system temperature, pressurizer pressure and level and steam gencelor pressure and level during the load transients.

Performance Criterion The primary and secondary control systems, with no manual intervention, maintain reactor power, reactor coolant system temperature, pressurizer pressure and level, and steam o wmvvooi4 no9eris* Revision: 9

[ W95tingh00S8 14-117 Draft July 31,1996

14. Initial Test Program generator levels and pressures within acceptable ranges during steady-state and transient operation. Control system response is reviewed and adjustments to the control systems are made, if necessary, prior to proceeding to the next power plateau. .

l 14.2.10.4.21 100 Percent Load Rejection (First Plant Only)

Ob,lective Demonstrate the ability of the AP600 plant to accept a 100 percent load rejection from full power. i

! I

! Prerequisites

. The plant is operating at a stable power level of approximately 100 percent rated l thermal power. Reactor and turbine control systems are in the automatic mode of l operation. Plant temperatures, pressures, levels, and flow rates are within their normal l range for full-power operation. l

, 1 l

- Startup testing of the reactor and turbine control and protection systems is completed, and final setpoints are installed according to applicable plant technical manuals. ,

)

. The incore instrumentation system, including signal processing software, is operational, and all preoperational and startup testing is completed. i l

  • Instrumentation and data collection equipment is operational and available for logging l plant data. j

. Special test instrumentation is installed and operational as required to augment normal data logging ability.

Test Method

. With the plant at nominal full-power steady-state conditions, to effect a rejection of 100 percent load, manually place the main step-up transformer high side breaker in the trip position.

. Prior to the load rejection, and until the plant stabilizes at the lower power level, record key plant parameters using the plant computer and special test instrumentation.

The key plant parameters include plant temperatures, pressures, levels and flow rates for the primary and secondary systems.

Performance Criteria

= The plant is capable of accepting a 100 percent load rejection from full rated thermal power without reactor trip or operation of the steam generator relief valves or pressurizer safety valves.

Revision: 9 o wrrev9eoi4 aooo7:596 Draft July 31,1996 14-118 3 W8Stingt100S8

\

14. Initial Test Program I
  • The turbine is capable of continued stable operation at the minimum house loads. l l

14.2.10.4.22 Load Follow Demonstration (First Plant Only) 4 Objective

  • Demonstrate the ability of the AP600 plant to follow a design basis daily load follow cycle.

. *- Demonstrate the ability of the plant to respond to grid frequency changes while in the load follow cycle.

Prerequisites
  • The plant is operating at a stable power level of approximately 100 percent power and has been at that power for a sufficient length of time to have reached an equilibrium xenon condition.
  • Startup testing of the reactor and turbine control and protection systems are completed, and final setpoints are installed. ,
  • The incore instrumentation system, including signal processing software, is operational.

All preoperational and startup testing is completed.

  • Instrumentation and data collection equipment is operational and available for logging plant data.

Test Method

  • Prior to any load reduction, obtain thermal power measurement and statepoint data along with incore power distribution maps to serve as the reference plant condition.
  • Using normal plant procedures, reduce turbine load at a rate such that a reactor thermal power level of approximately 50 percent is achieved linearly in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
  • After remaining at 50 percent rated thermal power for more than two hours but less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, increase turbine load at a rate such that a reactor power level of approximately 100 percent rated thermal power is achieved linearly in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
  • At selected times during the power decrease, while at reduced power, during the power increase, and after reaching approximately full rated thermal power, obtain data from both incore and excore instrumentation to monitor plant performance.
  • While within the load-follow maneuver, demonstrate the ability to respond to grid frequency changes by increasing and decreasing load by as much as 10 percent at a rate of 2 percent per minute.

o \ssanev90014 R04 0715% Revision: 9

[ W8Stingh00S8 14-119 Draft July 31,1996

u--:

14. Initial Test Program Performance Criteria
  • - Core power distribution limits, as specified in the plant technical specifications, are not exceeded when the plant power is varied according to the design basis load-follow cycle or while in the cycle, responding to load changes simulating grid frequency changes.
  • Load follow maneuvers, including response to grid frequency changes, can be j accomplished without changes to the reactor coolant boron concentration.

14.2.10.4.23 Hot Full Power Boron Endpoint i Objective l Measure the reactor coolant system critical boron concentration at beginning of cycle life )

for the all rods out, hot full power, xenon equilibrium condition.

1 Prerequisites l

1

  • The reactor is operating at approximately 100 percent of full licensed power and has

~ '

been at that power for a sufficient time to reach xenon equilibrium.

  • The reactor power level and reactor coolant system boron concentration and temperature are stable, and control and shutdown rod banks are in the near fully withdrawn position. l
  • Current core burnup data are available.

Test Method

. During the power ascension test program, and, as soon as practicable after achieving ~

i equilibrium xenon at full licensed power, obtain and analyze samples of reactor coolant for dissolved boron content. I

  • Using plant calorimetric and statepoint data obtained at the same time as coolant sampling, correct the measured boron concentration, as required, for control rod i insertion, nonequilibrium xenon, and any difference between T,,, and T,,.
  • The resultant boron value, corresponding to the measured critical boron concentration for all rods out, hot full power, and equilibrium xenon, is compared with design predictions for the current accumulated core bumup (Figure 4.3-3).
  • As permitted by the plant technical specifications, use the corrected measured boron concentration to renormalize the predicted curve of boron concentration as a function of core burnup.

Revision: 9 .si.nev9eoi4 noo47:596 Draft July 31,1996 14 120 T W86tingh00S8

14. Initial Test Program l

i Performance Criterion The reactivity equivalent of th .. fference between measured and predicted boron concentra-tions (Table 4.3-2) is less tha.. .ne design limit (subsection 4.3.3.3).

14.2.10.4.24 Plant Trip from 100 Percent Power Objectives a Verify the ability of the plant automatic control systems to sustain a trip from 100 percent rated thermal power and bring the plant to stable conditions following the j transient.  ;

- Determine the overall response time of the hot leg resistance temperature detector.

  • Optimize the control systems setpoints, if necessary.

Prerequisite The plant is operating in a steady-state condition at full rated thermal power.

Test Method

= Trip the reactor by opening the reactor-trip breaker.

  • Monitor and record selected plant parameters.
  • If necessary, adjust the control systems setpoints to obtain optimal response.

Performance Criteria a Following a plant trip from 100 percent rated thermal power, primary and secondary control systems and operator actions can s*.abilize reactor coolant system temperature, pressurizer pressure and level, and steam generator levels to no-load operating tem-perature and pressure.

= The steam dump control system operates to prevent opening of primary and secondary safety valves.

  • The hot leg RTD time responses are verified to be less than or equal to values used in the safety analysis.

.s m9ooi4ammim Revision: 9 3 W86tingh00$8 14-121 Draft July 31,1996

14. Initial Test Program  !

VR --

14.2.10.4.25 Thermal Expansion Objective Demonstrate that essential nuclear steam supply system and balance-of-plant components can expand without obstruction and that the expansion is in accordance with design. Also, during cooldown, the components return to their approximate baseline cold position.

Testing will be conducted to resolve discrepancies from hot functional testing (See subsection 14.2.9.1.1) and to test modifications made since hot functional testing was completed. Systems not tested during hot functional testing will be tested.

Prerequisite Temporary instrumentation is installed, as required, to monitor the deflections for the components under test.

Test Method For the components being tested the following apply:

~

  • During plant heatup and cooldown, record deflection data. -

- Verify support movements by recording hot and cold positions.

Performance Criteria For the components being tested, the following apply:

  • 'Ihere is no evidence of blocking of the thermal expansion of any piping or component, other than by installed suppons, restraints, and hangers.

. Spring hanger movements must remain within the hot and cold setpoints and supports must not become fully retracted or extended.

  • Piping and components retum to their approximate baseline cold position.

Revision: 9 os==v9eoi4 nomi3%

Draft July 31,1996 14 122 W Westingh00S8 l

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