ML17151B013: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:WOLF CREEK CHAPTER 14.0   TABLE OF CONTENTS INITIAL TEST PROGRAM Section                        Title                      Page 14.1        SPECIFIC INFORMATION TO BE INCLUDED          14.1-1                    IN THE PSAR 14.2        INITIAL TEST PROGRAM                        14.2-1 14.2.1      SUMMARY OF TEST PROGRAM AND OBJECTIVES      14.2-1 14.2.1.1    Preoperational Test Program                  14.2-1 14.2.1.2    Initial Startup Test Program                14.2-2 14.2.2      ORGANIZATION AND STAFFING                    14.2-3 14.2.2.1    General Description                          14.2-3 14.2.2.2    Startup Organization                        14.2-4 14.2.2.3    Operating Staff                              14.2-6 14.2.2.4    Major Participating Organizations            14.2-6 14.2.2.5    Quality Assurance                            14.2-8 14.2.2.6    Qualifications of Key Personnel              14.2-8
{{#Wiki_filter:WOLF CREEK CHAPTER 14.0 TABLE OF CONTENTS INITIAL TEST PROGRAM


14.2.3      TEST PROCEDURES                              14.2-8 14.2.3.1    Startup Test Procedures                     14.2-8 14.2.3.2    Procedure Review and Approval                14.2-10 14.2.4      CONDUCT OF TEST PROGRAM                      14.2-12 14.2.4.1    Administrative Procedures                    14.2-12 14.2.4.2    Turnover From Construction to KG&E          14.2-13                  Startup 14.2.4.3    Component and Prerequisite Testing          14.2-14 14.2.4.4    Preoperational Testing                      14.2-14 14.2.4.5    Initial Startup Testing                      14.2-14 14.2.4.6    Test Prerequisites                          14.2-15 14.2.4.7    Test Evaluation                              14.2-15 14.2.4.8    Design Modifications                        14.2-15
Section                        Title                     Page 


14.2.5      REVIEW, EVALUATION, AND APPROVAL OF         14.2-15 TEST RESULTS  14.2.6      TEST RECORDS                                14.2-16 
14.1        SPECIFIC INFORMATION TO BE INCLUDED         14.1-1 IN THE PSAR


14.2.7      CONFORMANCE OF TEST PROGRAMS WITH            14.2-16 REGULATORY GUIDES 14.2.8      UTILIZATION OF REACTOR OPERATING AND        14.2-16                  TESTING EXPERIENCE IN DEVELOPMENT OF TEST PROGRAMS
14.2         INITIAL TEST PROGRAM                        14.2-1


14.2.9       TRIAL USE OF PLANT OPERATING AND EMERGENCY  14.2-18                  PROCEDURES 14.0-i                          Rev. 29 WOLF CREEK                    TABLE OF CONTENTS (CONTINUED)
14.2.1       SUMMARY OF TEST PROGRAM AND OBJECTIVES      14.2-1  
Section                      Title                      Page  14.2.10      INITIAL FUEL LOADING CRITICALITY AND POWER  14.2-18 ASCENSION 14.2.10.1   Fuel Loading                                14.2-19 14.2.10.2    Initial Criticality                          14.2-22 14.2.10.3    Low Power Testing                            14.2-23 14.2.10.4    Power Level Ascension                        14.2-23


14.2.11      TEST PROGRAM SCHEDULE                        14.2-24  14.2.12      INDIVIDUAL TEST DESCRIPTIONS                14.2-25 14.2.12.1   Safety-Related Preoperational Test           14.2-25 Procedures 14.2.12.2    Nonsafety-related Preoperational Test        14.2-121                  Procedures 14.2.12.3    Startup Test Procedures                      14.2-158 
14.2.1.1     Preoperational Test Program                  14.2-1


14.0-ii                        Rev. 29 WOLF CREEK                    TABLE OF CONTENTS (CONTINUED)
14.2.1.2     Initial Startup Test Program                14.2-2  
LIST OF TABLES  Table No.                    Title 14.2-1        Safety-Related Preoperational Test Procedures  14.2-2       Non-Safety-Related Preoperational Test Procedures


14.2-3       Initial Startup Test
14.2.2      ORGANIZATION AND STAFFING                    14.2-3 14.2.2.1    General Description                          14.2-3
 
14.2.2.2    Startup Organization                        14.2-4


14.0-iii                        Rev. 0 WOLF CREEK CHAPTER 14.0  INITIAL TEST PROGRAM 14.1  SPECIFIC INFORMATION TO BE INCLUDED IN PRELIMINARY SAFETY        ANALYSIS REPORTS    This section is not applicable to a USAR.   
14.2.2.3    Operating Staff                              14.2-6


14.1-1                      Rev. 1 WOLF CREEK CHAPTER 14.0  INITIAL TEST PROGRAM  14.2 INITIAL TEST PROGRAM  14.2.1  SUMMARY OF TEST PROGRAM AND OBJECTIVES
14.2.2.4    Major Participating Organizations            14.2-6 14.2.2.5    Quality Assurance                            14.2-8 14.2.2.6    Qualifications of Key Personnel              14.2-8


The Initial Test Program encompassed the scope of events following completion of construction and construction-related inspections and tests and terminating with Power Ascension Testing. The Initial Test Program was conducted in two separate and sequential subprograms:  the Preoperational Test Program and the Initial Startup Test Program. At the conclusion of these subprograms, the plant was ready for normal power operation. Testing during the Initial Test Program was accomplished in four sequential phases:
14.2.3      TEST PROCEDURES                              14.2-8


Preoperational Test Program
14.2.3.1    Startup Test Procedures                      14.2-8 14.2.3.2    Procedure Review and Approval                14.2-10


Phase I - Preoperational Testing Initial Startup Test Program
14.2.4      CONDUCT OF TEST PROGRAM                      14.2-12  


Phase II - Initial Fuel Loading and Zero Power Testing
14.2.4.1    Administrative Procedures                    14.2-12 


Phase III - Low Power Physics Testing  
14.2.4.2    Turnover From Construction to KG&E          14.2-13 Startup 14.2.4.3    Component and Prerequisite Testing           14.2-14


Phase IV - Power Ascension Testing
14.2.4.4    Preoperational Testing                      14.2-14


Prior to preoperational testing of a particular system, certain prerequisite and construction tests were conducted in order to verify the integrity, proper installation, cleanliness, and functional operability of the system components.  
14.2.4.5    Initial Startup Testing                      14.2-14


14.2.1.1  Preoperational Test Program  The Preoperational Test Program is defined as that part of the Initial Test Program that commences with the completion of construction and construction-related inspections and tests and terminates with commencement of nuclear fuel loading.  
14.2.4.6    Test Prerequisites                          14.2-15 14.2.4.7    Test Evaluation                              14.2-15 14.2.4.8    Design Modifications                        14.2-15


The Preoperational Test Program included both safety-related and nonsafety-related preoperational tests. The Preoperational Test Program used a graded approach to determine the extent of testing to be performed. The safety-related preoperational tests (Table 14.2-1) demonstrated the capability of safety-related structures, systems, and components to meet performance requirements and to satisfy design criteria. The nonsafety-related preoperational tests (Table 14.2-2) were conducted on nonsafety-related systems and components to satisfy reliability and availability. Preoperational tests were conducted on those systems that: 
14.2.5      REVIEW, EVALUATION, AND APPROVAL OF          14.2-15


14.2-1                          Rev. 0 WOLF CREEK      a. Are 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;
TEST RESULTS 14.2.6      TEST RECORDS                                14.2-16 
: b. Are 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. Are relied upon for establishing conformance with safety limits or limiting conditions for operations that are included in the technical specifications;
: d. Are classified as engineered safety features actuation          systems or are relied upon to support or ensure operation of engineered safety features actuation systems within design limits;
: e. Are assumed to function during an accident or for which credit is taken in the accident analysis;
: f. Are used to process, store, control, or limit the release of radioactive materials.  


The objectives of the Preoperational Test Program were to:
14.2.7      CONFORMANCE OF TEST PROGRAMS WITH            14.2-16
: a. Verify that plant components and systems, including alarms and indications, are constructed and fulfill          their design intent; 
: b. Demonstrate, to the extent practicable, proper system/component response to postulated accidents;
: c. Familiarize plant staff operating, technical, and maintenance personnel with plant operation.  


The completion of preoperational testing constituted the completion of Phase I of the Initial Test Program.
REGULATORY GUIDES


14.2.1.2  Initial Startup Test Program  The Initial Startup Test Program is defined as that part of the Initial Test Program that commences with the start of nuclear fuel loading and terminates with the completion of power ascension testing. The initial startup tests (Table 14.2-3) ensured that fuel loading was accomplished in a safe manner, confirmed the
14.2.8      UTILIZATION OF REACTOR OPERATING AND        14.2-16 TESTING EXPERIENCE IN DEVELOPMENT


14.2-2                        Rev.0 WOLF CREEK design basis, demonstrated, where practical, that the plant operates and responds properly to anticipated transients and postulated accidents, and ensured that the plant can be safely brought to rated capacity and sustained power operation.
OF TEST PROGRAMS
The objectives of the Initial Startup Test Program were to:
: a. Accomplish a controlled, orderly, and safe initial core loading;
: b. Accomplish a controlled, orderly, and safe initial criticality;
: c. Conduct low power testing sufficient to ensure that design parameters are satisfied and safety analysis          assumptions are conservative; 
: d. Perform a controlled, orderly, and safe power ascension with testing terminating at plant rated conditions;
: e. Provide sufficient testing of transient and accident conditions to verify safe operation during transient or accident conditions.


The completion of initial startup testing constituted the completion of Phases II, III, and IV of the Initial Test Program.  
14.2.9      TRIAL USE OF PLANT OPERATING AND EMERGENCY  14.2-18 PROCEDURES


14.2.2  ORGANIZATION AND STAFFING
14.0-i                          Rev. 29 WOLF CREEK TABLE OF CONTENTS (CONTINUED)


14.2.2.1  General Description  The Operating Agent, as defined in Section 1.4, was responsible for the overall administration and technical direction of the WCGS startup program. In recognition of this responsibility, the Director of Nuclear Operations, under the direction of the Vice President - Nuclear, established a startup organization to coordinate and direct the comprehensive planning, development, implementation and performance of the test program. The Startup Organization was headed by the Startup Manager who reported to the Plant Manager both administratively and technically.
Section                      Title                      Page 14.2.10      INITIAL FUEL LOADING CRITICALITY AND POWER  14.2-18


During the preoperational startup program, the Startup Manager acted to coordinate activities between the Startup Organization, the construction staff, and the operating staff.
ASCENSION
Prior to commencing preoperational testing activities, a Joint Test Group (JTG) as described in Section 14.2.3.2.2 was formed to review and recommend for approval startup administrative procedures, preoperational test procedures, and preoperational test


14.2-3                        Rev. 0 WOLF CREEK results. A Plant Safety Review Committee (PSRC) as described in Section 14.2.3.2.3 was organized with the Plant Manager acting as chairman and it reviewed and recommended for approval initial startup test procedures and results.
14.2.10.1    Fuel Loading                                14.2-19 14.2.10.2    Initial Criticality                          14.2-22 14.2.10.3    Low Power Testing                            14.2-23
14.2.2.2 Startup Organization


The Startup Organization was directly responsible for the conduct of the WCGS preoperational test program. The duties and responsibilities of the startup organization also included:
14.2.10.4    Power Level Ascension                        14.2-23
: a. Familiarization of support personnel with specific tests.  
: b. Direction to support personnel and others during          performance of tests including appropriate interface          with station operators.
: c. Authority to disallow or terminate testing due to conditions which could endanger personnel or equipment.
: d. Identification of deficiencies that could adversely affect test performance.
: e. Assembly of test data and preparation of test reports for evaluation of test results by others.  


The Startup Organization was composed of system startup engineers, technicians, planners, craft labor, and other support personnel. The Operating Agent provided these personnel and used contractors to supply manpower for those positions that it could not staff. The staffing level for the Startup Organization increased as the test program progressed and construction activities decreased. Typical schedules for the test program are given in Section 14.2.11. Staffing and training of personnel involved in testing at WCGS were planned to provide sufficient manpower to support the testing schedule.  
14.2.11      TEST PROGRAM SCHEDULE                        14.2-24 14.2.12      INDIVIDUAL TEST DESCRIPTIONS                14.2-25


The Startup Organization reported administratively and technically to the Startup Manager; the duties performed by key individuals within the Startup Organization are summarized below.  
14.2.12.1    Safety-Related Preoperational Test          14.2-25


14.2.2.2.1  Startup Manager
Procedures


The Startup Manager had the authority and responsibility, as delegated by the Plant Manager, for the overall direction and administration of the functions and activities required to conduct the Startup Program. The responsibilities and duties of the Startup Manager also included:
14.2.12.2    Nonsafety-related Preoperational Test        14.2-121 Procedures


14.2-4                        Rev. 0 WOLF CREEK      a. Development of plans and schedules regarding the status          of the startup program.
14.2.12.3    Startup Test Procedures                     14.2-158
: b. Review and approval of administrative and technical test procedures and results. 
: c. Continuing analysis of construction and equipment installation schedules for compatibility with testing schedules and recommendations for corrective actions to minimize conflict.  
: d. Review and submittal of design related problems requiring engineering resolution, encountered by the Startup Organization in accordance with the appropriate Startup Administrative Procedures.       e. Maintaining liaison with all organizations supporting Startup and coordinating their activities.


14.2.2.2.2  Startup Section
14.0-ii                        Rev. 29 WOLF CREEK TABLE OF CONTENTS (CONTINUED)


The Startup Section was comprised primarily of the System Test Group, the Electrical Test Group and the Instrumentation and Control Group which had primary responsibility within the Startup Organization to perform testing.
LIST OF TABLES Table No.                     Title
This section also reviewed and recommended the acceptance of system or subsystem turnover documentation from Construction and coordinated system turnover and any subsequent system rework. It was responsible for preparing the test procedures, conducting the tests, and reporting the test results. For preoperational testing, this section documented the test results and presented them before the Joint Test Group for its review and recommendation for approval.
14.2.2.2.3  Operations Technical Support Section


The Operations Technical Support Section was responsible for providing technical support to the Startup Section during testing. The areas in which this support was given were instrumentation and control, chemistry, computer, health physics and reactor engineering.  
14.2-1        Safety-Related Preoperational Test Procedures 14.2-2        Non-Safety-Related Preoperational Test Procedures


This section was a permanent part of the WCGS operating staff until these functions were incorporated into other sections. They were involved in training, procedure preparation, and general preparation for support of plant operations.
14.2-3        Initial Startup Test
14.2.2.2.4  Startup Scheduling Section


The Startup Scheduling Section prepared and updated the Startup Schedule, utilizing input from cognizant system startup engineers and the construction organizations.  
14.0-iii                        Rev. 0


14.2-5                        Rev.7 WOLF CREEK 14.2.2.2.5  Quality Control Section The Quality Control Section formulated and implemented the Startup Quality Control Program. This program monitored the conduct of the Startup Organization's testing activities by reviewing administrative and technical test procedures, by witnessing major evolutions and selected flushes, hydros, and preoperational tests and by reviewing turnover packages. The Quality Control Section was under the direction of the Director - Quality. They provided support to the Startup Manager.
WOLF CREEK CHAPTER 14.0 INITIAL TEST PROGRAM


14.2.2.2.6 Startup Technical Support Section
14.1  SPECIFIC INFORMATION TO BE INCLUDED IN PRELIMINARY SAFETY ANALYSIS REPORTS This section is not applicable to a USAR.   


The Startup Technical Support Section was responsible for providing technical support to the Startup Organization during the conduct of the Startup Program.
14.1-1                      Rev. 1 WOLF CREEK CHAPTER 14.0 INITIAL TEST PROGRAM 14.2  INITIAL TEST PROGRAM 14.2.1  SUMMARY OF TEST PROGRAM AND OBJECTIVES
Their responsibilities included test procedure and test results review and approval, technical planning of major milestone activities, startup organization training and startup program compliance to FSAR commitments.  


14.2.2.3  Operating Staff  The WCGS operating staff was involved in the startup program in several capacities throughout preoperational and initial startup testing. This involvement included review of test procedures and results and the direct participation in test activities. Operating staff personnel were utilized by the startup organization as required for performance of testing under the direction of system startup engineers. Station operators assisted system startup engineers in performing tests and in the routine operations of systems.
The Initial Test Program encompassed the scope of events following completion of construction and construction-related inspections and tests and terminating
The operating staff directed the fuel loading and was responsible for plant operation during initial startup testing.


The operating staff was divided into sections headed by the Superintendent Operations, Superintendent of Maintenance, Superintendent of Plant Support, Superintendent of Technical Support, Nuclear Training Manager and Superintendent Regulatory Quality and Administrative Services. These section superintendents reported administratively and technically to the Plant Manager.
with Power Ascension Testing. The Initial Test Program was conducted in two
The duties and responsibilities of the operating staff during plant operations are described in Chapter 13.0.
14.2.2.4  Major Participating Organizations  14.2.2.4.1  Bechtel


Bechtel provided engineering input into the startup program. Bechtel was contacted to provide personnel experienced in nuclear plant startup to augment the startup organization for WCGS. Bechtel employees were assigned consistent with the startup program schedules.
separate and sequential subprograms:  the Preoperational Test Program and the  


14.2-6                        Rev. 12 WOLF CREEK 14.2.2.4.2  Daniel International Corporation (DIC)
Initial Startup Test Program. At the conclusion of these subprograms, the  
DIC, as contractor for WCGS, was responsible for the construction completion, and orderly release of components and turnover of systems to KG&E consistent with the startup program schedules. This responsibility included: 
: a. Certification that documentation for components, systems and structures, as required by purchase and installation specifications, is complete and available; and the maintenance of these certification files which provide the documentary evidence, and
: b. Provision of dedicated craft manpower support as required for performance of the startup program.
14.2.2.4.3  Westinghouse Electric Corporation Westinghouse, as the Nuclear Steam Supply System (NSSS) supplier, was responsible for providing technical assistance to KG&E during preoperational and initial startup testing performed on the NSSS equipment and systems.
Technical assistance is defined as technical guidance, advice and counsel based on current engineering, installation, and testing practices. Westinghouse employees were assigned consistent with the Startup Program schedules. This responsibility included:
: a. Assignment of personnel to provide advice and assistance to KG&E for test and operation of all equipment and systems in the Westinghouse area of responsibility.
: b. Supportive engineering services, including special          assistance during the initial fuel loading. 
: c. Providing test procedure outlines and technical assistance for tests of Westinghouse furnished components and systems.


14.2.2.4.4  General Electric (GE)
plant was ready for normal power operation. Testing during the Initial Test


GE is the supplier and installer of the turbine generator. GE supplied technical support for the startup and testing of the turbine generator. Some of the prerequisite testing (i.e., turbine oil flush) was performed by the GE personnel. GE has supplied recommended procedures for starting, operating, and shutting down equipment in their technical manuals for the turbine generator.
Program was accomplished in four sequential phases:


14.2-7                        Rev. 0 WOLF CREEK 14.2.2.5  Quality Assurance  The KG&E Quality Branch was responsible for assuring the quality of construction, plant testing, and operations activities in accordance with the WCGS Quality Program which is described in the Quality Program Manual.
Preoperational Test Program  
14.2.2.6  Qualifications of Key Personnel The qualifications for key plant operating personnel are described in Chapter 13.0.
The qualification requirements for startup personnel involved in the WCGS startup program conformed to capability levels per ANSI N45.2.6 and Regulatory Guide 1.8 recommendations.


All test personnel were indoctrinated in the startup administrative procedures, methods and controls.
Phase I - Preoperational Testing Initial Startup Test Program


14.2.3  TEST PROCEDURES
Phase II - Initial Fuel Loading and Zero Power Testing


The Initial Test Program was conducted in accordance with detailed preoperational and initial startup test procedures. KG&E maintained the overall responsibility for test procedure preparation, review, and approval during the preparational stages. KG&E was responsible for final procedure revision, review, and approval. These activities were completed in a timely fashion to ensure that the approved procedures for satisfying FSAR testing equipment commitments were available for review approximately 60 days prior to scheduled implementation or fuel load for preoperational and initial startup tests, respectively. Preoperational and initial start-up testing commitments not available for review approximately 60 days prior to scheduled implementation or fuel load, respectively, were handled on a case- by-case basis.
Phase III - Low Power Physics Testing


The following sections describe the general methods employed to control procedure development and review, and they also describe the responsibilities of the various organizations which participated in this process. The detailed controls and methods were described in the startup administrative procedures.
Phase IV - Power Ascension Testing
14.2.3.1  Procedure Preparation  Test procedures for the powerblock systems and components were developed by Westinghouse and Bechtel. Bechtel also prepared test procedures for the site safety-related systems and components. Test procedures for the site nonsafety-related systems and components were developed by various entities as coordinated by KG&E.


14.2-8                        Rev. 21 WOLF CREEK The format and content of the test procedures developed for the standard plant and safety-related site systems and components reflected the guidance provided in Regulatory Guide 1.68. The procedures contained as a minimum the following sections:
Prior to preoperational testing of a particular system, certain prerequisite
1.0  Objectives


The objectives section identified the general results to be accomplished by the test.
and construction tests were conducted in order to verify the integrity, proper


2.0  Acceptance Criteria
installation, cleanliness, and functional operability of the system components.  


The acceptance criteria section clearly defined quantitative and/or qualitative criteria against which the success or failure of the test procedure is judged.      3.0  References
14.2.1.1  Preoperational Test Program The Preoperational Test Program is defined as that part of the Initial Test


The references section identified those FSAR sections, vendor manuals, drawings, etc. that were pertinent to the performance and/or development of the test procedure.
Program that commences with the completion of construction and construction-


4.0  Test Equipment
related inspections and tests and terminates with commencement of nuclear fuel loading.  


The test equipment section identified temporary equipment required to conduct the test procedure and/or collect data.
The Preoperational Test Program included both safety-related and nonsafety-


5.0  Notes and Precautions            The notes and precautions sections listed limitations and precautions necessary to ensure personnel and equipment safety. Additional instructions needed to clarify the test procedure were also listed in this section.
related preoperational tests. The Preoperational Test Program used a graded


6.0  Prerequisites
approach to determine the extent of testing to be performed. The safety-


The prerequisites section identified those prerequisite tests and initial conditions that had to be completed and/or satisfied prior to the performance of the test procedure.
related preoperational tests (Table 14.2-1) demonstrated the capability of  


7.0  Test Procedure
safety-related structures, systems, and components to meet performance


The test procedure section provided a detailed step-by-step test method and instructions for data collection.
requirements and to satisfy design criteria. The nonsafety-related
All nonstandard arrangements required by the test procedure section were restored either in the test procedure section or the system restoration section.


14.2-9                        Rev. 0 WOLF CREEK      8.0  Test Data Sheets The test data sheet section provided specific forms for data collection. Additional instructions, if necessary, were also identified for each data sheet.
preoperational tests (Table 14.2-2) were conducted on nonsafety-related systems
9.0  System Restoration


The system restoration section returned the system to a safe operating or standby condition. Instructions for the removal and/or return of system temporary modifications required by the prerequisite and/or test procedure sections were clearly defined.
and components to satisfy reliability and availability. Preoperational tests were conducted on those systems that:


The procedural sections included, as applicable, appropriate requirements for initials and/or signatures to control the performance and sequencing of the test.
14.2-1                          Rev. 0 WOLF CREEK
: a. Are relied upon for safe shutdown and cooldown of the reactor under normal plant conditions and for


The test procedures were prepared using the latest design information available and functional requirements provided by the design engineers. This information was utilized in developing the detailed test methods which verified the ability of systems and components to function within their design specifications. The procedure preparation efforts were started more than 2 years before the first procedure to be performed. This early start allows for an orderly development of the test procedure program and of the test procedures.
maintaining the reactor in a safe condition for an  


The test procedures were reviewed by the cognizant design organization to ensure that the test procedure objectives and acceptance criteria are consistent with current design document requirements. Subsequent changes to test procedure objectives or acceptance criteria during the preparational stage were based on approved changes to design documents with the design organization's concurrence.
extended shutdown period;
: b. Are relied upon for safe shutdown and cooldown of the  


14.2.3.2  Procedure Review and Approval  Following initial procedure preparation, and prior to submittal to the JTG for review and approval recommendation, the test procedures were reviewed by the SNUPPS utilities (KG&E and Union Electric). Review comments were resolved between the SNUPPS utilities and the writing organization.
reactor under transient and postulated accident


A final revision was made by the writing organization, incorporating all applicable design changes, and was submitted to the utilities for their review and approval.
conditions and for maintaining the reactor in a safe


14.2-10    Rev. 0 WOLF CREEK Each utility had various organizations, groups, and committees, such as a startup organization, initial test group, and a plant safety review committee, comprised of individuals having appropriate technical backgrounds and experience. Individuals within these organizations, groups, and committees were responsible for: 
condition for an extended shutdown period following such  
: a. Reviewing procedures for accuracy and technical content;
: b. Verifying that the procedure has been revised to incorporate known design changes;
: c. Verifying procedure compatibility with field installation of equipment;
: d. Verifying procedure conformance with FSAR requirements          and plant operating technical specifications; 
: e. Reviewing procedures against reactor operating and testing experiences of similar power plants.


14.2.3.2.2  Joint Test Group (JTG)
conditions;
: c. Are relied upon for establishing conformance with safety


A subcommittee of the PSRC, the JTG was organized by the Operating Agent to review preoperational test procedures and preoperational test results.
limits or limiting conditions for operations that are


The primary JTG functions were to:
included in the technical specifications;
: a. Review preoperational test procedures and recommend their approval by the Startup Manager.
: d. Are classified as engineered safety features actuation systems or are relied upon to support or ensure
: b. Evaluate and authorize changes to preoperational test          procedures as detailed in the Startup Administrative Manual.
: c. Evaluate preoperational test procedure results and recommend their approval to the Startup Manager and Plant Manager.
: d. Review safety-related aspects of the startup administrative procedures.


Membership in the JTG included the following personnel or their designated representatives:
operation of engineered safety features actuation
: a. Superintendent Operations - Chairman      b. Superintendent of Plant Support


14.2-11    Rev. 12 WOLF CREEK      c. Superintendent of Regulatory, Quality and Administrative          Services
systems within design limits;
: d. Startup Technical Support Supervisor
: e. Are assumed to function during an accident or for which
: e. Assistant Startup Manager
: f. Operations Quality Assurance  (non-voting member)
: g. Bechtel Power Corporation-Engineering (non-voting member)
: h. Westinghouse-Engineering (non-voting member)


Others were requested to provide technical support to the JTG. This support was based on the procedure being reviewed, required technical expertise or other applicable factors. Participation in the JTG meeting was with the concurrence of the JTG and was limited to technical input only.
credit is taken in the accident analysis;
: f. Are used to process, store, control, or limit the  


14.2.3.2.3  Plant Safety Review Committee (PSRC)
release of radioactive materials.  


The PSRC was organized by the Operating Agent to ensure effective coordination of the engineering, construction, and operations activities affecting the startup program.
The objectives of the Preoperational Test Program were to:
: a. Verify that plant components and systems, including


The appropriate PSRC members ensured sufficient review of initial startup test procedures and results.  
alarms and indications, are constructed and fulfill their design intent;
: b. Demonstrate, to the extent practicable, proper


The primary PSRC startup functions were:
system/component response to postulated accidents;
: a. Review all initial startup test procedures and make          recommendations to the Plant Manager.
: c. Familiarize plant staff operating, technical, and  
: b. Evaluation and authorization of changes to initial startup test procedures.
: c. Evaluation of initial startup test procedure results.


Membership in the PSRC is given in the Quality Program Manual. 14.2.4  CONDUCT OF TEST PROGRAM
maintenance personnel with plant operation.  


14.2.4.1  Administrative Procedures The conduct of the preoperational startup program was controlled by administrative procedures. The preparation, maintenance,  and implementation of these procedures was the responsibility of the Startup Manager. The startup administrative procedures prescribed controls for startup activities such as:
The completion of preoperational testing constituted the completion of Phase I


14.2-12    Rev. 21 WOLF CREEK      a. Organization and interfaces; 
of the Initial Test Program.  
: b. Indoctrination and training;
: c. Preparation, review, approval, and modification of test          procedures;
: d. Format and content of test procedures;
: e. Tagging procedures;
: f. Test scheduling and test conduct;
: g. Test deficiencies and resolution;
: h. Startup quality control; and 
: i. Startup document control.  


14.2.4.2  Turnover from Construction to KG&E Startup Construction completion was scheduled in accordance with engineered system or subsystem boundaries. As systems or sub- systems were completed to support Startup testing, a turnover of the system or subsystem to KG&E Startup was processed. Turnover was conducted in accordance with established administrative procedures.
14.2.1.2  Initial Startup Test Program The Initial Startup Test Program is defined as that part of the Initial Test


As part of the turnover process, each safety-related system or subsystem received physical walkdowns to provide assurance of readiness for Startup testing and verification that installation requirements had been met.
Program that commences with the start of nuclear fuel loading and terminates
Walkdowns were performed jointly by KG&E Startup and KG&E Construction personnel under the direction of the KG&E Construction Manager. Discrepancies identified during the walkdowns were tracked and resolved in accordance with established administrative and quality procedures. The system or subsystem Turnover Package prepared by the constructor was reviewed by KG&E Construction and KG&E Startup personnel for accuracy, completeness and acceptability for Startup testing. In conjunction with the Turnover Package review, Startup personnel verified that the system or subsystem procurement and installation documentation review had been performed by Construction, and that discrepancies had been addressed. Acceptance of the Turnover Package by Startup followed satisfactory completion of the Turnover Package review. The Startup Manager was responsible for the approval and acceptance of the system or subsystem and the associated Turnover Package.


14.2-13    Rev. 0 WOLF CREEK Individual components could be released to Startup for calibration, testing or temporary operation prior to turnover.
with the completion of power ascension testing. The initial startup tests (Table 14.2-3) ensured that fuel loading was accomplished in a safe manner,  


All components released in this manner were incorporated into the scope of a subsequent system or subsystem turnover.
confirmed the  
14.2.4.3  Component and Prerequisite Testing  Upon Startup acceptance of a turned-over system, subsystem, or released component, prerequisite-type testing was performed to demonstrate proper operability and functional ability in support of, and prior to, the performance of preoperational testing. Local containment leak rate testing, as described in Section 14.2.12.2.13, was performed at WCGS as part of the prerequisite test program.


Administrative procedures were established to ensure that all prerequisites were met before testing was initiated. Upon completion of all prerequisite tests applicable to a system or subsystem, a documented review was conducted by Startup personnel to verify that appropriate documentation was able and that required prerequisite tests had been satisfactorily completed. All deficiencies which would prevent performance of preoperational tests or generate negative test results were identified and dispositioned prior to implementation of the preoperational tests.
14.2-2                        Rev.0 WOLF CREEK design basis, demonstrated, where practical, that the plant operates and responds properly to anticipated transients and postulated accidents, and  


14.2.4.4  Preoperational Testing  Technical direction and administration, including test execution and data recording, of the preoperational testing were the responsibility of the startup organization. The system startup engineers were responsible for the performance of tests and providing appropriate interface with station operators. The Startup Manager was responsible for the administration and surveillance of all testing activities during the preoperational test program.
ensured that the plant can be safely brought to rated capacity and sustained


14.2.4.5 Initial Startup Testing  During the initial startup testing phase, the Plant Manager had overall authority and responsibility for the startup program. The Startup Organization provided support to the plant operating staff which had responsibility for performing equipment operations and maintenance in accordance with the provisions of the plant operating license. The WCGS operating staff was also responsible for ensuring that the conduct of testing did not place the plant in an unsafe condition at any time.  
power operation.  


The shift supervisors had the authority to terminate or disallow testing at any time.  
The objectives of the Initial Startup Test Program were to:
: a. Accomplish a controlled, orderly, and safe initial core


14.2-14    Rev. 0 WOLF CREEK 14.2.4.6  Test Prerequisites  Each test procedure contained a set of prerequisites and initial conditions as prescribed by the startup administrative procedures. The system startup engineer ensured that all specified prerequisites were met prior to performing the test. The format for test procedures is described in Section 14.2.3.1.
loading;
: b. Accomplish a controlled, orderly, and safe initial  


14.2.4.7  Test Evaluation  Upon completion of system preoperational testing, the test results were submitted to the JTG for its review and subsequent recommendation for approval to the Startup Manager and Plant Manager.
criticality;
Between each major phase of the initial startup test program, the test results for all tests that were performed were reviewed by the PSRC. This review ensured that all required systems were tested satisfactorily and that test results were approved before proceeding to the next stage of testing.
: c. Conduct low power testing sufficient to ensure that  


These reviews are described in Section 14.2.5.  
design parameters are satisfied and safety analysis assumptions are conservative;
: d. Perform a controlled, orderly, and safe power ascension


14.2.4.8  Design Modifications  Modifications to the design of the equipment during the test program could be initiated in order to correct deficiencies discovered as a result of testing.
with testing terminating at plant rated conditions;
Any such modifications were either developed by the original design organization or other designated organizations. Modifications made to components or systems after completion of preoperational or initial startup testing were reviewed for retesting requirements on affected portions of the system.
: e. Provide sufficient testing of transient and accident


14.2.5  REVIEW, EVALUATION, AND APPROVAL OF TEST RESULTS
conditions to verify safe operation during transient or


The responsibility for review, evaluation, and recommendation for approval of test results from all preoperational tests rested with the JTG. In the case of all initial start-up tests, it rested with the PSRC. Following completion of a preoperational test, the responsible system startup engineer assembled the test data package for submittal to the members of the JTG for evaluation. Each test data package was reviewed to ensure that the test has been performed in accordance with the approved procedure and that all required data, checks, and signatures were properly recorded and that system performance met the approved acceptance criteria.  
accident conditions.  


14.2-15    Rev. 0 WOLF CREEK Members of the JTG reviewed the evaluation findings and recommended corrective action to be taken to resolve any outstanding deficiencies. If the deficiencies were not resolved to the satisfaction of the JTG, then appropriate retesting was required. If the evaluation indicated that deficiencies in the test method were responsible for unsatisfactory test results, the test procedure was revised accordingly before retesting was initiated. The review and approval process for procedure revisions was carried out in the manner described in Section 14.2.3. Whenever an evaluation of test results indicated deficiencies in system performance, the JTG referred the problem to the responsible engineering organization for evaluation.
The completion of initial startup testing constituted the completion of Phases


If the test documentation and system performance were acceptable, the JTG recommended approval of the test by the Startup Manager and the Plant Manager.  
II, III, and IV of the Initial Test Program.  


Following each major phase of the initial startup test program, the PSRC verified that all required tests were performed and that the test results were approved. This verification ensured that all required systems were operating properly and that testing for the next major phase was conducted in a safe and efficient manner. This type of review was performed to the extent required before major initial startup test phases such as fuel load, initial criticality, and power ascension. During the power ascension phase, review and approval of initial startup test procedure results was completed as described in KMLNRC-84-235.  
14.2.2  ORGANIZATION AND STAFFING


14.2.6 TEST RECORDS
14.2.2.1 General Description The Operating Agent, as defined in Section 1.4, was responsible for the overall


Test procedures and test data relating to preoperational and initial startup testing are retained in accordance with the measures described in the Quality Program Manual. 14.2.7  CONFORMANCE OF TEST PROGRAMS WITH REGULATORY GUIDES
administration and technical direction of the WCGS startup program. In


The regulatory guides applicable to the test program are listed, with positions, in Appendix 3A, Conformance to NRC Regulatory Guides.
recognition of this responsibility, the Director of Nuclear Operations, under the direction of the Vice President - Nuclear, established a startup
14.2.8  UTILIZATION OF REACTOR OPERATING AND TESTING EXPERIENCE IN DEVELOPMENT OF TEST PROGRAMS


Available information on reactor operating experiences was utilized in the development of the Initial Test Program, as follows:
organization to coordinate and direct the comprehensive planning, development,  


14.2-16    Rev. 21 WOLF CREEK      a. Bechtel reviewed and distributed pertinent Licensee          Event Reports for use in the development of preoperational test procedures as follows:
implementation and performance of the test program. The Startup Organization
: 1. The Licensee Event Summary Reports and other                pertinent information were reviewed on a periodic basis, and those reports deemed to be useful for updating test procedures and items of a generic nature were cataloged. A summary of these reports was distributed within Bechtel.
: 2. Copies of the specific reports were then made and distributed for use in the preparation of procedures. In addition, these reports were coded and filed in a computer retrieval system.      b. The operating experience assessment for Wolf Creek Generating Station Unit No. 1 (WCGS) was conducted by the nuclear divisions and plant staff who possess the appropriate experience in the area of concern. The sources of operating experience information included the use of the NETWORK and the INPO/NSAC SEEIN system. An administrative system which controlled the flow of information from NETWORK, INPO/NSAC SEEIN, etc., to the cognizant organizations including the Independent Safety Engineering Group (ISEG) was developed and functioning prior to fuel load.


The Licensing Section was responsible for coordinating the review of the NRC Information and Enforcement (IE)          Bulletins, Circulars, and Information Notices.
was headed by the Startup Manager who reported to the Plant Manager both
The Startup Group reviewed information provided by the other KG&E Nuclear Divisions and information provided by Bechtel and Westinghouse to determine its effect on the Wolf Creek Initial Test Program, making revisions to test and administrative procedures as required.


An instrumented auxiliary feedwater water-hammer test was performed only at Wolf Creek.  (This test was not required to be performed. It was being performed for the purpose of gathering engineering data only.)  Procedure S-O3AL04, Auxiliary Feedwater System Water Hammer Test, required a visual and audible water hammer test and was completed prior to the issuance of an operating license. See new Section 14.2.12.1.10.  
administratively and technically.  


Procedure S-070017, Loss of Heater Drain Pump Test, was performed on Callaway only. This test was conducted to verify analytical assumptions. No additional loss of heater drain pump tests are 
During the preoperational startup program, the Startup Manager acted to  


14.2-17    Rev. 0 WOLF CREEK required, since the data obtained from the first unit test is equally valid for subsequent units. See Section 14.2.12.3.41.
coordinate activities between the Startup Organization, the construction staff,


Procedure S-07SF09 RCCA or Bank Worth Measurement at Power, was performed at 50 percent power only at Callaway. Wolf Creek and Callaway have the same core and Nuclear instrumentation system design and the test at Callaway is considered a prototypical test for Wolf Creek. This position was accepted by the NRC in a July 3, 1985 letter to KG&E.  
and the operating staff.  


A natural circulation test was performed at Callaway only to demonstrate the length of time to stabilize natural circulation, core flow distribution, and the ability to establish and maintain natural circulation. Operators participating in the tests were able to recognize when natural circulation had stabilized and were able to control saturation margin, RCS pressure, and heat removal rate without exceeding specified operating limits. These tests were conducted insofar as possible to include all available licensed operators. Licensed operators were trained in these same areas on the simulator. The simulator has full capability of simulating natural circulation, using Westinghouse data initially. When the above tests were accomplished on the Callaway plant, actual data was incorporated into the Wolf Creek simulator program. See Chapter 18, item I.G.1, and Section 14.2.12.3.43.  
Prior to commencing preoperational testing activities, a Joint Test Group (JTG) as described in Section 14.2.3.2.2 was formed to review and recommend for


14.2.9  TRIAL USE OF PLANT OPERATING AND EMERGENCY PROCEDURES
approval startup administrative procedures, preoperational test procedures, and


The plant operating procedures were utilized, where applicable during the test program, to support testing, maintain plant conditions, and facilitate training. The trial use of operating procedures served to familiarize operating personnel with systems and plant operation during the testing phase and also served to ensure the adequacy of the procedures under actual or simulated operating conditions before plant operation begins. The emergency procedures were verified during startup as plant conditions, testing, and training warrant. Surveillance tests were performed as conditions warrant during the testing program, to demonstrate their adequacy.
preoperational test  


Plant operating procedures were developed in approximately the same time frame as the preparation of preoperational and initial startup tests. The operating procedures were revised as necessary to reflect experience gained during the testing program.
14.2-3                        Rev. 0 WOLF CREEK results. A Plant Safety Review Committee (PSRC) as described in Section 14.2.3.2.3 was organized with the Plant Manager acting as chairman and it


14.2.10  INITIAL FUEL LOADING, CRITICALITY, AND POWER ASCENSION
reviewed and recommended for approval initial startup test procedures and


Prior to the commencement of fuel loading, required preoperational test procedures were evaluated, and appropriate remedial action 
results.


14.2-18    Rev. 0 WOLF CREEK was taken if the acceptance criteria was not satisfied. At the completion of fuel loading, the reactor upper internals and pressure vessel head were installed, and additional mechanical and electrical tests were performed to prepare the plant for nuclear operation. After final precritical tests, nuclear operation of the reactor began. This phase of testing included initial criticality, low power testing, and power level ascension. The purpose of these tests was to establish the operational characteristics of the unit and core, to acquire data for the proper calibration of setpoints, and to ensure that operation is within license requirements. Section 14.2.12.3 summarizes the tests which are performed from fuel load to rated power. The fuel loading and post loading tests are described below.
14.2.2.2 Startup Organization


14.2.10.1  Fuel Loading  The Plant Manager or his designated representative with technical assistance provided by Westinghouse, was responsible for the coordination of initial core loading. The overall process of initial core loading was, in general, directed from the operating floor of the containment structure by a licensed senior reactor operator. The licensed senior reactor operator had no additional responsibilities other than core load operations.
The Startup Organization was directly responsible for the conduct of the WCGS


The core configuration was specified as part of the core design studies conducted well in advance of fuel loading. In the event mechanical damage was sustained during core loading operations to a fuel assembly of a type for which no spare was available onsite, an alternate core loading scheme could have been determined. Any such changes would have been approved by the appropriate Westinghouse personnel. Core loading procedures specified the condition of fluid systems to prevent inadvertent changes in boron concentration of the reactor coolant; the movement of fuel to preclude the possibility of mechanical damage; the conditions under which loading could proceed; and the responsibility and authority for continuous and complete fuel and core component accountability.
preoperational test program. The duties and responsibilities of the startup


The following conditions were met prior to core loading:  
organization also included:  
: a. The reactor containment structure was complete and containment integrity had been demonstrated.
: a. Familiarization of support personnel with specific
: b. Fuel handling tools and equipment were checked out and operators familiarized in the use and operation of equipment. Inspections of fuel assemblies, rod cluster          control assemblies, and reactor vessel were          satisfactorily completed.


14.2-19    Rev. 0 WOLF CREEK      c. The reactor vessel and associated components were in a          state of readiness to receive fuel. The water level was maintained above the bottom of the nozzles and recirculation maintained to ensure the required boron concentration could be increased via the recirculation          path or directly to the open vessel.
tests.  
: b. Direction to support personnel and others during performance of tests including appropriate interface with station operators.
: c. Authority to disallow or terminate testing due to  


Criteria for safe loading required that loading operations stop immediately if any of the following conditions occur.  
conditions which could endanger personnel or equipment.  
: a. An unanticipated increase in the neutron count rates by a factor of two occurs on all responding nuclear channels during any single loading step after the initial nucleus of eight fuel assemblies is loaded.
: d. Identification of deficiencies that could adversely
: b. An unanticipated increase in the count rate by a factor          of five on any individual responding nuclear channel during any single loading step after the initial nucleus of eight fuel assemblies is loaded.
: c. An unanticipated decrease in boron concentration greater than 20 ppm is determined from two successive samples of the reactor coolant.


Loading operations could not be restarted until the situation was evaluated.
affect test performance.  
An alarm in the containment and main control room was coupled to the source range channels with a setpoint equal to or less than five times the current count rate. This alarm automatically alerts the loading operation personnel of high count rate, and an immediate stop of all operations would be required until the situation was evaluated. In the event the evacuation alarm was actuated during core loading and after it has been determined that no hazards to personnel exist, preselected personnel would be permitted to reenter the containment to evaluate the cause and determine future action.
: e. Assembly of test data and preparation of test reports


The core was assembled in the reactor vessel and submerged in the reactor grade water containing sufficient dissolved boric acid to maintain a calculated core effective multiplication factor of 0.95 or lower. The refueling pool could be wet or dry during initial core loading. Core moderator, chemistry conditions (particularly boron concentration) were prescribed in the core loading procedure document and verified by chemical analysis of moderator samples taken prior to and during core loading operations.  
for evaluation of test results by others.  


At least two artificial neutron sources were introduced into the core at specified points in the core during the loading program to ensure a detector response of at least 2 counts per second attributable to neutrons.
The Startup Organization was composed of system startup engineers, technicians,


14.2-20    Rev. 0 WOLF CREEK Core loading instrumentation consisted of two permanently installed source range (pulse type) nuclear channels and two temporary incore source range channels. A third temporary channel could also be used as a spare. The permanent channels, when responding, were monitored in the main control room, and the temporary channels were installed and monitored in the containment. At least one permanent channel was equipped with an audible count rate indicator.
planners, craft labor, and other support personnel. The Operating Agent
Both plant channels have the capability of displaying the neutron flux level on a strip chart recorder. The temporary channels indicated on scalers, and a minimum of one channel was recorded on a strip chart recorder. Normally minimum count rates of two counts per second attributable to core neutrons were required on at least two of the four (i.e. two temporary and two permanent source range detectors) available nuclear source channels at all times following installation of the initial nucleus of eight fuel assemblies. A response check of nuclear instruments to a neutron source was performed within 8 hours prior to loading of the core, or upon resumption of loading if delay was for more than 8 hours.
Fuel assemblies, together with inserted components (control rod assemblies, burnable, poison assemblies, source spider, or thimble plugging devices) were placed in the reactor vessel one at a time, according to a previously established and approved sequence developed to provide reliable core monitoring with minimum possibility of core mechanical damage. The core loading procedure documents prescribed the successive movements of each fuel assembly and its specified inserts from its initial position in the storage racks to its final position in the core. Fuel assembly status boards were maintained throughout the core loading operation.


An initial nucleus of eight fuel assemblies, one containing a neutron source, is the minimum source-fuel nucleus which permitted subsequent meaningful inverse count rate monitoring. This initial nucleus was determined by calculation to be markedly subcritical (Keff  0.95) under the required conditions of loading.
provided these personnel and used contractors to supply manpower for those positions that it could not staff. The staffing level for the Startup Organization increased as the test program progressed and construction
Each subsequent fuel addition was accompanied by detailed neutron count rate monitoring to determine that the just-loaded fuel assembly did not excessively increase the count rate and that the extrapolated inverse count rate ratio was behaving as expected. These results for each loading step were evaluated before the next fuel assembly was loaded. The final, as loaded, core configuration was subcritical (Keff < 0.95) under the required loading conditions. 


14.2-21    Rev. 0 WOLF CREEK 14.2.10.2 Initial Criticality  Prior to initial criticality, the following tests were performed and the results evaluated.
activities decreased. Typical schedules for the test program are given in  
: a. At the completion of core loading, the reactor upper internals and pressure vessel head were installed. A pressure test was conducted after filling, and venting was completed to check the leaktightness of the vessel head installation.
: b. Mechanical and electrical tests were performed on the control rod drive mechanisms. These tests included a complete operational checkout of the mechanisms and calibration of the individual rod position indicators.      c. Tests were performed on the reactor trip circuits to test manual trip operation, and actual control rod assembly drop times were measured for each control rod assembly. At all times that the control rod drive mechanisms were being tested, the boron concentration in the coolant was maintained so that the shutdown margin requirements specified in the Technical Specifications were met. During individual RCCA or RCC bank motion, source range instrumentation was monitored for unexpected changes in core reactivity.
: d. The reactor control and reactor protection systems were checked with simulated inputs to produce trip signals for various trip conditions.      e. A functional electrical and mechanical check was made of the incore nuclear flux mapping system near normal operating temperature and pressure.


Initial criticality was achieved by a combination of shutdown and control bank withdrawal and reactor coolant system boron concentration dilution. The plant conditions, precautions, and specific instructions for the approach to criticality were specified by approved procedures.
Section 14.2.11. Staffing and training of personnel involved in testing at


Initially, the shutdown and control banks of control rods were withdrawn incrementally in the normal withdrawal sequence, leaving the last withdrawn control bank partially inserted in the core to provide effective control when criticality was achieved. The boron concentration in the reactor coolant system was reduced and criticality achieved by boron dilution or by subsequent rod withdrawal following boron dilution. Throughout this period, samples of the primary coolant were obtained and analyzed for boron concentration.
WCGS were planned to provide sufficient manpower to support the testing


14.2-22    Rev. 0 WOLF CREEK Inverse count rate ratio monitoring using data from the normal plant source range instrumentation was used as an indication of the proximity and rate of approach to criticality. Inverse count rate ratio data was plotted as a function of rod bank position during rod motion and as a function of reactor makeup water addition during reactor coolant system boron concentration reduction.  
schedule.  


14.2.10.3  Low Power Testing  Following initial criticality, a program of reactor physics measurements was undertaken to verify that the basic static and kinetic characteristics of the core were as expected and that the values of the kinetic coefficients assumed in the safeguards analysis were conservative.
The Startup Organization reported administratively and technically to the  


Procedures specified the sequence of tests and measurements to be conducted and the conditions under which each was performed in order to ensure both safety of operation and the validity and consistency of the results obtained. If test results deviated significantly from design predictions, if unacceptable behavior had been revealed, or if unexplained anomalies had developed, the plant would have been brought to a safe stable condition and the situation reviewed to determine the course of subsequent plant operation.
Startup Manager; the duties performed by key individuals within the Startup
These measurements were made at low power and primarily at or near normal operating temperature and pressure. Measurements were made in order to verify the calculated values of control rod bank reactivity worths, the isothermal temperature coefficient under various core conditions, differential boron concentration reactivity worth, and critical boron concentrations as functions of control rod configuration. In addition, measurements of the relative power distributions were made, and concurrent tests were conducted on the instrumentation, including source and intermediate range nuclear channels.


Gamma and neutron radiation surveys were performed at selected points throughout the station. Periodic sampling was performed to verify chemical and radio-chemical analysis of the reactor coolant.  
Organization are summarized below.  


14.2.10.4 Power Level Ascension  After the operating characteristics of the reactor were verified by low power testing, a program of power level ascension brought the unit to its full rated power level in successive stages. At each successive stage, hold points were provided to evaluate and approve test results prior to proceeding to the next stage. The minimum test requirements for each successive stage of power ascension were specified in the initial startup test procedures.
14.2.2.2.1 Startup Manager


14.2-23    Rev. 0 WOLF CREEK Measurements were made to determine the relative power distribution in the core as functions of power level and control assembly bank position.
The Startup Manager had the authority and responsibility, as delegated by the  


Secondary system heat balance measurements ensured that the indications of power level were consistent and provide bases for calibration of the power range nuclear channels. The ability of the reactor coolant system to respond effectively to signals from primary and secondary instrumentation under a variety of conditions encountered in normal operations was verified.
Plant Manager, for the overall direction and administration of the functions


At prescribed power levels, the dynamic response characteristics of the primary and secondary systems were evaluated. System response characteristics were measured for design step load changes, rapid load reduction, and plant trips.  
and activities required to conduct the Startup Program. The responsibilities


Adequacy of radiation shielding was verified by gamma and neutron radiation surveys at selected points throughout the station at various power levels. Periodic sampling was performed to verify the chemical and radio-chemical analysis of the reactor coolant.
and duties of the Startup Manager also included:


14.2.11  TEST PROGRAM SCHEDULE
14.2-4                        Rev. 0 WOLF CREEK
: a. Development of plans and schedules regarding the status of the startup program.
: b. Review and approval of administrative and technical test


Detailed schedules for testing were prepared, reviewed, and revised on a continuing basis as plant construction progressed.
procedures and results.
: c. Continuing analysis of construction and equipment


Preoperational tests which were not performed according to schedule were reviewed on a case-by-case basis. Administrative procedures were established to ensure that all prerequisites were met before testing was initiated. Upon completion of all prerequisite tests applicable to a system or subsystem, a documented review was conducted by Start-up personnel to verify that appropriate documentation was available and that required prerequisite tests were satisfactorily completed. All deficiencies which would have prevented performance of preoperational tests or generated negative test results were identified and dispositioned prior to implementation of the preoperational tests.
installation schedules for compatibility with testing  


Preoperational testing was scheduled to commence approximately 18 months prior to fuel loading. The preoperational tests were performed and sequenced during this period as a function of system turnover, system interrelationships, and acceptance for testing.
schedules and recommendations for corrective actions to


Initial startup testing was scheduled to be conducted over a period of approximately 3 to 5 months, commencing with fuel loading. The sequential schedule for initial startup tests ensured, insofar as practicable, that test requirements were completed
minimize conflict.
: d. Review and submittal of design related problems


14.2-24    Rev. 0 WOLF CREEK prior to exceeding 25-percent power for all plant structures, systems, and components that are relied upon to prevent, limit, or mitigate the consequences of postulated accidents.
requiring engineering resolution, encountered by the  


The development of the test procedures was an ongoing process consisting of preparation, review, and revision. Preoperational test procedures were available for NRC review approximately 60 days prior to the performance of an individual test. If an individual test procedure was not available 60 days prior to the test, the NRC was notified of the test date and the date the test procedure was available. Initial startup test procedures were available for NRC review at least 60 days prior to fuel loading.
Startup Organization in accordance with the appropriate


14.2.12  INDIVIDUAL TEST DESCRIPTIONS
Startup Administrative Procedures.  
: e. Maintaining liaison with all organizations supporting


Test abstracts were provided for both safety-related and selected nonsafety-related preoperational tests. The abstracts included test prerequisites and summaries of test methods, objectives, and acceptance criteria.  
Startup and coordinating their activities.  


14.2.12.1  Safety-Related Preoperational Test Procedures  The following sections contain test abstracts used for safety- related preoperational tests. Table 14.2-1 provides an index of these tests.
14.2.2.2.2 Startup Section
The preoperational test procedures were designated SO3 (Safety- Related/Common to WCGS and Callaway), SU3 (Safety-Related/WCGS Specific), SO4 thru SO9 (Nonsafety-Related/Common to WCGS and Callaway) and SU4 thru SU9 (Nonsafety-Related/WCGS Specific) as appropriate.


14.2.12.1.1  Steam Dump System Preoperational Test (S-03AB01)
The Startup Section was comprised primarily of the System Test Group, the


14.2.12.1.1.1  Objectives
Electrical Test Group and the Instrumentation and Control Group which had
: a. To demonstrate the operability of the steam dump control          system control circuits in both the average temperature          and steam pressure modes of operation.
: b. To demonstrate the operation of the main steam dump valves and main steam cooldown valves, including valve response to safety signals.
: c. To verify the operation of the main steam line drain valves' control circuits, including valve response to a turbine trip signal.


14.2-25 Rev. 0 WOLF CREEK      d. To verify the operation of the main steam to turbine-          driven feedwater pump supply valves' control logics, including valve response to an auxiliary feedwater actuation signal (AFAS).
primary responsibility within the Startup Organization to perform testing.   
: e. To verify the operation of the main steam atmospheric          relief valves' control circuits. 14.2.12.1.1.2  Prerequisites
: a. Required component testing, instrument calibration, and system flushing/cleaning are completed.   
: b. Required electrical power supplies and control circuits are operational.


14.2.12.1.1.3  Test Method
This section also reviewed and recommended the acceptance of system or
: a. Operability of the steam dump control system control circuits is verified in both the average temperature and steam pressure modes.
: b. Operability of the main steam dump valves' and main          steam cooldown valves' control circuits is verified, including valve response to turbine impulse low pressure, low-low average temperature, and condenser shell high pressure signals.
: c. Operability of the main steam line drain valves' control circuits is verified, including valve response to a turbine trip signal.
: d. Operability of the main steam to turbine-driven auxiliary feedwater pump supply valves' control logics is verified, including valve response to an AFAS.
: e. Operability of the main steam atmospheric relief          valves' control circuits is verified.
14.2.12.1.1.4  Acceptance Criteria
: a. The response of the main steam dump valves and the main          steam cooldown valves to the associated turbine impulse low pressure, low-low average temperature, and condenser shell high pressure signals is in accordance with system design.
: b. The main steam line drain valves open on receipt of a turbine trip signal.


14.2-26 Rev. 13 WOLF CREEK      c. The main steam to turbine-driven auxiliary feedwater          pump supply valves open on receipt of an AFAS.
subsystem turnover documentation from Construction and coordinated system  
: d. The response of the main steam atmospheric relief          valves to pressure signals is in accordance with system design.


14.2.12.1.2  Main Steam Safety Valve Test (SU3-AB02) 14.2.12.1.2.1  Objectives
turnover and any subsequent system rework. It was responsible for preparing the


To verify the pressure relief setpoints of the main steam safety valves.  
test procedures, conducting the tests, and reporting the test results. For


NOTE:  This objective may be accomplished either by bench testing or with a pneumatic test device.
preoperational testing, this section documented the test results and presented


14.2.12.1.2.2  Prerequisites The following prerequisites apply when a pneumatic test      device is used.
them before the Joint Test Group for its review and recommendation for approval.  
: a. Required instrument calibration is complete.
: b. Hot Functional Testing is in progress.
: c. A Source of compressed air is available to provide air to the air set pressure device installed on the valve under test.  


The following prerequisites apply when bench testing is performed.  
14.2.2.2.3  Operations Technical Support Section
: a. Bench testing facility is available.       b. An approved WCGS procedure is available to accomplish bench testing.
: c. A source of compressed gas is available to provide pressure to the valve under test.  


14.2.12.1.2.3  Test Method
The Operations Technical Support Section was responsible for providing


The following test method applied when a pneumatic test device is used.
technical support to the Startup Section during testing. The areas in which


Main steam pressure is adjusted within the required range, and air is admitted to the air set pressure device on the safety valve under test. Actual lift pressure is calculated, using the steam pressure and converted air pressure at the time of lift.
this support was given were instrumentation and control, chemistry, computer,  


14.2-27 Rev. 13 WOLF CREEK      The following test applies when bench testing is performed.
health physics and reactor engineering.  
With the main steam safety valve mounted on the bench test facility, the spring assembly is preheated and the safety valve is pressurized with compressed gas. Actual set      pressure is determined at the time of lift.  


14.2.12.1.2.4  Acceptance Criteria
This section was a permanent part of the WCGS operating staff until these functions were incorporated into other sections. They were involved in training, procedure preparation, and general preparation for support of plant operations.  


Each main steam safety valve lifts within its respective setpoint tolerance.  
14.2.2.2.4  Startup Scheduling Section


14.2.12.1.3  Main Steam Line Isolation Valve Test (S-03AB03)
The Startup Scheduling Section prepared and updated the Startup Schedule, utilizing input from cognizant system startup engineers and the construction


14.2.12.1.3.1  Objectives      a. To verify the response of the main steam bypass, drain, and auxiliary feedwater turbine warmup valves to steam line isolation signals.
organizations.  
: b. To demonstrate the operability of the main steam isolation valve control circuits, including control circuit response to a steam line isolation signal (SLIS).  


14.2.12.1.3.2  Prerequisites
14.2-5                        Rev.7 WOLF CREEK 14.2.2.2.5 Quality Control Section
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits          are operational.
: c. The main steam line isolation valve accumulators are charged, and the associated hydraulic systems are operational.


14.2.12.1.3.3  Test Method
The Quality Control Section formulated and implemented the Startup Quality


An SLIS is initiated, and the response of the main steam bypass, main steam drain, and auxiliary feedwater turbine warmup valves is verified.
Control Program. This program monitored the conduct of the Startup


14.2.12.1.3.4  Acceptance Criteria
Organization's testing activities by reviewing administrative and technical test procedures, by witnessing major evolutions and selected flushes, hydros,  
: a. The main steam bypass, drain, and auxiliary feedwater turbine warmup valves close on receipt of an SLIS.


14.2.12.1.4  Main Steam System Preoperational Test (S-03AB04)
and preoperational tests and by reviewing turnover packages. The Quality


14.2-28 Rev. 0 WOLF CREEK 14.2.12.1.4.1  Objectives 
Control Section was under the direction of the Director - Quality. They
: a. To determine, during hot functional testing, the operating times of the main steam isolation valves, main steam bypass valves, main steam dump valves, main          steam cooldown valves, and the main steam atmospheric          relief valves. 
: b. To verify the response of the main steam isolation valves to steam line isolation signals.
14.2.12.1.4.2  Prerequisites
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. Hot functional testing is in progress.
: d. The condenser is available to receive steam from the          main steam system.  


14.2.12.1.4.3  Test Method
provided support to the Startup Manager.  
: a. The main steam isolation valves, main steam bypass valves, main steam dump valves, main steam cooldown valves, and the main steam atmospheric relief valves          are operated, and operating times are recorded. 
: b. An SLIS is initiated, and the response of the main steam isolation valves is verified.
14.2.12.1.4.4  Acceptance Criteria
: a. The operating times of the main steam isolation valves, main steam dump valves, main steam bypass valves, main steam cooldown valves, and the main steam atmospheric          relief valves are within design specifications. 
: b. The main steam isolation valves close on receipt of a steam line isolation signal.
14.2.12.1.5  Main Feedwater System Preoperational Test (S-03AEO1)


14.2.12.1.5.1 Objectives
14.2.2.2.6 Startup Technical Support Section
: a. To demonstrate the operation of the feedwater system valves and to verify the response of the feedwater system valves to a feedwater isolation signal (FIS).


14.2-29 Rev. 13 WOLF CREEK      b. To perform the initial operation of the steam generator          feedwater pumps (SGFP).
The Startup Technical Support Section was responsible for providing technical


14.2.12.1.5.2  Prerequisites
support to the Startup Organization during the conduct of the Startup Program.   
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The closed cooling water system is available to provide cooling water to the SGFP lube oil coolers.
: d. The compressed air system is available to provide air to          system air-operated valves. 
: e. The steam seal system is available to provide seal steam and packing exhaust for the SGFPs.
: f. The main turbine is available for turning gear operation.
: g. The condensate system is available to supply suction for the SGFPs.
: h. The main condenser is available to receive SGFP turbine exhaust.
: i. The auxiliary steam system is available to provide steam          flow to the SGFP turbines.
14.2.12.1.5.3 Test Method
: a. Feedwater system valves are operated, and the proper response of required system valves to an FIS is verified.
: b. The turbine-driven SGFPs are operated as limited by steam, and operating data are recorded.
: c. The motor-driven SGFP is operated, and operating data are recorded.


14.2.12.1.5.4  Acceptance Criteria
Their responsibilities included test procedure and test results review and approval, technical planning of major milestone activities, startup organization training and startup program compliance to FSAR commitments.  
: a. The feedwater control valves, steam generator feedwater isolation valves, feedwater chemical injection isolation valves, and feedwater bypass control valves close on receipt of an FIS.  


14.2-30    Rev. 0 WOLF CREEK      b. The closing time of the feedwater isolation valves is          within design specifications.
14.2.2.3  Operating Staff The WCGS operating staff was involved in the startup program in several
: c. The performance of the motor-driven SGFP is within design specifications.
14.2.12.1.6  Steam Generator Level Control Test (S-03AE02)


14.2.12.1.6.1  Objectives
capacities throughout preoperational and initial startup testing. This
: a. To demonstrate the operability of the feedwater control valves (FWCVs).
: b. To demonstrate the operability of the FWCV bypass valves.      c. To demonstrate the response of the FWCVs and bypass valves to signals generated by the steam generator level control system.  


14.2.12.1.6.2  Prerequisites
involvement included review of test procedures and results and the direct participation in test activities. Operating staff personnel were utilized by
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.  


14.2.12.1.6.3  Test Method
the startup organization as required for performance of testing under the
: a. The FWCVs are operated from their respective          controllers, and the FWCVs' response to feedwater flow, steamline flow, and steam generator level is verified.
: b. The FWCV bypass valves are operated from their respective controllers, and their response to steam generator level and neutron flux signal is verified.


14.2.12.1.6.4  Acceptance Criteria
direction of system startup engineers. Station operators assisted system  
: a. The response of the FWCVs to feedwater flow, steamline flow, and steam generator level is in accordance with system design.
: b. The response of the FWCV bypass valves to steam generator level and neutron flux signal is in accordance with system design.


14.2-31    Rev. 0 WOLF CREEK 14.2.12.1.7 Auxiliary Feedwater Motor-Driven Pump and Valve              Preoperational Test (S-03ALOl)
startup engineers in performing tests and in the routine operations of systems.   


14.2.12.1.7.1  Objectives To demonstrate the operability of the motor-driven auxiliary feedwater pumps, determine by flow test their ability to supply water to the steam generators, and verify their response to safety signals. The operation of system motor-operated valves, including their response to safety signals, is also verified.
The operating staff directed the fuel loading and was responsible for plant


14.2.12.1.7.2  Prerequisites
operation during initial startup testing.  
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits          are operational.
: c. The condensate storage tank contains an adequate supply of demineralized water for the performance of this test.
: d. The steam generators are available to receive water from the auxiliary feedwater system.  


14.2.12.1.7.3  Test Method
The operating staff was divided into sections headed by the Superintendent
: a. Performance characteristics of the motor-driven auxiliary feedwater pumps are verified while discharging to the steam generators.
: b. System component control circuits are verified,          including the operation of the motor-driven auxiliary feedwater pumps and system valves on receipt of safety signals.


14.2.12.1.7.4  Acceptance Criteria
Operations, Superintendent of Maintenance, Superintendent of Plant Support, Superintendent of Technical Support, Nuclear Training Manager and Superintendent Regulatory Quality and Administrative Services. These section
: a. Motor-driven auxiliary feedwater pump performance characteristics must be within design specifications.
: b. Motor-driven auxiliary feedwater pumps automatically start on receipt of an engineered safety features actuation signal (ESFAS) in the absence of an SIS signal and a Class IE 4.16 kV bus undervoltage signal.
: c. Auxiliary feedwater suction valves from essential service water system open, and suction valves from condensate storage tank close, on condensate storage tank low-suction-pressure signals, coincident with an auxiliary feedwater pump ESFAS.  


14.2-32    Rev. 0 WOLF CREEK 14.2.12.1.8 Auxiliary Feedwater Turbine-Driven Pump and Valve              Preoperational Test (SU3-AL02)
superintendents reported administratively and technically to the Plant Manager.   


14.2.12.1.8.1  Objectives
The duties and responsibilities of the operating staff during plant operations
: a. To verify the auxiliary feedwater pump turbine mechanical trip and throttle valve automatic operation on an auxiliary feedwater actuation signal (AFAS).
: b. To perform the initial coupled operation of the turbine-driven auxiliary feedwater pump. Full flow characteristics of the turbine-driven pump will be demonstrated during hot functional testing.
: c. To perform five consecutive, successful, cold starts of          the turbine-driven auxiliary feedwater pumps.
14.2.12.1.8.2  Prerequisites
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.


b    Required electrical power supplies and control circuits are operational.
are described in Chapter 13.0.  
: c. The steam generators are available to receive water from the auxiliary feedwater pumps.
: d. The steam generator blowdown system is available to maintain the normal operating levels in the steam          generators during auxiliary feedwater pump operation.
: e. The auxiliary steam system is available to supply steam to the auxiliary feedwater pump turbine.
: f. For the performance characteristic test of this pump, hot functional testing (HFT) is in progress.  


14.2.12.1.8.3 Test Method
14.2.2.4 Major Participating Organizations 14.2.2.4.1  Bechtel
: a. An AFAS is simulated, and opening of the mechanical trip and throttle valve is verified.  
: b. The turbine-driven auxiliary feedwater pump is operated during HFT, and performance characteristics are recorded.
: c. The ability of the turbine-driven auxiliary feedwater pumps to start successfully five consecutive times from cold conditions is verified.  


14.2-33    Rev. 0 WOLF CREEK 14.2.12.1.8.4  Acceptance Criteria 
Bechtel provided engineering input into the startup program. Bechtel was contacted to provide personnel experienced in nuclear plant startup to augment
: a. The auxiliary feedwater pump mechanical trip and throttle valve opens automatically on an AFAS.
: b. Operating characteristics of the turbine-driven auxiliary feedwater pump are in accordance with design.
: c. The turbine driven auxiliary feedwater pump starts successfully five consecutive times from a cold start.


14.2.12.1.9  Auxiliary Feedwater Motor-Driven Pump Endurance Test (SU3-AL03)
the startup organization for WCGS. Bechtel employees were assigned consistent


14.2.12.1.9.1  Objectives      a. To demonstrate that the motor-driven auxiliary feedwater pumps can operate for 48 continuous hours without exceeding any of their limiting design specifications.
with the startup program schedules.  
: b. To demonstrate that the motor-driven auxiliary feedwater pumps can operate for 1 hour after a cooldown from the 48-hour test.
: c. To demonstrate that the room environmental conditions are not exceeded during the 48-hour test.  


14.2.12.1.9.2 Prerequisites
14.2-6                        Rev. 12 WOLF CREEK 14.2.2.4.2 Daniel International Corporation (DIC)
: a. Required component testing, instrument calibration and          system flushing/cleaning are complete.   
: b. Required electrical power supplies and control circuits are operational.
: c. The appropriate auxiliary feedwater pump room coolers are operational.
: d. The condensate storage tank is available as a water source and to receive recirculation flow.


14.2.12.1.9.3  Test Method
DIC, as contractor for WCGS, was responsible for the construction completion,


Each motor-driven pump is started and operated for 48 hours after reaching rated speed and rated discharge pressure and flow, or a greater pressure and less flow. During the endurance run, pump- operating data and the pump room environmental conditions are recorded. At the completion of each endurance test, the pump is cooled for 8 hours and until pump data returns to within 20 F of the original pretest data. The pump is then started and operated for 1 hour.
and orderly release of components and turnover of systems to KG&E consistent


14.2-34    Rev. 0 WOLF CREEK 14.2.12.1.9.4  Acceptance Criteria 
with the startup program schedules. This responsibility included:
: a. The operating parameters (vibration, bearing temperatures, etc.) of each motor-driven auxiliary feedwater pump do not exceed the design specifications. 
: a. Certification that documentation for components, systems
: b. The environmental conditions of each motor-driven auxiliary feedwater pump room do not exceed the design specifications.


14.2.12.1.10  Auxiliary Feedwater System Water Hammer Test (S-03AL04)
and structures, as required by purchase and installation


14.2.12.1.10.1  Objectives To demonstrate that the injection of auxiliary feedwater at rated flow into a steam generator at or near normal operating temperatures will not cause damaging water hammer to the steam generators and/or feedwater system.
specifications, is complete and available; and the  


14.2.12.1.10.2  Prerequisites
maintenance of these certification files which provide
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The steam generators are at or near normal operating temperature.
: d. The condensate storage tank is available as a water          source.


14.2.12.1.10.3  Test Method
the documentary evidence, and
: b. Provision of dedicated craft manpower support as


Auxiliary feedwater is injected into each steam generator. The feedwater system piping and the steam generators are monitored visually and audibly to verify that no damaging water hammer occurs.  
required for performance of the startup program.  


14.2.12.1.10.4 Acceptance Criteria
14.2.2.4.3 Westinghouse Electric Corporation
 
Westinghouse, as the Nuclear Steam Supply System (NSSS) supplier, was
 
responsible for providing technical assistance to KG&E during preoperational


No damaging water hammer occurs.  
and initial startup testing performed on the NSSS equipment and systems.


14.2.12.1.11  Auxiliary Feedwater Turbine-Driven Pump Endurance Test (SU3-AL05)
Technical assistance is defined as technical guidance, advice and counsel based


14.2.12.1.11.1  Objectives
on current engineering, installation, and testing practices. Westinghouse


14.2-35    Rev. 0 WOLF CREEK      a. To demonstrate that the turbine-driven auxiliary          feedwater pump can operate for 48 continuous hours without exceeding any of its limiting design specifications.
employees were assigned consistent with the Startup Program schedules. This
: b. To demonstrate that the turbine-driven auxiliary feedwater pump can operate for 1 hour after a cool down from the 48-hour test.
: c. To demonstrate that the room environmental conditions are not exceeded during the 48-hour test.  


14.2.12.1.11.2  Prerequisites
responsibility included:
: a. Required component testing, instrument calibration and          system flushing/cleaning are complete. 
: a. Assignment of personnel to provide advice and assistance
: b. Required electrical power supplies and control circuits are operational.
: c. The appropriate auxiliary feedwater pump room coolers are operational.
: d. The condensate storage tank is available as a water source and to receive recirculation flow.
: e. A steam source is available.


14.2.12.1.11.3  Test Method The pump is started and operated for 48 hours after reaching rated speed and rated discharge pressure and flow, or a greater pressure and less flow. The turbine-driven auxiliary feedwater pump operating steam is as close to normal operating temperature as possible and is at least 400 F. During the endurance run, pump-operating data and the pump room environmental conditions are recorded. At the completion of the endurance test, the pump is cooled for 8 hours and until pump data returns to within 20 F of the original pretest data.
to KG&E for test and operation of all equipment and  
The pump is then started and operated for 1 hour.


14.2.12.1.11.4  Acceptance Criteria
systems in the Westinghouse area of responsibility.  
: a. The operating parameters (vibration, bearing temperatures, etc.) do not exceed the design specifications.  
: b. Supportive engineering services, including special assistance during the initial fuel loading.  
: b. The environmental conditions of the turbine-driven auxiliary feedwater pump room do not exceed the design specifications.  
: c. Providing test procedure outlines and technical


14.2-36    Rev. 0 WOLF CREEK 14.2.12.1.12  Reactor Coolant Pump Initial Operation (S-03BB01) 14.2.12.1.12.1  Objectives
assistance for tests of Westinghouse furnished


To demonstrate the operating characteristics of the reactor coolant pumps and verify the operation of their associated oil lift pumps.  
components and systems.  


14.2.12.1.12.2 Prerequisites
14.2.2.4.4 General Electric (GE)
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The chemical and volume control system is available to          provide seal water to the reactor coolant pump seals.
: d. The component cooling water system is available to supply cooling water to the reactor coolant pumps.


14.2.12.1.12.3  Test Method
GE is the supplier and installer of the turbine generator. GE supplied


The reactor coolant pumps and associated oil lift pumps are operated, and pump operating data are recorded.  
technical support for the startup and testing of the turbine generator. Some


14.2.12.1.12.4  Acceptance Criteria
of the prerequisite testing (i.e., turbine oil flush) was performed by the GE


Reactor coolant pump and oil lift pump operating characteristics are within design specifications. 14.2.12.1.13  Pressurizer Relief Tank Cold Preoperational Test (SU3-BB02)
personnel. GE has supplied recommended procedures for starting, operating, and  


14.2.12.1.13.1  Objectives
shutting down equipment in their technical manuals for the turbine generator.  


To demonstrate that the reactor makeup water system can supply design pressurizer relief tank (PRT) spray flow against design backpressure. The operation of the PRT nitrogen isolation valves, including their response to a containment isolation signal, is also verified.
14.2-7                        Rev. 0 WOLF CREEK 14.2.2.5  Quality Assurance The KG&E Quality Branch was responsible for assuring the quality of  


14.2.12.1.13.2  Prerequisites
construction, plant testing, and operations activities in accordance with the
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.


14.2-37    Rev. 0 WOLF CREEK      c. The reactor makeup water system is available to supply          water to the PRT.
WCGS Quality Program which is described in the Quality Program Manual.  
: d. The service gas system is available to pressurize the PRT.
14.2.12.1.13.3  Test Method
: a. With a design backpressure in the PRT, a reactor makeup water pump is operated to obtain the spray flow to the PRT.
: b. The response of the PRT nitrogen isolation valves to a containment isolation signal is verified.
14.2.12.1.13.4  Acceptance Criteria 
: a. The reactor makeup water system supplies the design spray flow to the PRT with design backpressure in the PRT.
: b. PRT nitrogen isolation valves close on receipt of a containment isolation signal. Valve closure times are within design specifications.  


14.2.12.1.14 RTD Bypass Flow Measurement (SU3-BB03)
14.2.2.6 Qualifications of Key Personnel


At WCGS, test S-07BB01 (USAR Section 14.2.12.3.3) was used to satisfy the requirement for verification of design specifications.
The qualifications for key plant operating personnel are described in Chapter
14.2.12.1.15  Pressurizer Pressure Control Test (S-03BB04) 14.2.12.1.15.1  Objectives


To demonstrate the stability and response of the pressurizer pressure control system, including the verification of pressurizer pressure alarm and control functions.
13.0.
The qualification requirements for startup personnel involved in the WCGS


14.2.12.1.15.2  Prerequisites
startup program conformed to capability levels per ANSI N45.2.6 and Regulatory
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The plant is at normal operating temperature and pressure with all reactor coolant pumps running, and hot functional testing is in progress.


14.2-38    Rev. 0 WOLF CREEK 14.2.12.1.15.3  Test Method 
Guide 1.8 recommendations.  
: a. Pressurizer pressure is varied, and the ability of the pressurizer pressure control system to automatically control and stabilize pressurizer pressure is verified. 
: b. Pressurizer pressure is varied, and pressurizer pressure control system alarm and control setpoints are verified.  


14.2.12.1.15.4  Acceptance Criteria
All test personnel were indoctrinated in the startup administrative procedures,  
: a. The pressurizer pressure control system responds, in accordance with system design, to an increase and decrease in system pressure.
: b. Pressurizer pressure control system alarm and control          setpoints are within design specifications.


14.2.12.1.16  Reactor Coolant System Hot Preoperational Test (S-03BB05)
methods and controls.  


14.2.12.1.16.1 Objectives
14.2.3 TEST PROCEDURES
: a. To operate the reactor coolant system at full flow conditions for a minimum of 240 hours to provide the necessary vibration cycles on the vessel's internal components prior to their inspection at core loading.
: b. To provide coordination and initial conditions necessary for the conduct of those preoperational tests to be          performed during heatup, normal operating temperature          and pressure, and cooldown of the reactor coolant system.


14.2.12.1.16.2  Prerequisites
The Initial Test Program was conducted in accordance with detailed preoperational and initial startup test procedures. KG&E maintained the overall responsibility for test procedure preparation, review, and approval
: a. The reactor coolant system cold hydrostatic test is complete.  
: b. The reactor vessel internals and head are installed, and the vessel is available to support this test.
: c. All systems and components required to support heatup, operations at normal temperature and pressure, and cooldown of the reactor coolant system are available.
: d. Required instrument calibration is complete.


14.2-39    Rev. 0 WOLF CREEK      e. The examination of the reactor internals in accordance          with Section 3.9(N).2.4, is complete
during the preparational stages. KG&E was responsible for final procedure


14.2.12.1.16.3  Test Method
revision, review, and approval. These activities were completed in a timely
: a. The reactor coolant system is operated at full flow conditions for a minimum of 240 hours.
: b. Those preoperational tests required to be performed during heatup, normal operating temperature and pressure, and cooldown of the reactor coolant system are completed, as coordinated by this test.


14.2.12.1.16.4  Acceptance Criteria The reactor coolant system has operated at full flow conditions for a minimum of 240 hours.
fashion to ensure that the approved procedures for satisfying FSAR testing


Notes:  1. The acceptance criteria for individual systems are a part of the individual test procedures sequenced by this procedure.
equipment commitments were available for review approximately 60 days prior to
: 2. A post-hot functional examination of the reactor internals is performed as described in Section 3.9(N).2.4.


14.2.12.1.17  Thermal Expansion (S-03BB06)
scheduled implementation or fuel load for preoperational and initial startup


14.2.12.1.17.1  Objectives To verify that during heatup and cooldown of the reactor coolant system the associated components, piping, support, and restraint deflections are unobstructed and within design specifications.
tests, respectively. Preoperational and initial start-up testing commitments


14.2.12.1.17.2  Prerequisites
not available for review approximately 60 days prior to scheduled
: a. This test is conducted in conjunction with hot functional testing.
: b. Supports, restraints, and hangers are installed and reference points and predicted movements established.
: c. Required instrument calibration is complete.


14.2.12.1.17.3  Test Method
implementation or fuel load, respectively, were handled on a case- by-case


During the reactor coolant system heatup and cooldown, deflection data are recorded.  
basis.  


14.2-40    Rev. 0 WOLF CREEK 14.2.12.1.17.4  Acceptance Criteria 
The following sections describe the general methods employed to control
: a. Unrestricted expansion and movements are verified to be within design specifications.
: b. Components, piping, supports, and restraints return to their baseline cold position in accordance with system design.


14.2.12.1.18  Pressurizer Level Control Test (S-03BB07)
procedure development and review, and they also describe the responsibilities


14.2.12.1.18.1  Objectives
of the various organizations which participated in this process. The detailed controls and methods were described in the startup administrative procedures.  


To demonstrate the stability and response of the pressurizer level control system, including the verification of pressurizer level alarm and control functions.
14.2.3.1  Procedure Preparation Test procedures for the powerblock systems and components were developed by
14.2.12.1.18.2  Prerequisites
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The letdown and charging portions of the chemical and volume control system are available to vary pressurizer level.
: d. The plant is at normal operating temperature and          pressure, and hot functional testing is in progress.
14.2.12.1.18.3 Test Method
: a. Pressurizer level is varied and the ability of the pressurizer level control system to automatically control and stabilize pressurizer level is verified.
: b. Pressurizer level is varied, and pressurizer level control system alarm and control setpoints are verified.


14.2.12.1.18.4  Acceptance Criteria
Westinghouse and Bechtel. Bechtel also prepared test procedures for the site
: a. The response and stability of the pressurizer level control system are within design specifications.
: b. The pressurizer level control system alarm and control functions are within design specifications.


14.2-41    Rev. 0 WOLF CREEK 14.2.12.1.19  Pressurizer Heater and Spray Capability Test               (SU3-BB08)
safety-related systems and components. Test procedures for the site nonsafety-related systems and components were developed by various entities as


14.2.12.1.19.1 Objectives To determine the electrical capacity of the pressurizer heaters, and the rate of pressure increase from the operation of all pressurizer heaters.  
coordinated by KG&E.  


14.2.12.1.19.2  Prerequisites
14.2-8                        Rev. 21 WOLF CREEK The format and content of the test procedures developed for the standard plant and safety-related site systems and components reflected the guidance provided
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.      c. The plant is at normal operating temperature and pressure with all reactor coolant pumps running, and hot functional testing is in progress.


14.2.12.1.19.3  Test Method
in Regulatory Guide 1.68. The procedures contained as a minimum the following
: a. Pressurizer heaters are energized, and heater capacity is calculated.
: b. With the pressurizer spray valves closed, all pressurizer heaters are energized, and the time to reach a 2,300 psig system pressure is measured and recorded.


14.2.12.1.19.4  Acceptance Criteria      a. The capacity of the pressurizer heaters is within design limits.
sections:  
: b. The pressurizer pressure response to the actuation of all pressurizer heaters is within design limits.


14.2.12.1.20 Reactor Coolant System Flow Measurement Test (SU3-BB09)
1.0 Objectives


At WCGS, Test S-07BB03 (USAR Section 14.2.12.3.5) is used to satisfy the requirements for verification of design specifications.
The objectives section identified the general results to  


14.2.12.1.21  Reactor Coolant System Flow Coastdown Test (SU3-BB10)
be accomplished by the test.  


14.2-42    Rev. 0 WOLF CREEK At WCGS, Test S-07BB04 (USAR Section 14.2.12.3.6) is used to satisfy the requirements for verification of design specifications.
2.0  Acceptance Criteria


14.2.12.1.22  Reactor Coolant System Hydrostatic Test (S-03BBll) 14.2.12.1.22.1  Objectives
The acceptance criteria section clearly defined


To verify the integrity and leaktightness of the reactor coolant system and the high-pressure portions of associated systems.
quantitative and/or qualitative criteria against which


14.2.12.1.22.2  Prerequisites
the success or failure of the test procedure is judged.
: a. Required system flushing/cleaning are complete.
3.0 References
: b. The reactor coolant pumps are available to support this          test. 
: c. The reactor vessel's lower internals, upper internals, filter assembly, and the closure head are installed.
The studs are tensioned to design value for the associated hydrostatic test pressure
: d. Temporary temperature instrumentation is installed for measuring the temperature of the steam generator tube sheets, the bottom of the pressurizer, and the closure flange of the reactor vessel.
: e. A charging pump or test pump is available to pressurize the system.  
: f. Required instrument calibration is complete.
14.2.12.1.22.3 Test Method


The minimum temperature for pressurizing the system is established. The reactor coolant pumps are operated as required to establish the required temperature. The system is then pressurized to test pressure, and system welds, flanges, piping, and components are monitored for leakage.
The references section identified those FSAR sections,  


14.2.12.1.22.4  Acceptance Criteria
vendor manuals, drawings, etc. that were pertinent to


The reactor coolant system and associated high-pressure systems are verified leaktight in accordance with the requirements of the ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Components," through the Winter 1975 Addenda.
the performance and/or development of the test


14.2.12.1.23  Pressurizer Continuous Spray Flow Verification Test (SU3-BB12)
procedure.  


14.2-43    Rev. 0 WOLF CREEK At WCGS, Test S-07BB05 (USAR Section 14.2.12.3.7) was used to satisfy the requirements for verification of design specifications.
4.0 Test Equipment


14.2.12.1.24  Pressurizer Relief Valve and PRT Hot Preoperational Test (S-03BB13) 14.2.12.1.24.1  Objectives
The test equipment section identified temporary


To demonstrate that the operating times of the pressurizer power- operated relief valves are within design specifications. The ability of the reactor coolant drain tank portion of the liquid radwaste system to cool down the pressurizer relief tank (PRT) at the design rate is also verified.
equipment required to conduct the test procedure and/or


14.2.12.1.24.2  Prerequisites
collect data.  
: a. Required component testing and instrument calibration          are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The PRT is at a normal operating level and is aligned for normal operation.
: d. The liquid radwaste system is available to cool down the PRT via the reactor coolant drain tank heat exchanger.
: e. The plant is at normal operating temperature and pres-sure, and hot functional testing is in progress.
14.2.12.1.24.3  Test Method 
: a. Pressurizer power-operated relief valves are operated, and opening times recorded.
: b. Following the operation of the pressurizer power-operated relief valves, the PRT is cooled down via the reactor coolant drain tank heat exchanger, and the cooldown rate is calculated and recorded.  


14.2.12.1.24.4 Acceptance Criteria
5.0 Notes and Precautions The notes and precautions sections listed limitations
: a. Power-operated relief valve operating times are within design specifications.


14.2-44    Rev. 0 WOLF CREEK      b. The reactor coolant drain tank portion of the liquid          radwaste system cools down the PRT at a rate within design specifications.
and precautions necessary to ensure personnel and


14.2.12.1.25  Reactor Coolant Loop Vibration Surveillance Test (S-              03BB14)
equipment safety. Additional instructions needed to


14.2.12.1.25.1  Objectives
clarify the test procedure were also listed in this


To verify that the dynamic effects experienced during reactor coolant loop steady flow and reactor coolant loop pump transients as measured during hot functional testing (HFT) do not exceed acceptance criteria for the primary loop piping and components.  
section.  


14.2.12.1.25.2 Prerequisites       a. Hot functional testing is in progress.
6.0 Prerequisites  
: b. Reference points for vibrational measurement of the reactor coolant piping and components are established.
: c. All subject systems are available for the specified dynamic operation.
: d. Required instrument calibration is complete.


14.2.12.1.25.3  Test Method
The prerequisites section identified those prerequisite
: a. The systems are aligned for the specified dynamic operation.      b. The specified dynamic event is initiated and the reactor coolant piping and component responses are monitored.


14.2.12.1.25.4  Acceptance Criteria
tests and initial conditions that had to be completed


The measured deflections for each of the test measurement points are within a specified percent of the calculated reference deflections.
and/or satisfied prior to the performance of the test  


14.2.12.1.26  Leak Detection System Preoperational Test (SU3-BB15A)
procedure.  


14.2.12.1.26.1 Objectives
7.0 Test Procedure
: a. To determine, during hot functional testing, the amount of identified and unidentified leakage from the reactor coolant system and verify that the leakage is within design limits.


14.2-45    Rev. 0 WOLF CREEK      b. To demonstrate the ability to detect an increase in          reactor coolant system leakage.
The test procedure section provided a detailed step-by-  


14.2.12.1.26.2  Prerequisites
step test method and instructions for data collection.  
: a. Required instrument calibration is complete.
: b. Hot functional testing is in progress, and the reactor coolant system is at normal operating temperature and pressure.
: c. The volume control tank contains an adequate supply of water to support this test.
: d. The reactor coolant drain tank and associated pumps are          available to support this test.
14.2.12.1.26.3  Test Method
: a. The reactor coolant system identified and unidentified leakage rates are determined by monitoring the reactor coolant system water inventory.
: b. A known leakage rate is initiated, and the ability to detect an increase in leakage is verified.  


14.2.12.1.26.4  Acceptance Criteria
All nonstandard arrangements required by the test
: a. Reactor coolant system identified and unidentified leakage is within design limits.      b. The ability to detect an increase in reactor coolant system leakage is verified.


14.2.12.1.27  Leak Detection System Preoperational Test (SU3-BB15B)
procedure section were restored either in the test


14.2.12.1.27.1  Objectives
procedure section or the system restoration section.  
: a. To demonstrate the operation of the leak detection system and to verify the ability of the system to detect leakage within the required time limit as specified by design.
: b. The operation of the containment particulate and radioactive gas monitoring portions of the Leak Detection System are verified in SU4-SP01, Process Radiation Monitoring System Preoperational Test.  


14.2-46    Rev. 0 WOLF CREEK 14.2.12.1.27.2  Prerequisites  
14.2-9                        Rev. 0 WOLF CREEK 8.0 Test Data Sheets
: a. Required component testing and instrument calibration are complete.
: b. The containment normal sumps, instrument tunnel sump, floor drain tank, auxiliary building sump and associated pumps are available to support this test.


14.2.12.1.27.3  Test Method
The test data sheet section provided specific forms for
: a. A known simulated leakage is initiated, and the ability of the system to detect the leakage within the design time is verified.
14.2.12.1.27.4  Acceptance Criteria 
: a. The ability of the leak detection system to detect a leak within the design time is verified.


14.2.12.1.28  RTD/TC Cross Calibration (S-03BB16)
data collection. Additional instructions, if necessary,


14.2.12.1.28.1  Objectives
were also identified for each data sheet.  


To provide a functional checkout of the reactor coolant system resistance temperature detectors (RTDs) and incore thermocouples and to generate isothermal cross-calibration data for subsequent correction factors to indicated temperatures.  
9.0  System Restoration


14.2.12.1.28.2  Prerequisites      a. Required component testing and instrument calibration are complete.
The system restoration section returned the system to a  
: b. Required electrical power supplies and control circuits are operational.
: c. Initial plant heatup, during hot functional testing, is in progress, and all reactor coolant pumps are operating.


14.2.12.1.28.3  Test Method
safe operating or standby condition. Instructions for


At various temperature plateaus, RTD and incore thermocouple data are recorded.
the removal and/or return of system temporary
Isothermal cross-calibration correction factors for individual thermocouples and the installation corrections for individual RTDs are determined.


14.2-47    Rev. 0 WOLF CREEK 14.2.12.1.28.4  Acceptance Criteria 
modifications required by the prerequisite and/or test
: a. Individual RTD readings are within the design specifications.
: b. The installation corrections of the RTDs are within design specifications.


14.2.12.1.29  Chemical and Volume Control System Major Component Test (S-03BG01)
procedure sections were clearly defined.  


14.2.12.1.29.1  Objectives
The procedural sections included, as applicable, appropriate requirements for initials and/or signatures to control the performance and sequencing of the test.  


To demonstrate the operation of the centrifugal charging pumps and associated minimum flow valves, including their response to safety signals.
The test procedures were prepared using the latest design information available  
14.2.12.1.29.2  Prerequisites
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The refueling water storage tank contains an adequate supply of demineralized water for the performance of this test.
: d. The component cooling water system is available to          provide cooling water to the centrifugal charging pump          oil coolers.


14.2.12.1.29.3  Test Method
and functional requirements provided by the design engineers. This information
: a. Centrifugal charging pumps are operated, and performance characteristics are verified.
: b. Centrifugal charging pump and minimum flow valve control logics are verified, including their response to safety signals.  


14.2.12.1.29.4  Acceptance Criteria
was utilized in developing the detailed test methods which verified the ability
: a. Centrifugal charging pump performance characteristics are within design specifications.
: b. Each centrifugal charging pump receives a start signal from the load sequencer.


14.2-48    Rev. 0 WOLF CREEK      c. If a safety injection signal is present, a centrifugal          charging pump minimum flow valve will open if the associated pump flow is low and will close if the associated pump flow is above the minimum flow requirement of the pump.
of systems and components to function within their design specifications. The
14.2.12.1.30  Seal Injection Preoperational Test (SU3-BG02)


14.2.12.1.30.1  Objective
procedure preparation efforts were started more than 2 years before the first


To demonstrate the ability of the chemical and volume control system to supply adequate seal water injection flow to the reactor coolant pumps and verify the operation of the seal water return containment isolation valves, including their response to a CIS.
procedure to be performed. This early start allows for an orderly development
14.2.12.1.30.2  Prerequisites 
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The volume control tank contains an adequate supply of demineralized water for the performance of this test.
: d. Cooling water is available to the charging pumps.


14.2.12.1.30.3  Test Method
of the test procedure program and of the test procedures.  
: a. With a charging pump in operation, seal water throttle          valves are adjusted to maintain the required flow to each reactor coolant pump.
: b. Seal water return containment isolation valves control logics are verified, including their response to a CIS.  


14.2.12.1.30.4  Acceptance Criteria
The test procedures were reviewed by the cognizant design organization to  
: a. Seal water injection flow to each reactor coolant pump is within design specifications.
: b. Seal water return containment isolation valves close on receipt of a CIS. Valve closure times are within design specifications.


14.2-49    Rev. 0 WOLF CREEK 14.2.12.1.31  Charging System Preoperational Test (SU3-BG03) 14.2.12.1.31.1  Objective
ensure that the test procedure objectives and acceptance criteria are


To demonstrate positive displacement charging pump (replaced by the normal charging pump per DCP 04590) operating characteristics and to verify the operation of the regenerative heat exchanger inlet isolation valves and the letdown isolation valves, including their response to a safety injection signal (SIS).
consistent with current design document requirements. Subsequent changes to  


14.2.12.1.31.2  Prerequisites 
test procedure objectives or acceptance criteria during the preparational stage were based on approved changes to design documents with the design organization's concurrence.  
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The volume control tank contains an adequate supply of demineralized water for the performance of this test.
: d. Cooling water is available to the positive displacement          charging pump (replaced by the normal charging pump per            DCP 04590).      e. The reactor coolant system is available to receive charging system flow.  


14.2.12.1.31.3 Test Method 
14.2.3.2 Procedure Review and Approval Following initial procedure preparation, and prior to submittal to the JTG for
: a. The positive displacement charging pump (replaced by the          normal charging pump per DCP 04590)is operated, and          pump operating data are recorded.   
: b. Regenerative heat exchanger inlet isolation valve and letdown system isolation valve control circuits are verified, including valve response to safety injection          signals.


14.2.12.1.31.4  Acceptance Criteria
review and approval recommendation, the test procedures were reviewed by the  
: a. Positive displacement charging pump (replaced by the           normal charging pump per DCP 04590)operating          characteristics are within design specifications. 
: b. Charging pump to regenerative heat exchanger inlet isolation valves close on receipt of an SIS. Valve closure times are within design specifications. 
: c. The letdown line containment isolation valves close on receipt of a containment isolation signal. Valve closure times are within design specifications.


14.2-50    Rev. 12 WOLF CREEK 14.2.12.1 32  Boron Thermal Regeneration System Preoperational              Test (SU3-BG04)
SNUPPS utilities (KG&E and Union Electric). Review comments were resolved between the SNUPPS utilities and the writing organization.  


14.2.12.1.32.1  Objective To verify the operation of the boron thermal regeneration system, and associated control circuits. Performance characteristics of the chemical and volume control system chiller pumps are also verified.
A final revision was made by the writing organization, incorporating all


14.2.12.1.32.2  Prerequisites
applicable design changes, and was submitted to the utilities for their review
: a. Required component testing, instrument calibration and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits          are operational. 
: c. The volume control tank contains an adequate supply of demineralized water for the performance of this test.
: d. The chemical and volume control system chiller surge tank contains an adequate supply of demineralized water for the performance of this test.


14.2.12.1.32.3  Test Method
and approval.  
: a. The chemical and volume control system chiller pumps are operated and performance characteristics are verified.
: b. Boron thermal regeneration system component control          circuits are verified.
14.2.12.1.32.4  Acceptance Criteria
: a. The chemical and volume control system chiller pumps' operating characteristics are within design specifications.
: b. The chemical and volume control system chiller pumps start automatically when the boron thermal regeneration system is placed in the borate or dilute mode of operation.  


14.2.12.1.33  Boric Acid Blending System Preoperational Test (SU3-BG05)
14.2-10    Rev. 0 WOLF CREEK Each utility had various organizations, groups, and committees, such as a startup organization, initial test group, and a plant safety review committee,


14.2.12.1.33.1  Objectives
comprised of individuals having appropriate technical backgrounds and  
: a. To demonstrate the operating characteristics of boron injection makeup and boric acid transfer pumps and 


14.2-51    Rev. 0 WOLF CREEK          verify the ability of the boric acid blending system to          make up at design flow rates to the chemical and volume control system (CVCS).
experience. Individuals within these organizations, groups, and committees
: b. To verify the operation of system component control          circuits in all modes of operation.
: c. To demonstrate by flow test the ability of the reactor makeup water system to supply water to the boric acid blender.
: d. To demonstrate by flow test the ability of the boric acid system to supply an emergency boration flow to the charging pump suction.
: e. To verify the operation of volume control tank valves          and associated control circuits, including valve response to safety signals.


14.2.12.1.33.2  Prerequisites
were responsible for:
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: a. Reviewing procedures for accuracy and technical content;
: b. Required electrical power supplies and control circuits are operational.
: b. Verifying that the procedure has been revised to  
: c. The reactor makeup water system is available to supply water to the boric acid blender and boric acid batching tank.      d. A charging pump is available to receive and discharge flow from the boric acid transfer pumps.
: e. The volume control tank (VCT) contains an adequate supply of demineralized water for the performance of this test.


14.2.12.1.33.3  Test Method
incorporate known design changes;
: a. The boron injection makeup and boric acid pumps are operated, performance data recorded, and the ability of the system to make up to the CVCS at design flow rates is verified.
: c. Verifying procedure compatibility with field
: b. System component control circuits are verified in all modes of operation.  


14.2-52    Rev. 0 WOLF CREEK      c. With a reactor makeup water pump in operation, flow is          verified to the boric acid blender and boric acid batching tank.
installation of equipment;
: d. With both boric acid transfer pumps in operation and a          charging pump taking a suction from the VCT and discharging to the reactor coolant loops, the emergency boration flow rate from the transfer pumps to the charging pump suction is recorded.
: d. Verifying procedure conformance with FSAR requirements and plant operating technical specifications;
: e. The emergency boration flow rate via gravity feed from the boric acid tanks to the charging pump suction is recorded.
: e. Reviewing procedures against reactor operating and  
: f. Proper operation of the reactor makeup water system is          verified when the reactor makeup control system (RMCS)          is operated in the manual, dilute, alternate dilute, and automatic modes.
: g. The operation of the VCT outlet valves control circuits is verified, including their response to a safety injection signal.


14.2.12.1.33.4  Acceptance Criteria
testing experiences of similar power plants.  
: a. The boron injection makeup and boric acid transfer pump operating characteristics are within design specifications.
: b. The flow rate to the boric acid blender from the reactor          makeup water system is within design specifications. 
: c. The emergency boration flow rates to the charging pump suction are within design specifications.
: d. The boric acid transfer pumps and the reactor makeup water pumps start automatically on a low level in the volume control tank when the RMCS is in the automatic mode.
: e. VCT outlet valves close on receipt of a safety injection signal when the associated charging pump supply valve from the refueling water storage tank is open.
: f. Refueling water storage tank to charging pump suction valves open on receipt of a safety injection signal.
: g. The boric acid transfer pumps stop on receipt of a load shed signal.  


14.2-53    Rev. 0 WOLF CREEK      h. The boric acid filter to charging pump valve supply          breaker trips open on receipt of a load shed signal.
14.2.3.2.2 Joint Test Group (JTG)


14.2.12.1.34  Chemical and Volume Control System Hot Preoperational Test (S-03BG06) 14.2.12.1.34.1  Objectives
A subcommittee of the PSRC, the JTG was organized by the Operating Agent to  
: a. To determine by flow test that all letdown and cleanup flow rates are within design specifications.
: b. To determine, by comparison of boron concentrations, that boric acid addition to the reactor coolant system has occurred, using the normal and emergency flow paths.
: c. To determine by flow test the ability of the chemical          and volume control system (CVCS) to make up at design flow rates and boron concentrations to the reactor coolant system in all modes of operation.
: d. To determine by operational test that the letdown containment isolation valve closure times are within design specifications.
: e. To demonstrate the ability of the pump room coolers to maintain room temperatures within design limits.


14.2.12.1.34.2  Prerequisites
review preoperational test procedures and preoperational test results.  
: a. Required component testing, instrument calibration, and           system flushing/cleaning are complete. 
: b. Required electrical power supplies and control circuits are operational.
: c. The plant is at normal operating temperature and pressure, and hot functional testing is in progress.
: d. The CVCS pump rooms are closed, and their associated pump room coolers are operational.  


14.2.12.1.34.3  Test Method
The primary JTG functions were to:
: a. The letdown throttle valves are adjusted to establish letdown flow within design specifications.
: a. Review preoperational test procedures and recommend
: b. Boric acid addition to the reactor coolant system is verified, using the normal and emergency flow paths, by comparing the change in boron concentrations.


14.2-54    Rev. 0 WOLF CREEK      c. With a charging pump in operation, the ability of the           CVCS, in all modes of operation, to make up at design flow rates and boron concentrations to the reactor coolant system is verified.  
their approval by the Startup Manager.  
: d. With letdown flow established, the letdown containment isolation valves are operated, and operating times are recorded.
: b. Evaluate and authorize changes to preoperational test procedures as detailed in the Startup Administrative
: e. During CVCS pump operation, pump room temperature data are recorded.


14.2.12.1.34.4  Acceptance Criteria
Manual.  
: a. All letdown and cleanup flow rates are within design          specifications 
: c. Evaluate preoperational test procedure results and  
: b. The boric acid addition system is capable of adding boron to the reactor coolant system via both the normal and emergency flow paths.  
: c. The CVCS makeup flow rates and boron additions to the reactor coolant system are within design specifications in all modes of operation.
: d. The letdown containment isolation valves' closure times are within design specifications.
: e. The CVCS pump room coolers maintain the room temperature within design limits.      f. The boron thermal regeneration system (BTRS) can vary the reactor coolant boron concentration as required for daily load cycle at 85 percent core life.


14.2.12.1.35  Fuel Pool Cooling and Cleanup System Preoperational Test (SU3-EC01)
recommend their approval to the Startup Manager and  


14.2.12.1.35.1  Objectives
Plant Manager.  
: a. To demonstrate the operating characteristics of the fuel pool cooling, fuel pool cleanup, and pool skimmer pumps and to verify that the associated instrumentation and controls are functioning properly.
: d. Review safety-related aspects of the startup
: b. To verify that the fuel pool cleanup pump refueling water storage tank (RWST) suction isolation valves close on receipt of a safety injection signal (SIS).


14.2-55    Rev. 0 WOLF CREEK      c. To verify that each fuel pool cooling pump room cooler          starts when the associated fuel pool cooling pump starts.  
administrative procedures.  


14.2.12.1.35.2  Prerequisites 
Membership in the JTG included the following personnel or their designated
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. Cooling water is available to the fuel pool cooling and cleanup system heat exchangers.
: d. The liquid radwaste system is available to drain the           refueling pool to the RWST.
: e. The essential service water system is available to provide cooling water to the spent fuel pool pump room coolers.
: f. The spent fuel pool and fuel transfer canals are filled to their normal operating levels.


14.2.12.1.35.3  Test Method
representatives:
: a. The fuel pool cooling, fuel pool cleanup, and pool skimmer pumps are operated in their various modes, and pump operating data are recorded.      b. System component control circuits are verified, including the operation of system pumps and valves on receipt of safety signals.
: a. Superintendent Operations - Chairman
: c. The ability of each fuel pool cooling pump room cooler to start when the associated fuel pool cooling pump starts is verified.
: b. Superintendent of Plant Support


14.2.12.1.35.4  Acceptance Criteria
14.2-11    Rev. 12 WOLF CREEK
: a. The operating characteristics of the fuel pool cooling, fuel pool cleanup, and pool skimmer pumps are within design specifications.  
: c. Superintendent of Regulatory, Quality and Administrative Services
: b. The fuel pool cleanup pumps RWST suction isolation valves close on receipt of an SIS.  
: d. Startup Technical Support Supervisor
: e. Assistant Startup Manager
: f. Operations Quality Assurance  (non-voting member)
: g. Bechtel Power Corporation-Engineering (non-voting


14.2-56    Rev. 0 WOLF CREEK      c. Each fuel pool cooling pump trips on a low spent fuel          pool level signal.
member)
: d. Each fuel pool cooling pump trips on receipt of a load shed signal. 
: h. Westinghouse-Engineering (non-voting member)
: e. Each fuel pool cooling pump room cooler starts when the associated fuel pool cooling pump starts.  


14.2.12.1.36  Spent Fuel Pool Leak Test (S-03EC02)
Others were requested to provide technical support to the JTG. This support was based on the procedure being reviewed, required technical expertise or other applicable factors. Participation in the JTG meeting was with the concurrence


14.2.12.1.36.1  Objectives
of the JTG and was limited to technical input only.  
: a. To demonstrate the integrity of the spent fuel pool, cask loading pit, and fuel transfer canal.      b. To demonstrate the leaktightness of the cask loading pit gate and the fuel transfer canal gate.  


14.2.12.1.36.2 Prerequisites
14.2.3.2.3 Plant Safety Review Committee (PSRC)
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The spent fuel pool is filled to the normal operating level.
: d. The cask loading pit level is below the level of the          fuel pool gate.
: e. The fuel transfer canal level is below the level of the fuel pool gate.
: f. The reactor makeup water system is available to provide demineralized water to the spent fuel pool.
: g. A source of compressed air is available to pressurize the system standpipes.


14.2.12.1.36.3  Test Method
The PSRC was organized by the Operating Agent to ensure effective coordination


The cask loading pit gate and fuel transfer canal gate are visually inspected for leakage. A leak test is performed on the spent fuel pool, cask loading pit, and fuel transfer canal, using the associated leak chase standpipes.
of the engineering, construction, and operations activities affecting the  


14.2-57    Rev. 0 WOLF CREEK 14.2.12.1.36.4  Acceptance No leakage is observed from the spent fuel pool, cask loading pit, fuel transfer canal, cask loading pit gate, and fuel transfer canal gate.
startup program.  
14.2.12.1.37  Essential Service Water System Preoperational Test (SU3-EF01)


Test SU3-EF02 combined with Test SU3-EF01, Essential Service Water System Preoperational Test.
The appropriate PSRC members ensured sufficient review of initial startup test


14.2.12.1.37.1  Objectives
procedures and results.  
: a. To demonstrate the capability of the essential service water system to provide cooling water flow during the          LOCA mode of operation. The operation and response of          system valves to align the system in the LOCA flow mode on safety injection signals, load sequence signals, and low suction pressure signals are also verified.
: b. To demonstrate the operating characteristics of the essential service water (ESW) pumps and verify their response to safety signals.
: c. To demonstrate the operability of the backpressure control valves, including their response to safety signals.  


14.2.12.1.37.2  Prerequisites
The primary PSRC startup functions were:
: a. Required component testing, instrument calibration, and           system flushing/cleaning are complete.  
: a. Review all initial startup test procedures and make recommendations to the Plant Manager.  
: b. Required electrical power supplies and control circuits are operational.
: b. Evaluation and authorization of changes to initial
: c. The compressed air system is available to the system air-operated valves.


14.2.12.1.37.3  Test Method
startup test procedures.  
: a. System operating characteristics are verified in the LOCA mode of operation.
: c. Evaluation of initial startup test procedure results.  
: b. Safety signals are simulated, and the responses of the system valves and the ESW pumps are verified.
: c. The ESW pumps are operated and pump operating data are recorded.  


14.2-58    Rev. 0 WOLF CREEK      d. The operability of the backpressure control valves,          including their response to safety signals is verified.  
Membership in the PSRC is given in the Quality Program Manual.
14.2.4  CONDUCT OF TEST PROGRAM


14.2.12.1.37.4 Acceptance Criteria
14.2.4.1  Administrative Procedures
: a. Components supplied by the essential service water system receive flows that are within design specifications in the LOCA mode of system operation.
: b. System valve operation in response to safety signals is within design requirements.
: c. System valve operating times are within design specifications.
: d. The ESW pumps' operating characteristics are within          design specifications.
: e. Each ESW pump responds properly to load sequence and load shed signals.
: f. The time required for each ESW pump to reach rated flow is within design specifications.
: g. System backpressure valves close upon receipt of a LOCA sequencer or safety injection signal.
: h. An auxiliary feedwater pump low suction pressure signal will close the ESW pump breakers if a zero sequencer signal is not present. 14.2.12.1.38 Component Cooling Water System Preoperational Test (S-03EG01)


14.2.12.1.38.1  Objectives
The conduct of the preoperational startup program was controlled by
: a. To demonstrate the capability of the component cooling water system to provide cooling water during the normal, shutdown, and post-LOCA modes of operation.
: b. To demonstrate the operating characteristics of the component cooling water pumps and to verify that the associated instrumentation and controls are functioning properly, including system response to safety signals.


14.2.12.1.38.2  Prerequisites
administrative procedures. The preparation, maintenance, and implementation
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.


14.2-59    Rev. 0 WOLF CREEK      b. Required electrical power supplies and control circuits          are operational.  
of these procedures was the responsibility of the Startup Manager. The startup administrative procedures prescribed controls for startup activities such as:


14 2.12.1.38.3  Test Method
14.2-12   Rev. 21 WOLF CREEK
: a. System operating characteristics are verified in the normal, shutdown, and post-LOCA modes of operation.  
: a. Organization and interfaces;
: b. Safety signals are simulated, and the response of system pumps and valves is verified.  
: b. Indoctrination and training;
: c. Preparation, review, approval, and modification of test procedures;
: d. Format and content of test procedures;
: e. Tagging procedures;
: f. Test scheduling and test conduct;
: g. Test deficiencies and resolution;
: h. Startup quality control; and  
: i. Startup document control.  


14.2.12.1.38.4 Acceptance Criteria
14.2.4.2 Turnover from Construction to KG&E Startup Construction completion was scheduled in accordance with engineered system or
: a. The performance characteristics of each component cooling water pump are within design specifications.      b. Components supplied by the component cooling water system receive flows that are within design specifications with the system operating in the normal, shutdown, and post-LOCA modes.
: c. Component cooling water pump and valve responses to load sequence, containment isolation, and safety injection signals are within design specifications.
: d. Closure times for the component cooling water supply and return valves to the reactor coolant system are within design specifications.
: e. Component cooling water pump response to centrifugal          charging pump start signals is in accordance with system           design.


14.2.12.1.39  Residual Heat Removal System Cold Preoperational Test (SU3-EJ01)
subsystem boundaries. As systems or sub- systems were completed to support


14.2.12.1.39.1  Objective
Startup testing, a turnover of the system or subsystem to KG&E Startup was processed. Turnover was conducted in accordance with established


To demonstrate the operability of the Residual Heat Removal (RHR) pumps, demonstrate by flow test their ability to supply water at rated pressure and flow, and verify their response to safety signals. The operation of system motor-operated valves, including their response to safety signals, are also verified. The RWST control and alarm circuits are also verified.  
administrative procedures.  


14.2.12.1.39.2  Prerequisites
As part of the turnover process, each safety-related system or subsystem
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.


14.2-60    Rev. 0 WOLF CREEK      b. Required electrical power supplies and control circuits          are operational.
received physical walkdowns to provide assurance of readiness for Startup
: c. The reactor vessel head is removed and the water level is above the nozzles. 
: d. The refueling water storage tank contains an adequate supply of demineralized water for the performance of this test.
: e. Cooling water is available to the RHR pumps and heat exchangers.
: f. The instrument air system is available to supply air to system air-operated valves. 14.2.12.1.39.3  Test Method
: a. Performance characteristics of the RHR pumps are verified during discharge to the reactor coolant hot and cold loops and test recirculation.
: b. RWST and RHR system component control circuits are verified, including the operation of the RHR pumps and system valves on receipt of safety signals.


14.2.12.1.39.4 Acceptance Criteria
testing and verification that installation requirements had been met.   
: a. RHR pump performance characteristics are within design specifications.      b. RHR system components align or actuate in accordance with system design to safety injection, containment isolation, load sequencing, load shed, and tank level signals.
: c. The time required for each RHR pump to reach rated speed is within design specifications.
: d. RHR system motor-operated valve closure times are within design specifications.


14.2.12.1.40  Residual Heat Removal System Hot Preoperational Test (S-U3-EJ02)
Walkdowns were performed jointly by KG&E Startup and KG&E Construction


14.2.12.1.40.1  Objectives
personnel under the direction of the KG&E Construction Manager. Discrepancies
: a. To demonstrate the ability of the residual heat removal (RHR) system to cool down the reactor coolant system (RCS) at its design rate.  


14.2-61    Rev. 0 WOLF CREEK      b. To demonstrate the ability of the RHR pump room coolers          to maintain room temperature within design limits.
identified during the walkdowns were tracked and resolved in accordance with


14.2.12.1.40.2  Prerequisites
established administrative and quality procedures.
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
The system or subsystem Turnover Package prepared by the constructor was
: b. Required electrical power supplies and control circuits are operational.  
: c. The component cooling water system is supplying water to each RHR heat exchanger.
: d. The RCS is being cooled down during hot functional          testing. 
: e. The RHR pump rooms are closed, and their associated pump room coolers are operational.


14.2.12.1.40.3  Test Method
reviewed by KG&E Construction and KG&E Startup personnel for accuracy,  
: a. While the RCS is being cooled down with the RHR system, the heat transfer is obtained by performing a heat balance across each RHR heat exchanger.
: b. When RHR pump room temperatures have stabilized, room temperature data is recorded.


14.2.12.1.40.4  Acceptance Criteria      a. The RHR system is capable of cooling down the reactor coolant system at its design rate.
completeness and acceptability for Startup testing. In conjunction with the  
: b. The RHR pump room coolers can maintain room temperature within design limits.


14.2.12.1.41  Safety Injection System Cold Preoperational Test (SU3-EM01)
Turnover Package review, Startup personnel verified that the system or


14.2.12.1.41.1  Objectives
subsystem procurement and installation documentation review had been performed


To demonstrate the response of the safety injection pumps and associated valves to safety signals.
by Construction, and that discrepancies had been addressed. Acceptance of the  


14.2.12.1.41.2  Prerequisites
Turnover Package by Startup followed satisfactory completion of the Turnover
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete


14.2-62    Rev. 0 WOLF CREEK      b. Required electrical power supplies and control circuits          are operational.
Package review. The Startup Manager was responsible for the approval and  


14.2.12.1.41.3  Test Method The response of the safety injection pumps and associated valves to safety signals is verified
acceptance of the system or subsystem and the associated Turnover Package.


14.2.12.1.41.4  Acceptance Criteria
14.2-13    Rev. 0 WOLF CREEK Individual components could be released to Startup for calibration, testing or temporary operation prior to turnover.  
: a. The safety injection pumps and associated valves align or actuate in accordance with system design to containment isolation signals, load shedding signals, and load sequencing signals.
 
14.2.12.1.42  Safety Injection Flow Verification Test (SU3-EM02) 14.2.12.1.42.1  Objectives
All components released in this manner were incorporated into the scope of a
: a. To demonstrate the operating characteristics of the safety injection pumps and the centrifugal charging pumps.
: b. To demonstrate the capability of the safety injection pumps to provide balanced flow to the reactor coolant system and prevent runout flow in the cold leg and hot leg injection modes.
: c. To demonstrate the capability of the charging pumps to provide balanced flow to the reactor coolant system and          prevent runout flow in the boron injection mode. 
: d. To demonstrate the capability of the residual heat removal pumps to provide required net positive suction head to the safety injection pumps and the centrifugal charging pumps.
: e. To demonstrate that the safety injection and centrifugal charging pump room coolers maintain room temperature within design limits.
: f. To demonstrate that associated system valve operating times are within specified limits.


14.2.12.1.42.2  Prerequisites
subsequent system or subsystem turnover.  
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.  


14.2-63    Rev. 0 WOLF CREEK      b. Required electrical power supplies and control circuits          are operational.
14.2.4.3  Component and Prerequisite Testing Upon Startup acceptance of a turned-over system, subsystem, or released
: c. The CVCS is available to supply rated flow to the reactor coolant system via the boron injection path,          while simultaneously supplying other required loads.
: d. The residual heat removal system is available to supply adequate suction head to the safety injection and centrifugal charging pumps during required injection modes.
: e. The borated refueling water storage tank contains an adequate supply of demineralized water for this test.
: f. The reactor vessel is available to receive water, and          the temporary reactor vessel pumpdown system is operational (if required).
: g. The auxiliary building HVAC system is available to cool the pump rooms and verify associated pump interlocks.
: h. The accumulator safety injection system piping from the safety injection system to the reactor coolant system is available, and an accumulator tank is capable of receiving water.
: i. Cooling water is available to required pumps and heat exchangers.
: j. The compressed air system is available to supply air to          associated system valves.
: k. The residual heat removal system hot leg and cold leg flow orifices have been sized for required flow.


14.2.12.1.42.3  Test Method
component, prerequisite-type testing was performed to demonstrate proper
: a. The safety injection pumps are operated in the cold leg flow mode to verify pump performance characteristics and to identify the weaker pump.
: b. The safety injection cold leg branch lines are balanced using the weaker safety injection pump and the balance checked with the stronger pump. The balance is performed so that injection flow is maximized while preventing pump runout.


14.2-64    Rev. 0 WOLF CREEK      c. The safety injection hot leg branch lines are balanced,           using their respective safety injection pump. The balance is performed so that injection flow is maximized while preventing pump runout.
operability and functional ability in support of, and prior to, the performance of preoperational testing. Local containment leak rate testing, as described in  
: d. The centrifugal charging pumps are operated in the boron injection mode to determine pump performance characteristics and to identify the weaker pump.
: e. The boron injection branch lines are balanced, using the weaker centrifugal charging pump and the balance checked with the stronger pump. The balance is performed such that injection flow is maximized while preventing pump runout.
: f. Each residual heat removal pump is operated in series          with the centrifugal charging pumps and safety injection pumps to verify that the residual heat removal pumps can supply adequate suction head.
: g. With each centrifugal charging pump and safety injection pump operating, pump room temperatures are allowed to stabilize, and room temperature data are recorded.


14.2.12.1.42.4  Acceptance Criteria
Section 14.2.12.2.13, was performed at WCGS as part of the prerequisite test
: a. The safety injection and centrifugal charging pump response times and valve operating times are within design specifications.
: b. The safety injection pump room coolers start with their          respective pump.
: c. The NPSH provided by the residual heat removal pumps to the centrifugal charging pumps and safety injection pumps is within system design specifications.
: d. Safety injection cold leg, hot leg, and safety injection pump flows are within design specifications.
: e. Boron injection and centrifugal charging pump flows are within design specifications.
: f. The safety injection and centrifugal charging pump room coolers can maintain room temperature within design limits.


14.2-65    Rev. 0 WOLF CREEK 14.2.12.1.43  Safety Injection Check Valve Test (SU3-EM03) 14.2.12.1.43.1  Objectives
program.  


To demonstrate the integrity of accumulator outlet line and loop safety injection line check valves and backup check valves by performing backleakage tests. The operability of the various safety injection line check valves under their design pressure conditions is also verified.
Administrative procedures were established to ensure that all prerequisites


14.2.12.1.43.2  Prerequisites
were met before testing was initiated. Upon completion of all prerequisite
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits          are operational. 
: c. The reactor coolant system is at normal operating pressure.  


14.2.12.1.43.3  Test Method
tests applicable to a system or subsystem, a documented review was conducted by  
: a. Check valve leak testing is performed with the reactor coolant system at normal operating pressure.
: b. Check valve operability is performed by verifying flow through the check valves at reduced reactor coolant pressure.


14.2.12.1.43.4  Acceptance Criteria      a. Check valve leakage rates are within limits established by Technical Specifications Section 3.4.6.2f.
Startup personnel to verify that appropriate documentation was able and that
: b. Injection line check valve operability is demonstrated by verification of flow through the check valves in each of the safety injection lines to the reactor coolant system.


14.2.12.1.44  Boron Injection Tank and Recirculation Pump Test (SU3-EM04)
required prerequisite tests had been satisfactorily completed. All deficiencies


This test has been deleted at Wolf Creek since the boron injection requirements have been eliminated due to the decrease in required boron concentration.  
which would prevent performance of preoperational tests or generate negative test results were identified and dispositioned prior to implementation of the preoperational tests.  


14.2-66    Rev. 0 WOLF CREEK 14.2.12.1.45  Containment Spray System Nozzle Air Test (S-03EN01) 14.2.12.1.45.1 Objectives
14.2.4.4 Preoperational Testing Technical direction and administration, including test execution and data


To demonstrate that the spray nozzles in the containment spray header are clear of obstructions.
recording, of the preoperational testing were the responsibility of the startup


14.2.12.1.45.2  Prerequisites
organization. The system startup engineers were responsible for the performance of tests and providing appropriate interface with station


A source of compressed air is available to pressurize the spray headers.
operators. The Startup Manager was responsible for the administration and


14.2.12.1.45.3  Test Method
surveillance of all testing activities during the preoperational test program.  


Air flow is initiated through the containment spray headers, and unobstructed flow is verified through each nozzle. 14.2.12.1.45.4  Acceptance Criteria
14.2.4.5 Initial Startup Testing During the initial startup testing phase, the Plant Manager had overall


All containment spray nozzles are clear and unobstructed, as evidenced by air passing through each nozzle.  
authority and responsibility for the startup program. The Startup Organization


14.2.12.1.46  Containment Spray System  Preoperational Test (SU3-EN02)
provided support to the plant operating staff which had responsibility for performing equipment operations and maintenance in accordance with the


14.2.12.1.46.1  Objectives
provisions of the plant operating license. The WCGS operating staff was also  
: a. To demonstrate the operation of system components, including their response to safety signals, and verify that the associated instrumentation and controls are functioning properly. System flow characteristics in          the test and simulated accident modes are also verified. 
: b. To demonstrate the ability of the pump room coolers to maintain room temperatures within design limits.


14.2.12.1.46.2  Prerequisites
responsible for ensuring that the conduct of testing did not place the plant in
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The refueling water storage tank contains an adequate supply of demineralized water for the performance of this test.
: d. The auxiliary building HVAC system is available to cool the pump rooms and verify associated pump interlocks.


14.2-67    Rev. 0 WOLF CREEK      e. The containment spray pump rooms are closed.
an unsafe condition at any time.  
14.2.12.1.46.3  Test Method
: a. Performance characteristics of the containment spray          pumps are verified in the test mode, recirculating to the refueling water storage tank, and in the simulated accident mode.
: b. System component control circuits are verified, including the operation of system pumps and valves on receipt of load sequence/shedder and CSAS/CIS signals, respectively.
: c. During system operations, spray additive eductor          operating characteristics are verified. 
: d. During containment spray pump operation, pump room temperature data are recorded.  


14.2.12.1.46.4  Acceptance Criteria
The shift supervisors had the authority to terminate or disallow testing at any
: a. Containment spray pump performance characteristics are within design specifications for the tested modes of operation.
: b. Containment spray pump and valve response to load sequence/shedder and CSAS/CIS is verified, and the associated response times are within design specifications.      c. Spray additive eductor operating characteristics are within design specifications.
: d. The containment spray pump room coolers maintain the room temperature within design limits.


14.2.12.1.47  Accumulator Testing (S-03EP01)
time.  


14.2.12.1.47.1 Objectives
14.2-14    Rev. 0 WOLF CREEK 14.2.4.6 Test Prerequisites Each test procedure contained a set of prerequisites and initial conditions as


To determine the operability of each safety injection accumulator and obtain, by flow test, each accumulator's discharge line resistance to flow. The ability of the accumulator discharge line isolation valves to open under maximum differential pressure conditions is verified, as is the response of accumulator system valves to safety signals.
prescribed by the startup administrative procedures. The system startup


14.2-68    Rev. 0 WOLF CREEK 14.2.12.1.47.2  Prerequisites 
engineer ensured that all specified prerequisites were met prior to performing the test. The format for test procedures is described in Section 14.2.3.1.  
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The reactor vessel head and reactor internals are not installed, and the vessel is available to receive water.
: d. A source of compressed air and nitrogen is available.
: e. The refueling water storage tank contains an adequate supply of demineralized water for the performance of this          test.
14.2.12.1.47.3  Test Method
: a. Each accumulator is filled and partially pressurized with the discharge valves closed. The discharge valves are opened, discharging the accumulators to the reactor vessel, and performance data are recorded.
: b. Each accumulator discharge line isolation valve is operated under maximum differential pressure conditions of normal accumulator precharge pressure and zero reactor coolant pressure, and the valve operating times are recorded.
: c. Accumulator system valve control circuits are verified,          including their response to safety injection and containment isolation signals.  


14.2.12.1.47.4 Acceptance Criteria
14.2.4.7 Test Evaluation Upon completion of system preoperational testing, the test results were
: a. Each accumulator's discharge line resistance to flow (L/D) is in accordance with design specifications.
: b. Each accumulator's discharge line isolation valve opening time under maximum differential pressure conditions is within design specifications.
: c. The accumulator system nitrogen supply containment isolation valve closes on receipt of a containment isolation signal. Valve closure time is within design specifications.
: d. Each accumulator discharge isolation valve opens on receipt of a safety injection signal.


14.2-69    Rev. 0 WOLF CREEK 14.2.12.1.48  Auxiliary Feedwater Pump Turbine Preoperational                Test (SU3-FC01)
submitted to the JTG for its review and subsequent recommendation for approval


14.2.12.1.48.1  Objectives
to the Startup Manager and Plant Manager.  
: a. To demonstrate the operation of the auxiliary feedwater pump (AFWP) turbine and its support equipment, while uncoupled from the pump.
: b. To demonstrate control of the AFWP turbine from the control room as well as the auxiliary shutdown panel.  


14.2.12.1.48.2  Prerequisites
Between each major phase of the initial startup test program, the test results
: a. Required component testing, instrument calibration and          system flushing/cleaning are complete. 
: b. Steam is available to the AFWP turbine.


14.2.12.1.48.3  Test Method
for all tests that were performed were reviewed by the PSRC. This review
: a. AFWP turbine system valves are operated and required response to various signals is verified.
: b. The turbine is operated and proper control is verified from the control room as well as the auxiliary shutdown panel, and operating data are recorded.
: c. The turbine is brought to high speed at which time the mechanical and electronic overspeed trips are verified. 14.2.12.1.48.4  Acceptance Criteria
: a. The AFWP turbine can be controlled from the control room panel and the auxiliary shutdown panel.
: b. The mechanical and electronic overspeed trips actuate to shut down the turbine in accordance with the design.  


14.2.12.1.49  Essential Service Water Pumphouse HVAC Preoperational Test (SU3-GD01)
ensured that all required systems were tested satisfactorily and that test


14.2.12.1.49.1  Objectives
results were approved before proceeding to the next stage of testing.  
: a. To demonstrate the capacity of the essential service water (ESW) pumproom supply fans.
: b. To demonstrate ESW pumproom unit heater response to a load shed signal.  


14.2-70    Rev. 0 WOLF CREEK 14.2.12.1.49.2  Prerequisites 
These reviews are described in Section 14.2.5.  
: a. Required component testing and instrument calibration are completed.
: b. Required electrical power supplies and control circuits are operational.
: c. The ESW pumphouse HVAC system is air balanced.  


14.2.12.1.49.3 Test Methods
14.2.4.8 Design Modifications Modifications to the design of the equipment during the test program could be
: a. The ESW pumphouse supply fans are operated and flow data are recorded.
: b. Response of the ESW pumproom unit heaters to load shed          signal is verified.


14.2.12.1.49.4 Acceptance Criteria
initiated in order to correct deficiencies discovered as a result of testing.   
: a. The ESW pumphouse supply fan capacities are within design specification.
: b. A load shed signal will trip the ESW pumproom unit heaters' circuit breaker.


14.2.12.1.50  Miscellaneous Building HVAC System Preoperational Tests (SU3-GF01, SU3-GF02, SU3-GF03)
Any such modifications were either developed by the original design organization or other designated organizations. Modifications made to


14.2.12.1.50.1  Objectives  To demonstrate the capacity of;  1) the auxiliary feedwater pump room cooler fans, 2) the main steam enclosure building supply and exhaust fans and 3) the tendon access gallery transfer fans and to verify that the associated instrumentation and controls are functioning properly. The responses of the main steam enclosure building dampers and tendon access gallery dampers to safety signals are also verified.
components or systems after completion of preoperational or initial startup


(At Wolf Creek Generating Station, this test was performed in three independent parts. In addition, the auxiliary boiler room fan was treated as part of preoperational test SU4-GF01.)
testing were reviewed for retesting requirements on affected portions of the  


14.2.12.1.50.2 Prerequisites
system.
: a. Required component testing and instrument calibration are complete.
 
: b. Required electrical power supplies and control circuits are operational.
14.2.5 REVIEW, EVALUATION, AND APPROVAL OF TEST RESULTS


14.2-71    Rev. 0 WOLF CREEK      c. The miscellaneous building HVAC system is air balanced.
The responsibility for review, evaluation, and recommendation for approval of  
14.2.12.1.50.3  Test Method
: a. Flow data are recorded while the fans are operating. 
: b. The response of system dampers to a safety injection signal (SIS) is verified.


14.2.12.1.50.4  Acceptance Criteria
test results from all preoperational tests rested with the JTG. In the case of  
: a. System fan capacities are within design specifications.
: b. The main steam enclosure building and tendon access gallery dampers close on receipt of a SIS. 14.2.12.1.51  Fuel Building  HVAC  System  Preoperational  Test (S-03GG01)


14.2.12.1.51.1  Objectives
all initial start-up tests, it rested with the PSRC.
Following completion of a preoperational test, the responsible system startup


To demonstrate that the emergency exhaust fans are capable of maintaining a negative pressure in the fuel building or the auxiliary building during accident conditions with the buildings isolated. To demonstrate the capacities of the fuel building supply unit fans, emergency exhaust fans, and the spent fuel pool pump room cooler fans. The operability of system instrumentation and controls, including the components' response to safety signals, is also verified.
engineer assembled the test data package for submittal to the members of the  


14.2.12.1.51.2  Prerequisites      a. Required component testing, instrument calibration, and system air balancing are complete.
JTG for evaluation. Each test data package was reviewed to ensure that the  
: b. Required electrical power supplies and control circuits are operational.
: c. The compressed air system is available to supply the air-operated dampers in the fuel building.
: d. Required portions of the auxiliary building HVAC system have been air balanced and are available to support this test.


14.2.12.1.51.3  Test Method
test has been performed in accordance with the approved procedure and that all
: a. With the fuel building closed, the system is operated in its normal configuration,  and the fuel building  supply 


14.2-72    Rev. 0 WOLF CREEK          unit fan and spent fuel pool pump room cooler fan          capacities are verified.
required data, checks, and signatures were properly recorded and that system
: b. With a fuel building isolation signal (FBIS) present, the emergency exhaust fan capacities and negative fuel          building pressures are verified.
: c. With a safety injection signal (SIS) present and the auxiliary building isolated, the emergency exhaust fan capacities and negative auxiliary building pressures are verified.


14.2.12.1.51.4  Acceptance Criteria
performance met the approved acceptance criteria.  
: a. The auxiliary building and fuel building pressures          maintained by the emergency exhaust fans are within          design specifications.
: b. The fuel building supply fans, emergency exhaust fans, and spent fuel pool pump room cooler fans' capacities are within design specifications.
: c. The fuel building ventilation system fans and dampers properly respond to FBIS and SIS, in accordance with system design.  


14.2.12.1.52  Control Building HVAC System Preoperational Test (SU3-GK01)
14.2-15    Rev. 0 WOLF CREEK Members of the JTG reviewed the evaluation findings and recommended corrective action to be taken to resolve any outstanding deficiencies. If the


14.2.12.1.52.1  Objectives  To demonstrate the capacities of the control building supply air unit, control building exhaust fans, access control exhaust fans, control room pressurization fans, control room filtration fans, control room air conditioning units, access control fan coil units, counting room fan coil unit, and Class IE electrical equipment ac units. To demonstrate that the control room pressurization fans are capable of maintaining a positive pressure in the control room following a control room ventilation isolation signal (CRVIS). The system instrumentation and controls, including the components' responses to safety signals, are also verified. To demonstrate that the ventilation to battery rooms 1 through 4 is in accordance with system design.
deficiencies were not resolved to the satisfaction of the JTG, then appropriate


14.2.12.1.52.2  Prerequisites
retesting was required. If the evaluation indicated that deficiencies in the
: a. Required component testing, instrument calibration, and system air balancing are complete.  


14.2-73    Rev. 0 WOLF CREEK      b. Required electrical power supplies and control circuits          are operational.
test method were responsible for unsatisfactory test results, the test procedure was revised accordingly before retesting was initiated. The review
: c. The compressed air system is available to supply air to system air-operated dampers.
14.2.12.1.52.3  Test Method
: a. The control building system fans are operated, and fan capacities are verified.
: b. Proper response of system components to control room ventilation isolation signals (CRVIS) and safety injection signals (SIS) is verified.
: c. With a CRVIS present, the ability of each control room          pressurization fan to maintain the control room at a positive pressure is verified.
: d. The air flow to battery rooms 1 through 4 is verified.


14.2.12.1.52.4  Acceptance Criteria
and approval process for procedure revisions was carried out in the manner
: a. The control building HVAC system fan capacities are within design specifications.
: b. The control building HVAC system fans and dampers properly respond to CRVIS and SIS in accordance with system design.
: c. The control room pressure maintained by the control room          pressurization fans is within design specification.
: d. The air flow to battery rooms 1 through 4 is in accordance with system design.


14.2.12.1.53  Auxiliary Building HVAC System Preoperational Test (SU3-GL01)
described in Section 14.2.3. Whenever an evaluation of test results indicated


14.2.12.1.53.1  Objectives
deficiencies in system performance, the JTG referred the problem to the


To demonstrate the capacities of the auxiliary building supply unit fans, auxiliary/fuel building normal exhaust fans, the auxiliary building fan coil units, pump room coolers, penetration room coolers, decon tank exhaust scrubber fans, access tunnel transfer fan, and penetration cooling fan. The system instrumentation and controls, including components' response to safety and fire signals, are also verified.  
responsible engineering organization for evaluation.  


14.2-74    Rev. 0 WOLF CREEK 14.2.12.1.53.2  Prerequisites 
If the test documentation and system performance were acceptable, the JTG
: a. Required component testing, instrument calibration, and system air balancing are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The compressed air system is available to supply the air-operated dampers in the auxiliary building.
: d. The fuel building HVAC system has been air balanced, and is available to support this test.


14.2.12.1.53.3  Test Method      a. The system is operated in its normal configuration, and the system fan capacities are verified.
recommended approval of the test by the Startup Manager and the Plant Manager.  
: b. Proper responses of system components to safety injection and fire signals are verified.  


14.2.12.1.53.4  Acceptance Criteria
Following each major phase of the initial startup test program, the PSRC verified that all required tests were performed and that the test results were approved. This verification ensured that all required systems were operating
: a. The auxiliary building fan capacities are within design specifications.
: b. The auxiliary building fans and dampers properly respond to safety injection and fire signals, in accordance with system design. 14.2.12.1.54  Diesel Generator Building HVAC Preoperational Test (S-03GM01)


14.2.12.1.54.1  Objectives
properly and that testing for the next major phase was conducted in a safe and


To demonstrate the capacities of the diesel generator room supply fans and to verify that the system instrumentation and controls function properly, including the response of fans and associated dampers to a diesel generator run signal and room temperature signals.
efficient manner. This type of review was performed to the extent required


14.2.12.1.54.2  Prerequisites
before major initial startup test phases such as fuel load, initial
: a. Required component testing and instrument calibration are completed.
: b. Required electrical power supplies and control circuits are operational.


14.2-75    Rev. 0 WOLF CREEK      c. The diesel generator building HVAC system is air          balanced.
criticality, and power ascension. During the power ascension phase, review and  
: d. The respective diesel generator is not operating while the room is under test.
14.2.12.1.54.3  Test Method
: a. Flow data are recorded, while the diesel generator room supply fans are operating.
: b. The responses of the diesel generator room supply fans and exhaust dampers to a diesel generator run signal and to room temperature signals are verified.
14.2.12.1.54.4  Acceptance Criteria 
: a. The capacities of the diesel generator room supply fans are within design specifications.
: b. The diesel generator room exhaust dampers open on receipt of a diesel generator run signal.
: c. The diesel generator room supply fans start on a high room temperature signal and stop on a low room temperature signal.


14.2.12.1.55  Containment Cooling System Preoperational Test (SU3-GN01) 14.2.12.1.55.1  Objectives To demonstrate the capacities of the hydrogen mixing, containment cooling, and pressurizer cooling fans and verify their associated instrumentation and controls function properly, including fan response to safety signals.
approval of initial startup test procedure results was completed as described


14.2.12.1.55.2  Prerequisites
in KMLNRC-84-235.  
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The essential service water system is available to supply water to the containment coolers.
: d. The containment cooling system has been air balanced.  


14.2-76    Rev. 0 WOLF CREEK 14.2.12.1.55.3 Test Method 
14.2.6 TEST RECORDS
: a. The hydrogen mixing, containment cooling, and pressurizer cooling fans are operated, flow data recorded, and fan capacities calculated. 
: b. The response of the hydrogen mixing and containment cooling fans to safety signals is verified.


14.2.12.1.55.4  Acceptance Criteria
Test procedures and test data relating to preoperational and initial startup
: a. The capacities of the hydrogen mixing, containment cooling, and pressurizer cooling fans are within design specifications.
: b. The hydrogen mixing and containment cooling fans align          or actuate in response to safety injection, shutdown sequencer, and LOCA sequencer signals, in accordance with system design.


14.2.12.1.56  CRDM Cooling Preoperational Test (S-03GN02)
testing are retained in accordance with the measures described in the Quality Program Manual.
14.2.7  CONFORMANCE OF TEST PROGRAMS WITH REGULATORY GUIDES


14.2.12.1.56.1  Objectives
The regulatory guides applicable to the test program are listed, with


To demonstrate the operating characteristics of the cavity cooling, control rod drive mechanism (CRDM), and the elevator machine room exhaust fans and verify their associated instrumentation and controls, including their response to safety signals.  
positions, in Appendix 3A, Conformance to NRC Regulatory Guides.  


14.2.12.1.56.2 Prerequisites      a. Required component testing and instrument calibration are complete.
14.2.8 UTILIZATION OF REACTOR OPERATING AND TESTING EXPERIENCE IN
: b. Required electrical power supplies and control circuits are operational.
: c. The CRDM and cavity cooling portions of the containment cooling system are air balanced.


14.2.12.1.56.3  Test Method
DEVELOPMENT OF TEST PROGRAMS
: a. The cavity cooling, elevator machine room exhaust, and CRDM fans are operated, flow data recorded, and fan capacities calculated.
: b. The response of the CRDM fans to a safety injection signal is verified.


14.2-77    Rev. 0 WOLF CREEK 14.2.12.1.56.4  Acceptance Criteria 
Available information on reactor operating experiences was utilized in the  
: a. The capacities of the cavity cooling, elevator machine room exhaust, and CRDM fans are within design specifications. 
: b. The appropriate CRDM fans supply breakers open on receipt of a safety injection signal.


14.2.12.1.57  Integrated Containment Leak Rate Test (SU3-GP01)
development of the Initial Test Program, as follows:


14.2.12.1.57.1  Objective
14.2-16    Rev. 21 WOLF CREEK
: a. Bechtel reviewed and distributed pertinent Licensee Event Reports for use in the development of


To demonstrate that the total leakage from the containment does not exceed the maximum allowable leakage rate at the calculated peak containment internal pressure. The operability of the containment cooling fans at design accident pressure is also verified.
preoperational test procedures as follows:
: 1. The Licensee Event Summary Reports and other pertinent information were reviewed on a periodic


14.2.12.1.57.2  Prerequisites
basis, and those reports deemed to be useful for
: a. The containment penetration leakage rate tests (type B tests) and containment isolation valve leakage tests (type C tests) are complete and the containment has been pressurized to 115 percent of the design pressure.
: b. All containment isolation valves are closed by normal actuation methods.
: c. Containment penetrations, including equipment hatches and personnel airlocks, are closed.      d. Portions of fluid systems that are part of the containment boundary, that may be opened directly to the containment or outside atmosphere under post-accident conditions, are opened or vented to the appropriate atmosphere to place the containment in as close to post-accident conditions as possible.
: e. Required instrument calibration is complete.


14.2.12.1.57.3  Test Method
updating test procedures and items of a generic
: a. The integrated containment leak rate test (type A test) is conducted, using the absolute method, described in the ANSI/ANS 56.8-1981 Containment System Leakage Testing Requirements. Measurements of containment atmosphere dry-bulb temperature, dew point and pressure are  taken to  calculate the  leakage rate. A standard 


14.2-78    Rev. 0 WOLF CREEK          statistical analysis of data is conducted, using a          linear least squares fit regression analysis to calculate the leakage rate.
nature were cataloged. A summary of these reports
: b. On completion of the leak rate test, a verification test          is conducted to confirm the capability of the data acquisition and reduction system to satisfactorily determine the calculated integrated leakage rate. The verification test is accomplished by imposing a known leakage rate on the containment, or by pumping back a known quantity of air into the containment through a calibrated flow measurement device.
: c. While at the design accident pressure, data is recorded for the containment cooling fans. 14.2.12.1.57.4  Acceptance Criteria


The containment integrated leakage does not exceed the maximum allowable leakage rate at a calculated peak containment internal pressure, as defined in 10 CFR 50, Appendix J.
was distributed within Bechtel.
: 2. Copies of the specific reports were then made and


The containment cooling fan operation at design accident pressure is in accordance with design.
distributed for use in the preparation of


14.2.12.1.58  Reactor Containment Structural Integrity Acceptance Test (SU3-GP02)
procedures. In addition, these reports were coded


14.2.12.1.58.1  Objectives To demonstrate the structural integrity of the reactor containment building.
and filed in a computer retrieval system.  
14.2.12.1.58.2  Prerequisites
: b. The operating experience assessment for Wolf Creek
: a. Containment penetrations are installed, and penetration leak tests are completed.  
: b. Containment penetrations, including equipment hatches and personnel airlocks, are closed.
: c. Required instrument calibration is complete.


14.2.12.1.58.3  Test Method
Generating Station Unit No. 1 (WCGS) was conducted by


The containment is pressurized at 115 percent of the design pressure, and deflection measurements and concrete crack inspections are made to determine that the actual structural response is within the limits predicted by the design analyses.
the nuclear divisions and plant staff who possess the  


14.2-79    Rev. 0 WOLF CREEK 14.2.12.1.58.4  Acceptance Criteria The containment structural response is within the limits predicted by design analyses.
appropriate experience in the area of concern. The  
14.2.12.1.59  Post-Accident Hydrogen Removal System Preoperational Test (S-03GS01)


14.2.12.1.59.1  Objectives
sources of operating experience information included the  
: a. To demonstrate that the hydrogen recombiner performance characteristics are within design specifications.
: b. To determine the operation of system dampers and valves, including the response of hydrogen purge and hydrogen          monitoring containment isolation valves to a CIS. 
: c. To demonstrate the operability of the hydrogen analyzers and their ability to sample the containment atmosphere.


14.2.12.1.59.2  Prerequisites
use of the NETWORK and the INPO/NSAC SEEIN system. An
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.  


14.2.12.1.59.3  Test Method
administrative system which controlled the flow of  
: a. Performance characteristics are recorded, while the           hydrogen recombiners are operating.
: b. System valve and damper control circuits are verified, including the response of hydrogen purge and hydrogen monitoring containment isolation valves to a CIS.
: c. The hydrogen analyzers are operated, and performance data recorded.


14.2.12.1.59.4  Acceptance Criteria
information from NETWORK, INPO/NSAC SEEIN, etc., to the
: a. Hydrogen recombiner performance characteristics are within design specifications.
: b. Hydrogen purge and hydrogen monitoring containment isolation valves close on receipt of a CIS. Valve closure times are within design specifications.  


14.2-80    Rev. 0 WOLF CREEK 14.2.12.1.60  Containment Purge System HVAC Preoperational Test                (S-03GT01)
cognizant organizations including the Independent Safety


14.2.12.1.60.1  Objectives To demonstrate the capacities of the containment minipurge supply and exhaust, shutdown purge supply and exhaust, and containment atmospheric control fans.
Engineering Group (ISEG) was developed and functioning
The operation of system instrumentation and controls, including the response of system fans and dampers to safety signals, is also verified.


14.2.12.1.60.2  Prerequisites
prior to fuel load.  
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits          are operational.
: c. The containment purge HVAC system has been air balanced.
: d. The compressed air system is available to supply air to system valves and dampers.  


14.2.12.1.60.3  Test Method
The Licensing Section was responsible for coordinating
: a. The containment minipurge supply and exhaust, shutdown purge supply and exhaust, and containment atmospheric control fans are operated, flow data recorded, and fan capacities calculated.
: b. The response of system fans and dampers to safety          signals is verified.


14.2.12.1.60.4  Acceptance Criteria
the review of the NRC Information and Enforcement (IE)
: a. The capacities of the containment minipurge supply and exhaust, shutdown purge supply and exhaust, and containment atmospheric control fans are within design specifications.
Bulletins, Circulars, and Information Notices.  
: b. System fans and dampers align or actuate in response to containment purge isolation and safety injection signals, in accordance with system design. Damper closure times are within design specifications.  


14.2-81    Rev. 0 WOLF CREEK 14.2.12.1.61  Gaseous Radwaste System Preoperational Test                (S-03HA01)
The Startup Group reviewed information provided by the


14.2.12.1.61.1  Objectives
other KG&E Nuclear Divisions and information provided by
: a. To demonstrate the performance characteristics of the gas decay tank drain pump, waste gas compressors, and catalytic hydrogen recombiners, including their response to safety signals.
: b. To verify the operability of system valves, including the response of the waste gas discharge valve to a high-radiation signal.
: c. To verify that system instrumentation and controls          function properly.
14.2.12.1.61.2  Prerequisites
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The component cooling water system is available to supply cooling water to the waste gas compressors and catalytic hydrogen recombiners.
: d. The service gas system is available to provide nitrogen,          hydrogen, and oxygen to the catalytic hydrogen          recombiners.
: e. The reactor makeup water system is available to provide water to the waste gas compressors, catalytic hydrogen recombiners, and the waste gas decay tank drain header.


14.2.12.1.61.3  Test Method
Bechtel and Westinghouse to determine its effect on the  
: a. Performance characteristics of the gas decay tank drain pump, and waste gas compressors are verified.
: b. Hydrogen is introduced to the system and the catalytic hydrogen recombiners performance are verified.
: c. System component control circuits are verified, including component response to safety signals.


14.2.12.1.61.4  Acceptance Criteria
Wolf Creek Initial Test Program, making revisions to
: a. Performance characteristics of the gas decay tank drain pump, waste gas compressors, and catalytic hydrogen recombiners are within design specifications.


14.2-82    Rev. 0 WOLF CREEK      b. The waste gas discharge valve automatically closes on a          high-radiation signal.
test and administrative procedures as required.  
: c. The waste gas compressors trip on a high-high or low-low moisture separator level, high or low moisture separator          pressure, low compressor suction pressure, or low component cooling water flow.
: d. The hydrogen recombiner oxygen feed valve closes on high-high hydrogen concentration in the recombiner feed, high-high oxygen concentration in the recombiner discharge, high cooler-condenser discharge temperature, high-high recombiner discharge temperature, low-low recombiner flow, and high-high recombiner reactor inlet temperature.      e. The hydrogen recombiner oxygen feed valve signal is blocked on high oxygen concentration in the recombiner feed and high catalyst bed temperature.
: f. The volume control tank vent valve closes on a hydrogen recombiner trip, low volume control tank pressure, and low waste gas compressor suction pressure.  


14.2.12.1.62  Emergency  Fuel  Oil  System  Preoperational  Test (S-03JE01)
An instrumented auxiliary feedwater water-hammer test was performed only at


14.2.12.1.62.1  Objectives
Wolf Creek. (This test was not required to be performed. It was being


To demonstrate the capability of the system to provide an adequate fuel supply to the emergency diesel generator fuel oil day tanks and verify that the associated instrumentation and controls are functioning properly.  
performed for the purpose of gathering engineering data only.)  Procedure S-


14.2.12.1.62.2  Prerequisites
O3AL04, Auxiliary Feedwater System Water Hammer Test, required a visual and  
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.


14.2.12.1.62.3  Test Method
audible water hammer test and was completed prior to the issuance of an
: a. Fuel oil is transferred from the fuel oil storage tank to the fuel oil day tanks by means of the transfer pumps. Flow and pressure characteristics are recorded.
: b. Fuel oil day tank levels are varied to verify the transfer pump automatic operations.


14.2-83    Rev. 0 WOLF CREEK      c. Response to fire and emergency diesel generator start          signals are verified.  
operating license. See new Section 14.2.12.1.10.  


14.2.12.1.62.4  Acceptance Criteria
Procedure S-070017, Loss of Heater Drain Pump Test, was performed on Callaway
: a. The transfer pump flow capacity is verified for later comparison to the fuel consumption rate (S-03NF02).
: b. Control circuit automatic operation from fuel oil day tank levels, fire signals, and diesel generator start signals is within design specifications.


14.2.12.1.63  Spent Fuel Pool Crane Preoperational Test (SU3-KE01) 14.2.12.1.63.l  Objectives 
only. This test was conducted to verify analytical assumptions. No
: a. To demonstrate proper operation of the spent fuel pool bridge crane control circuits and associated interlocks.
: b. To document the data obtained during testing of the spent fuel pool bridge crane at 125 percent of rated load.
: c. To verify the ability of the spent fuel pool bridge crane and associated fuel handling tools to transfer a dummy fuel assembly.  


14.2.12.1.63.2 Prerequisites
additional loss of heater drain pump tests are  
: a. Required component testing and instrument calibration          are completed.
: b. Required electrical power supplies and control circuits are operational.
: c. A dummy fuel assembly is available.


14.2.12.1.63.3 Test Method
14.2-17    Rev. 0 WOLF CREEK required, since the data obtained from the first unit test is equally valid for subsequent units. See Section 14.2.12.3.41.  
: a. Operability of the spent fuel pool bridge crane control circuits and associated interlocks is verified.
: b. Ability of the spent fuel pool bridge crane and associated fuel handling tools to transfer a dummy fuel assembly is verified.  


14.2-84    Rev. 0 WOLF CREEK 14.2.12.1.63.4  Acceptance Criteria 
Procedure S-07SF09 RCCA or Bank Worth Measurement at Power, was performed at 50
: a. The spent fuel pool bridge crane electric and manual hoists support 125 percent of their rated load.
: b. The spent fuel pool bridge crane monorail center span deflection at rated load is within design specifications.
: c. The spent fuel pool crane bridge, trolley and hoist speeds at rated loads are within design specifications.
: d. All control circuits and interlocks associated with the spent fuel pool bridge crane operate in accordance with system design.      e. While transferring a dummy fuel assembly, the spent fuel pool bridge crane and associated fuel handling tools operate in accordance with system design.


14.2.12.1.64  New Fuel Elevator Preoperational Test (SU3-KE02)
percent power only at Callaway. Wolf Creek and Callaway have the same core and Nuclear instrumentation system design and the test at Callaway is considered a


14.2.12.1.64.1  Objectives
prototypical test for Wolf Creek. This position was accepted by the NRC in a  
: a. To demonstrate proper operation of the new fuel elevator control circuits and associated interlocks.
: b. To verify the ability of the new fuel elevator to raise and lower a dummy fuel assembly.
14.2.12.1.64.2  Prerequisites 
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. A dummy fuel assembly is available.


14.2.12.1.64.3  Test Method
July 3, 1985 letter to KG&E.  


Operability of the new fuel elevator including control circuits and associated interlocks is verified.
A natural circulation test was performed at Callaway only to demonstrate the  


14.2.12.1.64.4  Acceptance Criteria
length of time to stabilize natural circulation, core flow distribution, and  
: a. All control circuits and interlocks associated with the new fuel elevator operate in accordance with system design.


14.2-85    Rev. 0 WOLF CREEK      b. While raising and lowering a dummy fuel assembly, the          new fuel elevator operates in accordance with system design.  
the ability to establish and maintain natural circulation. Operators


14.2.12.1.65  Fuel  Handling  and  Storage  Preoperational Test                (SU3-KE03)
participating in the tests were able to recognize when natural circulation had


14.2.12.1.65.1  Objectives
stabilized and were able to control saturation margin, RCS pressure, and heat
: a. To verify the ability of the spent fuel cask handling crane, and associated fuel handling tools to transfer a dummy fuel assembly.
: b. To demonstrate proper operation of the spent fuel cask handling crane control circuits and associated          interlocks. 
: c. To document the data obtained during testing of the spent fuel cask handling crane at 125 percent of rated load.


14.2.12.1.65.2  Prerequisites
removal rate without exceeding specified operating limits. These tests were conducted insofar as possible to include all available licensed operators.
: a. Required component testing and instrument calibration are complete.
Licensed operators were trained in these same areas on the simulator. The
: b. Required electrical power supplies and control circuits are operational.
: c. A dummy fuel assembly is available. 14.2.12.1.65.3  Test Method
: a. During the transfer of a dummy fuel assembly, the operability of the spent fuel cask handling crane and associated fuel handling tools is verified.  
: b. Operability of the spent fuel cask handling crane control circuits and associated interlocks is verified.  


14.2.12.1.65.4  Acceptance Criteria
simulator has full capability of simulating natural circulation, using
: a. While transferring a dummy fuel assembly, the spent fuel cask handling crane and associated fuel handling tools operate in accordance with system design.
: b. All control circuits and interlocks associated with the spent fuel cask handling crane operate in accordance with system design.


14.2-86    Rev. 0 WOLF CREEK      c. The spent fuel cask handling crane hoist supports 125          percent of rated load.
Westinghouse data initially. When the above tests were accomplished on the
: d. The spent fuel cask handling crane bridge center span deflection at rated load is within design          specifications.
: e. The spent fuel cask handling crane bridge, trolley and hoist speeds at rated loads are within design specifications.  


14.2.12.1.66  Fuel  Transfer  System  Preoperational  Test (SU3-KE04)
Callaway plant, actual data was incorporated into the Wolf Creek simulator


14.2.12.1.66.l  Objectives      a. To demonstrate proper operation of the fuel transfer system control circuits and associated interlocks.  
program. See Chapter 18, item I.G.1, and Section 14.2.12.3.43.  
: b. To verify the ability of the fuel transfer system and associated handling tools to transfer a dummy fuel assembly.  


14.2.12.1.66.2 Prerequisites
14.2.9 TRIAL USE OF PLANT OPERATING AND EMERGENCY PROCEDURES
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.      c. A dummy fuel assembly is available.


14.2.12.1.66.3  Test Method
The plant operating procedures were utilized, where applicable during the test
: a. Operability of the fuel transfer system control circuits and associated interlocks is verified.
: b. During the transfer of a dummy fuel assembly, the operability of the fuel transfer system and associated handling tools is verified.


14.2.12.1.66.4  Acceptance Criteria
program, to support testing, maintain plant conditions, and facilitate
: a. All control circuits and interlocks associated with the fuel transfer system operate in accordance with system design.


14.2-87    Rev. 0 WOLF CREEK      b. While transferring a dummy fuel assembly, the fuel          transfer system and associated handling tools operate in accordance with system design.  
training. The trial use of operating procedures served to familiarize


14.2.12.1.67  Refueling Machine and RCC Change Fixture                Preoperational Test (SU3-KE05)
operating personnel with systems and plant operation during the testing phase


14.2.12.1.67.1  Objectives
and also served to ensure the adequacy of the procedures under actual or
: a. To demonstrate proper operation of the refueling machine, rod cluster control change fixture and containment building polar crane control circuits and associated interlocks.
: b. To document the data obtained during testing of the           containment building polar crane at 125 percent of rated          load.
: c. To verify the ability of the refueling machine to transfer a dummy fuel assembly.


14.2.12.1.67.2  Prerequisites
simulated operating conditions before plant operation begins. The emergency procedures were verified during startup as plant conditions, testing, and training warrant. Surveillance tests were performed as conditions warrant
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. A dummy fuel assembly is available.      d. A dummy control rod assembly is available.  


14.2.12.1.67.3  Test Method
during the testing program, to demonstrate their adequacy.  
: a. Operability of the refueling machine and rod cluster control change fixture control circuits and associated bridge, trolley, hoist and gripper interlocks is verified.
: b. Operability of the containment building polar crane control circuits and associated interlocks is verified.  


14.2.12.1.67.4  Acceptance Criteria
Plant operating procedures were developed in approximately the same time frame
: a. All control circuits and interlocks associated with the refueling machine and rod cluster control change fixture operate in accordance with system design.


14.2-88    Rev. 0 WOLF CREEK      b. The control circuits and interlocks associated with the           containment building polar crane operate in accordance with system design.
as the preparation of preoperational and initial startup tests. The operating
: c. The containment polar crane main and auxiliary hoists          support 125 percent of their rated load.
: d. The containment polar crane bridge center span deflection at rated load is within design specifications.
: e. The containment polar crane bridge, trolley, and hoist speeds at rated loads are within design specifications.
: f. While transferring a dummy fuel assembly, the refueling          machine operates in accordance with system design.
14.2.12.1.68  Refueling Machine Indexing Test (S-03KE06)


14.2.12.1.68.1  Objectives
procedures were revised as necessary to reflect experience gained during the  
: a. To verify the indexing of the refueling machine and establish bridge rail reference points for future operations.
: b. To demonstrate the ability to transfer the dummy fuel assembly to the reactor vessel.


14.2.12.1.68.2  Prerequisites
testing program.  
: a. Required component testing and instrument calibration          are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. A dummy fuel assembly is available.  


14.2.12.1.68.3 Test Method
14.2.10 INITIAL FUEL LOADING, CRITICALITY, AND POWER
: a. While transferring a dummy fuel assembly with the refueling machine, the bridge rail is marked at key transfer points.


14.2.12.1.68.4  Acceptance Criteria
ASCENSION
: a. The refueling machine can load a dummy fuel assembly in each of the reactor vessel fuel loading locations.


14.2.12.1.69  Fuel Handling System Integrated Preoperational Test (SU3-KE07)
Prior to the commencement of fuel loading, required preoperational test


14.2-89    Rev. 0 WOLF CREEK 14.2.12.1.69.1  Objective To verify the ability of the refueling machine, new fuel elevator, fuel transfer system, spent fuel bridge crane, spent fuel cask handling crane and associated fuel handling tools to transfer a dummy fuel assembly.
procedures were evaluated, and appropriate remedial action  
14.2.12.1.69.2  Prerequisites
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The reactor vessel, refueling pool, refueling canal and           spent fuel pool are filled with demineralized water.  
: d. A dummy fuel assembly is available.


14.2.12.1.69.3  Test Method
14.2-18    Rev. 0 WOLF CREEK was taken if the acceptance criteria was not satisfied. At the completion of fuel loading, the reactor upper internals and pressure vessel head were


During the transfer of a dummy fuel assembly, the operability of the refueling machine, new fuel elevator, fuel transfer system, spent fuel bridge crane, spent fuel cask handling crane and associated fuel handling tools is verified.
installed, and additional mechanical and electrical tests were performed to


14.2.12.1.69.4  Acceptance Criteria
prepare the plant for nuclear operation. After final precritical tests,


While transferring a dummy fuel assembly, the refueling machine, new fuel elevator, fuel transfer system, spent fuel bridge crane, spent fuel cask handling crane and associated fuel handling tools operate in accordance with system design.
nuclear operation of the reactor began. This phase of testing included initial criticality, low power testing, and power level ascension. The purpose of
14.2.12.1.70  Diesel  Generator  Mechanical Preoperational  Test (S-03KJ01)


14.2.12.1.70.1  Objectives
these tests was to establish the operational characteristics of the unit and  
: a. To demonstrate the performance characteristics of the diesel generators and associated auxiliaries, and verify that each diesel reaches rated speed within the required time.
: b. To verify the operability of all control circuits associated with the diesel generator and diesel auxiliaries, including the control circuits response to safety signals.


14.2-90    Rev. 0 WOLF CREEK      c. To demonstrate the capability of each air storage tank to         provide five diesel cranking cycles without being recharged.
core, to acquire data for the proper calibration of setpoints, and to ensure


14.2.12.1.70.2  Prerequisites 
that operation is within license requirements. Section 14.2.12.3 summarizes
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The essential service water system is available to provide cooling water to the diesel engine intercooler heat exchanger.      d. The emergency fuel oil system is available to provide fuel oil to the diesel generators.
: e. The fire protection system is available to support this test.


14.2.12.1.70.3  Test Method
the tests which are performed from fuel load to rated power. The fuel loading
: a. The diesel generators are started, and the time required to reach rated speed is recorded.
: b. With the diesel generators and associated auxiliaries operating, performance characteristics are verified.
: c. The operability of all control circuits associated with          the diesel generator and diesel auxiliaries, including the control circuits' response to safety signals, is verified.
: d. The ability of each air storage tank to provide five diesel cranking cycles, without being recharged, is verified.


14.2.12.1.70.4  Acceptance Criteria
and post loading tests are described below.  
: a. The time required for each diesel generator to reach rated speed is within design specifications.
: b. The performance characteristics of the diesel generators and associated auxiliaries are within design specifications.
: c. Each diesel generator starts automatically on receipt of a safety injection signal or a bus under-voltage signal.  


14.2-91    Rev. 0 WOLF CREEK      d. Each diesel generator trips automatically on receipt of          each of the following signals:
14.2.10.1  Fuel Loading The Plant Manager or his designated representative with technical assistance


Lube oil pressure low Jacket coolant temperature high                Crankcase pressure high Start failure Engine overspeed Diesel generator ground overcurrent Diesel generator differential current
provided by Westinghouse, was responsible for the coordination of initial core
: e. The diesel generator neutral ground overcurrent trip signal is bypassed when the diesel generator is operating in the emergency mode.
: f. Each air storage tank is capable of providing five          diesel cranking cycles, without being recharged.
: g. Each starting air compressor has the ability to charge its respective air tank from minimum to normal pressure within the required time.


14.2.12.1.71  4160-V  (Class IE)  System  Preoperational Test (S-03NB01)
loading. The overall process of initial core loading was, in general, directed from the operating floor of the containment structure by a licensed senior


14.2.12.1.71.1  Objectives
reactor operator. The licensed senior reactor operator had no additional
: a. To demonstrate that the 4,160-V Class IE busses can be energized from their normal and alternate sources.
: b. To verify that a 4,160-V Class IE bus digital          undervoltage signal trips the associated incoming feeder breakers.
: c. To verify that a degraded bus voltage condition will trip the associated incoming feeder breakers.
: d. To verify proper operation of system instrumentation and alarms.  


14.2.12.1.71.2  Prerequisites
responsibilities other than core load operations.  
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.  


14.2-92    Rev. 0 WOLF CREEK 14.2.12.1.71.3  Test Method 
The core configuration was specified as part of the core design studies
: a. The 4,160-V Class IE busses are energized from their normal source, and bus voltages are recorded.
: b. The 4,160-V Class IE busses are energized from their alternate source, and bus voltages are recorded.
: c. 4,160-V Class IE bus undervoltage signals are simulated, and proper operation of the 4,160-V Class IE feeder breakers is verified.


14.2.12.1.71.4  Acceptance Criteria
conducted well in advance of fuel loading. In the event mechanical damage was
: a. The voltage of each 4,160-V Class IE bus, when supplied          from its normal source, is within design specifications.
: b. The voltage of each 4,160-V Class IE bus, when supplied from its alternate source, is within design specifications.
: c. A 4,160-V Class IE bus digital undervoltage signal will trip the appropriate bus incoming feeder breakers.
: d. A degraded voltage condition on either 4,160-V Class IE bus will cause an alarm and, if it continues, trip the appropriate bus incoming feeder breakers.
: e. A degraded voltage condition on either 4,160-V Class IE bus coincident with a safety injection actuation signal          will immediately trip the bus incoming feeder breakers.
14.2.12.1.72  Diesel Generator Electric Preoperational Test (S-03NE01)


14.2.12.1.72.1  Objectives
sustained during core loading operations to a fuel assembly of a type for which
: a. To demonstrate that each diesel generator is capable of 35 consecutive valid starts with no failure.
 
: b. To demonstrate the ability of each diesel generator to carry the design load for the time required to reach equilibrium temperature plus l hour, without exceeding design limits.
no spare was available onsite, an alternate core loading scheme could have been
: c. To demonstrate the ability of each diesel generator to attain and stabilize frequency and voltage within the design limits and time.


14.2-93    Rev. 0 WOLF CREEK      d. To demonstrate the capability of each diesel generator          to withstand a full-load rejection without exceeding speeds or voltages that cause tripping or damage.
determined. Any such changes would have been approved by the appropriate
: e. To demonstrate the operability of each diesel generator          feeder breaker and associated interlocks.
: f. To demonstrate the ability of the diesel cooling water system to maintain the diesel temperature within design specifications, while the diesel generators are operating at full load.
: g. To demonstrate the ability of each diesel generator to start and shed the largest single motor while supplying all other sequenced loads, maintaining voltage and          frequency within design limits.
14.2.12.l.72.2  Prerequisites
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The essential service water system is available to provide cooling water to the diesel generator intercooler heat exchanger.
: d. The emergency fuel oil system is available to provide          fuel oil to the diesel generators. 
: e. The fire protection system is available to support this test.
: f. The 4.16-kV busses are available for loading to support this test.


14.2.12.1.72.3  Test Method
Westinghouse personnel.
: a. The ability of each diesel generator to undergo 35 consecutive starts with no failure is verified.
Core loading procedures specified the condition of fluid systems to prevent
: b. The ability of each diesel generator to carry the design load for the time required to reach equilibrium temperature, plus 1 hour, without exceeding design limits, is verified.


14.2-94    Rev. 0 WOLF CREEK      c. The ability of each diesel generator to attain and          stabilize frequency and voltage within the design limits and time is verified.
inadvertent changes in boron concentration of the reactor coolant; the movement
: d. The ability of each diesel generator to withstand a          full-load rejection, without exceeding speeds or voltages that cause tripping, is verified.
: e. The operability of each diesel generator feeder breaker and associated interlocks is verified.
: f. While operating each diesel generator at full-load conditions, the ability of the diesel cooling water system to maintain diesel temperatures within design specifications is verified.      g. The ability of each diesel generator to start and shed the largest fully loaded single motor while supplying all other sequenced loads and maintain voltage and frequency within design limits is verified.


14.2.12.1.72.4  Acceptance Criteria
of fuel to preclude the possibility of mechanical damage; the conditions under
: a. Each diesel generator is capable of carrying the design load for the time required to reach equilibrium temperature, plus 1 hour, without exceeding design limits.
: b. Each diesel generator can attain and stabilize frequency and voltage within design limits and time.      c. Each diesel generator is capable of withstanding a full-load rejection without exceeding speeds or voltages that cause tripping.
: d. When a diesel generator is operating in the nonemergency (test) mode, the associated diesel generator feeder breaker trips on receipt of any of the following signals:


Generator overcurrent Reverse power Loss of field Underfrequency
which loading could proceed; and the responsibility and authority for
: e. The diesel generator stops and the associated diesel generator feeder breaker trips on receipt of any of the following signals:


Generator differential current Neutral ground overcurrent
continuous and complete fuel and core component accountability.


14.2-95    Rev. 0 WOLF CREEK      f. When a diesel generator is operating in the emergency          mode, the following trip signals are bypassed:  
The following conditions were met prior to core loading:  
: a. The reactor containment structure was complete and


Neutral ground overcurrent Generator overcurrent                Reverse power Loss of field Underfrequency
containment integrity had been demonstrated.  
: g. Each diesel generator cooling water system, with the diesel generators operating at full-load, maintains the diesel temperatures within design specifications.  
: b. Fuel handling tools and equipment were checked out and  
: h. Each diesel generator has the capability of starting and shedding the largest fully loaded single motor while          supplying all other sequenced loads, maintaining voltage          and frequency within design limits.
: i. Diesel generators are capable of 35 consecutive valid starts with no failure.


14.2.12.1.73  Integrated Control Logic Test (SU3-NF01)
operators familiarized in the use and operation of


14.2.12.1.73.1  Objectives
equipment. Inspections of fuel assemblies, rod cluster control assemblies, and reactor vessel were satisfactorily completed.  
: a. To demonstrate that the actuation of the LOCA sequencer, shutdown sequencer, safety-related load shed, and nonsafety-related load shed circuits on receipt of the appropriate undervoltage, safety injection, containment spray actuation, diesel generator breaker position, and          normal and alternate 4,160-V feeder breaker position          signals is in accordance with system design.
: b. To demonstrate that the LOCA sequencer, shutdown sequencer,  safety-related  load  shed,  and nonsafety-related load shed circuits shed and sequence loads in accordance with system design.  


14.2.12.1.73.2  Prerequisites
14.2-19    Rev. 0 WOLF CREEK
: a. Required component testing and instrument calibration are complete.
: c. The reactor vessel and associated components were in a state of readiness to receive fuel. The water level was
: b. Required electrical power supplies and control circuits are operational.  


14.2.12.1.73.3  Test Method
maintained above the bottom of the nozzles and  
: a. Undervoltage, safety injection, containment spray actuation, diesel generator breaker position, and normal and 


14.2-96    Rev. 0 WOLF CREEK          alternate 4,160-V feeder breaker position signals are          initiated, and the actuation of the LOCA sequencer, shutdown sequencer, safety-related load shed, and nonsafety-related load shed circuits is verified.
recirculation maintained to ensure the required boron
: b. Signals are initiated to actuate the LOCA sequencer, shutdown sequencer, safety-related load shed, and nonsafety-related load shed circuits, and proper load shed and load sequencing are verified.


14.2.12.1.73.4  Acceptance Criteria
concentration could be increased via the recirculation path or directly to the open vessel.  
: a. Actuation of the LOCA sequencer, shutdown sequencer, safety-related load shed, and nonsafety-related load shed circuits on receipt of under-voltage, safety          injection, containment spray actuation, diesel generator          breaker position, and normal and alternate 4,160-V feeder breaker position signals is in accordance with system design.
: b. The LOCA sequencer, shutdown sequencer, safety-related load shed, and nonsafety-related load shed circuits shed and sequence loads in accordance with system design.  


14.2.12.1.74  LOCA Sequencer Preoperational Test (S-03NF02)
Criteria for safe loading required that loading operations stop immediately if


14.2.12.1.74.1  Objectives
any of the following conditions occur.  
: a. To demonstrate that initiation of a safety injection signal (SIS) will shed the nonsafety-related loads,          start the diesel generator, and sequence the associated          equipment. The ability of each 4,160-V Class IE load group to supply the sequenced loads while maintaining voltage within design specifications is also verified.  
: a. An unanticipated increase in the neutron count rates by a
: b. To demonstrate that a loss of offsite power concurrent with SIS will shed the safety-related loads, start the diesel generator, close the diesel generator feeder breaker, and sequence the associated equipment. The ability of each diesel generator to supply the sequenced loads while maintaining voltage and frequency within design specifications is also verified.
: c. To demonstrate the ability of each diesel generator to carry the short-time rating load for 2 hours and the continuous rated load for 22 hours, without exceeding design limits.
: d. To demonstrate that each diesel generator, following operation  for  2 hours at the short-time rated load and 


14.2-97    Rev. 0 WOLF CREEK          22 hours at the continuous rated load, will start          automatically on a loss of ac voltage concurrent with an SIS, attain voltage and frequency within design limits and time, and accept the LOCA sequenced loads, while maintaining voltage and frequency within design limits. 
factor of two occurs on all responding nuclear channels
: c. To demonstrate the ability of the diesel cooling water system to maintain the diesel temperature within design specifications, while the diesel generators are operating for 2 hours at the short-time rating load and 22 hours at the continuous rating load.
: f. To determine the fuel oil consumption of each diesel, while operating for 22 hours at the continuous rating load.      g. To demonstrate the ability of the 125 V dc system to perform its design functions while at minimum voltage.
: h. To demonstrate the independence between the redundant on ac and dc power sources.


14.2.12.1.74.2  Prerequisites
during any single loading step after the initial nucleus
: a. Required component testing and instrument calibration are complete.
: b. Each diesel generator and its associated auxiliaries are available.
: c. All components actuated by the LOCA sequencer and          safety-related and nonsafety-related load shed circuits are available.


14.2.12.1.74.3  Test Method
of eight fuel assemblies is loaded.  
: a. A train A SIS is initiated, and the following are verified:
: b. An unanticipated increase in the count rate by a factor of five on any individual responding nuclear channel
: 1. Group l nonsafety-related loads are shed.  
: 2. Group 1 diesel generator starts.
: 3. Group 1 LOCA sequencer is actuated, and associated components are sequenced. The times for sequenced pumps to reach full flow are verified.
: 4. With bus NB01 supplying the sequenced loads from its normal source, bus voltage is recorded.


14.2-98    Rev. 0 WOLF CREEK      b. With group 2 dc load group isolated from its power          source and group 1 dc load group voltage set to minimum, a loss of offsite power is initiated concurrent with a train A SIS, and the following are verified:
during any single loading step after the initial nucleus
: 1. Safety-related group 1 loads are shed.
: 2. Group 1 diesel generator starts, and its feeder breaker closes.
: 3. Group 1 LOCA sequencer is actuated, and associated components are sequenced. The times for sequenced pumps to reach full flow are verified.
: 4. With the group 1 diesel generator supplying the                sequenced loads, bus voltage and frequency are                recorded.
: 5. The group 2 ac and dc busses are monitored to verify the absence of voltage on these busses and loads, indicating no interconnection at load groups.
: c. The ability of the group 1 diesel generator to carry the short-time rating load for 2 hours without exceeding design limits is verified.
: d. The ability of the group 1 diesel generator to carry the continuous rated load for 22 hours without exceeding design limits is verified. Group l diesel fuel oil          consumption is also determined. 
: e. Following group 1 diesel generator operation for 2 hours at the short-time rated load and 22 hours at the continuous rated load, the group 1 diesel generator is shutdown, a loss of group 1 ac voltage is initiated concurrent with a train A SIS, and the ability of the group l diesel generator to start, attain voltage and frequency within design limits and time, and accept the loads resulting from the design accident loading sequence while maintaining voltage and frequency within design limits is verified. If this test is not satisfactorily completed,  it is not necessary to repeat the tests of items c and d prior to rerunning this test. Instead, prior to rerunning this test, the diesel generator may be operated at the continuous rated load for l hour or until operating temperature has stabilized.


14.2-99    Rev. 0 WOLF CREEK      f. A train B SIS is initiated, and the following are          verified:
of eight fuel assemblies is loaded.  
: 1. Group 2 nonsafety-related loads are shed.
: c. An unanticipated decrease in boron concentration greater
: 2. Group 2 diesel generator starts.
: 3. Group 2 LOCA sequencer is actuated, and associated components are sequenced. The times for sequenced pumps to reach full flow are verified.
: 4. With Bus NB02 supplying the sequenced loads from its normal source, bus voltage is recorded.
: g. With group 1 dc load group isolated from its power          source and group 2 dc load group voltage set to minimum,          a loss of offsite power is initiated concurrent with a train B SIS, and the following are verified:
: 1. Safety-related group 2 loads are shed.
: 2. Group 2 diesel generator starts, and its feeder breaker closes.
: 3. Group 2 LOCA sequencer is actuated, and associated components are sequenced. The times for sequenced pumps to reach full flow are verified.
: 4. With the group 2 diesel generator supplying the sequenced loads, bus voltage and frequency are                recorded. 
: 5. The group l ac and dc busses are monitored to verify the absence of voltage on these busses and loads, indicating no interconnection of load groups.
: h. The ability of the group 2 diesel generator to carry the short-time rating load for 2 hours without exceeding design limits is verified.  
: i. The ability of the group 2 diesel generator to carry the continuous rated load for 22 hours without exceeding design limits is verified. Group 2 diesel fuel oil consumption is also determined.  


14.2-100    Rev. 0 WOLF CREEK      j. Following group 2 diesel generator operation for 2 hours          at the short-time rated load and 22 hours at the continuous rated load, the group 2 diesel generator is shutdown, a loss of group 2 ac voltage is initiated concurrent with a train B SIS, and the ability of the          group 2 diesel generator to start, attain voltage and frequency within design limits and time, and accept the LOCA sequenced loads, while maintaining voltage and frequency within design limits, is verified. If this test is not satisfactorily completed, it is not necessary to repeat the tests of items h and i prior to rerunning this test. Instead, prior to rerunning this test, the diesel generator may be operated at the continuous rated load for l hour or until operating temperature has stabilized.      k. The ability of the diesel cooling water system to maintain the diesel temperature within design specifications, while the diesel generators are operating for 2 hours at the short-time rating load and 22 hours at the continuous rating load, is verified.
than 20 ppm is determined from two successive samples of  


14.2.12.1.74.4  Acceptance Criteria
the reactor coolant.  
: a. A train A SIS initiates the following, in accordance with system design:
: 1. Group 1 nonsafety-related loads are shed.
: 2. Group 1 diesel generator starts.            3. Group l LOCA sequencer actuates, and the associated components are sequenced. Sequenced pumps reach full flow within the required times.
: b. Bus NB01, while powered from its normal source, supplies the sequenced loads while maintaining voltage within design specifications.
: c. With the group 2 dc load group isolated from its power source and the group 1 dc load group voltage at minimum, a loss of offsite power concurrent with a train A SIS initiates the following, in accordance with system design:
: 1. Safety-related group 1 loads are shed.
: 2. Group 1 diesel generator starts, and its feeder breaker closes.  


14.2-101    Rev. 0 WOLF CREEK          3. Group l LOCA sequencer actuates, and the associated                components are sequenced. Sequenced pumps reach full flow within design times.
Loading operations could not be restarted until the situation was evaluated.
: d. Group l diesel generator supplies the sequenced loads,          while maintaining voltage and frequency within design specifications.
: e. With load group 1 supplying loads following a loss of offsite power concurrent with a train A SIS, the group 2 ac and dc busses are verified de-energized, indicating no interconnection of load groups.
: f. Following group 1 diesel generator operation for 2 hours at the short-time rated load and 22 hours at the          continuous rated load, the group 1 diesel generator          starts, attains voltage and frequency within design limits and time, and accepts the LOCA sequenced loads while maintaining voltage and frequency within design limits, on loss of group 1 ac voltage concurrent with a train A SIS.
: g. A train B SIS initiates the following, in accordance with the system design:
: 1. Group 2 nonsafety-related loads are shed.
: 2. Group 2 diesel generator starts.
: 3. Group 2 LOCA sequencer actuates, and the associated              components are sequenced. Sequenced pumps reach              full flow within design times.
: h. Bus NB02, while powered from its normal source, supplies the required loads while maintaining the voltage within design specifications.
: i. With the group 1 dc load group isolated from its power source and the group 2 dc load group voltage at minimum, a loss of offsite power concurrent with a train B SIS initiates the following, in accordance with system design:
: 1. Safety-related group 2 loads are shed.
: 2. Group 2 diesel generator starts, and its feeder breaker closes.  


14.2-102    Rev. 0 WOLF CREEK          3. Group 2 LOCA sequencer actuates, and the associated                components are sequenced. Sequenced pumps reach full flow within design times.
An alarm in the containment and main control room was coupled to the source
: j. Group 2 diesel generator supplies the required loads,          while maintaining voltage and frequency within design specifications.
: k. With load group 2 supplying loads following a loss of offsite power concurrent with a train B SIS, the group 1 ac and dc busses are verified de-energized, indicating no interconnection of load groups.
: l. Following group 2 diesel generator operation for 2 hours at the short-time rated load and 22 hours at continuous          rated load, group 2 diesel generator starts, attains          voltage and frequency within design limits and time, and accepts the LOCA sequenced loads while maintaining voltage and frequency within design limits, on loss of group 2 ac voltage concurrent with a train B SIS.
: m. Each diesel generator is capable of carrying the short-time rating load for 2 hours and the continuous rated load for 22 hours, without exceeding design limits.
: n. Fuel oil consumption of each diesel, while operating at the continuous rated load, is within design specifications.
: o. Each diesel generator cooling water system, with the          diesel generators operating for 2 hours at the short-          time rating load and 22 hours at the continuous rating load, maintains the diesel temperatures within design specifications.
: p. The controls required for the loss of offsite power concurrent with a SIS (shedding, sequencing, etc.)
function with minimum dc voltage available.


14.2.12.1.75  Shutdown Sequencer Preoperational Test (S-03NF03)
range channels with a setpoint equal to or less than five times the current


14.2.12.1.75.1  Objectives
count rate. This alarm automatically alerts the loading operation personnel of  
: a. To demonstrate that de-energization of either 4,160-V Class IE load group will start the associated diesel generator,  close the diesel  generator  feeder breaker, actuate the associated group load shed, and actuate the shutdown sequencer. All sequenced components are verified to start within required design times.


14.2-103    Rev. 0 WOLF CREEK      b. To demonstrate that each diesel generator will maintain          voltage and frequency within design specifications while supplying the design shutdown loads.
high count rate, and an immediate stop of all operations would be required
: c. To demonstrate the ability of the emergency 4.16-kV          loads to start at maximum and minimum design voltages.


14.2.12.1.75.2  Prerequisites
until the situation was evaluated. In the event the evacuation alarm was actuated during core loading and after it has been determined that no hazards to personnel exist, preselected personnel would be permitted to reenter the  
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. Each diesel generator and its associated auxiliaries are          available.
: d. All components actuated by the shutdown sequencer are available.


14.2.12.1.75.3  Test Method
containment to evaluate the cause and determine future action.  
: a. Class IE 4,160-V load group 1 is de-energized and the following are verified:
 
: 1. Group 1 load shedder actuates.
The core was assembled in the reactor vessel and submerged in the reactor grade
: 2. Group 1 diesel generator starts, and its feeder breaker closes.            3. Group 1 shutdown sequencer is actuated, and associated components are sequenced. Components are verified to actuate within the required design times.
: b. Class IE 4,160-V load group 2 is de-energized and the following are verified:
: 1. Group 2 load shedder actuates.  
: 2. Group 2 diesel generator starts, and its feeder breaker closes.
: 3. Group 2 shutdown sequencer is actuated, and associated components are sequenced. Components are verified to actuate within the required design times.


14.2-104    Rev. 0 WOLF CREEK      c. Emergency 4.16-kV loads are started while their          respective diesel generators are supplying:
water containing sufficient dissolved boric acid to maintain a calculated core
: 1. Minimum rated voltage
: 2. Maximum rated voltage
: d. The ability of each diesel generator to maintain voltage and frequency within the design specifications while supplying the design shutdown loads is verified.


14.2.12.1.75.4  Acceptance Criteria
effective multiplication factor of 0.95 or lower. The refueling pool could be
: a. De-energization of Class IE 4,160-V load group 1 initiates the following, in accordance with system          design: 
: 1. Group 1 diesel generator starts, and its feeder breaker closes.
: 2. Group 1 shutdown sequencer actuates, and associated components are sequenced. Components actuate within required design times.
: 3. Group 1 load shedder actuates.
: b. De-energization of Class IE 4,160-V load group 2 initiates the following, in accordance with system design:
: 1. Group 2 diesel generator starts, and its feeder                breaker closes.
: 2. Group 2 shutdown sequencer actuates, and associated components are sequenced. Components actuate within required design times.
: 3. Group 2 load shedder actuates.
: c. The emergency 4.16-kV loads start and reach rated speed within design times, with minimum and maximum design voltage.
: d. Each diesel generator maintains voltage and frequency within design specifications, while supplying the design shutdown loads.


14.2.12.1.76  480-V  (Class  IE)  System  Preoperational    Test (S-03NG01)
wet or dry during initial core loading. Core moderator, chemistry conditions


14.2.12.1.76.1  Objectives
(particularly boron concentration) were prescribed in the core loading


To demonstrate that the 480-V Class IE load centers can be energized  from their normal and alternate sources and verify the 
procedure document and verified by chemical analysis of moderator samples taken


14.2-105    Rev. 0 WOLF CREEK operability of system breaker protective interlocks. Proper operation of system instrumentation and controls is also verified.  
prior to and during core loading operations.  


14.2.12.1.76.2  Prerequisites
At least two artificial neutron sources were introduced into the core at
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.


14.2.12.1.76.3  Test Method
specified points in the core during the loading program to ensure a detector
: a. The 480-V Class IE load centers are energized from their normal source, and voltages are recorded.      b. The 480-V Class IE load centers are energized from their alternate source, and voltages are recorded.
: c. System breakers are operated, and breaker interlocks verified.


14.2.12.1.76.4  Acceptance Criteria
response of at least 2 counts per second attributable to neutrons.  
: a. The voltage for each 480-V Class IE load center, when supplied from its normal source, is within design specifications.
: b. The voltage for each 480-V Class IE load center, when supplied from its alternate source, is within design          specifications. 
: c. System breaker interlocks operate in accordance with the system design.  


14.2.12.1.77  480-V Class IE System (ESW) Preoperational Test (SU3-NG02).
14.2-20    Rev. 0 WOLF CREEK Core loading instrumentation consisted of two permanently installed source range (pulse type) nuclear channels and two temporary incore source range


14.2.12.1.77.1  Objectives
channels. A third temporary channel could also be used as a spare. The


To demonstrate that the nonpower block 480-V Class IE MCC can be energized from their normal source and to verify their bus voltage phase sequence. Proper operation of system instrumentation and controls is also verified.
permanent channels, when responding, were monitored in the main control room,


14.2.12.1.77.2 Prerequisites
and the temporary channels were installed and monitored in the containment. At least one permanent channel was equipped with an audible count rate indicator.   
: a. Required component testing and instrument calibration are completed.


14.2-106    Rev. 0 WOLF CREEK      b. Required electrical power supplies and control circuits          are operational.
Both plant channels have the capability of displaying the neutron flux level on


14.2.12.1.77.3  Test Method The nonpower block 480-V Class IE MCC are energized, voltages are recorded, and phase sequence is verified.
a strip chart recorder. The temporary channels indicated on scalers, and a


14.2.12.1.77.4  Acceptance Criteria
minimum of one channel was recorded on a strip chart recorder. Normally minimum
: a. The voltage for each nonpower block 480-V Class IE MCC is within design specification.
: b. The bus voltage phase sequence of the nonpower block 480-V Class IE MCC is in accordance with design. 14.2.12.1.78  125-V (Class IE) DC System Preoperational Test (S-03NK01)


14.2.12.1.78.1  Objectives
count rates of two counts per second attributable to core neutrons were


To demonstrate the ability of the batteries and chargers to provide power during normal operations and the battery to provide power during abnormal conditions. The battery chargers' ability to recharge their respective battery is also demonstrated. Proper operation of the system instrumentation and controls is also verified.
required on at least two of the four (i.e. two temporary and two permanent


14.2.12.1.78.2  Prerequisites
source range detectors) available nuclear source channels at all times
: a. Required component testing and instrument calibration          are complete. 
: b. Required electrical power supplies and control circuits are operational.
: c. Ventilation for the battery rooms is available.


14.2.12.1.78.3  Test Method
following installation of the initial nucleus of eight fuel assemblies. A
: a. Each battery is discharged, using a test load at the design duty cycle discharge rate.
: b. Each battery is fully discharged to determine its capacity factor.
: c. Each battery charger will charge its respective battery to normal conditions, after the battery has undergone a design duty cycle, while simultaneously supplying power at a rate equivalent to the design emergency loading.  


14.2-107    Rev. 0 WOLF CREEK 14.2.12.1.78.4  Acceptance Criteria 
response check of nuclear instruments to a neutron source was performed within
: a. Each battery is capable of maintaining output voltage above the design minimum, during a design duty cycle.
: b. Each battery has a capacity factor greater than or equal to design.
: c. The battery chargers are able to recharge the batteries to normal conditions, after the battery has undergone a design duty cycle, while simultaneously supplying power at a rate equivalent to the design emergency loading.


14.2.12.1.79  Instrument AC System (Class IE) Preoperational Test (S-03NN01)  14.2.12.1.79.1  Objectives
8 hours prior to loading of the core, or upon resumption of loading if delay was for more than 8 hours.  


To demonstrate that the 120-V Class IE ac distribution panel- boards can be fed from their normal source inverters and from their backup source transformers by manual transfer. The operability of system instrumentation and controls, including breaker protective interlocks, is also verified.
Fuel assemblies, together with inserted components (control rod assemblies,  


14.2.12.1.79.2  Prerequisites
burnable, poison assemblies, source spider, or thimble plugging devices) were
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational. 14.2.12.1.79.3  Test Method
: a. The 120-V Class IE ac distribution panelboards are energized from their normal source inverters, and panelboard voltages are recorded.
: b. The 120-V Class IE ac distribution panelboards are energized from their backup source transformers by manual transfer, and panelboard voltages are recorded.
: c. The system breakers are operated, and breaker interlocks are verified.


14.2.12.1.79.4  Acceptance Criteria
placed in the reactor vessel one at a time, according to a previously
: a. Each 120-V Class IE ac distribution panelboard voltage, when supplied from the normal source inverters of the panelboards, is within design specifications.


14.2-108    Rev. 0 WOLF CREEK      b. Each 120-V Class IE ac distribution panelboard voltage,          when supplied from the backup source transformers, is within design specifications.
established and approved sequence developed to provide reliable core monitoring
: c. System breaker interlocks operate in accordance with          system design.


14.2.12.1.80  Engineered Safeguards (NSSS) Preoperational Test (SU3-SA01)
with minimum possibility of core mechanical damage. The core loading procedure


14.2.12.1.80.1  Objectives
documents prescribed the successive movements of each fuel assembly and its
: a. To demonstrate the ability of the NSSS to initiate safety injection, containment isolation, containment spray actuation, main feedwater isolation, and steam          line isolation signals on receipt of the associated          input signals.
: b. To verify NSSS ESFAS loop response times.
: c. To demonstrate the ability of each solid-state protection system test panel to adequately test the associated NSSS ESFAS and reactor protection logic trains.
: d. To demonstrate the coincidence and redundancy of the NSSS ESFAS.
: e. To verify the operability of ESFAS block and permissive interlocks. 14.2.12.1.80.2  Prerequisites
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies are operational.


14.2.12.1.80.3  Test Method
specified inserts from its initial position in the storage racks to its final
: a. The ability of the NSSS ESFAS to actuate safety injection,  containment  isolation,  containment spray actuation, main feedwater isolation, and steam line isolation signals on receipt of the required coincidence of the following input signals for each redundant channel is verified:


          . High steam line pressure rate
position in the core. Fuel assembly status boards were maintained throughout
          . Low steam line pressure
          . Low pressurizer pressure


14.2-109    Rev. 0 WOLF CREEK          . High containment pressure (Hi-1, Hi-2, and Hi-3)          . High-high steam generator level
the core loading operation.  
          . Low Tavg
          . Low-low steam generator water level
: b. Input signals are initiated, and loop response times are verified.
: c. The ability of each solid-state protection system test panel to test the NSSS ESFAS logic trains is verified.
: d. ESFAS block and permissive interlocks are verified.  


14.2.12.1.80.4  Acceptance Criteria
An initial nucleus of eight fuel assemblies, one containing a neutron source,  
: a. The NSSS ESFAS actuates safety injection, containment          isolation, containment spray actuation, main feedwater isolation, and steam line isolation signals when their associated input signals are received from the following signals for each applicable channel:


          . High steam line pressure rate
is the minimum source-fuel nucleus which permitted subsequent meaningful
          . Low steam line pressure
          . Low pressurizer pressure
          . High containment pressure (Hi-1, Hi-2, and Hi-3)
          . High-high steam generator level
          . Low Tavg
          . Low-low steam generator water level
: b. NSSS ESFAS loop response times are within design          specifications. 
: c. ESFAS block and permissive interlocks operate in accordance with system design.


14.2.12.1.81  Engineered  Safeguards  (BOP)  Preoperational Test (SU3-SA02)
inverse count rate monitoring. This initial nucleus was determined by calculation to be markedly subcritical (K eff  0.95) under the required conditions of loading.  


14.2.12.1.81.1  Objectives
Each subsequent fuel addition was accompanied by detailed neutron count rate
: a. To demonstrate the operability of the BOP ESFAS to initiate containment purge isolation, control room ventilation isolation, fuel building ventilation isolation, auxiliary feedwater pump actuation, auxiliary feedwater suction valve switchover to essential service water (ESW), and steam generator blowdown and sample isolation signals on receipt of the associated input signals.


14.2-110    Rev. 0 WOLF CREEK      b. To verify BOP ESFAS loop response times. 
monitoring to determine that the just-loaded fuel assembly did not excessively
: c. To demonstrate the ability of the BOP ESFAS test panel to adequately test the associated BOP ESFAS logic trains. 
: d. To demonstrate the coincidence and redundancy of the BOP ESFAS.


14.2.12.1.81.2  Prerequisites
increase the count rate and that the extrapolated inverse count rate ratio was
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies are operational. 14.2.12.1.81.3  Test Method
: a. The ability of the BOP ESFAS to actuate containment purge isolation, control room ventilation isolation, fuel building ventilation isolation, auxiliary feedwater pump actuation, auxiliary feedwater suction valve switchover to ESW, and steam generator blowdown and sample isolation signals on receipt of the required coincidence of the following input signals for each redundant channel is verified.


o    Containment isolation (phase A) o    High atmospheric radiation o    High chlorine concentration          o    Loss of main feedwater flow          o    Low-low steam generator level o    Loss of offsite power o    Low feedwater pump suction pressure o    Safety injection
behaving as expected. These results for each loading step were evaluated before
: b. Input signals are initiated, and loop response times are verified.
: c. The ability of the BOP ESFAS test panel to test the BOP ESFAS logic trains is verified.  


14.2.12.1.81.4  Acceptance Criteria
the next fuel assembly was loaded. The final, as loaded, core configuration
: a. The BOP ESFAS actuates containment purge isolation, control room ventilation isolation, fuel building ventilation isolation, auxiliary feedwater pump actuation, auxiliary feedwater suction valve switchover to ESW, and 


14.2-111    Rev. 0 WOLF CREEK            steam generator blowdown and sample isolation signals when their associated input signals are received from the following signals for each applicable channel:
was subcritical (K eff < 0.95) under the required loading conditions.  
o    Containment isolation (phase A) o    High atmospheric radiation o    High chlorine concentration o    Loss of main feedwater flow o    Low-low steam generator level o    Loss of offsite power o    Low feedwater pump suction pressure o    Safety injection
: b. BOP ESFAS loop response times are within design          specifications.
14.2.12.1.82  Engineered Safeguards Verification Test (SU3-SA03)


14.2.12.1.82.1  Objectives
14.2-21    Rev. 0 WOLF CREEK 14.2.10.2 Initial Criticality Prior to initial criticality, the following tests were performed and the


To demonstrate the proper response of actuated components resulting from the following safety signals:  Safety injection, containment spray actuation, main feedwater isolation, steam line isolation, containment isolation, containment purge isolation, control room ventilation isolation, fuel building ventilation isolation, auxiliary feedwater pump actuation, auxiliary feedwater suction valve switch over to ESW, and steam generator blowdown and sample isolation.
results evaluated.
: a. At the completion of core loading, the reactor upper


14.2.12.1.82.2 Prerequisites
internals and pressure vessel head were installed. A
: a. Required component testing and instrument calibration          are complete.
: b. Required electrical power sources and control circuits are operational.
: c. Components actuated by the NSSS and BOP ESFAS are available.  


14.2.12.1.82.3  Test Method
pressure test was conducted after filling, and venting


NSSS and BOP ESFAS signals are initiated manually and the proper response and response times of the actuated components are verified.
was completed to check the leaktightness of the vessel


14.2-112    Rev. 0 WOLF CREEK 14.2.12.1.82.4  Acceptance Criteria Components required to actuate on receipt of safety signals respond properly in accordance with design specifications and within the times specified by design requirements.
head installation.  
14.2.12.1.83  Reactor Protection System Logic Test (S-03SB01)
: b. Mechanical and electrical tests were performed on the  


14.2.12.1.83.1  Objectives
control rod drive mechanisms. These tests included a  
: a. To demonstrate the ability of the reactor protection system to initiate a reactor trip on input of the associated input signals.
: b. To verify reactor protection loop response times.      c. To verify the operability of the reactor protection system block and permissive interlocks.
: d. To demonstrate the coincidence, redundancy, and fail safe (power loss) design of the reactor protection system.


14.2.12.1.83.2  Prerequisites
complete operational checkout of the mechanisms and
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational. 14.2.12.1.83.3  Test Method
: a. The ability of the reactor protection system to initiate a reactor trip on receipt of the proper coincidence of the following trip signals for each redundant channel is verified:


o  Source range high neutron flux o  Intermediate range high neutron flux o  Power range high neutron flux (low setpoint and high setpoint) o  Power range high positive neutron flux rate o  Power range high negative neutron flux rate          o  Overtemperature  T          o  Overpower  T          o  Low primary coolant flow          o  Reactor coolant pump bus undervoltage o  Reactor coolant pump bus underfrequency 
calibration of the individual rod position indicators.
: c. Tests were performed on the reactor trip circuits to


14.2-113    Rev. 0 WOLF CREEK          o  High pressurizer pressure          o  Low pressurizer pressure o  High pressurizer level o  Safety injection signal o  Turbine trip signal 
test manual trip operation, and actual control rod
: b. Loop response times are measured for the above listed trip signals.
: c. Reactor protection system block and permissive interlocks are verified.
: d. Power is isolated from the system, and the safe failure of the system is verified.
14.2.12.1.83.4  Acceptance Criteria 
: a. The reactor protection system initiates a reactor trip on receipt of the proper coincidence of the following signals for each applicable channel:


o  Source range high neutron flux o  Intermediate range high neutron flux o  Power range high neutron flux (low setpoint and high setpoint) o  Power range high positive neutron flux rate o  Power range high negative neutron flux rate          o  Overtemperature  T          o  Overpower  T          o  Low primary coolant flow          o  Reactor coolant pump bus undervoltage          o  Reactor coolant pump bus underfrequency o  High pressurizer pressure o  Low pressurizer pressure o  High pressurizer level o  Safety injection signal o  Turbine trip signal
assembly drop times were measured for each control rod
: b. Loop response times for the following trip signals are within design limits.


o  Power range high neutron flux (low setpoint and high setpoint) o  Power range high negative neutron flux rate          o  Overtemperature  T          o  Overpower  T          o  Low primary coolant flow          o  Reactor coolant pump bus undervoltage o  Reactor coolant pump bus underfrequency 
assembly. At all times that the control rod drive


14.2-114    Rev. 0 WOLF CREEK          o  High pressurizer pressure          o  Low pressurizer pressure
mechanisms were being tested, the boron concentration in  
: c. Reactor protection system block and permissive interlocks operate in accordance with system design. 
: d. The reactor protection system functions in accordance with system design on a loss of power.


14.2.12.1.84  Primary Sampling System Preoperational Test (S-03SJ01)
the coolant was maintained so that the shutdown margin


14.2.12.1.84.1  Objectives
requirements specified in the Technical Specifications
: a. To set sample panels' flow rates and to verify the           operability of the sample system containment isolation          valves. Proper operation of system instrumentation and controls is also verified.
: b. To verify that the post-accident sampling system (PASS) containment isolation valves operate properly.


14.2.12.1.84.2  Prerequisites
were met. During individual RCCA or RCC bank motion,  
: a. Required component testing instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operable.
: c. Plant conditions are established, and systems are          available, as necessary, to facilitate drawing samples from the sample points.
: d. The component cooling water system is available to provide cooling water to the auxiliary building sample station.
: e. The chemical and volume control system is available to receive discharge from the nuclear sampling station.
: f. The chemical and detergent waste system is available to receive discharge from the nuclear sampling station.


14.2.12.1.84.3  Test Method
source range instrumentation was monitored for
: a. Sample panel flows are adjusted, and flow data are recorded.


14.2-115    Rev. 0 WOLF CREEK      b. Operability of the sample containment isolation valves          is verified, including their response to an isolation signal. Valve operating times are recorded.  
unexpected changes in core reactivity.  
: d. The reactor control and reactor protection systems were


14.2.12.1.84.4  Acceptance Criteria 
checked with simulated inputs to produce trip signals
: a. The sample containment isolation valves close on receipt of an isolation signal.
: b. The sample containment isolation valves' closure times are within design specifications.


14.2.12.1.85  Process Radiation Monitoring System Preoperational Test (S-03SP01) 14.2.12.1.85.1  Objectives To demonstrate the operation of the process radiation monitors and to verify the ability of the process radiation monitoring system to provide alarm and isolation signals, as applicable, upon receipt of high radiation signals.
for various trip conditions.  
Operability of the radioactivity monitoring control room microprocessor is also verified.
: e. A functional electrical and mechanical check was made of  


14.2.12.1.85.2  Prerequisites
the incore nuclear flux mapping system near normal
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operable. 14.2.12.1.85.3  Test Method
: a. The check source for each monitor is remotely positioned, and the actuation of each monitor and the operability of its associated alarms and isolation signals are verified.
: b. Operability of the radioactivity monitoring control room microprocessor is verified.


14.2.12.1.85.4  Acceptance Criteria
operating temperature and pressure.  


The process radiation monitoring system provides alarm and isolation signals, in accordance with system design specifications.
Initial criticality was achieved by a combination of shutdown and control bank


14.2-116    Rev. 0 WOLF CREEK 14.2.12.1.86  Power Conversion and ECCS Thermal Expansion Test              (SU3-0004)
withdrawal and reactor coolant system boron concentration dilution. The plant


14.2.12.1.86.1  Objective To demonstrate snubber operability on all safety-related systems whose operating temperature exceeds 250 F.
conditions, precautions, and specific instructions for the approach to


14.2.12.1.86.2  Prerequisites
criticality were specified by approved procedures.  
: a. Preservice examinations as specified in the Tedesco letter to KG&E dated 2/10/81 have been completed on the systems being checked within the last 6 months.
: b. Other required component testing and instrument          calibration are completed. 
: c. Required electrical power supplies and control circuits are operational.
: d. Preoperational testing is in progress.  


14.2.12.1.86.3  Test Method
Initially, the shutdown and control banks of control rods were withdrawn
: a. During initial system heatup and cooldown, at specified temperature intervals, verify the expected snubber movement for any system which attains operating temperature.
: b. For those systems which do not attain operating          temperature, verify by observation and/or calculation          that the snubber will accommodate the projected thermal movement.
: c. Observe snubber swing clearances at specified heat-up and cooldown intervals.


14.2.12.1.86.4  Acceptance Criteria
incrementally in the normal withdrawal sequence, leaving the last withdrawn
: a. The expected snubber movement for any system that attains operating temperature is within design specifications.
: b. The expected snubber movement determined by observation and/or calculation for any system that does not attain operating temperature is within design specifications.
: c. Snubber swing clearance observed at specified heatup and cooldown intervals is within design specifications.


14.2-117    Rev. 0 WOLF CREEK 14.2.12.1.87  Power Conversion and ECCS Systems Dynamic Test              (S-030005)
control bank partially inserted in the core to provide effective control when


14.2.12.1.87.1  Objectives To demonstrate during specified transients that the systems' monitored points respond in accordance with design.
criticality was achieved. The boron concentration in the reactor coolant


14.2.12.1.87.2  Prerequisites
system was reduced and criticality achieved by boron dilution or by subsequent
: a. Reference points for measurement of the systems are established.
: b. Hot functional testing is in progress.
: c. All subject systems are available for the specified          dynamic operations.
: d. Required instrument calibration is complete.


14.2.12.1.87.3  Test Method
rod withdrawal following boron dilution. Throughout this period, samples of  
: a. The systems are aligned for the specified dynamic operation.
: b. The specified dynamic event of pump operation, valve operation, etc., is initiated, and the system is monitored for response.


14.2.12.1.87.4  Acceptance Criteria      a. The total stress shall not exceed applicable code limits.  
the primary coolant were obtained and analyzed for boron concentration.  


14.2.12.1.88  HEPA Filter Test (SU3-0006).  
14.2-22    Rev. 0 WOLF CREEK Inverse count rate ratio monitoring using data from the normal plant source range instrumentation was used as an indication of the proximity and rate of


14.2.12.1.88.1  Objectives
approach to criticality. Inverse count rate ratio data was plotted as a


To demonstrate the leaktightness and particulate removal efficiency of all HEPA filters and to verify the leaktightness of their associated charcoal adsorbers.
function of rod bank position during rod motion and as a function of reactor


14.2.12.1.88.2  Prerequisites
makeup water addition during reactor coolant system boron concentration reduction.  
: a. The ventilation systems containing HEPA filters and charcoal adsorbers have been air balanced and are operational and available to support this test.  


14.2-118    Rev. 0 WOLF CREEK      b. Required electrical power supplies and control circuits          are operational.
14.2.10.3  Low Power Testing Following initial criticality, a program of reactor physics measurements was
: c. Required instrument calibration is complete.
14.2.12.1.88.3  Test Method
: a. HEPA filters are inplace tested with cold poly-dispersed DOP, in accordance with the procedures set forth in ANSI N510.
: b. Charcoal adsorbers are inplace tested with a suitable refrigerant, in accordance with the procedures set forth in ANSI N510.
14.2.12.1.88.4  Acceptance Criteria 
: a. The airflow of each filter adsorber unit is equal to the design flow.
: b. Air flow distribution downstream of each HEPA filter is within 20 percent of the average velocity through the unit.
: c. HEPA DOP penetration is less than one percent at the design air flow.
: d. Charcoal adsorber bypass leakage is less than .05 percent at the design air flow.
14.2.12.1.89  Cooldown from Hot Standby External to the Control              Room (S-030008)


14.2.12.1.89.1  Objectives
undertaken to verify that the basic static and kinetic characteristics of the


To demonstrate, using a plant procedure, the potential capability to cooldown the plant from the hot standby to the cold shutdown condition, using instrumentation and controls external to the control room verifying that:
core were as expected and that the values of the kinetic coefficients assumed in the safeguards analysis were conservative.  
: a. The reactor coolant temperature and pressure can be lowered to permit the operation of the residual heat removal (RHR) system.  
 
: b. The RHR system can be operated and controlled.
Procedures specified the sequence of tests and measurements to be conducted and  
: c. The reactor coolant temperature can be  reduced  50 F,          using the RHR system, without exceeding technical          specification limits.


14.2-119    Rev. 0 WOLF CREEK 14.2.12.1.89.2  Prerequisites 
the conditions under which each was performed in order to ensure both safety of  
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The plant is in a hot standby condition.
: d. The authority and responsibility of the control room observers has been established and is specified in this procedure.


14.2.12.1.89.3  Test Method      a. The plant is cooled from hot standby, RHR is initiated, and a  >50&deg;F cooldown is performed with the RHR system          transferring heat to the ultimate heat sink, using          instrumentation and controls external to the control room.  
operation and the validity and consistency of the results obtained. If test  
: b. All actions performed by the control room observers are          documented within this procedure for use in evaluating their impact on the test results.


14.2.12.1.89.4  Acceptance Criteria
results deviated significantly from design predictions, if unacceptable


The following actions are capable of being performed, external to the control room:
behavior had been revealed, or if unexplained anomalies had developed, the  
: a. The reactor coolant temperature and pressure can be lowered to permit the operation of the RHR system.      b. The reactor coolant temperature can be  reduced  50 F,           using the RHR system, without exceeding technical          specification limits.


14.2.12.1.90  Compressed Gas Accumulator Testing (S-030009)
plant would have been brought to a safe stable condition and the situation


14.2.12.1.90.1  Objectives
reviewed to determine the course of subsequent plant operation.  


To demonstrate the ability of the auxiliary feedwater control valve/mainsteam atmospheric relief valve and main feedwater control valve accumulators to provide the design backup supply of compressed gas for continued design valve operation following a loss of the normal motive source.  
These measurements were made at low power and primarily at or near normal operating temperature and pressure. Measurements were made in order to verify


14.2-120    Rev. 0 WOLF CREEK 14.2.12.1.90.2  Prerequisites Required component testing, instrument calibration and system flushing/cleaning are complete.
the calculated values of control rod bank reactivity worths, the isothermal
14.2.12.1.90.3  Test Method


The accumulators are isolated from the compressed gas supply header and the associated valves are operated to demonstrate the ability of the accumulators to provide design motive force for the required valve cycles.
temperature coefficient under various core conditions, differential boron


14.2.12.1.90.4  Acceptance Criteria
concentration reactivity worth, and critical boron concentrations as functions


The auxiliary feedwater control valve/mainsteam atmospheric relief valve, and main feedwater control valve accumulators provide the design backup supply of compressed gas to their associated valves.
of control rod configuration. In addition, measurements of the relative power
14.2.12.2  Nonsafety-Related Preoperational Test Procedures  The following sections are the test abstract for each nonsafety- related preoperational test. Table 14.2-2 provides an index of these tests.
14.2.12.2.1  Turbine Trip Test (S-04AC02)


14.2.12.2.1.1  Objectives
distributions were made, and concurrent tests were conducted on the  
: a. To demonstrate the ability of the turbine trip and monitoring system to initiate a turbine trip on input of the associated input signals.
: b. To demonstrate the response of the moisture separator reheater drain valves, feedwater heater extraction check          valves, turbine main stop valves, turbine main stop          valve above seat drain valves, turbine control valves, turbine control valve above seat drain valves, intermediate stop valves, main steamline drain valves, startup drain valves, and intercept valves to a turbine trip signal.
: c. To demonstrate that a turbine trip signal initiates a reactor trip signal.
: d. To demonstrate that the turbine main stop valves operating times are within design specifications.


14.2-121    Rev. 0
instrumentation, including source and intermediate range nuclear channels.  


WOLF CREEK 14.2.12.2.1.2  Prerequisites 
Gamma and neutron radiation surveys were performed at selected points
: a. Required component testing and instrument calibration is complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The main turbine control oil and lube oil systems are available to provide oil to the turbine auxiliaries.
: d. The compressed air system is available to provide air to system air-operated valves.


14.2.12.2.1.3  Test Method      a. The ability of the turbine trip and monitoring system to initiate a turbine trip signal on receipt of each of the following input signals is verified:
throughout the station. Periodic sampling was performed to verify chemical and  


o  Manual trip pushbutton depressed o  Manual trip handle pulled o  Generator trip (EHC vital trip) o  Generator trip (unit trip) o  Reactor trip o  Loss of stator coolant o  Low lube oil pressure o  Loss of EHC 125 V dc power with turbine speed below 75 percent o  High turbine vibration          o  High exhaust hood temperature          o  Low hydraulic fluid pressure o  Moisture separator high level o  Low bearing oil pressure o  Low condenser vacuum o  Excessive thrust bearing wear o  Backup overspeed (Electrical) o  Loss of EHC 24-volt dc power
radio-chemical analysis of the reactor coolant.  
: b. A turbine trip signal is initiated, and the response of the following valves is verified:


o  Moisture separator reheater drain valves o  Feedwater heater extraction check valves o  Turbine main stop valves o  Turbine control valves o  Intermediate stop valves o  Turbine intercept valves o  Startup drain valves o  Main steam line drain valves
14.2.10.4  Power Level Ascension After the operating characteristics of the reactor were verified by low power


14.2-122    Rev. 0 WOLF CREEK          o  Turbine main stop valve above seat drain valves          o  Turbine control valve above seat drain valves
testing, a program of power level ascension brought the unit to its full rated
: c. A turbine trip signal is initiated, and a reactor trip input signal is verified.
14.2.12.2.1.4  Acceptance Criteria
: a. The turbine trip and monitoring system initiates a turbine trip on receipt of each of the following signals:


o  Manual trip pushbutton depressed o  Manual trip handle pulled o  Generator trip (EHC vital trip)          o  Generator trip (unit trip)          o  Reactor trip o  Loss of stator coolant o  Low lube oil pressure o  Loss of EHC 125 V dc power with turbine speed below 75 percent o  High turbine vibration o  High exhaust hood temperature o  Low hydraulic fluid pressure o  Moisture separator high level o  Low bearing oil pressure o  Low condenser vacuum o  Excessive thrust bearing wear o  Backup overspeed (electrical) o  Loss of EHC 24-volt dc power      b. The following valves open on receipt of a turbine trip signal:
power level in successive stages. At each successive stage, hold points were provided to evaluate and approve test results prior to proceeding to the next


o  Turbine main stop valve above seat drain valves o  Turbine control valve above seat drain valves o  Main steam line drain valves o  Moisture separator reheater drain valves o  Startup drain valves
stage. The minimum test requirements for each successive stage of power
: c. The following valves close on receipt of a turbine trip signal:


o  Low pressure heater extraction check valves o  Main stop valves o  Turbine control valves o  Intercept valves o  Intermediate stop valves
ascension were specified in the initial startup test procedures.


14.2-123   Rev. 0 WOLF CREEK     d. A turbine trip signal initiates a reactor trip signal. 
14.2-23   Rev. 0 WOLF CREEK Measurements were made to determine the relative power distribution in the core as functions of power level and control assembly bank position.  
: e. The turbine main stop valves operating times are within design specifications.
14.2.12.2.2  Turbine System Cold Test (S-04AC03)


14.2.12.2.2.1  Objectives
Secondary system heat balance measurements ensured that the indications of  
: a. To demonstrate the operability of the turning gear and associated control circuits.
: b. To demonstrate the operability of the electro-hydraulic control system.
14.2.12.2.2.2  Prerequisites 
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The main turbine control oil and lube oil systems are available to supply the turbine auxiliaries.


14.2.12.2.2.3  Test Method
power level were consistent and provide bases for calibration of the power range nuclear channels. The ability of the reactor coolant system to respond
: a. The operability of the turning gear and associated control circuits is verified.       b. A turbine simulator is utilized to verify the ability of the electro-hydraulic control system to perform its control functions.


14.2.12.2.2.4  Acceptance Criteria
effectively to signals from primary and secondary instrumentation under a  
: a. The turning gear motor trips on loss of bearing oil pressure, loss of all bearing lift pumps, or closure of the main transformer switchyard breaker.
: b. The turbine control and intercept valves close on a power load unbalance signal.
: c. The turbine load set is run back on a reactor          overtemperature T signal when in the manual mode.      d. The turbine load set is run back on a reactor          overpower T signal when in the manual mode. 


14.2-124    Rev. 0 WOLF CREEK      e. The turbine load is set back on a loss of circulating          water pump signal.
variety of conditions encountered in normal operations was verified.  
: f. Turbine loading is inhibited on a C-16 control interlock signal.
14.2.12.2.3  Condensate System Preoperational Test (S-04ADOl)


14.2.12.2.3.1  Objectives
At prescribed power levels, the dynamic response characteristics of the primary


To demonstrate the condensate pumps' operating characteristics and verify the operation of system valves and associated control circuits. The operability of the condensate storage and transfer system and associated components is also verified.
and secondary systems were evaluated. System response characteristics were
14.2.12.2.3.2  Prerequisites 
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The feedwater system is available to receive flow from the condensate pump discharge header.
: d. The demineralized water system is available to provide water to the condensate pump seals and a source of makeup to the condensate storage tank.
: e. The condensate storage tank is available to provide          makeup to the condenser hotwell.
: f. The closed cooling water system is available to provide cooling water to the condensate pump motor bearing oil coolers.  


14.2.12.2.3.3  Test Method
measured for design step load changes, rapid load reduction, and plant trips.  
: a. Condensate pumps are operated, and performance characteristics are verified.
: b. The response of each condensate pump to a condenser low-low level trip signal is verified.
: c. The operability of the condensate pump recirculation valves is verified.  


14.2-125    Rev. 0 WOLF CREEK 14.2.12.2.3.4  Acceptance Criteria 
Adequacy of radiation shielding was verified by gamma and neutron radiation
: a. The operating characteristics of the condensate pumps are within design specifications.
: b. Each condensate pump will receive a trip signal on a 2/3 condenser low-low level signal.
: c. Each condensate pump recirculation valve operates in accordance with design specifications.


14.2.12.2.4  Secondary  Vent and Drain System  Preoperational Test (S-04AF01)
surveys at selected points throughout the station at various power levels.
Periodic sampling was performed to verify the chemical and radio-chemical analysis of the reactor coolant.


14.2.12.2.4.1 Objectives      a. To demonstrate the operating characteristics of the heater drain pumps.
14.2.11 TEST PROGRAM SCHEDULE
: b. To demonstrate the operability of system valve and pump control circuits.


14.2.12.2.4.2  Prerequisites
Detailed schedules for testing were prepared, reviewed, and revised on a
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The compressed air system is available to the system          air-operated valves.
: d. The closed cooling water system is available to supply cooling water to the heater drain pumps.


14.2.12.2.4.3  Test Method
continuing basis as plant construction progressed.  
: a. The heater drain pumps are operated, and performance characteristics are verified.
: b. The operability of system valve and pump control circuits is verified.  


14.2.12.2.4.4  Acceptance Criteria
Preoperational tests which were not performed according to schedule were


The operating characteristics of the heater drain pumps are within design specifications.  
reviewed on a case-by-case basis. Administrative procedures were established


14.2-126    Rev. 0 WOLF CREEK 14.2.12.2.5  Condensate and Feedwater Chemical Feed System              Preoperational Test (S-04AQ01)
to ensure that all prerequisites were met before testing was initiated. Upon


14.2.12.2.5.1  Objectives
completion of all prerequisite tests applicable to a system or subsystem, a  
: a. To demonstrate the operating characteristics of the condensate oxygen control chemical addition pumps,            condensate pH control chemical addition pumps, condensate            oxygen control chemical circulating pumps, condensate pH            control chemical circulating pumps, feedwater chemical addition          pumps, and feedwater chemical addition circulating pump and  verify the operation of the associated control circuits. 
: b. To demonstrate the operability of the drum dispensing pumps.
14.2.12.2.5.2  Prerequisites
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The demineralized water storage and transfer system is available to provide a source of demineralized water to          the oxygen and pH control chemical supply and mixing          tanks. 
: d. The compressed air system is available to provide air to the drum dispensing pumps.
: e. The service gas system is available to provide a source of nitrogen to the oxygen and pH control chemical supply,          measuring, and mixing tanks.
14.2.12.2.5.3  Test Method
: a. System pumps are operated, and performance          characteristics are verified.
: b. The response of the condensate oxygen control chemical circulating          pumps, condensate pH control chemical circulating pumps,            and the feedwater chemical addition feed pumps to a low            level in their associated tank is verified.


14.2-127    Rev. 12 WOLF CREEK 14.2.12.2.5.4  Acceptance Criteria 
documented review was conducted by Start-up personnel to verify that
: a. The operating characteristics of the condensate oxygen control chemical addition pumps, condensate pH control            chemical addition pumps, condensate oxygen control chemical          circulating pumps, condensate ph control chemical circulating pumps,            feedwater chemical addition pumps, feedwater            chemical addition circulating pump, and the drum            dispensing pumps are within design specifications.
: b. The condensate oxygen control chemical circulating pumps, condensate          pH control chemical circulating pumps, feedwater chemical addition feed pumps, and the feedwater            chemical addition circulating pump trip on a low level            signal from their associated tanks.


14.2.12.2.6  Reactor  Makeup Water System  Preoperational  Test (S-04BL01) 14.2.12.2.6.1  Objectives
appropriate documentation was available and that required prerequisite tests
: a. To demonstrate the operating characteristics of the reactor makeup water transfer pumps and verify that the associated control circuits are functioning properly.
: b. To demonstrate the operation of the system automatic valves, including the response of the reactor makeup water system containment supply valve to a CIS.
14.2.12.2.6.2  Prerequisites 
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The demineralized water storage and transfer system is available to provide a source of water to the reactor makeup water storage tank.


14.2.12.2.6.3  Test Method
were satisfactorily completed. All deficiencies which would have prevented performance of preoperational tests or generated negative test results were identified and dispositioned prior to implementation of the preoperational
: a. The reactor makeup water transfer pumps are operated,          and pump operating data are recorded. 
: b. Reactor makeup water transfer pumps and system automatic valves control logics are verified, including their response to safety signals.


14.2-128    Rev. 12 WOLF CREEK      c. The reactor makeup water containment supply valve is          operated under flow conditions and operating times recorded.  
tests.  


14.2.12.2.6.4  Acceptance Criteria 
Preoperational testing was scheduled to commence approximately 18 months prior
: a. The operating characteristics of the reactor makeup water transfer pumps are within design specifications.
: b. Each reactor makeup water transfer pump trips on receipt of a reactor makeup water storage tank low level signal.
: c. Each reactor makeup water transfer pump starts, after a time delay, with the other pump running and the receipt of a low header pressure signal.      d. The reactor makeup water containment supply valve closure time is within design specifications.
: e. The reactor makeup containment supply valve closes on receipt of a CIS.


14.2.12.2.7  Condenser Air Removal System Preoperational Test (S-04CG01)
to fuel loading. The preoperational tests were performed and sequenced during


14.2.12.2.7.1  Objectives
this period as a function of system turnover, system interrelationships, and  
: a. To demonstrate the operation of the condenser air removal portion of the turbine building HVAC system motoroperated dampers, including automatic operation on          a safety injection signal. 
: b. To demonstrate the capacities of the condenser air removal filtration fans and verify the operation of their associated control circuits.
: c. To demonstrate the operability of the condenser air removal system vacuum pumps, control valves, and their associated control circuits.


14.2.12.2.7.2  Prerequisites
acceptance for testing.  
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.  


14.2-129    Rev. 0 WOLF CREEK      c. The condenser air removal filtration system portion of          the turbine building HVAC system is available to support this test.
Initial startup testing was scheduled to be conducted over a period of  
: d. The condensate storage tank is available to provide a           source of water to the vacuum pump seal water reservoirs.
: e. The service water system is available to provide cooling water to the mechanical vacuum pump seal water coolers.


14.2.12.2.7.3 Test Method
approximately 3 to 5 months, commencing with fuel loading. The sequential
: a. The condenser air removal filtration fans are operated, and fan capacities are verified.      b. Operation of the condenser air removal filtration dampers is verified, including their response to a safety injection signal.
: c. The ability of the mechanical vacuum pumps to reduce condenser pressure during startup operation is verified.
: d. Operability of the mechanical vacuum pumps and their associated control valves' control circuits is verified, including their response to a low condenser vacuum signal.


14.2.12.2.7.4  Acceptance Criteria
schedule for initial startup tests ensured, insofar as practicable, that test
: a. The condenser air removal filtration fans' capacities          are within design specifications.
: b. The condenser air removal filtration dampers close on receipt of a safety injection signal.
: c. The rate at which the mechanical vacuum pumps reduce condenser pressure is within design specifications.
: d. The mechanical vacuum pumps start automatically on receipt of a low condenser vacuum signal.


14.2.12.2.8  Circulating Water System Preoperational Test (SU4-DA01)
requirements were completed


14.2.12.2.8.1  Objective
14.2-24    Rev. 0 WOLF CREEK prior to exceeding 25-percent power for all plant structures, systems, and components that are relied upon to prevent, limit, or mitigate the consequences
: a. To demonstrate the operating characteristics of the circulating water pumps, water box venting pumps,   and


14.2-130    Rev. 0 WOLF CREEK          the condenser drain pump and verify the operation of           their associated control circuits.
of postulated accidents.  
: b. To demonstrate by operational test that the circulating water pump discharge valves operating times are within          design specifications.
: c. To demonstrate that the gland water system flow to the circulating water pumps is within design specifications.  


14.2.12.2.8.2  Prerequisites
The development of the test procedures was an ongoing process consisting of preparation, review, and revision. Preoperational test procedures were
: a. Required component testing, instrument calibration, and system flushing/cleaning are completed.
: b. Required electrical power supplies and control circuits          are operational.
: c. The circulatng water system and condenser are available to receive flow from the circulating water pumps.  


14.2.12.2.8.3  Test Method
available for NRC review approximately 60 days prior to the performance of an
: a. The circulating water pumps, water box venting pumps, and the condenser drain pump are operated and pump operating data is recorded.
: b. The response of the circulating water pumps and the condenser drain pump to control signals is verified.
: c. Circulating water pump discharge valve operating times          are recorded.


14.2.12.2.8.4  Acceptance Criteria
individual test. If an individual test procedure was not available 60 days
: a. The circulating water pumps operating characteristics are within design specifications.
: b. The water box venting pumps operating characteristics are within design specifications.
: c. The condenser drain pump operating characteristics are within design specifications
: d. The condenser drain pump stops on receipt of a standpipe low-level signal.
: e. Each circulating water pump trips on receipt of a two out of three condenser pit high level signal.  


14.2-131    Rev. 0 WOLF CREEK      f. Low gland seal water pressure or low gland seal flow          will prevent start of the circulating water pumps.
prior to the test, the NRC was notified of the test date and the date the test
: g. The gland seal water flow to each circulating water pump is within design specifications. 
: h. The operating times of the circulating water pump discharge valves are within design specifications.


14.2.12.2.9  Service Water System Preoperational Test (S-04EA01).  
procedure was available. Initial startup test procedures were available for


14.2.12.2.9.1  Objectives
NRC review at least 60 days prior to fuel loading.  
: a. To demonstrate the capability of the service water system and essential service water system to provide          rated cooling water flow during the normal and normal-          shutdown modes of operation to their respective loads.
: b. To  demonstrate the operating characteristics of the Service Water (SW) Pumps.
: c. To verify proper operation of site service water system controls and instrumentation.  


14.2.12.2.9.2 Prerequisites
14.2.12  INDIVIDUAL TEST DESCRIPTIONS
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits          are operational. 
: c. The essential service water system has been flow balanced in the LOCA mode.
: d. Site system controls and instruments are calibrated.
: e. The SW system is available to receive flow from the SW pumps.


14.2.12.2.9.3  Test Method
Test abstracts were provided for both safety-related and selected nonsafety-related preoperational tests. The abstracts included test prerequisites and summaries of test methods, objectives, and acceptance criteria.  
: a. Service water and essential service water system flows are verified in the normal and normal-shutdown modes.  
          (The service water pumps provide the motive force.)
: b. The SW pumps are operated and pump operating data is recorded.  


14.2-132    Rev. 0 WOLF CREEK 14.2.12.2.9.4 Acceptance Criteria 
14.2.12.1 Safety-Related Preoperational Test Procedures The following sections contain test abstracts used for safety- related
: a. Components supplied by the service water system and essential service water system receive flows that are within design specifications with the system operating          in the normal and normal-shutdown modes.
: b. The SW pumps operating characteristics are within design specifications.


14.2.12.2.10  Closed Cooling Water  System  Preoperational Test (S-04EB01)
preoperational tests. Table 14.2-1 provides an index of these tests.  


14.2.12.2.10.1  Objectives
The preoperational test procedures were designated SO3 (Safety- Related/Common
: a. To demonstrate the capability of the closed cooling          water system to provide cooling water flow to its associated components.
: b. To demonstrate the operating characteristics of the closed cooling water pumps and to verify that the associated instrumentation and controls are functioning properly.


14.2.12.2.10.2  Prerequisites
to WCGS and Callaway), SU3 (Safety-Related/WCGS Specific), SO4 thru SO9
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits          are operational.
14.2.12.2.10.3  Test Method


Performance characteristics of the closed cooling water pumps and flow data to supplied components are verified.
(Nonsafety-Related/Common to WCGS and Callaway) and SU4 thru SU9 (Nonsafety-


14.2.12.2.10.4  Acceptance Criteria
Related/WCGS Specific) as appropriate.  
: a. The performance characteristics of each closed cooling water pump are within design specifications.
: b. Flow to all components supplied by the closed cooling water system is verified.  


14.2-133    Rev. 0 WOLF CREEK 14.2.12.2.11 Fire Protection System Preoperational Test (SU4-               FP03)  
14.2.12.1.1 Steam Dump System Preoperational Test (S-03AB01)  


14.2.12.2.11.1  Objectives  
14.2.12.1.1.1  Objectives  
: a. To demonstrate the operating characteristics of the Fire Protection (FP) system jockey pump, motor-driven fire pump and the diesel-driven fire pump and verify the operation of their associated control circuits.  
: a. To demonstrate the operability of the steam dump control system control circuits in both the average temperature and steam pressure modes of operation.  
: b. To demonstrate the operability of the diesel oil system, including system instrumentation and controls.
: b. To demonstrate the operation of the main steam dump


14.2.12.2.11.2  Prerequisites
valves and main steam cooldown valves, including valve
: a. Required component testing, instrument calibration, and          system flushing/cleaning are completed.
: b. Required electrical power supplies and control circuits are operational.


14.2.12.2.11.3  Test Method
response to safety signals.  
: a. The jockey pump, the motor-driven fire pump and the diesel-driven fire pump are operated and operating data are recorded.
: c. To verify the operation of the main steam line drain
: b. The response of the motor-driven fire pump and diesel-driven fire pump to automatic start signals are verified.       c. With the diesel-driven fire pump operating at rated capacity, the capacity of the diesel oil day tank is verified.


14.2.12.2.11.4  Acceptance Criteria
valves' control circuits, including valve response to a  
: a. The FP pumps operating characteristics are within design specifications.
: b. The motor-driven fire pump and the diesel-driven fire pump automatically start upon receipt of their associated decreasing fire protection system pressure signal.
: c. With the diesel fire pump operating at rated capacity, the capacity of the diesel oil day tank is within design specifications.


14.2-134    Rev. 0 WOLF CREEK      d. With the diesel fire pump operating at rated capacity          and upon receipt of a diesel oil day tank low level alarm, the remaining capacity of the diesel oil day tank is within design specifications.
turbine trip signal.  
14.2.12.2.12  Radwaste Building HVAC System Preoperational Test (S-04GH01)


14.2.12.2.12.1  Objectives
14.2-25 Rev. 0 WOLF CREEK
: a. To verify the radwaste building supply and exhaust fans' control circuits, including automatic transfer between exhaust fans.
: d. To verify the operation of the main steam to turbine-driven feedwater pump supply valves' control logics,  
: b. To demonstrate the fan capacities of the radwaste          building supply and exhaust fans, recycle evaporator          room fan coil unit, waste evaporator room fan coil unit, control room (solidification) fan coil unit, sample laboratory fan  coil unit,  ground floor fan coil unit, basement floor fan coil unit, SLWS evaporator fan coil unit, and control room fan coil unit, and to verify that the associated instrumentation and controls function properly.


14.2.12.2.12.2  Prerequisites
including valve response to an auxiliary feedwater
: a. Required component testing, instrument calibration, and system air balancing are complete.
: b. Required electrical power supplies and control circuits          are operational.
14.2.12.2.12.3  Test Method
: a. The radwaste building system fans are operated, and fan capacities are verified.
: b. Operability of the radwaste building supply and exhaust fans' control circuits is verified.


14.2.12.2.12.4 Acceptance Criteria
actuation signal (AFAS).
: a. The radwaste building system fan capacities are within design specifications.
: e. To verify the operation of the main steam atmospheric relief valves' control circuits.
: b. The radwaste building supply air unit will not operate unless either radwaste exhaust fan is operating.
14.2.12.1.1.2 Prerequisites
: a. Required component testing, instrument calibration, and


14.2-135    Rev. 0 WOLF CREEK      c. A low flow on the operating radwaste building exhaust          fan will cause the operating fan to stop and the standby fan to start.
system flushing/cleaning are completed.  
: b. Required electrical power supplies and control circuits


14.2.12.2.13  Local Containment Leak Rate Test (SU8-GP01) 14.2.12.2.13.1  Objectives
are operational.  


To determine the leakage rate of the containment penetrations and the leakage rate of the containment isolation valves.
14.2.12.1.1.3  Test Method
: a. Operability of the steam dump control system control


14.2.12.2.13.2  Prerequisites
circuits is verified in both the average temperature and  
: a. All containment isolation valves are closed by normal actuation methods.      b. Associated piping is drained, and vent paths for leakage are established.
: c. Required instrument calibration is complete.


14.2.12.2.13.3  Test Method
steam pressure modes.  
: b. Operability of the main steam dump valves' and main steam cooldown valves' control circuits is verified,


The containment penetrations and containment isolation valves are leak tested by performing type B and type C tests, in accordance with 10 CFR 50, Appendix J.
including valve response to turbine impulse low


14.2.12.2.13.4  Acceptance Criteria
pressure, low-low average temperature, and condenser


The combined leakage from containment penetrations and containment isolation valves is within design limits.
shell high pressure signals.  
14.2.12.2.14  Liquid Radwaste System Preoperational Test (S-04HB01).  
: c. Operability of the main steam line drain valves' control


14.2.12.2.14.1  Objectives
circuits is verified, including valve response to a  
: a. To demonstrate the operating characteristics of the liquid radwaste system pumps and to verify the operation of their associated control circuits.
: b. To demonstrate the operation of the liquid radwaste system containment isolation valves, including their response to a CIS.
: c. To determine by operational test that the liquid radwaste system containment isolation valves' closure times are within design specifications.


14.2-136    Rev. 0 WOLF CREEK 14.2.12.2.14.2  Prerequisites 
turbine trip signal.  
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: d. Operability of the main steam to turbine-driven
: b. Required electrical power supplies and control circuits are operational.
: c. The component cooling water system is available to provide cooling water to the reactor coolant drain tank heat exchanger.


14.2.12.2.14.3  Test Method
auxiliary feedwater pump supply valves' control logics
: a. The liquid radwaste system pumps are operated, and          performance characteristics are recorded. 
: b. The operability of the system pump and valve control circuits is verified.
: c. The liquid radwaste system containment isolation valves are operated under flow conditions, and operating times are recorded.


14.2.12.2.14.4  Acceptance Criteria
is verified, including valve response to an AFAS.  
: a. The performance characteristics of the liquid radwaste system pumps are within design specifications.
: e. Operability of the main steam atmospheric relief valves' control circuits is verified.  
: b. Each pump trips on receipt of a low-level signal from          its respective tank. 
: c. The liquid radwaste system containment isolation valves close on receipt of a CIS.
: d. The liquid radwaste system containment isolation valves' closure times are within design specifications.
: e. The liquid radwaste effluent discharge valve closes on a high process radiation signal.  


14.2.12.2.15 Waste Evaporator Preoperational Test (SU4-HB02)
14.2.12.1.1.4 Acceptance Criteria
: a. The response of the main steam dump valves and the main steam cooldown valves to the associated turbine impulse


14.2.12.2.15.1  Objectives
low pressure, low-low average temperature, and condenser


To demonstrate the operability of the waste evaporator and its associated pumps, valves, and control circuits.
shell high pressure signals is in accordance with system


14.2-137    Rev. 0 WOLF CREEK 14.2.12.2.15.2  Prerequisites 
design.  
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.  
: b. The main steam line drain valves open on receipt of a  
: b. Required electrical power supplies and control circuits are operational.
: c. Cooling water is available to the waste evaporator.
: d. The auxiliary steam system is available to supply steam to the waste evaporator.
: e. The waste evaporator condensate tank and the primary evaporator bottoms tank are available to receive waste          evaporator effluent.
14.2.12.2.15.3  Test Method
: a. The waste evaporator is operated, and performance data is recorded.
: b. With the waste evaporator in operation, a low feed inlet pressure signal is initiated, and the evaporator is verified to shift to the recycle mode.
: c. The waste evaporator distillate pump is verified to trip on a low evaporator condenser level.


14.2.12.2.15.4  Acceptance Criteria      a. The waste evaporator process flow is within design specifications.
turbine trip signal.  
: b. The waste evaporator goes into the recycle mode on low feed inlet pressure.
: c. The waste evaporator distillate pump trips on a low evaporator condenser level.  


14.2.12.2.16  Solid Waste System Preoperational Test (S-04HC01)
14.2-26 Rev. 13 WOLF CREEK
: c. The main steam to turbine-driven auxiliary feedwater pump supply valves open on receipt of an AFAS.  
: d. The response of the main steam atmospheric relief valves to pressure signals is in accordance with system


14.2.12.2.16.1  Objectives
design.  
: a. To demonstrate the operating characteristics of the solid waste system pumps and to verify the operation of their associated control circuits.  


14.2-138    Rev. 0 WOLF CREEK      b. To demonstrate the ability of the decant station,          drumming  station,  cement  filling station,  and the solid radwaste bridge crane to process, solidify, and handle waste and to verify the operation of their associated control circuits.   
14.2.12.1.2 Main Steam Safety Valve Test (SU3-AB02)
: c. To demonstrate the ability of the dry waste compactors to process compressible wastes and to verify the operation of their associated control circuits.


14.2.12.2.16.2 Prerequisites
14.2.12.1.2.1 Objectives
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits          are operable.
: c. Reactor makeup water is available to provide a source of water to the decanting station.


14.2.12.2.16.3  Test Method
To verify the pressure relief setpoints of the main steam
: a. The solid waste system pumps are operated, and the pump operating data are recorded.
: b. The system component control circuits are verified, and the ability of the solid radwaste system to process, solidify, and handle waste is verified.
14.2.12.2.16.4. Acceptance Criteria 
: a. The operating characteristics of the evaporator bottoms tank pumps (primary and secondary) are within design specifications.
: b. There are no free liquids present in the packaged waste.
: c. The evaporator bottoms tank pumps (primary and secondary) trip on their respective tank low level signal.


14.2.12.2.17  Solid Waste Filter Handling System Preoperational Test (S-04HC02)
safety valves.  


14.2.12.2.17.1 Objectives
NOTE: This objective may be accomplished either by bench


To demonstrate the ability of the solid radwaste filter handling system to remove, transfer, and install a spent resin sluice filter assembly.  
testing or with a pneumatic test device.  


14.2-139    Rev. 0 WOLF CREEK 14.2.12.2.17.2  Prerequisites
14.2.12.1.2.2  Prerequisites  
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.


14.2.12.2.17.3  Test Method
The following prerequisites apply when a pneumatic test device is used.  
: a. Operability of the solid radwaste monorail hoist and handling cask winch and associated control circuits is verified.  
: a. Required instrument calibration is complete.  
: b. The ability of the solid radwaste filter handling system          to remove, transfer, and install a spent resin sluice          filter assembly is verified.
: b. Hot Functional Testing is in progress.  
: c. A Source of compressed air is available to provide air


14.2.12.2.17.4  Acceptance Criteria
to the air set pressure device installed on the valve


The filter handling system functions in accordance with design specifications.  
under test.  


14.2.12.2.18  Resin Transfer Preoperational Test (SU4-HC03)
The following prerequisites apply when bench testing is


14.2.12.2.18.1  Objectives
performed.  
: a. To demonstrate the ability to charge resins and activated charcoal to those systems containing potentially contaminated demineralizers or adsorbers.
: a. Bench testing facility is available.  
The ability of the spent resin sluice pumps to  transfer          resins and charcoal from demineralizers and adsorbers is           also verified.  
: b. An approved WCGS procedure is available to accomplish
: b. To demonstrate the operating characteristics of the spent resin sluice pumps, chemical addition metering pumps, and chemical drain tank pumps.
: c. To demonstrate the operability of system valve and pump control circuits.


14.2.12.2.18.2  Prerequisites
bench testing.  
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.  
: c. A source of compressed gas is available to provide
: b. Required electrical power supplies and control circuits are operational.  


14.2-140    Rev. 0 WOLF CREEK      c. Those systems containing potentially contaminated          demineralizers and adsorbers are available to support this test.
pressure to the valve under test.  
: d. The reactor makeup water system is available to provide          a source of water for resin charging.
: e. A means of bulk disposal is available to receive waste at the bulk disposal station.  


14.2.12.2.18.3  Test Method  
14.2.12.1.2.3  Test Method  
: a. Resins and charcoal are charged and transferred from selected potentially contaminated demineralizers and adsorbers.      b. The spent resin sluice pumps, chemical addition metering pumps, and chemical drain tank pumps are operated, and performance characteristics are obtained.
: c. The response of the spent resin sluice pumps, chemical addition metering pumps, and the chemical drain tank pumps to a low-level trip signal from their respective tanks is verified.


14.2.12.2.18.4  Acceptance Criteria
The following test method applied when a pneumatic test
: a. The operating characteristics of the spent resin sluice pumps, chemical addition metering pumps, and the chemical drain tank pump  are within design          specifications. 
: b. The spent resin sluice pumps, chemical addition metering pumps, and the chemical drain tank pump trip on receipt of a low-level trip signal from their respective tanks.


14.2.12.2.19  Fire Protection System (Water) Preoperational Test (SU4-KC01A, SU4-KC01B)
device is used.  


14.2.12.2.19.1  Objectives
Main steam pressure is adjusted within the required range,  
: a. To demonstrate the operability of the preaction sprinkler system, wet-pipe sprinkler system, and the automatic water spray system, including system instrumentation, alarms, and interlocks.
: b. To demonstrate the operability of system valves, including their response to safety signals.


14.2-141    Rev. 0 WOLF CREEK      c. To verify spray to the applicable electrical system          transformers.
and air is admitted to the air set pressure device on the


14.2.12.2.19.2  Prerequisites
safety valve under test. Actual lift pressure is calculated,  
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operable.
: c. The fire water pumps are available to provide a source of water to the fire protection system headers.


14.2.12.2.19.3  Test Method      a. Response of the preaction sprinkler system, wet-pipe sprinkler system, and automatic water spray system to fire detection signals is verified, including the operability of associated alarms, instrumentation, and interlocks.
using the steam pressure and converted air pressure at the  
: b. The fire protection system containment isolation valves are operated under flow conditions and operating times recorded.
: c. Response of the fire protection system containment isolation valves to a CIS is verified.
: d. Spray to the applicable electrical transformers is          verified.
14.2.12.2.19.4  Acceptance Criteria
: a. The preaction sprinkler system, wet-pipe sprinkler system, automatic water spray system and associated alarms, and instrumentation and interlocks operate in accordance with system design specifications.
: b. The fire protection system containment isolation valves' closure time is within design specifications.
: c. The fire protection system containment isolation valves close on receipt of a CIS.
: d. The spray to applicable electrical transformers is within design specifications.


14.2-142    Rev. 0 WOLF CREEK 14.2.12.2.20  Fire Protection System (Halon) Preoperational Test              (S-04KC02)
time of lift.  


14.2.12.2.20.1  Objectives To demonstrate the operability of the halon system, including the associated instrumentation, control circuits, and alarms.  
14.2-27 Rev. 13 WOLF CREEK The following test applies when bench testing is performed.  


14.2.12.2.20.2  Prerequisites
With the main steam safety valve mounted on the bench test
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operable. 14.2.12.2.20.3  Test Method


The operability of the halon system, including the associated instrumentation and alarms, is verified. System response to fire detection signals is also verified.
facility, the spring assembly is preheated and the safety


14.2.12.2.20.4  Acceptance Criteria
valve is pressurized with compressed gas. Actual set pressure is determined at the time of lift.  


The halon fire protection system operates in accordance with system design specifications.  
14.2.12.1.2.4  Acceptance Criteria


14.2.12.2.21  Fire Protection System Detection and Alarm Preoperational Test (S-04KC03) 14.2.12.2.21.1  Objectives To demonstrate the operability of the fire protection system detectors and alarms not verified during the performance of the halon and water system preoperational tests.
Each main steam safety valve lifts within its respective


14.2.12.2.21.2  Prerequisites
setpoint tolerance.  
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operable.  


14.2.12.2.21.3  Test Method
14.2.12.1.3  Main Steam Line Isolation Valve Test (S-03AB03)


Actuation of system alarms upon receipt of fire detection signals is verified.
14.2.12.1.3.1  Objectives
: a. To verify the response of the main steam bypass, drain,


14.2-143    Rev. 0 WOLF CREEK 14.2.12.2.21.4  Acceptance Criteria Fire protection system detectors and alarms operate in accordance with system design specifications.
and auxiliary feedwater turbine warmup valves to steam
14.2.12.2.22  Oily Waste System Preoperational Test (S-04LE01)


14.2.12.2.22.1  Objectives
line isolation signals.  
: b. To demonstrate the operability of the main steam


To demonstrate the sump pumps and miscellaneous condensate drain tank pumps' operating characteristics and response to sump/tank, level signals. The operation of system valves and associated control circuits and sump/tank level alarms are also verified.
isolation valve control circuits, including control  


14.2.12.2.22.2  Prerequisites      a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
circuit response to a steam line isolation signal
: b. Required electrical power supplies and control circuits are operational.
: c. The compressed air system is available to supply air to system valves and pumps.
: d. A water source (fire system) and a collection receptacle (oil/water separator, main condenser) are available for the testing of each sump/tank.


14.2.12.2.22.3  Test Method      a. The sump pumps and miscellaneous condensate drain tank pumps are operated, and performance characteristics are verified.
          (SLIS).  
: b. The response of each pump and associated alarms to sump/
tank high and low level signals is verified.
: c. The operability of system air-operated valves is verified, including the response to a process radiation signal.  


14.2.12.2.22.4 Acceptance Criteria
14.2.12.1.3.2 Prerequisites
: a. The performance characteristics of the system pumps are within design specifications.
: a. Required component testing, instrument calibration, and
: b. The turbine building oily waste header discharge valve closes on a high-radiation signal.  


14.2-144    Rev. 0 WOLF CREEK 14.2.12.2.23  Floor and Equipment Drain System Preoperational Test              (SU4-LF01)
system flushing/cleaning are complete.  
: b. Required electrical power supplies and control circuits are operational.  
: c. The main steam line isolation valve accumulators are


14.2.12.2.23.1  Objectives To demonstrate the sump pumps and hot machine shop oil interceptor pump's capacities and response to sump/tank level signals. The operation of system valves, their response to safety signals, and sump/tank level alarms are also verified.
charged, and the associated hydraulic systems are  


14.2.12.2.23.2  Prerequisites
operational.  
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits          are operational.
: c. The compressed air system is available to supply air to system valves and pumps.
: d. A water source (fire system or ESW) and a collection receptacle (holdup tank, radwaste system, etc.) are available for the testing of each sump/tank.  


14.2.12.2.23.3  Test Method  
14.2.12.1.3.3  Test Method  
: a. The sump pumps and hot machine shop oil interceptor pumps are operated, and their capacities are verified.
: b. The response of each system pump, system indication, and          alarms, to sump/tank high and low level signals is verified.
: c. The operability of system air- and motor-operated valves is verified, including their response to safety signals.


14.2.12.2.23.4  Acceptance Criteria
An SLIS is initiated, and the response of the main steam bypass, main steam
: a. The capacities of the floor and equipment drain system pumps are within design specifications.
: b. System valves properly respond to safety injection signals and containment isolation signals.
: c. The valve response times are within design specifications.


14.2-145    Rev. 0 WOLF CREEK 14.2.12.2.24  13.8-kV System Preoperational Test (S-04PA01) 14.2.12.2.24.1  Objectives
drain, and auxiliary feedwater turbine warmup valves is verified.  
: a. To demonstrate that the 13.8-kV busses can be energized          from the startup transformer.
: b. To demonstrate that automatic fast transfer of the busses from the unit auxiliary source to the startup source is within design specifications.
: c. To demonstrate that the unit auxiliary source or startup source feeder breakers will trip on a stuck breaker condition.
: d. To demonstrate proper operation of system          instrumentation and controls.  


14.2.12.2.24.2 Prerequisites
14.2.12.1.3.4 Acceptance Criteria
: a. Required component testing and instrument calibration are complete.
: a. The main steam bypass, drain, and auxiliary feedwater
: b. Required electrical power supplies and control circuits are operational.
: c. The 13.8-kV system has been energized.


14.2.12.2.24.3  Test Method
turbine warmup valves close on receipt of an SLIS.  
: a. The 13.8-kV busses are energized from the startup          transformer, and bus voltages are recorded.
: b. Automatic fast transfer from the unit auxiliary source to the startup source is verified.
: c. Stuck breaker conditions are simulated, and proper operation of the 13.8-kV auxiliary source and startup source feeder breakers is verified.  


14.2.12.2.24.4  Acceptance Criteria
14.2.12.1.4  Main Steam System Preoperational Test (S-03AB04)
: a. The 13.8-kV bus voltages are within design specifications, when energized from the startup transformer.
: b. Automatic fast transfer of the busses from the unit auxiliary source to the startup source is within design specifications.


14.2-146    Rev. 0 WOLF CREEK     c. The 13.8-kV auxiliary source and startup source feeder          breakers trip on receipt of a stuck breaker signal.  
14.2-28 Rev. 0 WOLF CREEK 14.2.12.1.4.1  Objectives
: a. To determine, during hot functional testing, the


14.2.12.2.25  4,160-V (Non-Class IE) System  Preoperational Test (S-04PB01) 14.2.12.2.25.1  Objectives
operating times of the main steam isolation valves,  
: a. To demonstrate that the 4,160-V busses can be energized from their normal and alternate sources, and to verify the operability of supply breaker and bus tie breaker protective interlocks.
: b. To demonstrate that automatic transfer is achieved through the tie breaker from the normal source to the          alternate source in the event of an electrical fault. 
: c. To demonstrate proper operation of system instrumentation and controls.


14.2.12.2.25.2  Prerequisites
main steam bypass valves, main steam dump valves, main steam cooldown valves, and the main steam atmospheric relief valves.  
: a. Required component testing and instrument calibration are complete.
: b. To verify the response of the main steam isolation
: b. Required electrical power supplies and control circuits are operational.
: c. The 4,160-V (non-Class IE) system has been energized.
14.2.12.2.25.3  Test Method 
: a. The 4,160-V non-Class IE busses are energized from their normal and alternate source, and bus voltages are recorded.  
: b. System supply breakers and bus tie breakers are operated, and breaker interlocks are verified.
: c. System electrical fault signals are simulated, and automatic transfer is verified through the tie breaker from the normal source to the alternate source for each 4,160-V bus.


14.2.12.2.25.4  Acceptance Criteria
valves to steam line isolation signals.  
: a. The voltage of each 4,160-V non-Class IE bus, when supplied from its normal source and alternate source, is within design specifications.  


14.2-147    Rev. 0 WOLF CREEK      b. System supply breaker and bus tie breaker interlocks          operate in accordance with the system design.  
14.2.12.1.4.2  Prerequisites
: c. Automatic transfer is achieved through the tie breaker from the normal source to the alternate source, for each          4,160-V bus, upon receipt of an electrical fault signal.
: a. Required component testing, instrument calibration, and


14.2.12.2.26  480-Volt (Non-Class IE) System Preoperational Test (S-04PG01)
system flushing/cleaning are complete.  
: b. Required electrical power supplies and control circuits


14.2.12.2.26.1  Objectives
are operational.  
: a. To demonstrate that the 480-V non-Class IE load centers can be energized from their normal sources and alternate sources, as applicable, and verify the operability of          feeder breaker and bus tie breaker protective          interlocks.  
: c. Hot functional testing is in progress.  
: b. To demonstrate that the 480-V busses supplied by 4160-V (Class IE) source breakers are shed on receipt of a load shed signal.
: d. The condenser is available to receive steam from the main steam system.  
: c. To demonstrate proper operation of system instrumentation and controls.  


14.2.12.2.26.2 Prerequisites
14.2.12.1.4.3 Test Method
: a. Required component testing and instrument calibration are complete.
: a. The main steam isolation valves, main steam bypass
: b. Required electrical power supplies and control circuits          are operational.
: c. The 480-V (non-Class IE and Class IE) systems have been energized.


14.2.12.2.26.3  Test Method
valves, main steam dump valves, main steam cooldown
: a. The 480-V non-Class IE load centers are energized from their normal source and alternate source, as applicable and voltages are recorded.
: b. System feeder breakers and bus tie breakers are operated, and breaker interlocks verified.
: c. A load shed signal is simulated, and the 480-V busses supplied by the 4,160-V (Class IE) source breakers are verified to shed.


14.2-148    Rev. 0 WOLF CREEK 14.2.12.2.26.4  Acceptance Criteria 
valves, and the main steam atmospheric relief valves are operated, and operating times are recorded.  
: a. The voltage for each 480-V non-Class IE load center, when supplied from its normal source and alternate source, as applicable, is within design specifications.
: b. An SLIS is initiated, and the response of the main steam
: b. System feeder breaker and bus tie breaker interlocks operate in accordance with the system design.
: c. The 480-V busses supplied by the 4160-V (Class IE) source breakers shed on receipt of a load shed signal.


14.2.12.2.27  250-V DC System Preoperational Test (S-04PJ01)
isolation valves is verified.  


14.2.12.2.27.1 Objectives  To demonstrate the ability of the battery and battery chargers to provide power to the busses. The battery chargers' ability to recharge their respective battery is also demonstrated. Proper operation of system instrumentation and controls is also verified.
14.2.12.1.4.4 Acceptance Criteria
: a. The operating times of the main steam isolation valves,


14.2.12.2.27.2  Prerequisites
main steam dump valves, main steam bypass valves, main
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. Ventilation for the battery room is available.      d. The 250-V dc system has been energized.


14.2.12.2.27.3  Test Method
steam cooldown valves, and the main steam atmospheric relief valves are within design specifications.  
: a. The battery is discharged, using a test load at the design duty cycle discharge rate.  
: b. The main steam isolation valves close on receipt of a  
: b. The battery is fully discharged to determine its capacity factor.
: c. The ability of each battery charger to charge the battery to normal conditions, after the battery has undergone a design duty cycle, while simultaneously supplying power at a rate equivalent to the largest motor current load is verified.
: d. A load shed signal is initiated, and the battery charger PJ31 ac supply breaker is verified to trip.


14.2-149    Rev. 0 WOLF CREEK 14.2.12.2.27.4  Acceptance Criteria 
steam line isolation signal.  
: a. The battery is capable of maintaining output voltage above the design minimum, during a design duty cycle.
: b. The battery capacity factor is in accordance with design requirements.
: c. The battery chargers are able to recharge the battery to normal conditions, after the battery has undergone a design duty cycle, while simultaneously supplying power at a rate equivalent to the largest motor current load.
: d. Battery charger PJ31 ac supply breaker trips on receipt of a load shed signal. 14.2.12.2.28  125-V (Non-Class IE) DC System Preoperational Test (S-04PK01, S-04PK02)


14.2.12.2.28.1 Objectives
14.2.12.1.5 Main Feedwater System Preoperational Test (S-03AEO1)


To demonstrate the ability of the batteries and chargers to provide power to the busses. The battery chargers' ability to recharge their respective battery is also demonstrated. Proper operation of system instrumentation and controls is also verified.
14.2.12.1.5.1  Objectives
: a. To demonstrate the operation of the feedwater system  


14.2.12.2.28.2  Prerequisites
valves and to verify the response of the feedwater
: a. Required component testing and instrument calibration are complete.      b. Required electrical power supplies and control circuits are operational.
: c. Ventilation for the battery room is available.


14.2.12.2.28.3  Test Method
system valves to a feedwater isolation signal (FIS).  
: a. Each battery is discharged, using a test load at the design duty cycle discharge rate.
: b. Each battery is fully discharged to determine its capacity factor.
: c. The ability of each battery charger to charge its respective battery to normal conditions, after the battery has undergone a design duty cycle, while simultaneously supplying power at a rate equivalent to the design instrumentation loading.  


14.2-150    Rev. 0 WOLF CREEK     d. A safety injection load shed signal is initiated, and          the battery charger PK21, PK22, PK23, and PK24 supply breaker is verified to trip.  
14.2-29 Rev. 13 WOLF CREEK  
: b. To perform the initial operation of the steam generator feedwater pumps (SGFP).  


14.2.12.2.28.4  Acceptance Criteria  
14.2.12.1.5.2 Prerequisites
: a. Each battery is capable of maintaining output voltage above the design minimum, during a design duty cycle.
: a. Required component testing, instrument calibration, and  
: b. Each battery capacity factor is in accordance with design requirements.
: c. The battery chargers are able to recharge the batteries to normal conditions, after the battery has undergone a design duty cycle, while simultaneously supplying power          at a rate equivalent to the design load. 
: d. Battery charger PK21, PK22, PK23, and PK24 supply breaker trips on receipt of a safety injection load shed signal.


14.2.12.2.29  Instrument AC (Non-Class IE) System Preoperational Test (S-04PN01)
system flushing/cleaning are complete.  
: b. Required electrical power supplies and control circuits


14.2.12.2.29.1  Objectives
are operational.  
: c. The closed cooling water system is available to provide


To demonstrate that the 120-V non-Class IE ac distribution panels can be fed from their associated supply transformers. Proper operation of system instrumentation and controls is also verified.
cooling water to the SGFP lube oil coolers.  
14.2.12.2.29.2  Prerequisites 
: d. The compressed air system is available to provide air to system air-operated valves.  
: a. Required component testing and instrument calibration are complete.  
: e. The steam seal system is available to provide seal steam
: b. Required electrical power supplies and control circuits are operational.  


14.2.12.2.29.3  Test Method
and packing exhaust for the SGFPs.  
: f. The main turbine is available for turning gear


The 120-V non-Class IE ac distribution panels are energized from their associated supply transformers, and the panel voltages are recorded.
operation.
: g. The condensate system is available to supply suction for


14.2.12.2.29.4  Acceptance Criteria
the SGFPs.  
: h. The main condenser is available to receive SGFP turbine


Each 120-V non-Class IE ac distribution panel voltage is within design specifications.  
exhaust.
: i. The auxiliary steam system is available to provide steam flow to the SGFP turbines.  


14.2-151    Rev. 0 WOLF CREEK 14.2.12.2.30 Emergency Lighting System Preoperational Test               (S-04QD01)
14.2.12.1.5.3 Test Method
: a. Feedwater system valves are operated, and the proper


14.2.12.2.30.1  Objectives To demonstrate the capability of the emergency lighting system to provide adequate lighting. Proper operation of system instrumentation and controls is also verified.
response of required system valves to an FIS is  


14.2.12.2.30.2  Prerequisites
verified.  
: b. The turbine-driven SGFPs are operated as limited by


Required electrical power supplies and control circuits are operable.  
steam, and operating data are recorded.  
: c. The motor-driven SGFP is operated, and operating data


14.2.12.2.30.3  Test Method The ability of the emergency lighting system to provide adequate lighting is verified. The operability of associated instrumentation and control circuits is also verified.  
are recorded.  


14.2.12.2.30.4  Acceptance Criteria  
14.2.12.1.5.4  Acceptance Criteria  
: a. The feedwater control valves, steam generator feedwater


The emergency lighting system operates in accordance with system design specifications.
isolation valves, feedwater chemical injection isolation


14.2.12.2.31  Public Address System Preoperational Test (S-04QF01)
valves, and feedwater bypass control valves close on


14.2.12.2.31.1  Objectives
receipt of an FIS.  


To demonstrate the capability of the public address system to provide adequate intraplant communications and to verify the operability of the evacuation alarm system.
14.2-30    Rev. 0 WOLF CREEK
14.2.12.2.31.2  Prerequisites
: b. The closing time of the feedwater isolation valves is within design specifications.  
: a. Required component testing and instrument calibration are complete.  
: c. The performance of the motor-driven SGFP is within
: b. Required electrical power supplies and control circuits are operable.  


14.2.12.2.31.3  Test Method
design specifications.  
: a. The public address system is operated from all locations, and adequate communications verified.
: b. Operability of the evacuation alarm system is verified.  


14.2-152    Rev. 0 WOLF CREEK 14.2.12.2.31.4  Acceptance Criteria 
14.2.12.1.6 Steam Generator Level Control Test (S-03AE02)  
: a. The evacuation alarm system operates in accordance with system design specifications.
14.2.12.2.32 Heat Tracing Freeze Protection System Preoperational Test (S-04QJ01)  


14.2.12.2.32.1  Objectives  
14.2.12.1.6.1  Objectives  
: a. To demonstrate the operability of the feedwater control


To demonstrate the ability of the freeze protection system to automatically control the associated heat tracing circuits in accordance with system design.
valves (FWCVs).
The operation of system instrumentation and controls is also verified.
: b. To demonstrate the operability of the FWCV bypass


14.2.12.2.32.2  Prerequisites      a. Required component testing and instrument calibration are complete.  
valves.  
: b. Required electrical power supplies and control circuits are operational.
: c. To demonstrate the response of the FWCVs and bypass


14.2.12.2.32.3  Test Method
valves to signals generated by the steam generator level


Temperature signals are varied and the energization/ deenergization of the associated heat tracing circuits is verified.  
control system.  


14.2.12.2.32.4 Acceptance Criteria
14.2.12.1.6.2 Prerequisites
: a. Required component testing and instrument calibration


The freeze protection system automatically controls the associated heat tracing circuits, in accordance with system design.
are complete.  
14.2.12.2.33  Secondary Sampling System Preoperational Test (S-04RM01)
: b. Required electrical power supplies and control circuits


14.2.12.2.33.1  Objectives
are operational.  
: a. To demonstrate the operating characteristics of the steam generator blowdown sample drain tank pump, sample chiller pump, and the condenser sample pumps, and verify the operability of their associated control circuits.
: b. To demonstrate that the system sample flows are within design specifications.  


14.2.12.2.33.2 Prerequisites
14.2.12.1.6.3 Test Method
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: a. The FWCVs are operated from their respective controllers, and the FWCVs' response to feedwater flow,  


14.2-153    Rev. 0 WOLF CREEK      b. Required electrical power supplies and control circuits          are operable.
steamline flow, and steam generator level is verified.  
: c. Plant conditions are established, and systems are available, as necessary, to facilitate drawing samples          from the sample points.
: b. The FWCV bypass valves are operated from their  
: d. The steam generator blowdown system is available to receive effluent from the steam generator blowdown sample drain tank.  
: e. The closed cooling water system is available to provide cooling water to the system sample coolers and chiller package.
14.2.12.2.33.3  Test Method 
: a. The steam generator blowdown sample drain tank pump, sample chiller pump, and the condenser sample pumps are operated, and pump performance data recorded.
Operability of their associated control circuits is also verified.
: b. System samples are obtained, and flows are recorded.


14.2.12.2.33.4  Acceptance Criteria
respective controllers, and their response to steam
: a. The steam generator blowdown sample drain tank pump, sample chiller pump, and condenser sample pump performance characteristics are within design          specifications. 
: b. Sample system flows are within design specifications.


14.2.12.2.34  Area Radiation Monitoring Preoperational Test (S-04SD01)
generator level and neutron flux signal is verified.  


14.2.12.2.34.1 Objectives
14.2.12.1.6.4 Acceptance Criteria
: a. The response of the FWCVs to feedwater flow, steamline


To demonstrate the operation of the area radiation monitors and to verify that a high radiation signal at each monitor will initiate an alarm.
flow, and steam generator level is in accordance with


14.2.12.2.34.2  Prerequisites
system design.  
: a. Required component testing and instrument calibration are complete.  
: b. The response of the FWCV bypass valves to steam
: b. Required electrical power supplies and control circuits are operational.


14.2-154    Rev. 0 WOLF CREEK 14.2.12.2.34.3  Test Method A calibration source is utilized to actuate the area radiation monitors, and their operability and associated alarms are verified.
generator level and neutron flux signal is in accordance
14.2.12.2.34.4  Acceptance Criteria


Each area radiation monitor actuates the associated alarms, on receipt of a high radiation signal.  
with system design.  


14.2.12.2.35 Seismic Monitoring Instrumentation System Preoperational Test (S-04SG01)  
14.2-31    Rev. 0 WOLF CREEK 14.2.12.1.7 Auxiliary Feedwater Motor-Driven Pump and Valve Preoperational Test (S-03ALOl)  


14.2.12.2.35.1  Objectives To demonstrate the operability of the seismic triggers and switches and strong motion accelerometers, including their associated alarms and recording and playback systems.
14.2.12.1.7.1  Objectives  


14.2.12.2.35.2  Prerequisites
To demonstrate the operability of the motor-driven auxiliary feedwater pumps,
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.


14.2.12.2.35.3  Test Method
determine by flow test their ability to supply water to the steam generators,


A test signal is initiated, and the operability of the seismic triggers and switches and strong motion accelerometers, including their associated alarms and recording and playback systems, is verified.  
and verify their response to safety signals. The operation of system motor-


14.2.12.2.35.4  Acceptance Criteria
operated valves, including their response to safety signals, is also verified.  


The seismic triggers and switches and strong motion accelerometers, including their associated alarms and recording and playback systems, operate in accordance with system design specifications.
14.2.12.1.7.2  Prerequisites
: a. Required component testing, instrument calibration, and  


14.2.12.2.36  Loose Parts Monitoring System Test (SU4-SQ02).  
system flushing/cleaning are complete.  
: b. Required electrical power supplies and control circuits are operational.  
: c. The condensate storage tank contains an adequate supply


14.2.12.2.36.1  Objective
of demineralized water for the performance of this test.  
: d. The steam generators are available to receive water from


To demonstrate the operability of the accelerometers, signal conditioning devices and diagnostic equipment, including associated alarms and recording and playback systems.  
the auxiliary feedwater system.  


14.2-155    Rev. 0 WOLF CREEK 14.2.12.2.36.2  Prerequisites  
14.2.12.1.7.3 Test Method
: a. Required component testing and instrument calibration are complete.
: a. Performance characteristics of the motor-driven
: b. Required electrical power supplies and control circuits are operational.
: c. Reactor coolant system is filled with water.
: d. Reactor coolant system is at normal operating temperature and pressure with all reactor coolant pumps running, and hot functional testing is in progress (for those portions of the testing to be performed during hot functional testing).      e. Reactor coolant system is at normal operating temperature and pressure with all reactor coolant pumps running after fuel loading during startup testing (for those portions of the testing to be performed during startup testing).


14.2.12.2.36.3  Test Method
auxiliary feedwater pumps are verified while discharging
: a. Test signals are initiated and the operability of the accelerometers, signal conditioners, and diagnostic circuitry, including alarms and recording and playback systems, is verified.
: b. Channel audio outputs are also recorded during hot          functional testing and after fuel loading during startup          testing to obtain a record of the reactor coolant system noise "signature."


14.2.12.2.36.4  Acceptance Criteria
to the steam generators.  
: b. System component control circuits are verified, including the operation of the motor-driven auxiliary


The accelerometers, signal conditioners, and diagnostic circuitry, including alarms and recording and playback systems operate to detect loose parts as specified in USAR Section 4.4.6.4.
feedwater pumps and system valves on receipt of safety


14.2.12.2.37  Plant Performance Test (SU8-0007)
signals.  


14.2.12.2.37.1 Objectives
14.2.12.1.7.4 Acceptance Criteria
: a. To monitor the balance-of-plant and electrical systems under loaded conditions during hot functional and power ascension testing. The ability of the ventilation systems to maintain ambient temperatures within design limits is also verified. To monitor the concrete temperatures surrounding hot penetrations and to verify evacuation alarm audibility in high noise areas.
: a. Motor-driven auxiliary feedwater pump performance


14.2-156    Rev. 0 WOLF CREEK 14.2.12.2.37.2  Prerequisites 
characteristics must be within design specifications.  
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.  
: b. Motor-driven auxiliary feedwater pumps automatically
: b. Required HVAC systems have been balanced.
: c. Required electrical power supplies and control circuits are operational.


14.2.12.2.37.3  Test Method
start on receipt of an engineered safety features


This procedure does not provide a test method. It provides a monitoring and data collection function only, with the resultant datum evaluated against provided design values, as applicable. 14.2.12.2.37.4  Acceptance Criteria
actuation signal (ESFAS) in the absence of an SIS signal
: a. Evacuation alarm audibility in high noise areas is verified.
: b. The containment coolers maintain containment temperature within design.


Note: Each monitored point is evaluated throughout the test to verify that the applicable system or component is functioning per design.  
and a Class IE 4.16 kV bus undervoltage signal.
: c. Auxiliary feedwater suction valves from essential


14.2.12.2.38  Electrical Distribution System Voltage Verification Test (S-090023) 14.2.12.2.38.1  Objectives To record actual loaded electrical distribution parameters during various steady-state and transient conditions.
service water system open, and suction valves from


14.2.12.2.38.2  Prerequisites
condensate storage tank close, on condensate storage
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.


14.2.12.2.38.3  Test Method
tank low-suction-pressure signals, coincident with an


The bus voltages and loadings of the electrical distribution system (down to the Class lE 120/208 V ac system) are recorded for 
auxiliary feedwater pump ESFAS.


14.2-157   Rev. 0 WOLF CREEK various steady state configurations. Data is also recorded during the starting of the largest Class 1E and non-Class lE motors. All monitored busses are loaded to at least 30 percent.
14.2-32   Rev. 0 WOLF CREEK 14.2.12.1.8  Auxiliary Feedwater Turbine-Driven Pump and Valve Preoperational Test (SU3-AL02)


14.2.12.2.38.4 Acceptance Criteria Not applicable.  
14.2.12.1.8.1 Objectives
: a. To verify the auxiliary feedwater pump turbine


Note:  The data obtained from this test procedure are used to verify electrical system voltage analysis.
mechanical trip and throttle valve automatic operation


14.2.12.3  Startup Test Procedures  The following sections are the test abstracts for each startup test. Table 14.2-3 provides an index of these tests.
on an auxiliary feedwater actuation signal (AFAS).  
14.2.12.3.1  Automatic Steam Generator Level Control (S-07AB01)
: b. To perform the initial coupled operation of the turbine-  


14.2.12.3.1.1  Objectives
driven auxiliary feedwater pump. Full flow
: a. To verify the stability of the automatic steam generator level control following simulated transients at low power conditions and the proper operation of the variable speed feature of the feedwater pumps.
: b. To demonstrate the performance characteristics of the          steam generator feedwater pumps.
14.2.12.3.1.2  Prerequisites
: a. The steam generator level control system has been checked and calibrated.
: b. Steam generator level instruments and set points have been set and calibrated.
: c. Main feedwater is operational.  


14.2.12.3.1.3  Test Method
characteristics of the turbine-driven pump will be
: a. Induce simulated steam generator level transients to          verify proper steam generator level control response. 
: b. Verify the variable speed features of the steam generator feedwater pumps by manipulation of controllers and test input signals, and verify the performance characteristics of the steam generator feedwater pumps.


14.2-158    Rev. 0 WOLF CREEK 14.2.12.3.1.4  Acceptance Criteria 
demonstrated during hot functional testing.  
: a. Automatic steam generator level control system response must be in accordance with the vendor's technical manual. 
: c. To perform five consecutive, successful, cold starts of the turbine-driven auxiliary feedwater pumps.  
: b. The steam generator feedwater pump's performance characteristics are within design specifications.  


14.2.12.3.2  Dynamic Automatic Steam Dump Control (SU7-AB02)
14.2.12.1.8.2  Prerequisites
: a. Required component testing, instrument calibration, and


14.2.12.3.2.1  Objectives
system flushing/cleaning are complete.  


To verify automatic operation of the  T average steam dump control system, demonstrate controller setpoint adequacy, and obtain final settings for steam pressure control of the condenser dump valves.
b    Required electrical power supplies and control circuits
14.2.12.3.2.2  Prerequisites
: a. The reactor coolant system is at normal operating pressure and temperature.
: b. The reactor is critical.
: c. The steam dump system has been checked and calibrated.
: d. Main feedwater and the condenser are operational.


14.2.12.3.2.3  Test Method
are operational.  
: a. Reactor power is increased by rod withdrawal and steam           dump to condenser to demonstrate setpoint adequacy.
: c. The steam generators are available to receive water from
: b. Pressure controller setpoint is increased prior to switching to  T average control, which will rapidly modulate open condenser dump valves.
: c. Simulate turbine operating conditions with reactor at power, then simulate turbine trip, resulting in the rapid opening of the steam dump valves.


14.2.12.3.2.4  Acceptance Criteria
the auxiliary feedwater pumps.  
: d. The steam generator blowdown system is available to


The steam dump system controllers must maintain stable reactor coolant system T average at the controllers set point with no divergent oscillations.
maintain the normal operating levels in the steam generators during auxiliary feedwater pump operation.
: e. The auxiliary steam system is available to supply steam


14.2.12.3.3  RTD Bypass Flow Measurement (S-07BB01)
to the auxiliary feedwater pump turbine.  
: f. For the performance characteristic test of this pump,


14.2.12.3.3.1  Objectives
hot functional testing (HFT) is in progress.  


To determine the flow rate necessary to achieve the design reactor coolant transport  time  in  each resistance temperature detector 
14.2.12.1.8.3  Test Method
: a. An AFAS is simulated, and opening of the mechanical trip


14.2-159    Rev. 0 WOLF CREEK (RTD) bypass loop and to measure the flow rate in each RTD bypass loop to ensure that the transport times are acceptable.
and throttle valve is verified.  
: b. The turbine-driven auxiliary feedwater pump is operated


14.2.12.3.3.2  Prerequisites
during HFT, and performance characteristics are  
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The reactor core is installed, and the plant is at normal operating temperature and pressure with all reactor coolant pumps running.
14.2.12.3.3.3  Test Method The flow rate necessary to achieve the design reactor coolant transport time for each hot and cold leg bypass loop is calculated, utilizing the hot and cold leg RTD bypass loop piping lengths. Hot and cold RTD bypass loop flow data are recorded.


14.2.12.3.3.4  Acceptance Criteria
recorded.  
: c. The ability of the turbine-driven auxiliary feedwater


The flow rate in each hot and cold leg RTD bypass loop, required to achieve the design reactor coolant transport time, is within design specifications.
pumps to start successfully five consecutive times from


14.2.12.3.4  Pressurizer  Heater  and  Spray  Capability  Test (S-07BB02) 14.2.12.3.4.1  Objectives To determine the rate of pressure reduction caused by fully opening the pressurizer spray valves and the rate of pressure increase from the operation of all pressurizer heaters.  
cold conditions is verified.  


14.2.12.3.4.2 Prerequisites
14.2-33    Rev. 0 WOLF CREEK 14.2.12.1.8.4  Acceptance Criteria
: a. Required component testing and instrument calibration are complete.
: a. The auxiliary feedwater pump mechanical trip and  
: b. Required electrical power supplies and control circuits are operational.
: c. The reactor core is installed with the plant in the hot shutdown condition at normal operating temperature and pressure with all reactor coolant pumps running.


14.2-160    Rev. 0 WOLF CREEK      d. The final setting of the continuous spray flow valves is          complete.  
throttle valve opens automatically on an AFAS.  
: e. The reactor coolant system is borated to the value required for fuel loading. 
: b. Operating characteristics of the turbine-driven
: f. This test is performed prior to initial criticality.


14.2.12.3.4.3  Test Method
auxiliary feedwater pump are in accordance with design.  
: a. With the pressurizer spray valves closed, all pressurizer heaters are energized, and the time to reach a 2,300 psig system pressure is measured and recorded.  
: c. The turbine driven auxiliary feedwater pump starts
: b. With the pressurizer heaters deenergized, both spray          valves are fully opened, and the time to reach a 2,000          psig system pressure is measured and recorded.  


14.2.12.3.4.4  Acceptance Criteria
successfully five consecutive times from a cold start.  


The pressurizer pressure response to the opening of the pressurizer spray valves and to the actuation of all pressurizer heaters is within design limits.  
14.2.12.1.9  Auxiliary Feedwater Motor-Driven Pump Endurance Test


14.2.12.3.5  Reactor Coolant System Flow Measurement (S-07BB03)  
            (SU3-AL03)  


14.2.12.3.5.1  Objectives  
14.2.12.1.9.1  Objectives  
: a. To confirm, after core installation but before initial critical operation, that reactor coolant system (RCS) flow rate as measured by loop elbow differential          pressure readings is greater than or equal to 90 percent          of the thermal design flow rate.
: a. To demonstrate that the motor-driven auxiliary feedwater
: b. To confirm during initial power operation that RCS flow rate as computed from calorimetric data is greater than or equal to the thermal design flow rate.


14.2.12.3.5.2  Prerequisites
pumps can operate for 48 continuous hours without
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The reactor core is installed, and the plant is at normal operating temperature and pressure.


14.2-161    Rev. 0 WOLF CREEK 14.2.12.3.5.3  Test Method 
exceeding any of their limiting design specifications.  
: a. Before critical operation, loop elbow differential pressure readings are taken with all reactor coolant pumps running, and RCS flow rate is calculated. 
: b. To demonstrate that the motor-driven auxiliary feedwater
: b. During initial power operation, calorimetric data are taken from Procedure S-07SC03, "Thermal Power Measurement and Statepoint Data Collection," and RCS flow rate is calculated.


14.2.12.3.5.4  Acceptance Criteria
pumps can operate for 1 hour after a cooldown from the


RCS flow rate by loop elbow differential pressure measurement is greater than or equal to 90 percent of the thermal design value and by calculation from calorimetric data is greater than or equal to the thermal design value.
48-hour test.  
14.2.12.3.6  Reactor Coolant System Flow Coastdown Test (SU7-BB04)
: c. To demonstrate that the room environmental conditions


14.2.12.3.6.1  Objectives
are not exceeded during the 48-hour test.  
: a. To measure the rate at which reactor coolant flow changes, subsequent to simultaneously tripping all reactor coolant pumps.
: b. To determine that the reactor coolant system low-flow delay time is less than or equal to the total low-flow delay time assumed in the safety analysis for loss of flow.
14.2.12.3.6.2  Prerequisites 
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The reactor core is installed, and the plant is at normal operating temperature and pressure with all reactor coolant pumps running.  


14.2.12.3.6.3 Test Method
14.2.12.1.9.2 Prerequisites
: a. Required component testing, instrument calibration and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits


Flow coastdown stabilization and loss of coolant delay-time data are recorded while tripping reactor coolant pumps.  
are operational.  
: c. The appropriate auxiliary feedwater pump room coolers


14.2-162    Rev. 0 WOLF CREEK 14.2.12.3.6.4  Acceptance Criteria 
are operational.  
: a. The rate of change of reactor coolant flow is within design specifications.
: d. The condensate storage tank is available as a water
: b. The reactor coolant system low-flow delay time is less than or equal to the total low-flow delay time assumed in the safety analysis for loss of flow.


14.2.12.3.7  Pressurizer  Continuous  Spray  Flow  Verification (S-07BB05)
source and to receive recirculation flow.  


14.2.12.3.7.1 Objectives
14.2.12.1.9.3 Test Method


To establish a setting for the pressurizer continuous spray flow valves to obtain an optimum continuous spray flow.
Each motor-driven pump is started and operated for 48 hours after reaching
14.2.12.3.7.2  Prerequisites
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The reactor core is installed with the plant in the hot shutdown condition at normal operating temperature and pressure with all reactor coolant pumps running.
: d. The reactor coolant system is borated to the value          required for fuel loading. 
: e. This test shall be performed prior to initial criticality.
: f. The preliminary setting of the continuous spray flow valves has been completed during hot functional testing.


14.2.12.3.7.3  Test Method
rated speed and rated discharge pressure and flow, or a greater pressure and


Continuous spray flow valves are adjusted to establish the optimum continuous spray flow, and the valve throttle positions are recorded.
less flow. During the endurance run, pump- operating data and the pump room


14.2.12.3.7.4  Acceptance Criteria
environmental conditions are recorded. At the completion of each endurance


The continuous spray flow valves are throttled to establish the optimum continuous spray flow to keep the spray line warm and minimize normal steady-state pressurizer heater loads.
test, the pump is cooled for 8 hours and until pump data returns to within 20 F


14.2-163    Rev. 0 WOLF CREEK 14.2.12.3.8  RTD/TC Cross Calibration (S-07BB06) 14.2.12.3.8.1  Objectives
of the original pretest data. The pump is then started and operated for 1
: a. To provide a functional checkout of the reactor coolant          system resistance temperature detectors (RTDs) and incore thermocouples and to generate isothermal cross-calibration data for subsequent correction factors to indicated temperatures.


NOTE            This portion of the test need be performed only if the data collected in S-03BB16, RTD/TC Cross Calibration, during hot functional testing, so warrants. 
hour.  
: b. To provide a functional checkout of the core subcooling monitor system including the detecting thermocouples.  


14.2.12.3.8.2 Prerequisites
14.2-34    Rev. 0 WOLF CREEK 14.2.12.1.9.4 Acceptance Criteria
: a. Required component testing and instrument calibration are complete.  
: a. The operating parameters (vibration, bearing
: b. Required electrical power supplies and control circuits          are operational.   
: c. Plant heatup, following core loading, is in progress, and all reactor coolant pumps are operating.


14.2.12.3.8.3  Test Method
temperatures, etc.) of each motor-driven auxiliary
: a. At various temperature plateaus RTD and incore thermocouple data are recorded. Isothermal cross-calibration correction factors for individual thermocouples and the installation corrections for individual RTDs are determined.
: b. At normal operating temperature, the thermocouple core subcooling monitors' operational and programmable          functions are verified, including associated alarms,          displays, and printouts.


14.2.12.3.8.4  Acceptance Criteria
feedwater pump do not exceed the design specifications.  
: a. Individual RTD readings are within the design specifications.  
: b. The environmental conditions of each motor-driven
: b. The installation corrections of the RTDs are within design specifications.


14.2-164    Rev. 0 WOLF CREEK      c. The thermocouple core subcooling monitor alarms,          displays, and printouts function in accordance with design specifications.
auxiliary feedwater pump room do not exceed the design  


14.2.12.3.9  Core Loading Instrumentation and Neutron Source              Requirements (S-07SC01)
specifications.  


14.2.12.3.9.1 Objectives
14.2.12.1.10 Auxiliary Feedwater System Water Hammer Test (S-


To verify proper alignment, calibration, and neutron response of the temporary core loading instrumentation prior to start of fuel- loading; to check the neutron response of the nuclear instrumentation system (NIS) source range channels prior to start of fuel-loading; and to check the neutron response of the temporary and NIS source range instrumentation prior to resumption of fuel-loading following any delay of 8 hours or more. To verify the signal to noise ratio is greater than 2.
03AL04)  
14.2.12.3.9.2  Prerequisites
: a. Hot functional testing is completed.
: b. The nuclear instrumentation system is installed and calibrated.


14.2.12.3.9.3  Test Method
14.2.12.1.10.1 Objectives
: a. A portable neutron source (1-5 curie), plus preshipment equipment checkout data, is used to verify proper alignment, calibration, and neutron response of the temporary core-loading instrumentation.       b. A portable neutron source (1-5 curie) is used to check the neutron response of the NIS source range detectors.
: c. A portable neutron source (1-5 curie) or movement of a source-bearing fuel element to produce the desired change in neutron level to verify the neutron response of the temporary and NIS source range instrumentation prior to resumption of fuel-loading following any delay of 8 hours or more.
: d. Perform a statistical evaluation of 10 observations for each channel, to verify operability of the equipment.


14.2.12.3.9.4  Acceptance Criteria
To demonstrate that the injection of auxiliary feedwater at rated flow into a steam generator at or near normal operating temperatures will not cause


Neutron instrumentation is operational, calibrated, and indicates a positive/negative change in count rate as the neutron level is increased and/or decreased. The signal to noise ratio is greater than 2.  
damaging water hammer to the steam generators and/or feedwater system.  


14.2-165    Rev. 0 WOLF CREEK 14.2.12.3.10  Thermal Power Measurement and Statepoint Data              Collection (S-07SC03)
14.2.12.1.10.2 Prerequisites
: a. Required component testing, instrument calibration, and  


14.2.12.3.10.1  Objectives To measure core thermal power and obtain data for instrumentation calibration.
system flushing/cleaning are complete.  
: b. Required electrical power supplies and control circuits


14.2.12.3.10.2  Prerequisites
are operational.  
: a. Calorimetric instrumentation is installed.
: c. The steam generators are at or near normal operating
: b. This test is performed at 30-percent, 50-percent, 75-percent, 90-percent, and 100-percent power.


14.2.12.3.10.3  Test Method  Collect data and calculate thermal power. Obtain statepoint data, compute the average for each parameter measured, convert to the appropriate units, and summarize the data for each RCS loop.  
temperature.  
: d. The condensate storage tank is available as a water source.  


14.2.12.3.10.4 Acceptance Criteria
14.2.12.1.10.3 Test Method


This test is for the collection of data.  
Auxiliary feedwater is injected into each steam generator. The feedwater system


14.2.12.3.11  Nuclear Instrumentation System Test (SU7-SE01)
piping and the steam generators are monitored visually and audibly to verify


14.2.12.3.11.1  Objectives
that no damaging water hammer occurs.  


The purpose of this test is to verify that the nuclear instrumentation system performs the required indications and control functions through the source, intermediate, and power ranges of operation prior to core loading.
14.2.12.1.10.4 Acceptance Criteria
14.2.12.3.11.2 Prerequisites
: a. The nuclear instrumentation system is installed, calibrated, aligned, and operational for a period of at least 4 hours.
: b. The plant is at ambient temperature and pressure.


14.2.12.3.11.3  Test Method
No damaging water hammer occurs.  
: a. The source and intermediate range channels are subjected to various test signals to verify that the appropriate indicators alarm, illuminate, or actuate, and the source range local and remote speakers function.  


14.2-166    Rev. 0 WOLF CREEK      b. The power range channels are subjected to various test          signals to observe proper meter reading and function of the comparator and rate circuitry.
14.2.12.1.11  Auxiliary Feedwater Turbine-Driven Pump Endurance
: c. The high voltage circuitry of the source and          intermediate range channels is tested.  


14.2.12.3.11.4  Acceptance Criteria
Test (SU3-AL05)


The control and indication functions and the reactor trip set points of the nuclear instrumentation system source, intermediate, and power range channels have been verified.  
14.2.12.1.11.1  Objectives


14.2.12.3.12  Operational  Alignment of Nuclear  Instrumentation (S-07SE02)  14.2.12.3.12.1  Objectives
14.2-35    Rev. 0 WOLF CREEK
: a. To demonstrate that the turbine-driven auxiliary feedwater pump can operate for 48 continuous hours


To 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 prior to initial criticality to at or near full reactor power.
without exceeding any of its limiting design


14.2.12.3.12.2  Prerequisites
specifications.  
: a. The nuclear instrumentation system has been aligned.  
: b. To demonstrate that the turbine-driven auxiliary
: b. This test is conducted prior to criticality, during power escalation, and at or near full power.
14.2.12.3.12.3  Test Method 
: a. All functions are calibrated, tested, and verified, utilizing permanently installed controls and adjustment mechanisms.
: b. Operational modes of the source range, intermediate range, and power range channels are set for their proper functions, as per the test instructions.


14.2.12.3.12.4  Acceptance Criteria
feedwater pump can operate for 1 hour after a cool down


The overlap between the source, intermediate, and power range channels must be at least 1-1/2 decades, and the power range channels are capable of being adjusted to agree with the results of plant calorimetric calculations.
from the 48-hour test.
: c. To demonstrate that the room environmental conditions


14.2-167    Rev. 0 WOLF CREEK 14.2.12.3.13  Axial Flux Difference Instrumentation Calibration              (S-07SE03)
are not exceeded during the 48-hour test.  


14.2.12.3.13.1 Objectives To derive calibration factors for overpower, overtemperature,  and T setpoints, based on incore flux data, calorimetric data, and excore nuclear instrumentation detector currents.
14.2.12.1.11.2 Prerequisites
: a. Required component testing, instrument calibration and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits


14.2.12.3.13.2  Prerequisites
are operational.  
: a. The axial flux difference instrumentation system has been aligned.
: c. The appropriate auxiliary feedwater pump room coolers
: b. Data has been obtained from flux maps taken at 30-          percent and 50-percent power.
14.2.12.3.13.3  Test Method


Collect data, as required by test instruction, at 50-percent and 75-percent power, perform FI calculations to calibration factors, and extrapolate results for use at the 100-percent power plateau.
are operational.  
14.2.12.3.13.4  Acceptance Criteria
: d. The condensate storage tank is available as a water


Calibration factors agree with Technical Specifications.  
source and to receive recirculation flow.
: e. A steam source is available.  


14.2.12.3.14 Control Rod Drive Mechanism Operational Test (S-07SF01)
14.2.12.1.11.3  Test Method


14.2.12.3.14.1  Objectives
The pump is started and operated for 48 hours after reaching rated speed and rated discharge pressure and flow, or a greater pressure and less flow. The


To demonstrate the proper operation of the rod drive mechanisms under both cold and hot plant conditions and to provide verification of proper slave cycler timing.
turbine-driven auxiliary feedwater pump operating steam is as close to normal


14.2.12.3.14.2  Prerequisites
operating temperature as possible and is at least 400 F. During the endurance
: a. The control rod drive mechanisms are installed.
: b. The rod drive motor-generator sets are installed and power is available.
: c. For the control rod drive mechanism timing test, the core is installed, rod position indication is installed, and the control rod driving mechanism cooling fans are operational.
: d. Nuclear instrumentation channels operable and operating.


14.2-168    Rev. 0 WOLF CREEK      e. A fast speed oscillograph (Visicorder or equivalent) to          monitor test parameters is available.
run, pump-operating data and the pump room environmental conditions are


14.2.12.3.14.3  Test Method
recorded. At the completion of the endurance test, the pump is cooled for 8
: a. With the reactor core installed and reactor in the cold shutdown condition, confirm that the slave cycler devices supply operating signals to the proper CRDM stepping magnet coils.
: b. Verify proper operation of all CRDMs under both cold and hot shutdown conditions. CRDM magnet coil currents and audio noise signals are recorded.


14.2.12.3.14.4  Acceptance Criteria  The control rod drive mechanisms conform to the requirements for proper mechanism operation and timing as described in the magnetic control rod drive mechanism instruction manual.  
hours and until pump data returns to within 20 F of the original pretest data.


14.2.12.3.15  Rod Control System (S-07SF02)
The pump is then started and operated for 1 hour.  


14.2.12.3.15.1 Objectives
14.2.12.1.11.4 Acceptance Criteria
: a. The operating parameters (vibration, bearing


To demonstrate and document that the rod control system performs the required control and indication functions just prior to initial criticality. To demonstrate operation of the rod inhibit functions.
temperatures, etc.) do not exceed the design


14.2.12.3.15.2  Prerequisites
specifications.  
: a. The reactor coolant system is at normal operating          pressure and temperature.  
: b. The environmental conditions of the turbine-driven
: b. The rod control system is installed and aligned.
: c. The source range nuclear instruments are operable.
: d. The rods are capable of withdrawal.
: e. The rod position indication system is operable.


14.2.12.3.15.3  Test Method
auxiliary feedwater pump room do not exceed the design
: a. With the reactor at no load operating temperature and pressure, and just prior to initial criticality, the control is checked for each applicable position of the bank selector switch for proper operation.


14.2-169    Rev. 0 WOLF CREEK      b. Status lights, alarms, and indicators are verified.
specifications.  
14.2.12.3.15.4  Acceptance Criteria


The control and indication functions in accordance with the rod position indication system and rod control system manuals. Rod motion is inhibited upon application of an inhibit function.  
14.2-36    Rev. 0 WOLF CREEK 14.2.12.1.12  Reactor Coolant Pump Initial Operation (S-03BB01)


14.2.12.3.16 Rod Drop Time Measurement (SU7-SF03)
14.2.12.1.12.1 Objectives


14.2.12.3.16.1  Objectives
To demonstrate the operating characteristics of the reactor coolant pumps and verify the operation of their associated oil lift pumps.  


To determine the rod drop time of each rod cluster control assembly under no-flow and full-flow conditions, with the reactor in the cold shutdown condition and at normal operating temperature and pressure. 14.2.12.3.16.2  Prerequisites  
14.2.12.1.12.2  Prerequisites  
: a. Initial core loading is completed.
: a. Required component testing, instrument calibration, and  
: b. Rod control system is installed and tested.
: c. Individual rod position indication is installed and checked.


14.2.12.3.16.3  Test Method
system flushing/cleaning are complete.  
: b. Required electrical power supplies and control circuits


Withdraw each rod cluster control assembly, interrupt the electrical power to the associated rod drive mechanism, and measure and record the rod drop time.
are operational.  
This test is performed with the reactor at cold and hot conditions and at no-flow and full- flow.
: c. The chemical and volume control system is available to provide seal water to the reactor coolant pump seals.  
14.2.12.3.16.4  Acceptance Criteria
: d. The component cooling water system is available to


The rod drop times are acceptable in accordance with plant technical specifications.  
supply cooling water to the reactor coolant pumps.  


14.2.12.3.17 Rod Position Indication System (SU7-SF04)
14.2.12.1.12.3  Test Method


14.2.12.3.17.1  Objectives
The reactor coolant pumps and associated oil lift pumps are operated, and pump


To verify that the rod position indication system satisfactorily performs required indication functions for each individual rod and that each rod operates satisfactorily over its entire range of travel.  
operating data are recorded.  


14.2-170    Rev. 0 WOLF CREEK 14.2.12.3.17.2  Prerequisites 
14.2.12.1.12.4 Acceptance Criteria
: a. Plant system conditions are established as follows:
: 1. Test performed at Tavg <200&deg;F, nominal RCS pressure              for Tavg noted          2. Test results verified at Tavg nominally 557&deg;F, RCS              pressure nominally 2235 psig and at least one reactor              coolant pump in service.
14.2.12.3.17.3 Test Method
: a. All shutdown rod banks are fully withdrawn by bank stopping at 18,210 and 228 steps to record the rod position, the Digital Rod Position Indication display (DRPI), and the group step position indication.
: b. All control rod banks are fully withdrawn by bank in 24 step increments while recording rod position as indicated by the plant control room DRPI readout, and the group step position indication.
: c. In addition, the pulse-to-analog converter chassis bank position digital readout is recorded for all control rod banks.


14.2.12.3.17.4  Acceptance Criteria
Reactor coolant pump and oil lift pump operating characteristics are within


The rod position indication system performs the required indication functions, and each rod operates over its entire range of travel within the limits of the rod position indication instruction manual and the plant precautions, limitations,setpoints manual, and WCGS Technical Specifications.  
design specifications.
14.2.12.1.13  Pressurizer Relief Tank Cold Preoperational Test


14.2.12.3.18  Automatic Reactor Control System (S-07SF05)  
              (SU3-BB02)  


14.2.12.3.18.1  Objectives  
14.2.12.1.13.1  Objectives  


To demonstrate the capability of the reactor control system to respond properly to input signals and to transmit proper control signals to other plant control systems and components.
To demonstrate that the reactor makeup water system can supply design


14.2.12.3.18.2  Prerequisites
pressurizer relief tank (PRT) spray flow against design backpressure. The  
: a. The reactor is at approximately 30-percent power.


14.2-171    Rev. 0 WOLF CREEK      b. Pressurizer level and pressure, steam dump, steam          generator level, and main feed pump speed control systems are in automatic.
operation of the PRT nitrogen isolation valves, including their response to a


14.2.12.3.18.3  Test Method T average will be successively varied  from the  Tref set point to verify the transient recovery capabilities of the auto reactor control system.  
containment isolation signal, is also verified.  


14.2.12.3.18.4 Acceptance Criteria
14.2.12.1.13.2 Prerequisites
: a. No manual intervention should be required to bring the plant conditions to equilibrium values following initiation of a 6 F temperature transient.
: a. Required component testing, instrument calibration, and
: b. Tavg should return to within +1.5 F of Tref following          initiation of a 6 F temperature transient.      c. Rod motion is inhibited by application of the appropriate inhibit inputs.
14.2.12.3.19  Incore Flux Mapping (S-07SR01, S-07SR02)


14.2.12.3.19.1  Objectives
system flushing/cleaning are complete.  
: b. Required electrical power supplies and control circuits


To obtain core power and temperature profiles for evaluating core performance.  
are operational.  


14.2.12.3.19.2  Prerequisites
14.2-37    Rev. 0 WOLF CREEK
: a. The incore monitoring system has been functionally tested.
: c. The reactor makeup water system is available to supply water to the PRT.  
: b. This test is performed at low power, 30-, 50-, 75-, 90-,
: d. The service gas system is available to pressurize the
and 100-percent power.  
: c. The reactor is stabilized prior to taking a map.


14.2.12.3.19.3  Test Method
PRT.  


The movable detectors are inserted into the core, data is obtained, and thermocouples are monitored while at a stable power. The obtained data is retained for evaluation.
14.2.12.1.13.3  Test Method
: a. With a design backpressure in the PRT, a reactor makeup


14.2.12.3.19.4  Acceptance Criteria Flux and temperature data is obtained at the various power levels. 
water pump is operated to obtain the spray flow to the  


14.2-172    Rev. 0 WOLF CREEK 14.2.12.3.20  Incore Instrumentation Test (S-07SR03, S-07SR04) 14.2.12.3.20.1  Objectives
PRT.  
: b. The response of the PRT nitrogen isolation valves to a


To set up and demonstrate operation of the incore instrumentation system.
containment isolation signal is verified.  
14.2.12.3.20.2  Prerequisites
: a. The incore instrumentation system is installed.
: b. Proper rotation and limit switch operation has been verified.
: c. Testing is performed at cold shutdown and hot standby.
14.2.12.3.20.3  Test Method At cold shutdown a dummy cable is inserted into each thimble, and proper rotation and limit switch operation is verified. At hot standby the detectors are inserted into the thimbles to demonstrate performance in all operational modes.  


14.2.12.3.20.4  Acceptance Criteria  
14.2.12.1.13.4  Acceptance Criteria  
: a. The reactor makeup water system supplies the design


The incore instrumentation system is capable of taking a flux map.
spray flow to the PRT with design backpressure in the


14.2.12.3.21  Operational Alignment of Process Temperature Instrumentation (S-07SF06)
PRT.  
: b. PRT nitrogen isolation valves close on receipt of a


14.2.12.3.21.1  Objectives  To align T and  Tavg process instrumentation under isothermal conditions, prior to criticality and at power.
containment isolation signal. Valve closure times are
14.2.12.3.21.2  Prerequisites
: a. This alignment is performed prior to initial criticality and again at 75-percent power. Alignment is checked at 100-percent power.
: b. All reactor coolant pumps shall be operating.  


14.2.12.3.21.3  Test Method
within design specifications.  
: a. Align T and Tavg per test instructions under isothermal          conditions prior to criticality and at approximately 75 


14.2-173    Rev. 0 WOLF CREEK          percent power. Extrapolate the 75-percent power data to          determine T and Tavg values for the 100-percent power          plateau.      b. At or near full power, check the alignment of the T          and Tavg channels for agreement with the results of          thermal power measurement. Realign any channels, as          necessary, to meet test specifications.
14.2.12.1.14  RTD Bypass Flow Measurement (SU3-BB03)


14.2.12.3.21.4  Acceptance Criteria The 100 percent power indications for T and Tavg channels must be within the maximum design values as specified in vendor design documents. 14.2.12.3.22  Startup  Adjustments of  Reactor  Control  System              (S-07SF07)  
At WCGS, test S-07BB01 (USAR Section 14.2.12.3.3) was used to satisfy the


14.2.12.3.22.1  Objectives
requirement for verification of design specifications.  


To obtain the optimum plant efficiency.  
14.2.12.1.15  Pressurizer Pressure Control Test (S-03BB04)


14.2.12.3.22.2 Prerequisites
14.2.12.1.15.1 Objectives
: a. The reactor coolant system is at normal operating pressure and temperature.
: b. Plant instrumentation shall have been aligned according to Operational Alignment of Process Temperature Instrumentation.
: c. The turbine control system shall have been aligned.


14.2.12.3.22.3  Test Method
To demonstrate the stability and response of the pressurizer pressure control  
: a. Obtain system temperature and steam pressure data at steady-state conditions for zero power and at hold points during power escalations.
: b. Evaluation of these data will provide the basis for adjustments to the reactor control system.


14.2.12.3.22.4  Acceptance Criteria
system, including the verification of pressurizer pressure alarm and control


The Tavg controller must be capable of maintaining full load steam pressure within turbine pressure limitations specified in the vendor's technical manual.  
functions.  


14.2-174    Rev. 0 WOLF CREEK 14.2.12.3.23 RCCA or Bank Worth Measurement at Zero Power (S-              07SF08)
14.2.12.1.15.2 Prerequisites
: a. Required component testing and instrument calibration


14.2.12.3.23.1  Objectives To determine the differential and integral reactivity worth of a rod cluster control bank (RCC) or an individual rod cluster control assembly (RCCA).
are complete.  
: b. Required electrical power supplies and control circuits


14.2.12.3.23.2  Prerequisites
are operational.  
: a. The reactor is critical with the neutron flux level within the range established for zero power physics testing.  
: c. The plant is at normal operating temperature and  
: b. The reactor coolant system is at normal operating           pressure and temperature.
14.2.12.3.23.3  Test Method


RCC and RCCA worth are validated by constant addition and/or dilution of boron in the reactor coolant system, causing rod movement to compensate for the boron addition and/or dilution. This rod movement will cause step changes in reactivity which are used to compute the worths.
pressure with all reactor coolant pumps running, and hot


14.2.12.3.23.4  Acceptance Criteria
functional testing is in progress.  


The integral reactivity worth of the RCC or RCCA over its entire range of travel agrees with acceptance criteria given in the Nuclear Design Report within tolerance values specified in vendor design documents.
14.2-38    Rev. 0 WOLF CREEK 14.2.12.1.15.3 Test Method
14.2.12.3.24  RCCA or Bank Worth Measurement at Power (SU7-SF09) 14.2.12.3.24.1 Objectives
: a. Pressurizer pressure is varied, and the ability of the  
: a. To measure RCCA worth for a rod ejected from the HFP rod insertion limit position.
: b. To determine in-core response resulting from a dropped rod with all other control rods near fully withdrawn.


14.2-175    Rev. 0 WOLF CREEK 14.2.12.3.24.2  Prerequisites Testing will be performed at 30-percent power with the reactor stable.
pressurizer pressure control system to automatically
* 14.2.12.3.24.3  Test Method 
: a. Ejected rod - Compute the change in reactivity associated with the change in RCCA position.
: b. Dropped rod - Determine the quadrant power tilt ratio and hot channel factors by use of the in-core flux mapping system.


14.2.12.3.24.4  Acceptance Criteria
control and stabilize pressurizer pressure is verified.  
: a. Ejected rod - The rod worth of the ejected rod is within          tolerance values specified in vendor design documents.  
: b. Pressurizer pressure is varied, and pressurizer pressure
: b. Dropped rod - The peaking factors are within the limits specified in vendor design documents.


14.2.12.3.25  Reactor Systems Sampling for Core Load (S-07SJ01)
control system alarm and control setpoints are verified.  


14.2.12.3.25.1 Objectives
14.2.12.1.15.4 Acceptance Criteria
: a. The pressurizer pressure control system responds, in


To verify uniform boron concentration, prior to core load, in the reactor coolant system and directly connected auxiliary systems.
accordance with system design, to an increase and  


14.2.12.3.25.2  Prerequisites
decrease in system pressure.  
: a. Boric acid tanks, pumps, and transfer lines are all          filled with 4 percent boric acid solution.
: b. Pressurizer pressure control system alarm and control setpoints are within design specifications.  
: b. Reactor coolant system is filled with reactor grade water which has been borated to a concentration as specified in the technical specifications.  


14.2.12.3.25.3  Test Method
14.2.12.1.16  Reactor Coolant System Hot Preoperational Test  
: a. Filling and circulating the reactor coolant system with borated water should be accomplished, utilizing normal flow paths as much as possible.


_______________________
              (S-03BB05)
* This test was performed at 50 percent power at Callaway.
Callaway has the same core and Nuclear Instrumentation System as Wolf Creek. Wolf Creek Core parameters measured prior to the pseudo rod drop test were compared with the corresponding results for Callaway to verify that the plant response was the same. This exemption was approved in a July 3, 1985 letter from the NRC.


14.2-176    Rev. 0 WOLF CREEK      b. Collect and analyze four samples taken at equidistant          depths in the reactor vessel simultaneously with one sample from the operating residual heat removal loop to check uniform boron concentration.
14.2.12.1.16.1 Objectives
14.2.12.3.25.4 Acceptance Criteria
: a. To operate the reactor coolant system at full flow


Boron concentration of the samples obtained from the designated sample points must be within a 30-ppm range of values.
conditions for a minimum of 240 hours to provide the  


14.2.12.3.26  Initial Core Loading (SU7-0001)
necessary vibration cycles on the vessel's internal


14.2.12.3.26.1  Objectives
components prior to their inspection at core loading.  
: a. To load fuel in a controlled manner.      b. To measure boron concentration.
: b. To provide coordination and initial conditions necessary


14.2.12.3.26.2  Prerequisites
for the conduct of those preoperational tests to be performed during heatup, normal operating temperature and pressure, and cooldown of the reactor coolant
: a. Sufficient preoperational testing has been completed to ensure the necessary equipment and attendant instrumentation is functional.
: b. Required technical specification surveillance is completed and the necessary systems are operable.


14.2.12.3.26.3  Test Method
system.  


Instruction includes a core-loading sequence which specifies the loading in a step-by-step fashion with the appropriate data collection records.
14.2.12.1.16.2 Prerequisites
14.2.12.3.26.4 Acceptance Criteria
: a. The reactor coolant system cold hydrostatic test is


A permanent record of the final as-loaded core configuration has been made, and the configuration is consistent with the fuel assembly core loading plan.
complete.  
Boron concentration is as specified in the Technical Specifications.  
: b. The reactor vessel internals and head are installed, and


14.2.12.3.27  Inverse Count Rate Ratio Monitoring For Core Loading (S-070002)
the vessel is available to support this test.  
: c. All systems and components required to support heatup,


14.2.12.3.27.1  Objectives
operations at normal temperature and pressure, and
: a. To obtain nuclear monitoring data during initial core loading.
: b. To prevent criticality during core loading.


14.2-177    Rev. 0 WOLF CREEK 14.2.12.3.27.2  Prerequisites 
cooldown of the reactor coolant system are available.  
: a. Temporary and plant source range nuclear instrumentation has been operational for a minimum of 4 hours to achieve stable operation.
: d. Required instrument calibration is complete.  
: b. Plant is prepared for initial core loading.  


14.2.12.3.27.3  Test Method
14.2-39    Rev. 0 WOLF CREEK
: e. The examination of the reactor internals in accordance with Section 3.9(N).2.4, is complete


Data from the nuclear monitoring channels is used to assess the safety with which core loading operations may be conducted. Inverse count rate ratio is plotted and evaluated to prevent any unexpected deviation from subcriticality.
14.2.12.1.16.3 Test Method
The core is monitored and maintained in a subcritical configuration throughout the core loading. 14.2.12.3.27.4 Acceptance Criteria
: a. The reactor coolant system is operated at full flow


The core is loaded without achieving criticality.  
conditions for a minimum of 240 hours.  
: b. Those preoperational tests required to be performed


14.2.12.3.28  Inverse Count Rate Ratio Monitoring for Approach to Initial Criticality (S-070003)
during heatup, normal operating temperature and


14.2.12.3.28.1  Objectives
pressure, and cooldown of the reactor coolant system are
: a. To obtain nuclear monitoring data during initial criticality.
: b. To anticipate and determine criticality.
14.2.12.3.28.2  Prerequisites 
: a. Both source range and intermediate range nuclear channels alarm, trip functions, and indicating devices have been checked out and calibrated.
: b. Both source range and intermediate range nuclear channels have been energized a minimum of 4 hours to insure stable operation.


14.2.12.3.28.3  Test Method
completed, as coordinated by this test.  
: a. Obtain base line count rates prior to rod withdrawal and boron dilution. After each increment of rod withdrawal, and periodically during boron dilution, count rates are obtained, and inverse count rate ratio is evaluated.
: b. Core reactivity is monitored during the approach to criticality.  


14.2-178    Rev. 0 WOLF CREEK 14.2.12.3.28.4  Acceptance Criteria To determine criticality.
14.2.12.1.16.4  Acceptance Criteria  


14.2.12.3.29  Initial Criticality (S-070004) 14.2.12.3.29.1  Objectives
The reactor coolant system has operated at full flow conditions for a minimum of 240 hours.  


To achieve initial criticality in a controlled manner.
Notes:  1. The acceptance criteria for individual systems are a  


14.2.12.3.29.2  Prerequisites
part of the individual test procedures sequenced by
: a. Initial core loading is completed.
: b. Required technical specification surveillance is          completed and the necessary systems operable. 
: c. Sufficient post-core loading precritical testing has been completed to ensure the necessary equipment and attendant instrumentation is functional.


14.2.12.3.29.3  Test Method
this procedure.  
: a. At preselected points during rod withdrawal and/or boron dilution, data is taken and inverse count rate plots made to enable extrapolation to be carried out to the expected critical point.
: 2. A post-hot functional examination of the reactor
: b. Initial criticality is achieved by boron dilution or, if desired, by withdrawing control rods. 14.2.12.3.29.4  Acceptance Criteria


The reactor is critical with the flux level established at approximately 1 x 10-8 amps on the intermediate range nuclear channels. 14.2.12.3.30  Determination of Core Power Range for Physics Testing (S-070005)
internals is performed as described in Section


14.2.12.3.30.1  Objectives
3.9(N).2.4.  


To determine the reactor power level at which effects from fuel heating is detectable and to establish the range of neutron flux in which zero power reactivity measurements are to be performed.  
14.2.12.1.17  Thermal Expansion (S-03BB06)


14.2.12.3.30.2 Prerequisites
14.2.12.1.17.1 Objectives
: a. The reactor is critical and stable in the intermediate range.


14.2-179    Rev. 0 WOLF CREEK      b. Control rods are sufficiently deep in the core to allow          positive reactivity insertion by rod withdrawal.
To verify that during heatup and cooldown of the reactor coolant system the associated components, piping, support, and restraint deflections are
: c. Reactor coolant temperature is established at a value that minimizes the moderator temperature coefficient          reactivity feedback.


14.2.12.3.30.3  Test Method
unobstructed and within design specifications.  
: a. Withdraw control rod bank and allow the neutron flux level to increase until nuclear heating effects are indicated by the reactivity computer.
: b. Record the reactivity computer picoammeter flux level and, if possible, the corresponding IR channel currents          at which nuclear heating occurs, to obtain zero power          testing range.  


14.2.12.3.30.4 Acceptance Criteria
14.2.12.1.17.2 Prerequisites
: a. This test is conducted in conjunction with hot


The power level at which zero power testing is conducted is determined.  
functional testing.  
: b. Supports, restraints, and hangers are installed and


14.2.12.3.31  Boron Endpoint Determination (S-070006)
reference points and predicted movements established.  
: c. Required instrument calibration is complete.  


14.2.12.3.31.1  Objectives
14.2.12.1.17.3 Test Method
 
During the reactor coolant system heatup and cooldown, deflection data are
 
recorded.
 
14.2-40    Rev. 0 WOLF CREEK 14.2.12.1.17.4  Acceptance Criteria
: a. Unrestricted expansion and movements are verified to be
 
within design specifications.
: b. Components, piping, supports, and restraints return to
 
their baseline cold position in accordance with system
 
design.
 
14.2.12.1.18 Pressurizer Level Control Test (S-03BB07)


To determine the critical reactor coolant system boron concentration appropriate to an endpoint configuration (RCC configuration).  
14.2.12.1.18.1  Objectives


14.2.12.3.31.2  Prerequisites      a. The reactor is critical within the range for zero power testing and stable.
To demonstrate the stability and response of the pressurizer level control
: b. The reactor coolant is at normal operating pressure and temperature.
: c. Rods are at the approximate end point configuration.


14.2.12.3.31.3  Test Method
system, including the verification of pressurizer level alarm and control functions.  


Boron endpoints are measured by determining the boron concentration of the reactor coolant system with the rods close to or at the desired configuration.
14.2.12.1.18.2  Prerequisites
If not, the rods are then quickly moved to the desired configuration with no boron adjustment. The change in reactivity is measured, and this reactivity is converted to an equal amount of boron to yield the endpoint at that particular rod configuration.
: a. Required component testing and instrument calibration


14.2-180    Rev. 1 WOLF CREEK 14.2.12.3.31.4  Acceptance Criteria The results of the boron endpoint calculations meet the requirements of the Nuclear Design Report within tolerance values specified in vendor design documents.
are complete.  
14.2.12.3.32  Isothermal  Temperature  Coefficient  Measurement (S-070007)
: b. Required electrical power supplies and control circuits


14.2.12.3.32.1  Objectives
are operational.  
: c. The letdown and charging portions of the chemical and


To determine isothermal temperature coefficient, then derive the moderator temperature coefficient from the isothermal data.
volume control system are available to vary pressurizer


14.2.12.3.32.2  Prerequisites      a. The reactor is critical within the range for zero power testing and stable.  
level.  
: b. The reactor coolant is at normal operating pressure and temperature.
: d. The plant is at normal operating temperature and pressure, and hot functional testing is in progress.  
: c. Control rods are at the approximate end point configuration.  


14.2.12.3.32.3  Test Method  
14.2.12.1.18.3  Test Method  
: a. Pressurizer level is varied and the ability of the


The isothermal temperature coefficient is determined by heating/cooling the reactor coolant system at a constant rate and plotting temperature versus reactivity. The moderator temperature coefficient may be derived from isothermal data, if desired.
pressurizer level control system to automatically
14.2.12.3.32.4  Acceptance Criteria


The average of the measured values of the isothermal and, if desired, the derived moderator temperature coefficient agrees with acceptance criteria given in the Nuclear Design Report within tolerance values specified in vendor design documents.
control and stabilize pressurizer level is verified.
: b. Pressurizer level is varied, and pressurizer level


14.2.12.3.33  Power Coefficient Determination (S-070008)
control system alarm and control setpoints are verified.  


14.2.12.3.33.1 Objectives
14.2.12.1.18.4 Acceptance Criteria
: a. The response and stability of the pressurizer level


To verify the power coefficient of reactivity.  
control system are within design specifications.  
: b. The pressurizer level control system alarm and control


14.2.12.3.33.2  Prerequisites
functions are within design specifications.  
: a. Reactor power level, reactor coolant temperature and pressures, and RCCA and RCC bank configuration are as follows:


14.2-181   Rev. 1 WOLF CREEK         1. RCS pressure - nominal 2235 psig 
14.2-41   Rev. 0 WOLF CREEK 14.2.12.1.19 Pressurizer Heater and Spray Capability Test (SU3-BB08)
: 2. RCCA, RCC bank configuration - nominally all rods out, D at bite position
: 3. Reactor power level - nominally 30, 50, 75, and 90 percent RTP
: 4. Tavg - consistent with the nominal value corresponding              to the Tavg program at the identified nominal              power levels.
: b. All subsystems which affect overall plant transient response should be in automatic mode of operation with the exception of the rod control system and automatic          makeup. The CVCS demineralizer shall be bypassed.
14.2.12.3.33.3 Test Method
: a. As generator electrical load is changed, the primary side is permitted to freely respond without any control rod motion.
: b. The power coefficient verification factor is calculated by measuring the change in RCS temperature and the corresponding change in core power.


14.2.12.3.33.4  Acceptance Criteria
14.2.12.1.19.1 Objectives


The average value of the measured verification factor agrees with that obtained from design predictions of the isothermal temperature coefficient and doppler power coefficient. This agreement is within limits given in the test instructions.
To determine the electrical capacity of the pressurizer heaters, and the rate


14.2.12.3.34  Load Swing Tests (S-070009)
of pressure increase from the operation of all pressurizer heaters.  


14.2.12.3.34.1 Objectives
14.2.12.1.19.2 Prerequisites
: a. Required component testing and instrument calibration


To verify proper nuclear plant transient response, including automatic control system performance, when load changes are introduced at the turbine generator.  
are complete.  
: b. Required electrical power supplies and control circuits


14.2.12.3.34.2  Prerequisites
are operational.  
: c. The plant is at normal operating temperature and


Step load changes are initiated from steady state conditions at approximately 30-, 75-, and 100-percent power.
pressure with all reactor coolant pumps running, and hot


14.2-182    Rev. 1 WOLF CREEK 14.2.12.3.34.3  Test Method 
functional testing is in progress.  
: a. Manually reduce the turbine generator output as rapidly as possible to achieve an approximate 10-percent load decrease/increase. 
: b. Plant variables are recorded, along with values observed on the normal plant instrumentation, during the load transient for those parameters required.  


14.2.12.3.34.4 Acceptance Criteria
14.2.12.1.19.3 Test Method
: a. Pressurizer heaters are energized, and heater capacity


The following acceptance criteria are to be used to determine successful test completion. Failure to meet these criteria does not constitute a need for stopping the test program, but correction of any deficiences should be accomplished, as required, consistent with the current plant schedule. 
is calculated.  
: a. Reactor and turbine must not trip.  
: b. With the pressurizer spray valves closed, all
: b. Safety injection is not initiated.
: c. Neither steam generator atmospheric relief valves nor safety  valves shall lift.      d. Neither pressurizer relief valves nor safety valves shall lift.
: e. No manual intervention shall be required to bring plant          conditions to steady state.
: f. Nuclear power overshoot (undershoot) must be less than 3 percent for load increase (decrease).


14.2.12.3.35  Large Load Reduction Test (S-070010)
pressurizer heaters are energized, and the time to reach


14.2.12.3.35.1  Objectives
a 2,300 psig system pressure is measured and recorded.  


To demonstrate satisfactory plant transient response to various specified load changes, to monitor the reactor control systems during these transients, and, if necessary, optimize the reactor control system setpoints.
14.2.12.1.19.4  Acceptance Criteria
: a. The capacity of the pressurizer heaters is within design


14.2.12.3.35.2  Prerequisites
limits.  
: b. The pressurizer pressure response to the actuation of


Step load reduction changes of 50 percent are initiated from steady state conditions at approximately 75- and 100-percent power.  
all pressurizer heaters is within design limits.  


14.2-183 Rev. 13 WOLF CREEK 14.2.12.3.35.3 Test Method 
14.2.12.1.20 Reactor Coolant System Flow Measurement Test  
: a. Manually reduce the turbine generator output to achieve an approximate 50-percent load reduction.
: b. Monitor plant response during the transient and record plant variables, as required.
: c. If necessary, adjust the reactor control system setpoints until optimal response is obtained.


14.2.12.3.35.4  Acceptance Criteria
              (SU3-BB09)


The following acceptance criteria are to be used to determine successful test completion. Failure to meet these criteria does not constitute a need for stopping the test program, but correction of any deficiencies should be accomplished, as required, consistent with the current plant schedule.  
At WCGS, Test S-07BB03 (USAR Section 14.2.12.3.5) is used to satisfy the
: a. Reactor and turbine must not trip.  
 
: b. Safety injection is not initiated.  
requirements for verification of design specifications.
: c. Steam generator safety valves shall not lift.  
 
14.2.12.1.21  Reactor Coolant System Flow Coastdown Test
 
              (SU3-BB10)
 
14.2-42    Rev. 0 WOLF CREEK At WCGS, Test S-07BB04  (USAR Section 14.2.12.3.6) is used to satisfy the requirements for verification of design specifications.
 
14.2.12.1.22  Reactor Coolant System Hydrostatic Test (S-03BBll)
 
14.2.12.1.22.1  Objectives
 
To verify the integrity and leaktightness of the reactor coolant system and the
 
high-pressure portions of associated systems.
 
14.2.12.1.22.2  Prerequisites
: a. Required system flushing/cleaning are complete.
: b. The reactor coolant pumps are available to support this test.
: c. The reactor vessel's lower internals, upper internals,
 
filter assembly, and the closure head are installed.
 
The studs are tensioned to design value for the
 
associated hydrostatic test pressure
: d. Temporary temperature instrumentation is installed for
 
measuring the temperature of the steam generator tube
 
sheets, the bottom of the pressurizer, and the closure
 
flange of the reactor vessel.
: e. A charging pump or test pump is available to pressurize
 
the system.
: f. Required instrument calibration is complete.
 
14.2.12.1.22.3  Test Method
 
The minimum temperature for pressurizing the system is established. The
 
reactor coolant pumps are operated as required to establish the required
 
temperature. The system is then pressurized to test pressure, and system
 
welds, flanges, piping, and components are monitored for leakage.
 
14.2.12.1.22.4  Acceptance Criteria
 
The reactor coolant system and associated high-pressure systems are verified
 
leaktight in accordance with the requirements of the ASME Boiler and Pressure
 
Vessel Code, Section III, "Nuclear Components," through the Winter 1975
 
Addenda.
 
14.2.12.1.23  Pressurizer Continuous Spray Flow Verification Test
 
              (SU3-BB12)
 
14.2-43    Rev. 0 WOLF CREEK At WCGS, Test S-07BB05 (USAR Section 14.2.12.3.7) was used to satisfy the requirements for verification of design specifications.
 
14.2.12.1.24  Pressurizer Relief Valve and PRT Hot Preoperational
 
Test (S-03BB13)
 
14.2.12.1.24.1  Objectives
 
To demonstrate that the operating times of the pressurizer power- operated
 
relief valves are within design specifications. The ability of the reactor
 
coolant drain tank portion of the liquid radwaste system to cool down the
 
pressurizer relief tank (PRT) at the design rate is also verified.
 
14.2.12.1.24.2  Prerequisites
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The PRT is at a normal operating level and is aligned
 
for normal operation.
: d. The liquid radwaste system is available to cool down the
 
PRT via the reactor coolant drain tank heat exchanger.
: e. The plant is at normal operating temperature and pres-
 
sure, and hot functional testing is in progress.
 
14.2.12.1.24.3  Test Method
: a. Pressurizer power-operated relief valves are operated,
 
and opening times recorded.
: b. Following the operation of the pressurizer power-
 
operated relief valves, the PRT is cooled down via the
 
reactor coolant drain tank heat exchanger, and the
 
cooldown rate is calculated and recorded.
 
14.2.12.1.24.4  Acceptance Criteria
: a. Power-operated relief valve operating times are within
 
design specifications.
 
14.2-44    Rev. 0 WOLF CREEK
: b. The reactor coolant drain tank portion of the liquid radwaste system cools down the PRT at a rate within
 
design specifications.
 
14.2.12.1.25  Reactor Coolant Loop Vibration Surveillance Test (S-03BB14)
 
14.2.12.1.25.1  Objectives
 
To verify that the dynamic effects experienced during reactor coolant loop
 
steady flow and reactor coolant loop pump transients as measured during hot
 
functional testing (HFT) do not exceed acceptance criteria for the primary loop
 
piping and components.
 
14.2.12.1.25.2  Prerequisites
: a. Hot functional testing is in progress.
: b. Reference points for vibrational measurement of the
 
reactor coolant piping and components are established.
: c. All subject systems are available for the specified
 
dynamic operation.
: d. Required instrument calibration is complete.
 
14.2.12.1.25.3  Test Method
: a. The systems are aligned for the specified dynamic
 
operation.
: b. The specified dynamic event is initiated and the reactor
 
coolant piping and component responses are monitored.
 
14.2.12.1.25.4  Acceptance Criteria
 
The measured deflections for each of the test measurement points are within a
 
specified percent of the calculated reference deflections.
 
14.2.12.1.26  Leak Detection System Preoperational Test
 
              (SU3-BB15A)
 
14.2.12.1.26.1  Objectives
: a. To determine, during hot functional testing, the amount
 
of identified and unidentified leakage from the reactor
 
coolant system and verify that the leakage is within
 
design limits.
 
14.2-45    Rev. 0 WOLF CREEK
: b. To demonstrate the ability to detect an increase in reactor coolant system leakage.
 
14.2.12.1.26.2  Prerequisites
: a. Required instrument calibration is complete.
: b. Hot functional testing is in progress, and the reactor
 
coolant system is at normal operating temperature and
 
pressure.
: c. The volume control tank contains an adequate supply of
 
water to support this test.
: d. The reactor coolant drain tank and associated pumps are available to support this test.
 
14.2.12.1.26.3  Test Method
: a. The reactor coolant system identified and unidentified
 
leakage rates are determined by monitoring the reactor
 
coolant system water inventory.
: b. A known leakage rate is initiated, and the ability to
 
detect an increase in leakage is verified.
 
14.2.12.1.26.4  Acceptance Criteria
: a. Reactor coolant system identified and unidentified
 
leakage is within design limits.
: b. The ability to detect an increase in reactor coolant
 
system leakage is verified.
 
14.2.12.1.27  Leak Detection System Preoperational Test
 
              (SU3-BB15B)
 
14.2.12.1.27.1  Objectives
: a. To demonstrate the operation of the leak detection
 
system and to verify the ability of the system to detect
 
leakage within the required time limit as specified by
 
design.
: b. The operation of the containment particulate and
 
radioactive gas monitoring portions of the Leak
 
Detection System are verified in SU4-SP01, Process
 
Radiation Monitoring System Preoperational Test.
 
14.2-46    Rev. 0 WOLF CREEK 14.2.12.1.27.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. The containment normal sumps, instrument tunnel sump,
 
floor drain tank, auxiliary building sump and associated
 
pumps are available to support this test.
 
14.2.12.1.27.3  Test Method
: a. A known simulated leakage is initiated, and the ability
 
of the system to detect the leakage within the design
 
time is verified.
 
14.2.12.1.27.4  Acceptance Criteria
: a. The ability of the leak detection system to detect a
 
leak within the design time is verified.
 
14.2.12.1.28  RTD/TC Cross Calibration (S-03BB16)
 
14.2.12.1.28.1  Objectives
 
To provide a functional checkout of the reactor coolant system resistance
 
temperature detectors (RTDs) and incore thermocouples and to generate
 
isothermal cross-calibration data for subsequent correction factors to
 
indicated temperatures.
 
14.2.12.1.28.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. Initial plant heatup, during hot functional testing, is
 
in progress, and all reactor coolant pumps are
 
operating.
 
14.2.12.1.28.3  Test Method
 
At various temperature plateaus, RTD and incore thermocouple data are recorded. 
 
Isothermal cross-calibration correction factors for individual thermocouples
 
and the installation corrections for individual RTDs are determined.
 
14.2-47    Rev. 0 WOLF CREEK 14.2.12.1.28.4  Acceptance Criteria
: a. Individual RTD readings are within the design
 
specifications.
: b. The installation corrections of the RTDs are within
 
design specifications.
 
14.2.12.1.29  Chemical and Volume Control System Major Component
 
Test (S-03BG01)
 
14.2.12.1.29.1  Objectives
 
To demonstrate the operation of the centrifugal charging pumps and associated minimum flow valves, including their response to safety signals.
 
14.2.12.1.29.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The refueling water storage tank contains an adequate
 
supply of demineralized water for the performance of
 
this test.
: d. The component cooling water system is available to provide cooling water to the centrifugal charging pump oil coolers.
 
14.2.12.1.29.3  Test Method
: a. Centrifugal charging pumps are operated, and performance
 
characteristics are verified.
: b. Centrifugal charging pump and minimum flow valve control
 
logics are verified, including their response to safety
 
signals.
 
14.2.12.1.29.4  Acceptance Criteria
: a. Centrifugal charging pump performance characteristics
 
are within design specifications.
: b. Each centrifugal charging pump receives a start signal
 
from the load sequencer.
 
14.2-48    Rev. 0 WOLF CREEK
: c. If a safety injection signal is present, a centrifugal charging pump minimum flow valve will open if the
 
associated pump flow is low and will close if the
 
associated pump flow is above the minimum flow
 
requirement of the pump.
 
14.2.12.1.30  Seal Injection Preoperational Test (SU3-BG02)
 
14.2.12.1.30.1  Objective
 
To demonstrate the ability of the chemical and volume control system to supply
 
adequate seal water injection flow to the reactor coolant pumps and verify the
 
operation of the seal water return containment isolation valves, including
 
their response to a CIS.
 
14.2.12.1.30.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The volume control tank contains an adequate supply of
 
demineralized water for the performance of this test.
: d. Cooling water is available to the charging pumps.
 
14.2.12.1.30.3  Test Method
: a. With a charging pump in operation, seal water throttle valves are adjusted to maintain the required flow to
 
each reactor coolant pump.
: b. Seal water return containment isolation valves control
 
logics are verified, including their response to a CIS.
 
14.2.12.1.30.4  Acceptance Criteria
: a. Seal water injection flow to each reactor coolant pump
 
is within design specifications.
: b. Seal water return containment isolation valves close on
 
receipt of a CIS. Valve closure times are within design
 
specifications.
 
14.2-49    Rev. 0 WOLF CREEK 14.2.12.1.31  Charging System Preoperational Test (SU3-BG03)
 
14.2.12.1.31.1  Objective
 
To demonstrate positive displacement charging pump (replaced by the normal charging pump per DCP 04590) operating characteristics and to verify the operation of the regenerative heat exchanger inlet isolation valves and the
 
letdown isolation valves, including their response to a safety injection signal
 
(SIS).
 
14.2.12.1.31.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The volume control tank contains an adequate supply of
 
demineralized water for the performance of this test.
: d. Cooling water is available to the positive displacement charging pump (replaced by the normal charging pump per DCP 04590).
: e. The reactor coolant system is available to receive
 
charging system flow.
 
14.2.12.1.31.3  Test Method
: a. The positive displacement charging pump (replaced by the normal charging pump per DCP 04590)is operated, and pump operating data are recorded.
: b. Regenerative heat exchanger inlet isolation valve and
 
letdown system isolation valve control circuits are
 
verified, including valve response to safety injection signals.
 
14.2.12.1.31.4  Acceptance Criteria
: a. Positive displacement charging pump (replaced by the normal charging pump per DCP 04590)operating characteristics are within design specifications.
: b. Charging pump to regenerative heat exchanger inlet
 
isolation valves close on receipt of an SIS. Valve
 
closure times are within design specifications.
: c. The letdown line containment isolation valves close on
 
receipt of a containment isolation signal. Valve
 
closure times are within design specifications.
 
14.2-50    Rev. 12 WOLF CREEK 14.2.12.1 32  Boron Thermal Regeneration System Preoperational Test (SU3-BG04)
 
14.2.12.1.32.1  Objective
 
To verify the operation of the boron thermal regeneration system, and
 
associated control circuits. Performance characteristics of the chemical and
 
volume control system chiller pumps are also verified.
 
14.2.12.1.32.2  Prerequisites
: a. Required component testing, instrument calibration and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The volume control tank contains an adequate supply of
 
demineralized water for the performance of this test.
: d. The chemical and volume control system chiller surge
 
tank contains an adequate supply of demineralized water
 
for the performance of this test.
 
14.2.12.1.32.3  Test Method
: a. The chemical and volume control system chiller pumps are
 
operated and performance characteristics are verified.
: b. Boron thermal regeneration system component control circuits are verified.
 
14.2.12.1.32.4  Acceptance Criteria
: a. The chemical and volume control system chiller pumps'
 
operating characteristics are within design
 
specifications.
: b. The chemical and volume control system chiller pumps
 
start automatically when the boron thermal regeneration
 
system is placed in the borate or dilute mode of
 
operation.
 
14.2.12.1.33  Boric Acid Blending System Preoperational Test (SU3-
 
BG05)
 
14.2.12.1.33.1  Objectives
: a. To demonstrate the operating characteristics of boron
 
injection makeup and boric acid transfer pumps and 
 
14.2-51    Rev. 0 WOLF CREEK verify the ability of the boric acid blending system to make up at design flow rates to the chemical and volume
 
control system (CVCS).
: b. To verify the operation of system component control circuits in all modes of operation.
: c. To demonstrate by flow test the ability of the reactor
 
makeup water system to supply water to the boric acid
 
blender.
: d. To demonstrate by flow test the ability of the boric
 
acid system to supply an emergency boration flow to the
 
charging pump suction.
: e. To verify the operation of volume control tank valves and associated control circuits, including valve
 
response to safety signals.
 
14.2.12.1.33.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The reactor makeup water system is available to supply
 
water to the boric acid blender and boric acid batching
 
tank.
: d. A charging pump is available to receive and discharge
 
flow from the boric acid transfer pumps.
: e. The volume control tank (VCT) contains an adequate
 
supply of demineralized water for the performance of
 
this test.
 
14.2.12.1.33.3  Test Method
: a. The boron injection makeup and boric acid pumps are
 
operated, performance data recorded, and the ability of
 
the system to make up to the CVCS at design flow rates
 
is verified.
: b. System component control circuits are verified in all
 
modes of operation.
 
14.2-52    Rev. 0 WOLF CREEK
: c. With a reactor makeup water pump in operation, flow is verified to the boric acid blender and boric acid
 
batching tank.
: d. With both boric acid transfer pumps in operation and a charging pump taking a suction from the VCT and
 
discharging to the reactor coolant loops, the emergency
 
boration flow rate from the transfer pumps to the
 
charging pump suction is recorded.
: e. The emergency boration flow rate via gravity feed from
 
the boric acid tanks to the charging pump suction is
 
recorded.
: f. Proper operation of the reactor makeup water system is verified when the reactor makeup control system (RMCS) is operated in the manual, dilute, alternate dilute, and
 
automatic modes.
: g. The operation of the VCT outlet valves control circuits
 
is verified, including their response to a safety
 
injection signal.
 
14.2.12.1.33.4  Acceptance Criteria
: a. The boron injection makeup and boric acid transfer pump
 
operating characteristics are within design
 
specifications.
: b. The flow rate to the boric acid blender from the reactor makeup water system is within design specifications.
: c. The emergency boration flow rates to the charging pump
 
suction are within design specifications.
: d. The boric acid transfer pumps and the reactor makeup
 
water pumps start automatically on a low level in the
 
volume control tank when the RMCS is in the automatic
 
mode.
: e. VCT outlet valves close on receipt of a safety injection
 
signal when the associated charging pump supply valve
 
from the refueling water storage tank is open.
: f. Refueling water storage tank to charging pump suction
 
valves open on receipt of a safety injection signal.
: g. The boric acid transfer pumps stop on receipt of a load
 
shed signal.
 
14.2-53    Rev. 0 WOLF CREEK
: h. The boric acid  filter to charging pump valve supply breaker trips open on receipt of a load shed signal.
 
14.2.12.1.34  Chemical and Volume Control System Hot
 
Preoperational Test (S-03BG06)
 
14.2.12.1.34.1  Objectives
: a. To determine by flow test that all letdown and cleanup
 
flow rates are within design specifications.
: b. To determine, by comparison of boron concentrations,
 
that boric acid addition to the reactor coolant system
 
has occurred, using the normal and emergency flow paths.
: c. To determine by flow test the ability of the chemical and volume control system (CVCS) to make up at design
 
flow rates and boron concentrations to the reactor
 
coolant system in all modes of operation.
: d. To determine by operational test that the letdown
 
containment isolation valve closure times are within
 
design specifications.
: e. To demonstrate the ability of the pump room coolers to
 
maintain room temperatures within design limits.
 
14.2.12.1.34.2  Prerequisites
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The plant is at normal operating temperature and
 
pressure, and hot functional testing is in progress.
: d. The CVCS pump rooms are closed, and their associated
 
pump room coolers are operational.
 
14.2.12.1.34.3  Test Method
: a. The letdown throttle valves are adjusted to establish
 
letdown flow within design specifications.
: b. Boric acid addition to the reactor coolant system is
 
verified, using the normal and emergency flow paths, by
 
comparing the change in boron concentrations.
 
14.2-54    Rev. 0 WOLF CREEK
: c. With a charging pump in operation, the ability of the CVCS, in all modes of operation, to make up at design
 
flow rates and boron concentrations to the reactor
 
coolant system is verified.
: d. With letdown flow established, the letdown containment
 
isolation valves are operated, and operating times are
 
recorded.
: e. During CVCS pump operation, pump room temperature data
 
are recorded.
 
14.2.12.1.34.4  Acceptance Criteria
: a. All letdown and cleanup flow rates are within design specifications
: b. The boric acid addition system is capable of adding
 
boron to the reactor coolant system via both the normal
 
and emergency flow paths.
: c. The CVCS makeup flow rates and boron additions to the
 
reactor coolant system are within design specifications
 
in all modes of operation.
: d. The letdown containment isolation valves' closure times
 
are within design specifications.
: e. The CVCS pump room coolers maintain the room temperature
 
within design limits.
: f. The boron thermal regeneration system (BTRS) can vary
 
the reactor coolant boron concentration as required for
 
daily load cycle at 85 percent core life.
 
14.2.12.1.35  Fuel Pool Cooling and Cleanup System Preoperational
 
Test (SU3-EC01)
 
14.2.12.1.35.1  Objectives
: a. To demonstrate the operating characteristics of the fuel
 
pool cooling, fuel pool cleanup, and pool skimmer pumps
 
and to verify that the associated instrumentation and
 
controls are functioning properly.
: b. To verify that the fuel pool cleanup pump refueling
 
water storage tank (RWST) suction isolation valves close
 
on receipt of a safety injection signal (SIS).
 
14.2-55    Rev. 0 WOLF CREEK
: c. To verify that each fuel pool cooling pump room cooler starts when the associated fuel pool cooling pump
 
starts.
 
14.2.12.1.35.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. Cooling water is available to the fuel pool cooling and
 
cleanup system heat exchangers.
: d. The liquid radwaste system is available to drain the refueling pool to the RWST.
: e. The essential service water system is available to
 
provide cooling water to the spent fuel pool pump room
 
coolers.
: f. The spent fuel pool and fuel transfer canals are filled
 
to their normal operating levels.
 
14.2.12.1.35.3  Test Method
: a. The fuel pool cooling, fuel pool cleanup, and pool
 
skimmer pumps are operated in their various modes, and
 
pump operating data are recorded.
: b. System component control circuits are verified,
 
including the operation of system pumps and valves on
 
receipt of safety signals.
: c. The ability of each fuel pool cooling pump room cooler
 
to start when the associated fuel pool cooling pump
 
starts is verified.
 
14.2.12.1.35.4  Acceptance Criteria
: a. The operating characteristics of the fuel pool cooling,
 
fuel pool cleanup, and pool skimmer pumps are within
 
design specifications.
: b. The fuel pool cleanup pumps RWST suction isolation
 
valves close on receipt of an SIS.
 
14.2-56    Rev. 0 WOLF CREEK
: c. Each fuel pool cooling pump trips on a low spent fuel pool level signal.
: d. Each fuel pool cooling pump trips on receipt of a load
 
shed signal.
: e. Each fuel pool cooling pump room cooler starts when the
 
associated fuel pool cooling pump starts.
 
14.2.12.1.36  Spent Fuel Pool Leak Test (S-03EC02)
 
14.2.12.1.36.1  Objectives
: a. To demonstrate the integrity of the spent fuel pool,
 
cask loading pit, and fuel transfer canal.
: b. To demonstrate the leaktightness of the cask loading pit
 
gate and the fuel transfer canal gate.
 
14.2.12.1.36.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The spent fuel pool is filled to the normal operating
 
level.
: d. The cask loading pit level is below the level of the fuel pool gate.
: e. The fuel transfer canal level is below the level of the
 
fuel pool gate.
: f. The reactor makeup water system is available to provide
 
demineralized water to the spent fuel pool.
: g. A source of compressed air is available to pressurize
 
the system standpipes.
 
14.2.12.1.36.3  Test Method
 
The cask loading pit gate and fuel transfer canal gate are visually inspected
 
for leakage. A leak test is performed on the spent fuel pool, cask loading
 
pit, and fuel transfer canal, using the associated leak chase standpipes.
 
14.2-57    Rev. 0 WOLF CREEK 14.2.12.1.36.4  Acceptance
 
No leakage is observed from the spent fuel pool, cask loading pit, fuel
 
transfer canal, cask loading pit gate, and fuel transfer canal gate.
 
14.2.12.1.37  Essential Service Water System Preoperational Test
 
              (SU3-EF01)
 
Test SU3-EF02 combined with Test SU3-EF01, Essential
 
Service Water System Preoperational Test.
 
14.2.12.1.37.1  Objectives
: a. To demonstrate the capability of the essential service
 
water system to provide cooling water flow during the LOCA mode of operation. The operation and response of system valves to align the system in the LOCA flow mode
 
on safety injection signals, load sequence signals, and
 
low suction pressure signals are also verified.
: b. To demonstrate the operating characteristics of the
 
essential service water (ESW) pumps and verify their
 
response to safety signals.
: c. To demonstrate the operability of the backpressure
 
control valves, including their response to safety
 
signals.
 
14.2.12.1.37.2  Prerequisites
: a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The compressed air system is available to the system
 
air-operated valves.
 
14.2.12.1.37.3  Test Method
: a. System operating characteristics are verified in the
 
LOCA mode of operation.
: b. Safety signals are simulated, and the responses of the
 
system valves and the ESW pumps are verified.
: c. The ESW pumps are operated and pump operating data are
 
recorded.
 
14.2-58    Rev. 0 WOLF CREEK
: d. The operability of the backpressure control valves, including their response to safety signals is verified.
 
14.2.12.1.37.4  Acceptance Criteria
: a. Components supplied by the essential service water
 
system receive flows that are within design
 
specifications in the LOCA mode of system operation.
: b. System valve operation in response to safety signals is
 
within design requirements.
: c. System valve operating times are within design
 
specifications.
: d. The ESW pumps' operating characteristics are within design specifications.
: e. Each ESW pump responds properly to load sequence and
 
load shed signals.
: f. The time required for each ESW pump to reach rated flow
 
is within design specifications.
: g. System backpressure valves close upon receipt of a LOCA
 
sequencer or safety injection signal.
: h. An auxiliary feedwater pump low suction pressure signal
 
will close the ESW pump breakers if a zero sequencer
 
signal is not present.
14.2.12.1.38  Component Cooling Water System Preoperational Test
 
              (S-03EG01)
 
14.2.12.1.38.1  Objectives
: a. To demonstrate the capability of the component cooling
 
water system to provide cooling water during the normal,
 
shutdown, and post-LOCA modes of operation.
: b. To demonstrate the operating characteristics of the
 
component cooling water pumps and to verify that the
 
associated instrumentation and controls are functioning
 
properly, including system response to safety signals.
 
14.2.12.1.38.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
 
14.2-59    Rev. 0 WOLF CREEK
: b. Required electrical power supplies and control circuits are operational.
 
14 2.12.1.38.3  Test Method
: a. System operating characteristics are verified in the
 
normal, shutdown, and post-LOCA modes of operation.
: b. Safety signals are simulated, and the response of system
 
pumps and valves is verified.
 
14.2.12.1.38.4  Acceptance Criteria
: a. The performance characteristics of each component
 
cooling water pump are within design specifications.
: b. Components supplied by the component cooling water
 
system receive flows that are within design
 
specifications with the system operating in the normal,
 
shutdown, and post-LOCA modes.
: c. Component cooling water pump and valve responses to load
 
sequence, containment isolation, and safety injection
 
signals are within design specifications.
: d. Closure times for the component cooling water supply and
 
return valves to the reactor coolant system are within
 
design specifications.
: e. Component cooling water pump response to centrifugal charging pump start signals is in accordance with system design.
 
14.2.12.1.39  Residual Heat Removal System Cold Preoperational
 
Test (SU3-EJ01)
 
14.2.12.1.39.1  Objective
 
To demonstrate the operability of the Residual Heat Removal (RHR) pumps,
 
demonstrate by flow test their ability to supply water at rated pressure and
 
flow, and verify their response to safety signals. The operation of system
 
motor-operated valves, including their response to safety signals, are also
 
verified. The RWST control and alarm circuits are also verified.
 
14.2.12.1.39.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
 
14.2-60    Rev. 0 WOLF CREEK
: b. Required electrical power supplies and control circuits are operational.
: c. The reactor vessel head is removed and the water level
 
is above the nozzles.
: d. The refueling water storage tank contains an adequate
 
supply of demineralized water for the performance of
 
this test.
: e. Cooling water is available to the RHR pumps and heat
 
exchangers.
: f. The instrument air system is available to supply air to
 
system air-operated valves.
14.2.12.1.39.3  Test Method
: a. Performance characteristics of the RHR pumps are
 
verified during discharge to the reactor coolant hot and
 
cold loops and test recirculation.
: b. RWST and RHR system component control circuits are
 
verified, including the operation of the RHR pumps and
 
system valves on receipt of safety signals.
 
14.2.12.1.39.4  Acceptance Criteria
: a. RHR pump performance characteristics are within design
 
specifications.
: b. RHR system components align or actuate in accordance
 
with system design to safety injection, containment
 
isolation, load sequencing, load shed, and tank level
 
signals.
: c. The time required for each RHR pump to reach rated speed
 
is within design specifications.
: d. RHR system motor-operated valve closure times are within
 
design specifications.
 
14.2.12.1.40  Residual Heat Removal System Hot Preoperational Test
 
              (S-U3-EJ02)
 
14.2.12.1.40.1  Objectives
: a. To demonstrate the ability of the residual heat removal
 
          (RHR) system to cool down the reactor coolant system
 
          (RCS) at its design rate.
 
14.2-61    Rev. 0 WOLF CREEK
: b. To demonstrate the ability of the RHR pump room coolers to maintain room temperature within design limits.
 
14.2.12.1.40.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The component cooling water system is supplying water to
 
each RHR heat exchanger.
: d. The RCS is being cooled down during hot functional testing.
: e. The RHR pump rooms are closed, and their associated pump
 
room coolers are operational.
 
14.2.12.1.40.3  Test Method
: a. While the RCS is being cooled down with the RHR system,
 
the heat transfer is obtained by performing a heat
 
balance across each RHR heat exchanger.
: b. When RHR pump room temperatures have stabilized, room
 
temperature data is recorded.
 
14.2.12.1.40.4  Acceptance Criteria
: a. The RHR system is capable of cooling down the reactor
 
coolant system at its design rate.
: b. The RHR pump room coolers can maintain room temperature
 
within design limits.
 
14.2.12.1.41  Safety Injection System Cold Preoperational Test
 
              (SU3-EM01)
 
14.2.12.1.41.1  Objectives
 
To demonstrate the response of the safety injection pumps and associated valves
 
to safety signals.
 
14.2.12.1.41.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete
 
14.2-62    Rev. 0 WOLF CREEK
: b. Required electrical power supplies and control circuits are operational.
 
14.2.12.1.41.3  Test Method
 
The response of the safety injection pumps and associated valves to safety
 
signals is verified
 
14.2.12.1.41.4  Acceptance Criteria
: a. The safety injection pumps and associated valves align
 
or actuate in accordance with system design to
 
containment isolation signals, load shedding signals,
 
and load sequencing signals.
 
14.2.12.1.42  Safety Injection Flow Verification Test (SU3-EM02)
 
14.2.12.1.42.1  Objectives
: a. To demonstrate the operating characteristics of the
 
safety injection pumps and the centrifugal charging
 
pumps.
: b. To demonstrate the capability of the safety injection
 
pumps to provide balanced flow to the reactor coolant
 
system and prevent runout flow in the cold leg and hot
 
leg injection modes.
: c. To demonstrate the capability of the charging pumps to
 
provide balanced flow to the reactor coolant system and prevent runout flow in the boron injection mode.
: d. To demonstrate the capability of the residual heat
 
removal pumps to provide required net positive suction
 
head to the safety injection pumps and the centrifugal
 
charging pumps.
: e. To demonstrate that the safety injection and centrifugal
 
charging pump room coolers maintain room temperature
 
within design limits.
: f. To demonstrate that associated system valve operating
 
times are within specified limits.
 
14.2.12.1.42.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
 
14.2-63    Rev. 0 WOLF CREEK
: b. Required electrical power supplies and control circuits are operational.
: c. The CVCS is available to supply rated flow to the
 
reactor coolant system via the boron injection path, while simultaneously supplying other required loads.
: d. The residual heat removal system is available to supply
 
adequate suction head to the safety injection and
 
centrifugal charging pumps during required injection
 
modes.
: e. The borated refueling water storage tank contains an
 
adequate supply of demineralized water for this test.
: f. The reactor vessel is available to receive water, and the temporary reactor vessel pumpdown system is
 
operational (if required).
: g. The auxiliary building HVAC system is available to cool
 
the pump rooms and verify associated pump interlocks.
: h. The accumulator safety injection system piping from the
 
safety injection system to the reactor coolant system is
 
available, and an accumulator tank is capable of
 
receiving water.
: i. Cooling water is available to required pumps and heat
 
exchangers.
: j. The compressed air system is available to supply air to associated system valves.
: k. The residual heat removal system hot leg and cold leg
 
flow orifices have been sized for required flow.
 
14.2.12.1.42.3  Test Method
: a. The safety injection pumps are operated in the cold leg
 
flow mode to verify pump performance characteristics and
 
to identify the weaker pump.
: b. The safety injection cold leg branch lines are balanced
 
using the weaker safety injection pump and the balance
 
checked with the stronger pump. The balance is
 
performed so that injection flow is maximized while
 
preventing pump runout.
 
14.2-64    Rev. 0 WOLF CREEK
: c. The safety injection hot leg branch lines are balanced, using their respective safety injection pump. The
 
balance is performed so that injection flow is maximized
 
while preventing pump runout.
: d. The centrifugal charging pumps are operated in the boron
 
injection mode to determine pump performance
 
characteristics and to identify the weaker pump.
: e. The boron injection branch lines are balanced, using the
 
weaker centrifugal charging pump and the balance checked
 
with the stronger pump. The balance is performed such
 
that injection flow is maximized while preventing pump
 
runout.
: f. Each residual heat removal pump is operated in series with the centrifugal charging pumps and safety injection
 
pumps to verify that the residual heat removal pumps can
 
supply adequate suction head.
: g. With each centrifugal charging pump and safety injection
 
pump operating, pump room temperatures are allowed to
 
stabilize, and room temperature data are recorded.
 
14.2.12.1.42.4  Acceptance Criteria
: a. The safety injection and centrifugal charging pump
 
response times and valve operating times are within
 
design specifications.
: b. The safety injection pump room coolers start with their respective pump.
: c. The NPSH provided by the residual heat removal pumps to
 
the centrifugal charging pumps and safety injection
 
pumps is within system design specifications.
: d. Safety injection cold leg, hot leg, and safety injection
 
pump flows are within design specifications.
: e. Boron injection and centrifugal charging pump flows are
 
within design specifications.
: f. The safety injection and centrifugal charging pump room
 
coolers can maintain room temperature within design
 
limits.
 
14.2-65    Rev. 0 WOLF CREEK 14.2.12.1.43  Safety Injection Check Valve Test (SU3-EM03)
 
14.2.12.1.43.1  Objectives
 
To demonstrate the integrity of accumulator outlet line and loop safety injection line check valves and backup check valves by performing backleakage
 
tests. The operability of the various safety injection line check valves under
 
their design pressure conditions is also verified.
 
14.2.12.1.43.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The reactor coolant system is at normal operating
 
pressure.
 
14.2.12.1.43.3  Test Method
: a. Check valve leak testing is performed with the reactor
 
coolant system at normal operating pressure.
: b. Check valve operability is performed by verifying flow
 
through the check valves at reduced reactor coolant
 
pressure.
 
14.2.12.1.43.4  Acceptance Criteria
: a. Check valve leakage rates are within limits established
 
by Technical Specifications Section 3.4.6.2f.
: b. Injection line check valve operability is demonstrated
 
by verification of flow through the check valves in each
 
of the safety injection lines to the reactor coolant
 
system.
 
14.2.12.1.44  Boron Injection Tank and Recirculation Pump Test
 
              (SU3-EM04)
 
This test has been deleted at Wolf Creek since the boron injection requirements
 
have been eliminated due to the decrease in required boron concentration.
 
14.2-66    Rev. 0 WOLF CREEK 14.2.12.1.45  Containment Spray System Nozzle Air Test (S-03EN01)
 
14.2.12.1.45.1  Objectives
 
To demonstrate that the spray nozzles in the containment spray header are clear of obstructions.
 
14.2.12.1.45.2  Prerequisites
 
A source of compressed air is available to pressurize the spray headers.
 
14.2.12.1.45.3  Test Method
 
Air flow is initiated through the containment spray headers, and unobstructed
 
flow is verified through each nozzle.
14.2.12.1.45.4  Acceptance Criteria
 
All containment spray nozzles are clear and unobstructed, as evidenced by air
 
passing through each nozzle.
 
14.2.12.1.46  Containment Spray System  Preoperational Test
 
              (SU3-EN02)
 
14.2.12.1.46.1  Objectives
: a. To demonstrate the operation of system components,
 
including their response to safety signals, and verify
 
that the associated instrumentation and controls are
 
functioning properly. System flow characteristics in the test and simulated accident modes are also verified.
: b. To demonstrate the ability of the pump room coolers to
 
maintain room temperatures within design limits.
 
14.2.12.1.46.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The refueling water storage tank contains an adequate
 
supply of demineralized water for the performance of
 
this test.
: d. The auxiliary building HVAC system is available to cool
 
the pump rooms and verify associated pump interlocks.
 
14.2-67    Rev. 0 WOLF CREEK
: e. The containment spray pump rooms are closed.
 
14.2.12.1.46.3  Test Method
: a. Performance characteristics of the containment spray pumps are verified in the test mode, recirculating to
 
the refueling water storage tank, and in the simulated
 
accident mode.
: b. System component control circuits are verified,
 
including the operation of system pumps and valves on
 
receipt of load sequence/shedder and CSAS/CIS signals,
 
respectively.
: c. During system operations, spray additive eductor operating characteristics are verified.
: d. During containment spray pump operation, pump room
 
temperature data are recorded.
 
14.2.12.1.46.4  Acceptance Criteria
: a. Containment spray pump performance characteristics are
 
within design specifications for the tested modes of
 
operation.
: b. Containment spray pump and valve response to load
 
sequence/shedder and CSAS/CIS is verified, and the
 
associated response times are within design
 
specifications.
: c. Spray additive eductor operating characteristics are
 
within design specifications.
: d. The containment spray pump room coolers maintain the
 
room temperature within design limits.
 
14.2.12.1.47  Accumulator Testing (S-03EP01)
 
14.2.12.1.47.1  Objectives
 
To determine the operability of each safety injection accumulator and obtain,
 
by flow test, each accumulator's discharge line resistance to flow. The
 
ability of the accumulator discharge line isolation valves to open under
 
maximum differential pressure conditions is verified, as is the response of
 
accumulator system valves to safety signals.
 
14.2-68    Rev. 0 WOLF CREEK 14.2.12.1.47.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The reactor vessel head and reactor internals are not
 
installed, and the vessel is available to receive water.
: d. A source of compressed air and nitrogen is available.
: e. The refueling water storage tank contains an adequate
 
supply of demineralized water for the performance of this test.
 
14.2.12.1.47.3  Test Method
: a. Each accumulator is filled and partially pressurized with
 
the discharge valves closed. The discharge valves are
 
opened, discharging the accumulators to the reactor
 
vessel, and performance data are recorded.
: b. Each accumulator discharge line isolation valve is
 
operated under maximum differential pressure conditions
 
of normal accumulator precharge pressure and zero reactor
 
coolant pressure, and the valve operating times are
 
recorded.
: c. Accumulator system valve control circuits are verified, including their response to safety injection and
 
containment isolation signals.
 
14.2.12.1.47.4  Acceptance Criteria
: a. Each accumulator's discharge line resistance to flow
 
          (L/D) is in accordance with design specifications.
: b. Each accumulator's discharge line isolation valve
 
opening time under maximum differential pressure
 
conditions is within design specifications.
: c. The accumulator system nitrogen supply containment
 
isolation valve closes on receipt of a containment
 
isolation signal. Valve closure time is within design
 
specifications.
: d. Each accumulator discharge isolation valve opens on
 
receipt of a safety injection signal.
 
14.2-69    Rev. 0 WOLF CREEK 14.2.12.1.48  Auxiliary Feedwater Pump Turbine Preoperational Test (SU3-FC01)
 
14.2.12.1.48.1  Objectives
: a. To demonstrate the operation of the auxiliary feedwater
 
pump (AFWP) turbine and its support equipment, while
 
uncoupled from the pump.
: b. To demonstrate control of the AFWP turbine from the
 
control room as well as the auxiliary shutdown panel.
 
14.2.12.1.48.2  Prerequisites
: a. Required component testing, instrument calibration and system flushing/cleaning are complete.
: b. Steam is available to the AFWP turbine.
 
14.2.12.1.48.3  Test Method
: a. AFWP turbine system valves are operated and required
 
response to various signals is verified.
: b. The turbine is operated and proper control is verified
 
from the control room as well as the auxiliary shutdown
 
panel, and operating data are recorded.
: c. The turbine is brought to high speed at which time the
 
mechanical and electronic overspeed trips are verified.
14.2.12.1.48.4  Acceptance Criteria
: a. The AFWP turbine can be controlled from the control room
 
panel and the auxiliary shutdown panel.
: b. The mechanical and electronic overspeed trips actuate to
 
shut down the turbine in accordance with the design.
 
14.2.12.1.49  Essential Service Water Pumphouse HVAC
 
Preoperational Test (SU3-GD01)
 
14.2.12.1.49.1  Objectives
: a. To demonstrate the capacity of the essential service
 
water (ESW) pumproom supply fans.
: b. To demonstrate ESW pumproom unit heater response to a
 
load shed signal.
 
14.2-70    Rev. 0 WOLF CREEK 14.2.12.1.49.2  Prerequisites
: a. Required component testing and instrument calibration
 
are completed.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The ESW pumphouse HVAC system is air balanced.
 
14.2.12.1.49.3  Test Methods
: a. The ESW pumphouse supply fans are operated and flow data
 
are recorded.
: b. Response of the ESW pumproom unit heaters to load shed signal is verified.
 
14.2.12.1.49.4  Acceptance Criteria
: a. The ESW pumphouse supply fan capacities are within
 
design specification.
: b. A load shed signal will trip the ESW pumproom unit
 
heaters' circuit breaker.
 
14.2.12.1.50  Miscellaneous Building HVAC System Preoperational
 
Tests (SU3-GF01, SU3-GF02, SU3-GF03)
 
14.2.12.1.50.1  Objectives To demonstrate the capacity of;  1) the auxiliary feedwater pump room cooler
 
fans, 2) the main steam enclosure building supply and exhaust fans and 3) the
 
tendon access gallery transfer fans and to verify that the associated
 
instrumentation and controls are functioning properly. The responses of the
 
main steam enclosure building dampers and tendon access gallery dampers to
 
safety signals are also verified.
 
(At Wolf Creek Generating Station, this test was performed in three independent
 
parts. In addition, the auxiliary boiler room fan was treated as part of
 
preoperational test SU4-GF01.)
 
14.2.12.1.50.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2-71    Rev. 0 WOLF CREEK
: c. The miscellaneous building HVAC system is air balanced.
 
14.2.12.1.50.3  Test Method
: a. Flow data are recorded while the fans are operating.
: b. The response of system dampers to a safety injection
 
signal (SIS) is verified.
 
14.2.12.1.50.4  Acceptance Criteria
: a. System fan capacities are within design specifications.
: b. The main steam enclosure building and tendon access
 
gallery dampers close on receipt of a SIS.
14.2.12.1.51  Fuel Building  HVAC  System  Preoperational  Test
 
              (S-03GG01)
 
14.2.12.1.51.1  Objectives
 
To demonstrate that the emergency exhaust fans are capable of maintaining a
 
negative pressure in the fuel building or the auxiliary building during
 
accident conditions with the buildings isolated. To demonstrate the capacities
 
of the fuel building supply unit fans, emergency exhaust fans, and the spent
 
fuel pool pump room cooler fans. The operability of system instrumentation and
 
controls, including the components' response to safety signals, is also
 
verified.
 
14.2.12.1.51.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system air balancing are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The compressed air system is available to supply the
 
air-operated dampers in the fuel building.
: d. Required portions of the auxiliary building HVAC system
 
have been air balanced and are available to support this
 
test.
 
14.2.12.1.51.3  Test Method
: a. With the fuel building closed, the system is operated in
 
its normal configuration,  and the fuel building  supply 
 
14.2-72    Rev. 0 WOLF CREEK unit fan and spent fuel pool pump room cooler fan capacities are verified.
: b. With a fuel building isolation signal (FBIS) present,
 
the emergency exhaust fan capacities and negative fuel building pressures are verified.
: c. With a safety injection signal (SIS) present and the
 
auxiliary building isolated, the emergency exhaust fan
 
capacities and negative auxiliary building pressures are
 
verified.
 
14.2.12.1.51.4  Acceptance Criteria
: a. The auxiliary building and fuel building pressures maintained by the emergency exhaust fans are within design specifications.
: b. The fuel building supply fans, emergency exhaust fans,
 
and spent fuel pool pump room cooler fans' capacities
 
are within design specifications.
: c. The fuel building ventilation system fans and dampers
 
properly respond to FBIS and SIS, in accordance with
 
system design.
 
14.2.12.1.52  Control Building HVAC System Preoperational Test
 
              (SU3-GK01)
 
14.2.12.1.52.1  Objectives To demonstrate the capacities of the control building supply air unit, control
 
building exhaust fans, access control exhaust fans, control room pressurization
 
fans, control room filtration fans, control room air conditioning units, access
 
control fan coil units, counting room fan coil unit, and Class IE electrical
 
equipment ac units. To demonstrate that the control room pressurization fans
 
are capable of maintaining a positive pressure in the control room following a
 
control room ventilation isolation signal (CRVIS). The system instrumentation
 
and controls, including the components' responses to safety signals, are also
 
verified. To demonstrate that the ventilation to battery rooms 1 through 4 is
 
in accordance with system design.
 
14.2.12.1.52.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system air balancing are complete.
 
14.2-73    Rev. 0 WOLF CREEK
: b. Required electrical power supplies and control circuits are operational.
: c. The compressed air system is available to supply air to
 
system air-operated dampers.
 
14.2.12.1.52.3  Test Method
: a. The control building system fans are operated, and fan
 
capacities are verified.
: b. Proper response of system components to control room
 
ventilation isolation signals (CRVIS) and safety
 
injection signals (SIS) is verified.
: c. With a CRVIS present, the ability of each control room pressurization fan to maintain the control room at a
 
positive pressure is verified.
: d. The air flow to battery rooms 1 through 4 is verified.
 
14.2.12.1.52.4  Acceptance Criteria
: a. The control building HVAC system fan capacities are
 
within design specifications.
: b. The control building HVAC system fans and dampers
 
properly respond to CRVIS and SIS in accordance with
 
system design.
: c. The control room pressure maintained by the control room pressurization fans is within design specification.
: d. The air flow to battery rooms 1 through 4 is in
 
accordance with system design.
 
14.2.12.1.53  Auxiliary Building HVAC System Preoperational Test
 
              (SU3-GL01)
 
14.2.12.1.53.1  Objectives
 
To demonstrate the capacities of the auxiliary building supply unit fans,
 
auxiliary/fuel building normal exhaust fans, the auxiliary building fan coil
 
units, pump room coolers, penetration room coolers, decon tank exhaust scrubber
 
fans, access tunnel transfer fan, and penetration cooling fan. The system
 
instrumentation and controls, including components' response to safety and fire
 
signals, are also verified.
 
14.2-74    Rev. 0 WOLF CREEK 14.2.12.1.53.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system air balancing are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The compressed air system is available to supply the
 
air-operated dampers in the auxiliary building.
: d. The fuel building HVAC system has been air balanced, and
 
is available to support this test.
 
14.2.12.1.53.3  Test Method
: a. The system is operated in its normal configuration, and
 
the system fan capacities are verified.
: b. Proper responses of system components to safety
 
injection and fire signals are verified.
 
14.2.12.1.53.4  Acceptance Criteria
: a. The auxiliary building fan capacities are within design
 
specifications.
: b. The auxiliary building fans and dampers properly respond
 
to safety injection and fire signals, in accordance with
 
system design.
14.2.12.1.54  Diesel Generator Building HVAC Preoperational Test
 
              (S-03GM01)
 
14.2.12.1.54.1  Objectives
 
To demonstrate the capacities of the diesel generator room supply fans and to
 
verify that the system instrumentation and controls function properly,
 
including the response of fans and associated dampers to a diesel generator run
 
signal and room temperature signals.
 
14.2.12.1.54.2  Prerequisites
: a. Required component testing and instrument calibration
 
are completed.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2-75    Rev. 0 WOLF CREEK
: c. The diesel generator building HVAC system is air balanced.
: d. The respective diesel generator is not operating while
 
the room is under test.
 
14.2.12.1.54.3  Test Method
: a. Flow data are recorded, while the diesel generator room
 
supply fans are operating.
: b. The responses of the diesel generator room supply fans
 
and exhaust dampers to a diesel generator run signal and
 
to room temperature signals are verified.
 
14.2.12.1.54.4  Acceptance Criteria
: a. The capacities of the diesel generator room supply fans
 
are within design specifications.
: b. The diesel generator room exhaust dampers open on
 
receipt of a diesel generator run signal.
: c. The diesel generator room supply fans start on a high
 
room temperature signal and stop on a low room
 
temperature signal.
 
14.2.12.1.55  Containment Cooling System Preoperational Test
 
              (SU3-GN01)
 
14.2.12.1.55.1  Objectives
 
To demonstrate the capacities of the hydrogen mixing, containment cooling, and
 
pressurizer cooling fans and verify their associated instrumentation and
 
controls function properly, including fan response to safety signals.
 
14.2.12.1.55.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The essential service water system is available to
 
supply water to the containment coolers.
: d. The containment cooling system has been air balanced.
 
14.2-76    Rev. 0 WOLF CREEK 14.2.12.1.55.3  Test Method
: a. The hydrogen mixing, containment cooling, and
 
pressurizer cooling fans are operated, flow data
 
recorded, and fan capacities calculated.
: b. The response of the hydrogen mixing and containment
 
cooling fans to safety signals is verified.
 
14.2.12.1.55.4  Acceptance Criteria
: a. The capacities of the hydrogen mixing, containment
 
cooling, and pressurizer cooling fans are within design
 
specifications.
: b. The hydrogen mixing and containment cooling fans align or actuate in response to safety injection, shutdown
 
sequencer, and LOCA sequencer signals, in accordance
 
with system design.
 
14.2.12.1.56  CRDM Cooling Preoperational Test (S-03GN02)
 
14.2.12.1.56.1  Objectives
 
To demonstrate the operating characteristics of the cavity cooling, control rod
 
drive mechanism (CRDM), and the elevator machine room exhaust fans and verify
 
their associated instrumentation and controls, including their response to
 
safety signals.
 
14.2.12.1.56.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The CRDM and cavity cooling portions of the containment
 
cooling system are air balanced.
 
14.2.12.1.56.3  Test Method
: a. The cavity cooling, elevator machine room exhaust, and
 
CRDM fans are operated, flow data recorded, and fan
 
capacities calculated.
: b. The response of the CRDM fans to a safety injection
 
signal is verified.
 
14.2-77    Rev. 0 WOLF CREEK 14.2.12.1.56.4  Acceptance Criteria
: a. The capacities of the cavity cooling, elevator machine
 
room exhaust, and CRDM fans are within design
 
specifications.
: b. The appropriate CRDM fans supply breakers open on
 
receipt of a safety injection signal.
 
14.2.12.1.57  Integrated Containment Leak Rate Test (SU3-GP01)
 
14.2.12.1.57.1  Objective
 
To demonstrate that the total leakage from the containment does not exceed the
 
maximum allowable leakage rate at the calculated peak containment internal pressure. The operability of the containment cooling fans at design accident pressure is also verified.
 
14.2.12.1.57.2  Prerequisites
: a. The containment penetration leakage rate tests (type B
 
tests) and containment isolation valve leakage tests
 
          (type C tests) are complete and the containment has been
 
pressurized to 115 percent of the design pressure.
: b. All containment isolation valves are closed by normal
 
actuation methods.
: c. Containment penetrations, including equipment hatches
 
and personnel airlocks, are closed.
: d. Portions of fluid systems that are part of the
 
containment boundary, that may be opened directly to the
 
containment or outside atmosphere under post-accident
 
conditions, are opened or vented to the appropriate
 
atmosphere to place the containment in as close to post-
 
accident conditions as possible.
: e. Required instrument calibration is complete.
 
14.2.12.1.57.3  Test Method
: a. The integrated containment leak rate test (type A test)
 
is conducted, using the absolute method, described in
 
the ANSI/ANS 56.8-1981 Containment System Leakage
 
Testing Requirements. Measurements of containment
 
atmosphere dry-bulb temperature, dew point and pressure
 
are  taken to  calculate the  leakage rate. A standard 
 
14.2-78    Rev. 0 WOLF CREEK statistical analysis of data is conducted, using a linear least squares fit regression analysis to
 
calculate the leakage rate.
: b. On completion of the leak rate test, a verification test is conducted to confirm the capability of the data
 
acquisition and reduction system to satisfactorily
 
determine the calculated integrated leakage rate. The
 
verification test is accomplished by imposing a known
 
leakage rate on the containment, or by pumping back a
 
known quantity of air into the containment through a
 
calibrated flow measurement device.
: c. While at the design accident pressure, data is recorded
 
for the containment cooling fans.
14.2.12.1.57.4  Acceptance Criteria
 
The containment integrated leakage does not exceed the maximum allowable
 
leakage rate at a calculated peak containment internal pressure, as defined in
 
10 CFR 50, Appendix J.
 
The containment cooling fan operation at design accident pressure is in
 
accordance with design.
 
14.2.12.1.58  Reactor Containment Structural Integrity Acceptance
 
Test (SU3-GP02)
 
14.2.12.1.58.1  Objectives
 
To demonstrate the structural integrity of the reactor containment building.
 
14.2.12.1.58.2  Prerequisites
: a. Containment penetrations are installed, and penetration
 
leak tests are completed.
: b. Containment penetrations, including equipment hatches
 
and personnel airlocks, are closed.
: c. Required instrument calibration is complete.
 
14.2.12.1.58.3  Test Method
 
The containment is pressurized at 115 percent of the design pressure, and
 
deflection measurements and concrete crack inspections are made to determine
 
that the actual structural response is within the limits predicted by the
 
design analyses.
 
14.2-79    Rev. 0 WOLF CREEK 14.2.12.1.58.4  Acceptance Criteria
 
The containment structural response is within the limits predicted by design
 
analyses.
 
14.2.12.1.59  Post-Accident Hydrogen Removal System
 
Preoperational Test (S-03GS01)
 
14.2.12.1.59.1  Objectives
: a. To demonstrate that the hydrogen recombiner performance
 
characteristics are within design specifications.
: b. To determine the operation of system dampers and valves,
 
including the response of hydrogen purge and hydrogen monitoring containment isolation valves to a CIS.
: c. To demonstrate the operability of the hydrogen analyzers
 
and their ability to sample the containment atmosphere.
 
14.2.12.1.59.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2.12.1.59.3  Test Method
: a. Performance characteristics are recorded, while the hydrogen recombiners are operating.
: b. System valve and damper control circuits are verified,
 
including the response of hydrogen purge and hydrogen
 
monitoring containment isolation valves to a CIS.
: c. The hydrogen analyzers are operated, and performance
 
data recorded.
 
14.2.12.1.59.4  Acceptance Criteria
: a. Hydrogen recombiner performance characteristics are
 
within design specifications.
: b. Hydrogen purge and hydrogen monitoring containment
 
isolation valves close on receipt of a CIS. Valve
 
closure times are within design specifications.
 
14.2-80    Rev. 0 WOLF CREEK 14.2.12.1.60  Containment Purge System HVAC Preoperational Test (S-03GT01)
 
14.2.12.1.60.1  Objectives
 
To demonstrate the capacities of the containment minipurge supply and exhaust,
 
shutdown purge supply and exhaust, and containment atmospheric control fans. 
 
The operation of system instrumentation and controls, including the response of
 
system fans and dampers to safety signals, is also verified.
 
14.2.12.1.60.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The containment purge HVAC system has been air balanced.
: d. The compressed air system is available to supply air to
 
system valves and dampers.
 
14.2.12.1.60.3  Test Method
: a. The containment minipurge supply and exhaust, shutdown
 
purge supply and exhaust, and containment atmospheric
 
control fans are operated, flow data recorded, and fan
 
capacities calculated.
: b. The response of system fans and dampers to safety signals is verified.
 
14.2.12.1.60.4  Acceptance Criteria
: a. The capacities of the containment minipurge supply and
 
exhaust, shutdown purge supply and exhaust, and
 
containment atmospheric control fans are within design
 
specifications.
: b. System fans and dampers align or actuate in response to
 
containment purge isolation and safety injection
 
signals, in accordance with system design. Damper
 
closure times are within design specifications.
 
14.2-81    Rev. 0 WOLF CREEK 14.2.12.1.61  Gaseous Radwaste System Preoperational Test (S-03HA01)
 
14.2.12.1.61.1  Objectives
: a. To demonstrate the performance characteristics of the
 
gas decay tank drain pump, waste gas compressors, and
 
catalytic hydrogen recombiners, including their response
 
to safety signals.
: b. To verify the operability of system valves, including
 
the response of the waste gas discharge valve to a high-
 
radiation signal.
: c. To verify that system instrumentation and controls function properly.
 
14.2.12.1.61.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The component cooling water system is available to
 
supply cooling water to the waste gas compressors and
 
catalytic hydrogen recombiners.
: d. The service gas system is available to provide nitrogen, hydrogen, and oxygen to the catalytic hydrogen recombiners.
: e. The reactor makeup water system is available to provide
 
water to the waste gas compressors, catalytic hydrogen
 
recombiners, and the waste gas decay tank drain header.
 
14.2.12.1.61.3  Test Method
: a. Performance characteristics of the gas decay tank drain
 
pump, and waste gas compressors are verified.
: b. Hydrogen is introduced to the system and the catalytic
 
hydrogen recombiners performance are verified.
: c. System component control circuits are verified,
 
including component response to safety signals.
 
14.2.12.1.61.4  Acceptance Criteria
: a. Performance characteristics of the gas decay tank drain
 
pump, waste gas compressors, and catalytic hydrogen
 
recombiners are within design specifications.
 
14.2-82    Rev. 0 WOLF CREEK
: b. The waste gas discharge valve automatically closes on a high-radiation signal.
: c. The waste gas compressors trip on a high-high or low-low
 
moisture separator level, high or low moisture separator pressure, low compressor suction pressure, or low
 
component cooling water flow.
: d. The hydrogen recombiner oxygen feed valve closes on
 
high-high hydrogen concentration in the recombiner feed,
 
high-high oxygen concentration in the recombiner
 
discharge, high cooler-condenser discharge temperature,
 
high-high recombiner discharge temperature, low-low
 
recombiner flow, and high-high recombiner reactor inlet
 
temperature.
: e. The hydrogen recombiner oxygen feed valve signal is
 
blocked on high oxygen concentration in the recombiner
 
feed and high catalyst bed temperature.
: f. The volume control tank vent valve closes on a hydrogen
 
recombiner trip, low volume control tank pressure, and
 
low waste gas compressor suction pressure.
 
14.2.12.1.62  Emergency  Fuel  Oil  System  Preoperational  Test
 
              (S-03JE01)
 
14.2.12.1.62.1  Objectives
 
To demonstrate the capability of the system to provide an adequate fuel supply to the emergency diesel generator fuel oil day tanks and verify that the associated instrumentation and controls are functioning properly.
 
14.2.12.1.62.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2.12.1.62.3  Test Method
: a. Fuel oil is transferred from the fuel oil storage tank
 
to the fuel oil day tanks by means of the transfer
 
pumps. Flow and pressure characteristics are recorded.
: b. Fuel oil day tank levels are varied to verify the
 
transfer pump automatic operations.
 
14.2-83    Rev. 0 WOLF CREEK
: c. Response to fire and emergency diesel generator start signals are verified.
 
14.2.12.1.62.4  Acceptance Criteria
: a. The transfer pump flow capacity is verified for later
 
comparison to the fuel consumption rate (S-03NF02).
: b. Control circuit automatic operation from fuel oil day
 
tank levels, fire signals, and diesel generator start
 
signals is within design specifications.
 
14.2.12.1.63  Spent Fuel Pool Crane Preoperational Test
 
              (SU3-KE01)
 
14.2.12.1.63.l  Objectives
: a. To demonstrate proper operation of the spent fuel pool
 
bridge crane control circuits and associated interlocks.
: b. To document the data obtained during testing of the
 
spent fuel pool bridge crane at 125 percent of rated
 
load.
: c. To verify the ability of the spent fuel pool bridge
 
crane and associated fuel handling tools to transfer a
 
dummy fuel assembly.
 
14.2.12.1.63.2  Prerequisites
: a. Required component testing and instrument calibration are completed.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. A dummy fuel assembly is available.
 
14.2.12.1.63.3  Test Method
: a. Operability of the spent fuel pool bridge crane control
 
circuits and associated interlocks is verified.
: b. Ability of the spent fuel pool bridge crane and
 
associated fuel handling tools to transfer a dummy fuel
 
assembly is verified.
 
14.2-84    Rev. 0 WOLF CREEK 14.2.12.1.63.4  Acceptance Criteria
: a. The spent fuel pool bridge crane electric and manual
 
hoists support 125 percent of their rated load.
: b. The spent fuel pool bridge crane monorail center span
 
deflection at rated load is within design
 
specifications.
: c. The spent fuel pool crane bridge, trolley and hoist
 
speeds at rated loads are within design specifications.
: d. All control circuits and interlocks associated with the
 
spent fuel pool bridge crane operate in accordance with
 
system design.
: e. While transferring a dummy fuel assembly, the spent fuel
 
pool bridge crane and associated fuel handling tools
 
operate in accordance with system design.
 
14.2.12.1.64  New Fuel Elevator Preoperational Test (SU3-KE02)
 
14.2.12.1.64.1  Objectives
: a. To demonstrate proper operation of the new fuel elevator
 
control circuits and associated interlocks.
: b. To verify the ability of the new fuel elevator to raise
 
and lower a dummy fuel assembly.
 
14.2.12.1.64.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. A dummy fuel assembly is available.
 
14.2.12.1.64.3  Test Method
 
Operability of the new fuel elevator including control circuits and associated
 
interlocks is verified.
 
14.2.12.1.64.4  Acceptance Criteria
: a. All control circuits and interlocks associated with the
 
new fuel elevator operate in accordance with system
 
design.
 
14.2-85    Rev. 0 WOLF CREEK
: b. While raising and lowering a dummy fuel assembly, the new fuel elevator operates in accordance with system
 
design.
 
14.2.12.1.65  Fuel  Handling  and  Storage  Preoperational Test (SU3-KE03)
 
14.2.12.1.65.1  Objectives
: a. To verify the ability of the spent fuel cask handling
 
crane, and associated fuel handling tools to transfer a
 
dummy fuel assembly.
: b. To demonstrate proper operation of the spent fuel cask
 
handling crane control circuits and associated interlocks.
: c. To document the data obtained during testing of the
 
spent fuel cask handling crane at 125 percent of rated
 
load.
 
14.2.12.1.65.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. A dummy fuel assembly is available.
14.2.12.1.65.3  Test Method
: a. During the transfer of a dummy fuel assembly, the
 
operability of the spent fuel cask handling crane and
 
associated fuel handling tools is verified.
: b. Operability of the spent fuel cask handling crane
 
control circuits and associated interlocks is verified.
 
14.2.12.1.65.4  Acceptance Criteria
: a. While transferring a dummy fuel assembly, the spent fuel
 
cask handling crane and associated fuel handling tools
 
operate in accordance with system design.
: b. All control circuits and interlocks associated with the
 
spent fuel cask handling crane operate in accordance
 
with system design.
 
14.2-86    Rev. 0 WOLF CREEK
: c. The spent fuel cask handling crane hoist supports 125 percent of rated load.
: d. The spent fuel cask handling crane bridge center span
 
deflection at rated load is within design specifications.
: e. The spent fuel cask handling crane bridge, trolley and
 
hoist speeds at rated loads are within design
 
specifications.
 
14.2.12.1.66  Fuel  Transfer  System  Preoperational  Test
 
              (SU3-KE04)
 
14.2.12.1.66.l  Objectives
: a. To demonstrate proper operation of the fuel transfer
 
system control circuits and associated interlocks.
: b. To verify the ability of the fuel transfer system and
 
associated handling tools to transfer a dummy fuel
 
assembly.
 
14.2.12.1.66.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. A dummy fuel assembly is available.
 
14.2.12.1.66.3  Test Method
: a. Operability of the fuel transfer system control circuits
 
and associated interlocks is verified.
: b. During the transfer of a dummy fuel assembly, the
 
operability of the fuel transfer system and associated
 
handling tools is verified.
 
14.2.12.1.66.4  Acceptance Criteria
: a. All control circuits and interlocks associated with the
 
fuel transfer system operate in accordance with system
 
design.
 
14.2-87    Rev. 0 WOLF CREEK
: b. While transferring a dummy fuel assembly, the fuel transfer system and associated handling tools operate in
 
accordance with system design.
 
14.2.12.1.67  Refueling Machine and RCC Change Fixture Preoperational Test (SU3-KE05)
 
14.2.12.1.67.1  Objectives
: a. To demonstrate proper operation of the refueling
 
machine, rod cluster control change fixture and
 
containment building polar crane control circuits and
 
associated interlocks.
: b. To document the data obtained during testing of the containment building polar crane at 125 percent of rated load.
: c. To verify the ability of the refueling machine to
 
transfer a dummy fuel assembly.
 
14.2.12.1.67.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. A dummy fuel assembly is available.
: d. A dummy control rod assembly is available.
 
14.2.12.1.67.3  Test Method
: a. Operability of the refueling machine and rod cluster
 
control change fixture control circuits and associated
 
bridge, trolley, hoist and gripper interlocks is
 
verified.
: b. Operability of the containment building polar crane
 
control circuits and associated interlocks is verified.
 
14.2.12.1.67.4  Acceptance Criteria
: a. All control circuits and interlocks associated with the
 
refueling machine and rod cluster control change fixture
 
operate in accordance with system design.
 
14.2-88    Rev. 0 WOLF CREEK
: b. The control circuits and interlocks associated with the containment building polar crane operate in accordance
 
with system design.
: c. The containment polar crane main and auxiliary hoists support 125 percent of their rated load.
: d. The containment polar crane bridge center span
 
deflection at rated load is within design
 
specifications.
: e. The containment polar crane bridge, trolley, and hoist
 
speeds at rated loads are within design specifications.
: f. While transferring a dummy fuel assembly, the refueling machine operates in accordance with system design.
 
14.2.12.1.68  Refueling Machine Indexing Test (S-03KE06)
 
14.2.12.1.68.1  Objectives
: a. To verify the indexing of the refueling machine and
 
establish bridge rail reference points for future
 
operations.
: b. To demonstrate the ability to transfer the dummy fuel
 
assembly to the reactor vessel.
 
14.2.12.1.68.2  Prerequisites
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. A dummy fuel assembly is available.
 
14.2.12.1.68.3  Test Method
: a. While transferring a dummy fuel assembly with the
 
refueling machine, the bridge rail is marked at key
 
transfer points.
 
14.2.12.1.68.4  Acceptance Criteria
: a. The refueling machine can load a dummy fuel assembly in
 
each of the reactor vessel fuel loading locations.
 
14.2.12.1.69  Fuel Handling System Integrated Preoperational Test
 
              (SU3-KE07)
 
14.2-89    Rev. 0 WOLF CREEK 14.2.12.1.69.1  Objective
 
To verify the ability of the refueling machine, new fuel elevator, fuel
 
transfer system, spent fuel bridge crane, spent fuel cask handling crane and
 
associated fuel handling tools to transfer a dummy fuel assembly.
 
14.2.12.1.69.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The reactor vessel, refueling pool, refueling canal and spent fuel pool are filled with demineralized water.
: d. A dummy fuel assembly is available.
 
14.2.12.1.69.3  Test Method
 
During the transfer of a dummy fuel assembly, the operability of the refueling
 
machine, new fuel elevator, fuel transfer system, spent fuel bridge crane,
 
spent fuel cask handling crane and associated fuel handling tools is verified.
 
14.2.12.1.69.4  Acceptance Criteria
 
While transferring a dummy fuel assembly, the refueling machine, new fuel
 
elevator, fuel transfer system, spent fuel bridge crane, spent fuel cask
 
handling crane and associated fuel handling tools operate in accordance with system design.
 
14.2.12.1.70  Diesel  Generator  Mechanical Preoperational  Test
 
              (S-03KJ01)
 
14.2.12.1.70.1  Objectives
: a. To demonstrate the performance characteristics of the
 
diesel generators and associated auxiliaries, and verify
 
that each diesel reaches rated speed within the required
 
time.
: b. To verify the operability of all control circuits
 
associated with the diesel generator and diesel
 
auxiliaries, including the control circuits response to
 
safety signals.
 
14.2-90    Rev. 0 WOLF CREEK
: c. To demonstrate the capability of each air storage tank to provide five diesel cranking cycles without being
 
recharged.
 
14.2.12.1.70.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The essential service water system is available to
 
provide cooling water to the diesel engine intercooler
 
heat exchanger.
: d. The emergency fuel oil system is available to provide
 
fuel oil to the diesel generators.
: e. The fire protection system is available to support this
 
test.
 
14.2.12.1.70.3  Test Method
: a. The diesel generators are started, and the time required
 
to reach rated speed is recorded.
: b. With the diesel generators and associated auxiliaries
 
operating, performance characteristics are verified.
: c. The operability of all control circuits associated with the diesel generator and diesel auxiliaries, including
 
the control circuits' response to safety signals, is
 
verified.
: d. The ability of each air storage tank to provide five
 
diesel cranking cycles, without being recharged, is
 
verified.
 
14.2.12.1.70.4  Acceptance Criteria
: a. The time required for each diesel generator to reach
 
rated speed is within design specifications.
: b. The performance characteristics of the diesel generators
 
and associated auxiliaries are within design
 
specifications.
: c. Each diesel generator starts automatically on receipt of
 
a safety injection signal or a bus under-voltage signal.
 
14.2-91    Rev. 0 WOLF CREEK
: d. Each diesel generator trips automatically on receipt of each of the following signals:
 
Lube oil pressure low
 
Jacket coolant temperature high Crankcase pressure high
 
Start failure
 
Engine overspeed
 
Diesel generator ground overcurrent
 
Diesel generator differential current
: e. The diesel generator neutral ground overcurrent trip
 
signal is bypassed when the diesel generator is
 
operating in the emergency mode.
: f. Each air storage tank is capable of providing five diesel cranking cycles, without being recharged.
: g. Each starting air compressor has the ability to charge
 
its respective air tank from minimum to normal pressure
 
within the required time.
 
14.2.12.1.71  4160-V  (Class IE)  System  Preoperational Test
 
              (S-03NB01)
 
14.2.12.1.71.1  Objectives
: a. To demonstrate that the 4,160-V Class IE busses can be
 
energized from their normal and alternate sources.
: b. To verify that a 4,160-V Class IE bus digital undervoltage signal trips the associated incoming feeder
 
breakers.
: c. To verify that a degraded bus voltage condition will
 
trip the associated incoming feeder breakers.
: d. To verify proper operation of system instrumentation and
 
alarms.
 
14.2.12.1.71.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2-92    Rev. 0 WOLF CREEK 14.2.12.1.71.3  Test Method
: a. The 4,160-V Class IE busses are energized from their
 
normal source, and bus voltages are recorded.
: b. The 4,160-V Class IE busses are energized from their
 
alternate source, and bus voltages are recorded.
: c. 4,160-V Class IE bus undervoltage signals are simulated,
 
and proper operation of the 4,160-V Class IE feeder
 
breakers is verified.
 
14.2.12.1.71.4  Acceptance Criteria
: a. The voltage of each 4,160-V Class IE bus, when supplied from its normal source, is within design specifications.
: b. The voltage of each 4,160-V Class IE bus, when supplied
 
from its alternate source, is within design
 
specifications.
: c. A 4,160-V Class IE bus digital undervoltage signal will
 
trip the appropriate bus incoming feeder breakers.
: d. A degraded voltage condition on either 4,160-V Class IE
 
bus will cause an alarm and, if it continues, trip the
 
appropriate bus incoming feeder breakers.
: e. A degraded voltage condition on either 4,160-V Class IE
 
bus coincident with a safety injection actuation signal will immediately trip the bus incoming feeder breakers.
 
14.2.12.1.72  Diesel Generator Electric Preoperational Test
 
              (S-03NE01)
 
14.2.12.1.72.1  Objectives
: a. To demonstrate that each diesel generator is capable of
 
35 consecutive valid starts with no failure.
: b. To demonstrate the ability of each diesel generator to
 
carry the design load for the time required to reach
 
equilibrium temperature plus l hour, without exceeding
 
design limits.
: c. To demonstrate the ability of each diesel generator to
 
attain and stabilize frequency and voltage within the
 
design limits and time.
 
14.2-93    Rev. 0 WOLF CREEK
: d. To demonstrate the capability of each diesel generator to withstand a full-load rejection without exceeding
 
speeds or voltages that cause tripping or damage.
: e. To demonstrate the operability of each diesel generator feeder breaker and associated interlocks.
: f. To demonstrate the ability of the diesel cooling water
 
system to maintain the diesel temperature within design
 
specifications, while the diesel generators are
 
operating at full load.
: g. To demonstrate the ability of each diesel generator to
 
start and shed the largest single motor while supplying
 
all other sequenced loads, maintaining voltage and frequency within design limits.
 
14.2.12.l.72.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The essential service water system is available to
 
provide cooling water to the diesel generator
 
intercooler heat exchanger.
: d. The emergency fuel oil system is available to provide fuel oil to the diesel generators.
: e. The fire protection system is available to support this
 
test.
: f. The 4.16-kV busses are available for loading to support
 
this test.
 
14.2.12.1.72.3  Test Method
: a. The ability of each diesel generator to undergo 35
 
consecutive starts with no failure is verified.
: b. The ability of each diesel generator to carry the design
 
load for the time required to reach equilibrium
 
temperature, plus 1 hour, without exceeding design
 
limits, is verified.
 
14.2-94    Rev. 0 WOLF CREEK
: c. The ability of each diesel generator to attain and stabilize frequency and voltage within the design limits
 
and time is verified.
: d. The ability of each diesel generator to withstand a full-load rejection, without exceeding speeds or
 
voltages that cause tripping, is verified.
: e. The operability of each diesel generator feeder breaker
 
and associated interlocks is verified.
: f. While operating each diesel generator at full-load
 
conditions, the ability of the diesel cooling water
 
system to maintain diesel temperatures within design
 
specifications is verified.
: g. The ability of each diesel generator to start and shed
 
the largest fully loaded single motor while supplying
 
all other sequenced loads and maintain voltage and
 
frequency within design limits is verified.
 
14.2.12.1.72.4  Acceptance Criteria
: a. Each diesel generator is capable of carrying the design
 
load for the time required to reach equilibrium
 
temperature, plus 1 hour, without exceeding design
 
limits.
: b. Each diesel generator can attain and stabilize frequency
 
and voltage within design limits and time.
: c. Each diesel generator is capable of withstanding a full-
 
load rejection without exceeding speeds or voltages that
 
cause tripping.
: d. When a diesel generator is operating in the nonemergency
 
          (test) mode, the associated diesel generator feeder
 
breaker trips on receipt of any of the following
 
signals:
 
Generator overcurrent
 
Reverse power
 
Loss of field
 
Underfrequency
: e. The diesel generator stops and the associated diesel
 
generator feeder breaker trips on receipt of any of the
 
following signals:
 
Generator differential current
 
Neutral ground overcurrent
 
14.2-95    Rev. 0 WOLF CREEK
: f. When a diesel generator is operating in the emergency mode, the following trip signals are bypassed:
 
Neutral ground overcurrent
 
Generator overcurrent Reverse power
 
Loss of field
 
Underfrequency
: g. Each diesel generator cooling water system, with the
 
diesel generators operating at full-load, maintains the
 
diesel temperatures within design specifications.
: h. Each diesel generator has the capability of starting and
 
shedding the largest fully loaded single motor while supplying all other sequenced loads, maintaining voltage and frequency within design limits.
: i. Diesel generators are capable of 35 consecutive valid
 
starts with no failure.
 
14.2.12.1.73  Integrated Control Logic Test (SU3-NF01)
 
14.2.12.1.73.1  Objectives
: a. To demonstrate that the actuation of the LOCA sequencer,
 
shutdown sequencer, safety-related load shed, and
 
nonsafety-related load shed circuits on receipt of the
 
appropriate undervoltage, safety injection, containment
 
spray actuation, diesel generator breaker position, and normal and alternate 4,160-V feeder breaker position signals is in accordance with system design.
: b. To demonstrate that the LOCA sequencer, shutdown
 
sequencer,  safety-related  load  shed,  and nonsafety-
 
related load shed circuits shed and sequence loads in
 
accordance with system design.
 
14.2.12.1.73.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2.12.1.73.3  Test Method
: a. Undervoltage, safety injection, containment spray
 
actuation, diesel generator breaker position, and
 
normal and 
 
14.2-96    Rev. 0 WOLF CREEK alternate 4,160-V feeder breaker position signals are initiated, and the actuation of the LOCA sequencer,
 
shutdown sequencer, safety-related load shed, and
 
nonsafety-related load shed circuits is verified.
: b. Signals are initiated to actuate the LOCA sequencer,
 
shutdown sequencer, safety-related load shed, and
 
nonsafety-related load shed circuits, and proper load
 
shed and load sequencing are verified.
 
14.2.12.1.73.4  Acceptance Criteria
: a. Actuation of the LOCA sequencer, shutdown sequencer,
 
safety-related load shed, and nonsafety-related load
 
shed circuits on receipt of under-voltage, safety injection, containment spray actuation, diesel generator breaker position, and normal and alternate 4,160-V
 
feeder breaker position signals is in accordance with
 
system design.
: b. The LOCA sequencer, shutdown sequencer, safety-related
 
load shed, and nonsafety-related load shed circuits shed
 
and sequence loads in accordance with system design.
 
14.2.12.1.74  LOCA Sequencer Preoperational Test (S-03NF02)
 
14.2.12.1.74.1  Objectives
: a. To demonstrate that initiation of a safety injection
 
signal (SIS) will shed the nonsafety-related loads, start the diesel generator, and sequence the associated equipment. The ability of each 4,160-V Class IE load
 
group to supply the sequenced loads while maintaining
 
voltage within design specifications is also verified.
: b. To demonstrate that a loss of offsite power concurrent
 
with SIS will shed the safety-related loads, start the
 
diesel generator, close the diesel generator feeder
 
breaker, and sequence the associated equipment. The
 
ability of each diesel generator to supply the sequenced
 
loads while maintaining voltage and frequency within
 
design specifications is also verified.
: c. To demonstrate the ability of each diesel generator to
 
carry the short-time rating load for 2 hours and the
 
continuous rated load for 22 hours, without exceeding
 
design limits.
: d. To demonstrate that each diesel generator, following
 
operation  for  2 hours at the short-time rated load and 
 
14.2-97    Rev. 0 WOLF CREEK 22 hours at the continuous rated load, will start automatically on a loss of ac voltage concurrent with an
 
SIS, attain voltage and frequency within design limits
 
and time, and accept the LOCA sequenced loads, while
 
maintaining voltage and frequency within design limits.
: c. To demonstrate the ability of the diesel cooling water
 
system to maintain the diesel temperature within design
 
specifications, while the diesel generators are
 
operating for 2 hours at the short-time rating load and
 
22 hours at the continuous rating load.
: f. To determine the fuel oil consumption of each diesel,
 
while operating for 22 hours at the continuous rating
 
load.
: g. To demonstrate the ability of the 125 V dc system to
 
perform its design functions while at minimum voltage.
: h. To demonstrate the independence between the redundant on
 
ac and dc power sources.
 
14.2.12.1.74.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Each diesel generator and its associated auxiliaries are
 
available.
: c. All components actuated by the LOCA sequencer and safety-related and nonsafety-related load shed circuits
 
are available.
 
14.2.12.1.74.3  Test Method
: a. A train A SIS is initiated, and the following are
 
verified:
: 1. Group l nonsafety-related loads are shed.
: 2. Group 1 diesel generator starts.
: 3. Group 1 LOCA sequencer is actuated, and associated
 
components are sequenced. The times for sequenced
 
pumps to reach full flow are verified.
: 4. With bus NB01 supplying the sequenced loads from its
 
normal source, bus voltage is recorded.
 
14.2-98    Rev. 0 WOLF CREEK
: b. With group 2 dc load group isolated from its power source and group 1 dc load group voltage set to minimum,
 
a loss of offsite power is initiated concurrent with a
 
train A SIS, and the following are verified:
: 1. Safety-related group 1 loads are shed.
: 2. Group 1 diesel generator starts, and its feeder
 
breaker closes.
: 3. Group 1 LOCA sequencer is actuated, and associated
 
components are sequenced. The times for sequenced
 
pumps to reach full flow are verified.
: 4. With the group 1 diesel generator supplying the sequenced loads, bus voltage and frequency are recorded.
: 5. The group 2 ac and dc busses are monitored to
 
verify the absence of voltage on these busses and
 
loads, indicating no interconnection at load
 
groups.
: c. The ability of the group 1 diesel generator to carry the
 
short-time rating load for 2 hours without exceeding
 
design limits is verified.
: d. The ability of the group 1 diesel generator to carry the
 
continuous rated load for 22 hours without exceeding
 
design limits is verified. Group l diesel fuel oil consumption is also determined.
: e. Following group 1 diesel generator operation for 2 hours
 
at the short-time rated load and 22 hours at the
 
continuous rated load, the group 1 diesel generator is
 
shutdown, a loss of group 1 ac voltage is initiated
 
concurrent with a train A SIS, and the ability of the
 
group l diesel generator to start, attain voltage and
 
frequency within design limits and time, and accept the
 
loads resulting from the design accident loading
 
sequence while maintaining voltage and frequency within
 
design limits is verified. If this test is not
 
satisfactorily completed,  it is not necessary to repeat
 
the tests of items c and d prior to rerunning this
 
test. Instead, prior to rerunning this test, the diesel
 
generator may be operated at the continuous rated load
 
for l hour or until operating temperature has
 
stabilized.
 
14.2-99    Rev. 0 WOLF CREEK
: f. A train B SIS is initiated, and the following are verified:
: 1. Group 2 nonsafety-related loads are shed.
: 2. Group 2 diesel generator starts.
: 3. Group 2 LOCA sequencer is actuated, and associated
 
components are sequenced. The times for sequenced
 
pumps to reach full flow are verified.
: 4. With Bus NB02 supplying the sequenced loads from
 
its normal source, bus voltage is recorded.
: g. With group 1 dc load group isolated from its power source and group 2 dc load group voltage set to minimum, a loss of offsite power is initiated concurrent with a
 
train B SIS, and the following are verified:
: 1. Safety-related group 2 loads are shed.
: 2. Group 2 diesel generator starts, and its feeder
 
breaker closes.
: 3. Group 2 LOCA sequencer is actuated, and associated
 
components are sequenced. The times for sequenced
 
pumps to reach full flow are verified.
: 4. With the group 2 diesel generator supplying the
 
sequenced loads, bus voltage and frequency are recorded.
: 5. The group l ac and dc busses are monitored to
 
verify the absence of voltage on these busses and
 
loads, indicating no interconnection of load
 
groups.
: h. The ability of the group 2 diesel generator to carry the
 
short-time rating load for 2 hours without exceeding
 
design limits is verified.
: i. The ability of the group 2 diesel generator to carry the
 
continuous rated load for 22 hours without exceeding
 
design limits is verified. Group 2 diesel fuel oil
 
consumption is also determined.
 
14.2-100    Rev. 0 WOLF CREEK
: j. Following group 2 diesel generator operation for 2 hours at the short-time rated load and 22 hours at the
 
continuous rated load, the group 2 diesel generator is
 
shutdown, a loss of group 2 ac voltage is initiated
 
concurrent with a train B SIS, and the ability of the group 2 diesel generator to start, attain voltage and
 
frequency within design limits and time, and accept the
 
LOCA sequenced loads, while maintaining voltage and
 
frequency within design limits, is verified. If this
 
test is not satisfactorily completed, it is not necessary
 
to repeat the tests of items h and i prior to rerunning
 
this test. Instead, prior to rerunning this test, the
 
diesel generator may be operated at the continuous rated
 
load for l hour or until operating temperature has
 
stabilized.
: k. The ability of the diesel cooling water system to
 
maintain the diesel temperature within design
 
specifications, while the diesel generators are operating
 
for 2 hours at the short-time rating load and 22 hours at
 
the continuous rating load, is verified.
 
14.2.12.1.74.4  Acceptance Criteria
: a. A train A SIS initiates the following, in accordance
 
with system design:
: 1. Group 1 nonsafety-related loads are shed.
: 2. Group 1 diesel generator starts.
: 3. Group l LOCA sequencer actuates, and the associated
 
components are sequenced. Sequenced pumps reach
 
full flow within the required times.
: b. Bus NB01, while powered from its normal source, supplies
 
the sequenced loads while maintaining voltage within
 
design specifications.
: c. With the group 2 dc load group isolated from its power
 
source and the group 1 dc load group voltage at minimum,
 
a loss of offsite power concurrent with a train A SIS
 
initiates the following, in accordance with system
 
design:
: 1. Safety-related group 1 loads are shed.
: 2. Group 1 diesel generator starts, and its feeder
 
breaker closes.
 
14.2-101    Rev. 0 WOLF CREEK
: 3. Group l LOCA sequencer actuates, and the associated components are sequenced. Sequenced pumps reach
 
full flow within design times.
: d. Group l diesel generator supplies the sequenced loads, while maintaining voltage and frequency within design
 
specifications.
: e. With load group 1 supplying loads following a loss of
 
offsite power concurrent with a train A SIS, the group 2
 
ac and dc busses are verified de-energized, indicating
 
no interconnection of load groups.
: f. Following group 1 diesel generator operation for 2 hours
 
at the short-time rated load and 22 hours at the continuous rated load, the group 1 diesel generator starts, attains voltage and frequency within design
 
limits and time, and accepts the LOCA sequenced loads
 
while maintaining voltage and frequency within design
 
limits, on loss of group 1 ac voltage concurrent with a
 
train A SIS.
: g. A train B SIS initiates the following, in accordance
 
with the system design:
: 1. Group 2 nonsafety-related loads are shed.
: 2. Group 2 diesel generator starts.
: 3. Group 2 LOCA sequencer actuates, and the associated components are sequenced. Sequenced pumps reach full flow within design times.
: h. Bus NB02, while powered from its normal source, supplies
 
the required loads while maintaining the voltage within
 
design specifications.
: i. With the group 1 dc load group isolated from its power
 
source and the group 2 dc load group voltage at minimum,
 
a loss of offsite power concurrent with a train B SIS
 
initiates the following, in accordance with system
 
design:
: 1. Safety-related group 2 loads are shed.
: 2. Group 2 diesel generator starts, and its feeder
 
breaker closes.
 
14.2-102    Rev. 0 WOLF CREEK
: 3. Group 2 LOCA sequencer actuates, and the associated components are sequenced. Sequenced pumps reach
 
full flow within design times.
: j. Group 2 diesel generator supplies the required loads, while maintaining voltage and frequency within design
 
specifications.
: k. With load group 2 supplying loads following a loss of
 
offsite power concurrent with a train B SIS, the group 1
 
ac and dc busses are verified de-energized, indicating
 
no interconnection of load groups.
: l. Following group 2 diesel generator operation for 2 hours
 
at the short-time rated load and 22 hours at continuous rated load, group 2 diesel generator starts, attains voltage and frequency within design limits and time, and
 
accepts the LOCA sequenced loads while maintaining
 
voltage and frequency within design limits, on loss of
 
group 2 ac voltage concurrent with a train B SIS.
: m. Each diesel generator is capable of carrying the short-
 
time rating load for 2 hours and the continuous rated
 
load for 22 hours, without exceeding design limits.
: n. Fuel oil consumption of each diesel, while operating at
 
the continuous rated load, is within design
 
specifications.
: o. Each diesel generator cooling water system, with the diesel generators operating for 2 hours at the short-time rating load and 22 hours at the continuous rating
 
load, maintains the diesel temperatures within design
 
specifications.
: p. The controls required for the loss of offsite power
 
concurrent with a SIS (shedding, sequencing, etc.)
 
function with minimum dc voltage available.
 
14.2.12.1.75  Shutdown Sequencer Preoperational Test (S-03NF03)
 
14.2.12.1.75.1  Objectives
: a. To demonstrate that de-energization of either 4,160-V
 
Class IE load group will start the associated diesel
 
generator,  close the diesel  generator  feeder breaker,
 
actuate the associated group load shed, and actuate the
 
shutdown sequencer. All sequenced components are
 
verified to start within required design times.
 
14.2-103    Rev. 0 WOLF CREEK
: b. To demonstrate that each diesel generator will maintain voltage and frequency within design specifications while
 
supplying the design shutdown loads.
: c. To demonstrate the ability of the emergency 4.16-kV loads to start at maximum and minimum design voltages.
 
14.2.12.1.75.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. Each diesel generator and its associated auxiliaries are available.
: d. All components actuated by the shutdown sequencer are
 
available.
 
14.2.12.1.75.3  Test Method
: a. Class IE 4,160-V load group 1 is de-energized and the
 
following are verified:
: 1. Group 1 load shedder actuates.
: 2. Group 1 diesel generator starts, and its feeder
 
breaker closes.
: 3. Group 1 shutdown sequencer is actuated, and
 
associated components are sequenced. Components
 
are verified to actuate within the required design
 
times.
: b. Class IE 4,160-V load group 2 is de-energized and the
 
following are verified:
: 1. Group 2 load shedder actuates.
: 2. Group 2 diesel generator starts, and its feeder
 
breaker closes.
: 3. Group 2 shutdown sequencer is actuated, and
 
associated components are sequenced. Components
 
are verified to actuate within the required design
 
times.
 
14.2-104    Rev. 0 WOLF CREEK
: c. Emergency 4.16-kV loads are started while their respective diesel generators are supplying:
: 1. Minimum rated voltage
: 2. Maximum rated voltage
: d. The ability of each diesel generator to maintain voltage
 
and frequency within the design specifications while
 
supplying the design shutdown loads is verified.
 
14.2.12.1.75.4  Acceptance Criteria
: a. De-energization of Class IE 4,160-V load group 1
 
initiates the following, in accordance with system design:
: 1. Group 1 diesel generator starts, and its feeder
 
breaker closes.
: 2. Group 1 shutdown sequencer actuates, and associated
 
components are sequenced. Components actuate
 
within required design times.
: 3. Group 1 load shedder actuates.
: b. De-energization of Class IE 4,160-V load group 2
 
initiates the following, in accordance with system
 
design:
: 1. Group 2 diesel generator starts, and its feeder breaker closes.
: 2. Group 2 shutdown sequencer actuates, and associated
 
components are sequenced. Components actuate
 
within required design times.
: 3. Group 2 load shedder actuates.
: c. The emergency 4.16-kV loads start and reach rated speed
 
within design times, with minimum and maximum design
 
voltage.
: d. Each diesel generator maintains voltage and frequency
 
within design specifications, while supplying the design
 
shutdown loads.
 
14.2.12.1.76  480-V  (Class  IE)  System  Preoperational    Test
 
              (S-03NG01)
 
14.2.12.1.76.1  Objectives
 
To demonstrate that the 480-V Class IE load centers can be energized  from
 
their normal and alternate sources and verify the 
 
14.2-105    Rev. 0 WOLF CREEK operability of system breaker protective interlocks. Proper operation of system instrumentation and controls is also verified.
 
14.2.12.1.76.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2.12.1.76.3  Test Method
: a. The 480-V Class IE load centers are energized from their
 
normal source, and voltages are recorded.
: b. The 480-V Class IE load centers are energized from their
 
alternate source, and voltages are recorded.
: c. System breakers are operated, and breaker interlocks
 
verified.
 
14.2.12.1.76.4  Acceptance Criteria
: a. The voltage for each 480-V Class IE load center, when
 
supplied from its normal source, is within design
 
specifications.
: b. The voltage for each 480-V Class IE load center, when
 
supplied from its alternate source, is within design specifications.
: c. System breaker interlocks operate in accordance with the
 
system design.
 
14.2.12.1.77  480-V Class IE System (ESW) Preoperational Test
 
              (SU3-NG02).
 
14.2.12.1.77.1  Objectives
 
To demonstrate that the nonpower block 480-V Class IE MCC can be energized from
 
their normal source and to verify their bus voltage phase sequence. Proper
 
operation of system instrumentation and controls is also verified.
 
14.2.12.1.77.2  Prerequisites
: a. Required component testing and instrument calibration
 
are completed.
 
14.2-106    Rev. 0 WOLF CREEK
: b. Required electrical power supplies and control circuits are operational.
 
14.2.12.1.77.3  Test Method
 
The nonpower block 480-V Class IE MCC are energized, voltages are recorded, and
 
phase sequence is verified.
 
14.2.12.1.77.4  Acceptance Criteria
: a. The voltage for each nonpower block 480-V Class IE MCC
 
is within design specification.
: b. The bus voltage phase sequence of the nonpower block
 
480-V Class IE MCC is in accordance with design.
14.2.12.1.78  125-V (Class IE) DC System Preoperational Test
 
              (S-03NK01)
 
14.2.12.1.78.1  Objectives
 
To demonstrate the ability of the batteries and chargers to provide power
 
during normal operations and the battery to provide power during abnormal
 
conditions. The battery chargers' ability to recharge their respective battery
 
is also demonstrated. Proper operation of the system instrumentation and
 
controls is also verified.
 
14.2.12.1.78.2  Prerequisites
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. Ventilation for the battery rooms is available.
 
14.2.12.1.78.3  Test Method
: a. Each battery is discharged, using a test load at the
 
design duty cycle discharge rate.
: b. Each battery is fully discharged to determine its
 
capacity factor.
: c. Each battery charger will charge its respective battery
 
to normal conditions, after the battery has undergone a
 
design duty cycle, while simultaneously supplying power
 
at a rate equivalent to the design emergency loading.
 
14.2-107    Rev. 0 WOLF CREEK 14.2.12.1.78.4  Acceptance Criteria
: a. Each battery is capable of maintaining output voltage
 
above the design minimum, during a design duty cycle.
: b. Each battery has a capacity factor greater than or equal
 
to design.
: c. The battery chargers are able to recharge the batteries
 
to normal conditions, after the battery has undergone a
 
design duty cycle, while simultaneously supplying power
 
at a rate equivalent to the design emergency loading.
 
14.2.12.1.79  Instrument AC System (Class IE) Preoperational Test
 
              (S-03NN01) 14.2.12.1.79.1  Objectives
 
To demonstrate that the 120-V Class IE ac distribution panel- boards can be fed
 
from their normal source inverters and from their backup source transformers by
 
manual transfer. The operability of system instrumentation and controls,
 
including breaker protective interlocks, is also verified.
 
14.2.12.1.79.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
14.2.12.1.79.3  Test Method
: a. The 120-V Class IE ac distribution panelboards are
 
energized from their normal source inverters, and
 
panelboard voltages are recorded.
: b. The 120-V Class IE ac distribution panelboards are
 
energized from their backup source transformers by
 
manual transfer, and panelboard voltages are recorded.
: c. The system breakers are operated, and breaker interlocks
 
are verified.
 
14.2.12.1.79.4  Acceptance Criteria
: a. Each 120-V Class IE ac distribution panelboard voltage,
 
when supplied from the normal source inverters of the
 
panelboards, is within design specifications.
 
14.2-108    Rev. 0 WOLF CREEK
: b. Each 120-V Class IE ac distribution panelboard voltage, when supplied from the backup source transformers, is
 
within design specifications.
: c. System breaker interlocks operate in accordance with system design.
 
14.2.12.1.80  Engineered Safeguards (NSSS) Preoperational Test
 
              (SU3-SA01)
 
14.2.12.1.80.1  Objectives
: a. To demonstrate the ability of the NSSS to initiate
 
safety injection, containment isolation, containment
 
spray actuation, main feedwater isolation, and steam line isolation signals on receipt of the associated input signals.
: b. To verify NSSS ESFAS loop response times.
: c. To demonstrate the ability of each solid-state
 
protection system test panel to adequately test the
 
associated NSSS ESFAS and reactor protection logic
 
trains.
: d. To demonstrate the coincidence and redundancy of the
 
NSSS ESFAS.
: e. To verify the operability of ESFAS block and permissive
 
interlocks.
14.2.12.1.80.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies are operational.
 
14.2.12.1.80.3  Test Method
: a. The ability of the NSSS ESFAS to actuate safety
 
injection,  containment  isolation,  containment spray
 
actuation, main feedwater isolation, and steam line
 
isolation signals on receipt of the required coincidence
 
of the following input signals for each redundant
 
channel is verified:
 
          . High steam line pressure rate
 
          . Low steam line pressure
 
          . Low pressurizer pressure
 
14.2-109    Rev. 0 WOLF CREEK
          . High containment pressure (Hi-1, Hi-2, and Hi-3)
          . High-high steam generator level
 
          . Low Tavg
 
          . Low-low steam generator water level
: b. Input signals are initiated, and loop response times are
 
verified.
: c. The ability of each solid-state protection system test
 
panel to test the NSSS ESFAS logic trains is verified.
: d. ESFAS block and permissive interlocks are verified.
 
14.2.12.1.80.4  Acceptance Criteria
: a. The NSSS ESFAS actuates safety injection, containment isolation, containment spray actuation, main feedwater
 
isolation, and steam line isolation signals when their
 
associated input signals are received from the following
 
signals for each applicable channel:
 
          . High steam line pressure rate
 
          . Low steam line pressure
 
          . Low pressurizer pressure
 
          . High containment pressure (Hi-1, Hi-2, and Hi-3)
 
          . High-high steam generator level
 
          . Low Tavg
 
          . Low-low steam generator water level
: b. NSSS ESFAS loop response times are within design specifications.
: c. ESFAS block and permissive interlocks operate in
 
accordance with system design.
 
14.2.12.1.81  Engineered  Safeguards  (BOP)  Preoperational Test
 
              (SU3-SA02)
 
14.2.12.1.81.1  Objectives
: a. To demonstrate the operability of the BOP ESFAS to
 
initiate containment purge isolation, control room
 
ventilation isolation, fuel building ventilation
 
isolation, auxiliary feedwater pump actuation, auxiliary
 
feedwater suction valve switchover to essential service
 
water (ESW), and steam generator blowdown and sample
 
isolation signals on receipt of the associated input
 
signals.
 
14.2-110    Rev. 0 WOLF CREEK
: b. To verify BOP ESFAS loop response times.
: c. To demonstrate the ability of the BOP ESFAS test panel
 
to adequately test the associated BOP ESFAS logic
 
trains.
: d. To demonstrate the coincidence and redundancy of the BOP
 
ESFAS.
 
14.2.12.1.81.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies are operational.
14.2.12.1.81.3  Test Method
: a. The ability of the BOP ESFAS to actuate containment
 
purge isolation, control room ventilation isolation,
 
fuel building ventilation isolation, auxiliary feedwater
 
pump actuation, auxiliary feedwater suction valve
 
switchover to ESW, and steam generator blowdown and
 
sample isolation signals on receipt of the required
 
coincidence of the following input signals for each
 
redundant channel is verified.
 
o    Containment isolation (phase A)
 
o    High atmospheric radiation
 
o    High chlorine concentration o    Loss of main feedwater flow o    Low-low steam generator level
 
o    Loss of offsite power
 
o    Low feedwater pump suction pressure
 
o    Safety injection
: b. Input signals are initiated, and loop response times are
 
verified.
: c. The ability of the BOP ESFAS test panel to test the BOP
 
ESFAS logic trains is verified.
 
14.2.12.1.81.4  Acceptance Criteria
: a. The BOP ESFAS actuates containment purge isolation,
 
control room ventilation isolation, fuel building
 
ventilation isolation, auxiliary feedwater pump
 
actuation, auxiliary feedwater suction valve switchover
 
to ESW, and 
 
14.2-111    Rev. 0 WOLF CREEK steam generator blowdown and sample isolation signals
 
when their associated input signals are received from
 
the following signals for each applicable channel:
 
o    Containment isolation (phase A)
 
o    High atmospheric radiation
 
o    High chlorine concentration
 
o    Loss of main feedwater flow
 
o    Low-low steam generator level
 
o    Loss of offsite power
 
o    Low feedwater pump suction pressure
 
o    Safety injection
: b. BOP ESFAS loop response times are within design specifications.
 
14.2.12.1.82  Engineered Safeguards Verification Test (SU3-SA03)
 
14.2.12.1.82.1  Objectives
 
To demonstrate the proper response of actuated components resulting from the
 
following safety signals:  Safety injection, containment spray actuation, main
 
feedwater isolation, steam line isolation, containment isolation, containment
 
purge isolation, control room ventilation isolation, fuel building ventilation
 
isolation, auxiliary feedwater pump actuation, auxiliary feedwater suction
 
valve switch over to ESW, and steam generator blowdown and sample isolation.
 
14.2.12.1.82.2 Prerequisites
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power sources and control circuits
 
are operational.
: c. Components actuated by the NSSS and BOP ESFAS are
 
available.
 
14.2.12.1.82.3  Test Method
 
NSSS and BOP ESFAS signals are initiated manually and the proper response and
 
response times of the actuated components are verified.
 
14.2-112    Rev. 0 WOLF CREEK 14.2.12.1.82.4  Acceptance Criteria
 
Components required to actuate on receipt of safety signals respond properly in
 
accordance with design specifications and within the times specified by design
 
requirements.
 
14.2.12.1.83  Reactor Protection System Logic Test (S-03SB01)
 
14.2.12.1.83.1  Objectives
: a. To demonstrate the ability of the reactor protection
 
system to initiate a reactor trip on input of the
 
associated input signals.
: b. To verify reactor protection loop response times.
: c. To verify the operability of the reactor protection
 
system block and permissive interlocks.
: d. To demonstrate the coincidence, redundancy, and fail
 
safe (power loss) design of the reactor protection
 
system.
 
14.2.12.1.83.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
14.2.12.1.83.3  Test Method
: a. The ability of the reactor protection system to initiate
 
a reactor trip on receipt of the proper coincidence of
 
the following trip signals for each redundant channel is
 
verified:
 
o  Source range high neutron flux
 
o  Intermediate range high neutron flux
 
o  Power range high neutron flux (low setpoint and
 
high setpoint)
 
o  Power range high positive neutron flux rate
 
o  Power range high negative neutron flux rate o  Overtemperature  T          o  Overpower  T          o  Low primary coolant flow o  Reactor coolant pump bus undervoltage
 
o  Reactor coolant pump bus underfrequency 
 
14.2-113    Rev. 0 WOLF CREEK o  High pressurizer pressure o  Low pressurizer pressure
 
o  High pressurizer level
 
o  Safety injection signal
 
o  Turbine trip signal
: b. Loop response times are measured for the above listed
 
trip signals.
: c. Reactor protection system block and permissive
 
interlocks are verified.
: d. Power is isolated from the system, and the safe failure
 
of the system is verified.
 
14.2.12.1.83.4  Acceptance Criteria
: a. The reactor protection system initiates a reactor trip
 
on receipt of the proper coincidence of the following
 
signals for each applicable channel:
 
o  Source range high neutron flux
 
o  Intermediate range high neutron flux
 
o  Power range high neutron flux (low setpoint and
 
high setpoint)
 
o  Power range high positive neutron flux rate
 
o  Power range high negative neutron flux rate o  Overtemperature  T          o  Overpower  T          o  Low primary coolant flow o  Reactor coolant pump bus undervoltage o  Reactor coolant pump bus underfrequency
 
o  High pressurizer pressure
 
o  Low pressurizer pressure
 
o  High pressurizer level
 
o  Safety injection signal
 
o  Turbine trip signal
: b. Loop response times for the following trip signals are
 
within design limits.
 
o  Power range high neutron flux (low setpoint and
 
high setpoint)
 
o  Power range high negative neutron flux rate o  Overtemperature  T          o  Overpower  T          o  Low primary coolant flow o  Reactor coolant pump bus undervoltage
 
o  Reactor coolant pump bus underfrequency 
 
14.2-114    Rev. 0 WOLF CREEK o  High pressurizer pressure o  Low pressurizer pressure
: c. Reactor protection system block and permissive
 
interlocks operate in accordance with system design.
: d. The reactor protection system functions in accordance
 
with system design on a loss of power.
 
14.2.12.1.84  Primary Sampling System Preoperational Test
 
              (S-03SJ01)
 
14.2.12.1.84.1  Objectives
: a. To set sample panels' flow rates and to verify the operability of the sample system containment isolation valves. Proper operation of system instrumentation and
 
controls is also verified.
: b. To verify that the post-accident sampling system (PASS)
 
containment isolation valves operate properly.
 
14.2.12.1.84.2  Prerequisites
: a. Required component testing instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operable.
: c. Plant conditions are established, and systems are available, as necessary, to facilitate drawing samples
 
from the sample points.
: d. The component cooling water system is available to
 
provide cooling water to the auxiliary building sample
 
station.
: e. The chemical and volume control system is available to
 
receive discharge from the nuclear sampling station.
: f. The chemical and detergent waste system is available to
 
receive discharge from the nuclear sampling station.
 
14.2.12.1.84.3  Test Method
: a. Sample panel flows are adjusted, and flow data are
 
recorded.
 
14.2-115    Rev. 0 WOLF CREEK
: b. Operability of the sample containment isolation valves is verified, including their response to an isolation
 
signal. Valve operating times are recorded.
 
14.2.12.1.84.4  Acceptance Criteria
: a. The sample containment isolation valves close on receipt
 
of an isolation signal.
: b. The sample containment isolation valves' closure times
 
are within design specifications.
 
14.2.12.1.85  Process Radiation Monitoring System Preoperational
 
Test (S-03SP01)
 
14.2.12.1.85.1  Objectives
 
To demonstrate the operation of the process radiation monitors and to verify
 
the ability of the process radiation monitoring system to provide alarm and
 
isolation signals, as applicable, upon receipt of high radiation signals. 
 
Operability of the radioactivity monitoring control room microprocessor is also
 
verified.
 
14.2.12.1.85.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operable.
14.2.12.1.85.3  Test Method
: a. The check source for each monitor is remotely
 
positioned, and the actuation of each monitor and the
 
operability of its associated alarms and isolation
 
signals are verified.
: b. Operability of the radioactivity monitoring control room
 
microprocessor is verified.
 
14.2.12.1.85.4  Acceptance Criteria
 
The process radiation monitoring system provides alarm and isolation signals,
 
in accordance with system design specifications.
 
14.2-116    Rev. 0 WOLF CREEK 14.2.12.1.86  Power Conversion and ECCS Thermal Expansion Test (SU3-0004)
 
14.2.12.1.86.1  Objective
 
To demonstrate snubber operability on all safety-related systems whose
 
operating temperature exceeds 250 F.
 
14.2.12.1.86.2  Prerequisites
: a. Preservice examinations as specified in the Tedesco
 
letter to KG&E dated 2/10/81 have been completed on the
 
systems being checked within the last 6 months.
: b. Other required component testing and instrument calibration are completed.
: c. Required electrical power supplies and control circuits
 
are operational.
: d. Preoperational testing is in progress.
 
14.2.12.1.86.3  Test Method
: a. During initial system heatup and cooldown, at specified
 
temperature intervals, verify the expected snubber
 
movement for any system which attains operating
 
temperature.
: b. For those systems which do not attain operating temperature, verify by observation and/or calculation that the snubber will accommodate the projected thermal
 
movement.
: c. Observe snubber swing clearances at specified heat-up
 
and cooldown intervals.
 
14.2.12.1.86.4  Acceptance Criteria
: a. The expected snubber movement for any system that
 
attains operating temperature is within design
 
specifications.
: b. The expected snubber movement determined by observation
 
and/or calculation for any system that does not attain
 
operating temperature is within design specifications.
: c. Snubber swing clearance observed at specified heatup and
 
cooldown intervals is within design specifications.
 
14.2-117    Rev. 0 WOLF CREEK 14.2.12.1.87  Power Conversion and ECCS Systems Dynamic Test (S-030005)
 
14.2.12.1.87.1  Objectives
 
To demonstrate during specified transients that the systems' monitored points
 
respond in accordance with design.
 
14.2.12.1.87.2  Prerequisites
: a. Reference points for measurement of the systems are
 
established.
: b. Hot functional testing is in progress.
: c. All subject systems are available for the specified dynamic operations.
: d. Required instrument calibration is complete.
 
14.2.12.1.87.3  Test Method
: a. The systems are aligned for the specified dynamic
 
operation.
: b. The specified dynamic event of pump operation, valve
 
operation, etc., is initiated, and the system is
 
monitored for response.
 
14.2.12.1.87.4  Acceptance Criteria
: a. The total stress shall not exceed applicable code
 
limits.
 
14.2.12.1.88  HEPA Filter Test (SU3-0006).
 
14.2.12.1.88.1  Objectives
 
To demonstrate the leaktightness and particulate removal efficiency of all HEPA
 
filters and to verify the leaktightness of their associated charcoal adsorbers.
 
14.2.12.1.88.2  Prerequisites
: a. The ventilation systems containing HEPA filters and
 
charcoal adsorbers have been air balanced and are
 
operational and available to support this test.
 
14.2-118    Rev. 0 WOLF CREEK
: b. Required electrical power supplies and control circuits are operational.
: c. Required instrument calibration is complete.
 
14.2.12.1.88.3  Test Method
: a. HEPA filters are inplace tested with cold poly-dispersed
 
DOP, in accordance with the procedures set forth in ANSI
 
N510.
: b. Charcoal adsorbers are inplace tested with a suitable
 
refrigerant, in accordance with the procedures set forth
 
in ANSI N510.
 
14.2.12.1.88.4  Acceptance Criteria
: a. The airflow of each filter adsorber unit is equal to the
 
design flow.
: b. Air flow distribution downstream of each HEPA filter is
 
within 20 percent of the average velocity through the
 
unit.
: c. HEPA DOP penetration is less than one percent at the
 
design air flow.
: d. Charcoal adsorber bypass leakage is less than .05
 
percent at the design air flow.
 
14.2.12.1.89  Cooldown from Hot Standby External to the Control Room (S-030008)
 
14.2.12.1.89.1  Objectives
 
To demonstrate, using a plant procedure, the potential capability to cooldown
 
the plant from the hot standby to the cold shutdown condition, using
 
instrumentation and controls external to the control room verifying that:
: a. The reactor coolant temperature and pressure can be
 
lowered to permit the operation of the residual heat
 
removal (RHR) system.
: b. The RHR system can be operated and controlled.
: c. The reactor coolant temperature can be  reduced  50 F,          using the RHR system, without exceeding technical specification limits.
 
14.2-119    Rev. 0 WOLF CREEK 14.2.12.1.89.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The plant is in a hot standby condition.
: d. The authority and responsibility of the control room
 
observers has been established and is specified in this
 
procedure.
 
14.2.12.1.89.3  Test Method
: a. The plant is cooled from hot standby, RHR is initiated,
 
and  a  >
50&deg;F cooldown is performed with the RHR system transferring heat to the ultimate heat sink, using instrumentation and controls external to the control room.
: b. All actions performed by the control room observers are documented within this procedure for use in evaluating
 
their impact on the test results.
 
14.2.12.1.89.4  Acceptance Criteria
 
The following actions are capable of being performed, external to the control
 
room:
: a. The reactor coolant temperature and pressure can be
 
lowered to permit the operation of the RHR system.
: b. The reactor coolant temperature can be  reduced  50 F,          using the RHR system, without exceeding technical specification limits.
 
14.2.12.1.90  Compressed Gas Accumulator Testing (S-030009)
 
14.2.12.1.90.1  Objectives
 
To demonstrate the ability of the auxiliary feedwater control valve/mainsteam
 
atmospheric relief valve and main feedwater control valve accumulators to
 
provide the design backup supply of compressed gas for continued design valve
 
operation following a loss of the normal motive source.
 
14.2-120    Rev. 0 WOLF CREEK 14.2.12.1.90.2  Prerequisites
 
Required component testing, instrument calibration and system flushing/cleaning
 
are complete.
 
14.2.12.1.90.3  Test Method
 
The accumulators are isolated from the compressed gas supply header and the
 
associated valves are operated to demonstrate the ability of the accumulators
 
to provide design motive force for the required valve cycles.
 
14.2.12.1.90.4  Acceptance Criteria
 
The auxiliary feedwater control valve/mainsteam atmospheric relief valve, and
 
main feedwater control valve accumulators provide the design backup supply of compressed gas to their associated valves.
 
14.2.12.2  Nonsafety-Related Preoperational Test Procedures The following sections are the test abstract for each nonsafety- related
 
preoperational test. Table 14.2-2 provides an index of these tests.
 
14.2.12.2.1  Turbine Trip Test (S-04AC02)
 
14.2.12.2.1.1  Objectives
: a. To demonstrate the ability of the turbine trip and
 
monitoring system to initiate a turbine trip on input of
 
the associated input signals.
: b. To demonstrate the response of the moisture separator
 
reheater drain valves, feedwater heater extraction check valves, turbine main stop valves, turbine main stop valve above seat drain valves, turbine control valves,
 
turbine control valve above seat drain valves,
 
intermediate stop valves, main steamline drain valves,
 
startup drain valves, and intercept valves to a turbine
 
trip signal.
: c. To demonstrate that a turbine trip signal initiates a
 
reactor trip signal.
: d. To demonstrate that the turbine main stop valves
 
operating times are within design specifications.
 
14.2-121    Rev. 0
 
WOLF CREEK 14.2.12.2.1.2  Prerequisites
: a. Required component testing and instrument calibration is
 
complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The main turbine control oil and lube oil systems are
 
available to provide oil to the turbine auxiliaries.
: d. The compressed air system is available to provide air to
 
system air-operated valves.
 
14.2.12.2.1.3  Test Method
: a. The ability of the turbine trip and monitoring system to
 
initiate a turbine trip signal on receipt of each of the
 
following input signals is verified:
 
o  Manual trip pushbutton depressed
 
o  Manual trip handle pulled
 
o  Generator trip (EHC vital trip)
 
o  Generator trip (unit trip)
 
o  Reactor trip
 
o  Loss of stator coolant
 
o  Low lube oil pressure
 
o  Loss of EHC 125 V dc power with turbine speed
 
below 75 percent
 
o  High turbine vibration o  High exhaust hood temperature o  Low hydraulic fluid pressure
 
o  Moisture separator high level
 
o  Low bearing oil pressure
 
o  Low condenser vacuum
 
o  Excessive thrust bearing wear
 
o  Backup overspeed (Electrical)
 
o  Loss of EHC 24-volt dc power
: b. A turbine trip signal is initiated, and the response of
 
the following valves is verified:
 
o  Moisture separator reheater drain valves
 
o  Feedwater heater extraction check valves
 
o  Turbine main stop valves
 
o  Turbine control valves
 
o  Intermediate stop valves
 
o  Turbine intercept valves
 
o  Startup drain valves
 
o  Main steam line drain valves
 
14.2-122    Rev. 0 WOLF CREEK o  Turbine main stop valve above seat drain valves o  Turbine control valve above seat drain valves
: c. A turbine trip signal is initiated, and a reactor trip
 
input signal is verified.
 
14.2.12.2.1.4  Acceptance Criteria
: a. The turbine trip and monitoring system initiates a
 
turbine trip on receipt of each of the following
 
signals:
 
o  Manual trip pushbutton depressed
 
o  Manual trip handle pulled
 
o  Generator trip (EHC vital trip) o  Generator trip (unit trip) o  Reactor trip
 
o  Loss of stator coolant
 
o  Low lube oil pressure
 
o  Loss of EHC 125 V dc power with turbine speed
 
below 75 percent
 
o  High turbine vibration
 
o  High exhaust hood temperature
 
o  Low hydraulic fluid pressure
 
o  Moisture separator high level
 
o  Low bearing oil pressure
 
o  Low condenser vacuum
 
o  Excessive thrust bearing wear
 
o  Backup overspeed (electrical)
 
o  Loss of EHC 24-volt dc power
: b. The following valves open on receipt of a turbine trip
 
signal:
 
o  Turbine main stop valve above seat drain valves
 
o  Turbine control valve above seat drain valves
 
o  Main steam line drain valves
 
o  Moisture separator reheater drain valves
 
o  Startup drain valves
: c. The following valves close on receipt of a turbine trip
 
signal:
 
o  Low pressure heater extraction check valves
 
o  Main stop valves
 
o  Turbine control valves
 
o  Intercept valves
 
o  Intermediate stop valves
 
14.2-123    Rev. 0 WOLF CREEK
: d. A turbine trip signal initiates a reactor trip signal.
: e. The turbine main stop valves operating times are within
 
design specifications.
 
14.2.12.2.2  Turbine System Cold Test (S-04AC03)
 
14.2.12.2.2.1  Objectives
: a. To demonstrate the operability of the turning gear and
 
associated control circuits.
: b. To demonstrate the operability of the electro-hydraulic
 
control system.
 
14.2.12.2.2.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The main turbine control oil and lube oil systems are
 
available to supply the turbine auxiliaries.
 
14.2.12.2.2.3  Test Method
: a. The operability of the turning gear and associated
 
control circuits is verified.
: b. A turbine simulator is utilized to verify the ability of
 
the electro-hydraulic control system to perform its
 
control functions.
 
14.2.12.2.2.4  Acceptance Criteria
: a. The turning gear motor trips on loss of bearing oil
 
pressure, loss of all bearing lift pumps, or closure of
 
the main transformer switchyard breaker.
: b. The turbine control and intercept valves close on a
 
power load unbalance signal.
: c. The turbine load set is run back on a reactor overtemperature T signal when in the manual mode.
: d. The turbine load set is run back on a reactor overpower T signal when in the manual mode.
 
14.2-124    Rev. 0 WOLF CREEK
: e. The turbine load is set back on a loss of circulating water pump signal.
: f. Turbine loading is inhibited on a C-16 control interlock
 
signal.
 
14.2.12.2.3  Condensate System Preoperational Test (S-04ADOl)
 
14.2.12.2.3.1  Objectives
 
To demonstrate the condensate pumps' operating characteristics and verify the
 
operation of system valves and associated control circuits. The operability of
 
the condensate storage and transfer system and associated components is also
 
verified.
 
14.2.12.2.3.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The feedwater system is available to receive flow from
 
the condensate pump discharge header.
: d. The demineralized water system is available to provide
 
water to the condensate pump seals and a source of
 
makeup to the condensate storage tank.
: e. The condensate storage tank is available to provide makeup to the condenser hotwell.
: f. The closed cooling water system is available to provide
 
cooling water to the condensate pump motor bearing oil
 
coolers.
 
14.2.12.2.3.3  Test Method
: a. Condensate pumps are operated, and performance
 
characteristics are verified.
: b. The response of each condensate pump to a condenser low-
 
low level trip signal is verified.
: c. The operability of the condensate pump recirculation
 
valves is verified.
 
14.2-125    Rev. 0 WOLF CREEK 14.2.12.2.3.4  Acceptance Criteria
: a. The operating characteristics of the condensate pumps
 
are within design specifications.
: b. Each condensate pump will receive a trip signal on a 2/3
 
condenser low-low level signal.
: c. Each condensate pump recirculation valve operates in
 
accordance with design specifications.
 
14.2.12.2.4  Secondary  Vent and  Drain System  Preoperational
 
Test (S-04AF01)
 
14.2.12.2.4.1  Objectives
: a. To demonstrate the operating characteristics of the
 
heater drain pumps.
: b. To demonstrate the operability of system valve and pump
 
control circuits.
 
14.2.12.2.4.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The compressed air system is available to the system air-operated valves.
: d. The closed cooling water system is available to supply
 
cooling water to the heater drain pumps.
 
14.2.12.2.4.3  Test Method
: a. The heater drain pumps are operated, and performance
 
characteristics are verified.
: b. The operability of system valve and pump control
 
circuits is verified.
 
14.2.12.2.4.4  Acceptance Criteria
 
The operating characteristics of the heater drain pumps are within design
 
specifications.
 
14.2-126    Rev. 0 WOLF CREEK 14.2.12.2.5  Condensate and Feedwater Chemical Feed System Preoperational Test (S-04AQ01)
 
14.2.12.2.5.1  Objectives
: a. To demonstrate the operating characteristics of the 
 
condensate oxygen control chemical addition pumps, condensate pH control chemical addition pumps, condensate oxygen control chemical circulating pumps, condensate pH control chemical circulating pumps, feedwater chemical addition pumps, and feedwater chemical addition circulating pump and  verify the operation of the associated control circuits.
: b. To demonstrate the operability of the drum dispensing
 
pumps.
 
14.2.12.2.5.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The demineralized water storage and transfer system is
 
available to provide a source of demineralized water to the oxygen and pH control chemical supply and mixing tanks.
: d. The compressed air system is available to provide air to
 
the drum dispensing pumps.
: e. The service gas system is available to provide a source
 
of nitrogen to the oxygen and pH control chemical supply, measuring, and mixing tanks.
 
14.2.12.2.5.3  Test Method
: a. System pumps are operated, and performance characteristics are verified.
: b. The response of the condensate oxygen control chemical circulating pumps, condensate pH control chemical circulating pumps, and the feedwater chemical addition feed pumps to a low level in their associated tank is verified.
 
14.2-127    Rev. 12 WOLF CREEK 14.2.12.2.5.4  Acceptance Criteria
: a. The operating characteristics of the condensate
 
oxygen control chemical addition pumps, condensate pH control chemical addition pumps, condensate oxygen control chemical circulating pumps, condensate ph control chemical circulating pumps, feedwater chemical addition pumps, feedwater chemical addition circulating pump, and the drum dispensing pumps are within design specifications.
: b. The condensate oxygen control chemical circulating pumps, condensate pH control chemical circulating pumps, feedwater 
 
chemical addition feed pumps, and the feedwater chemical addition circulating pump trip on a low level signal from their associated tanks.
 
14.2.12.2.6  Reactor  Makeup Water System  Preoperational  Test
 
            (S-04BL01)
 
14.2.12.2.6.1  Objectives
: a. To demonstrate the operating characteristics of the
 
reactor makeup water transfer pumps and verify that the
 
associated control circuits are functioning properly.
: b. To demonstrate the operation of the system automatic
 
valves, including the response of the reactor makeup
 
water system containment supply valve to a CIS.
 
14.2.12.2.6.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The demineralized water storage and transfer system is
 
available to provide a source of water to the reactor
 
makeup water storage tank.
 
14.2.12.2.6.3  Test Method
: a. The reactor makeup water transfer pumps are operated, and pump operating data are recorded.
: b. Reactor makeup water transfer pumps and system automatic
 
valves control logics are verified, including their
 
response to safety signals.
 
14.2-128    Rev. 12 WOLF CREEK
: c. The reactor makeup water containment supply valve is operated under flow conditions and operating times
 
recorded.
 
14.2.12.2.6.4  Acceptance Criteria
: a. The operating characteristics of the reactor makeup
 
water transfer pumps are within design specifications.
: b. Each reactor makeup water transfer pump trips on receipt
 
of a reactor makeup water storage tank low level signal.
: c. Each reactor makeup water transfer pump starts, after a
 
time delay, with the other pump running and the receipt
 
of a low header pressure signal.
: d. The reactor makeup water containment supply valve
 
closure time is within design specifications.
: e. The reactor makeup containment supply valve closes on
 
receipt of a CIS.
 
14.2.12.2.7  Condenser Air Removal System Preoperational Test
 
            (S-04CG01)
 
14.2.12.2.7.1  Objectives
: a. To demonstrate the operation of the condenser air
 
removal portion of the turbine building HVAC system
 
motoroperated dampers, including automatic operation on a safety injection signal.
: b. To demonstrate the capacities of the condenser air
 
removal filtration fans and verify the operation of
 
their associated control circuits.
: c. To demonstrate the operability of the condenser air
 
removal system vacuum pumps, control valves, and their
 
associated control circuits.
 
14.2.12.2.7.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2-129    Rev. 0 WOLF CREEK
: c. The condenser air removal filtration system portion of the turbine building HVAC system is available to support
 
this test.
: d. The condensate storage tank is available to provide a source of water to the vacuum pump seal water
 
reservoirs.
: e. The service water system is available to provide cooling
 
water to the mechanical vacuum pump seal water coolers.
 
14.2.12.2.7.3  Test Method
: a. The condenser air removal filtration fans are operated,
 
and fan capacities are verified.
: b. Operation of the condenser air removal filtration
 
dampers is verified, including their response to a
 
safety injection signal.
: c. The ability of the mechanical vacuum pumps to reduce
 
condenser pressure during startup operation is verified.
: d. Operability of the mechanical vacuum pumps and their
 
associated control valves' control circuits is verified,
 
including their response to a low condenser vacuum
 
signal.
 
14.2.12.2.7.4  Acceptance Criteria
: a. The condenser air removal filtration fans' capacities are within design specifications.
: b. The condenser air removal filtration dampers close on
 
receipt of a safety injection signal.
: c. The rate at which the mechanical vacuum pumps reduce
 
condenser pressure is within design specifications.
: d. The mechanical vacuum pumps start automatically on
 
receipt of a low condenser vacuum signal.
 
14.2.12.2.8  Circulating Water System Preoperational Test (SU4-
 
DA01)
 
14.2.12.2.8.1  Objective
: a. To demonstrate the operating characteristics of the
 
circulating water pumps,  water box venting pumps,  and 
 
14.2-130    Rev. 0 WOLF CREEK the condenser drain pump and verify the operation of their associated control circuits.
: b. To demonstrate by operational test that the circulating
 
water pump discharge valves operating times are within design specifications.
: c. To demonstrate that the gland water system flow to the
 
circulating water pumps is within design specifications.
 
14.2.12.2.8.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are completed.
: b. Required electrical power supplies and control circuits are operational.
: c. The circulatng water system and condenser are available
 
to receive flow from the circulating water pumps.
 
14.2.12.2.8.3  Test Method
: a. The circulating water pumps, water box venting pumps,
 
and the condenser drain pump are operated and pump
 
operating data is recorded.
: b. The response of the circulating water pumps and the
 
condenser drain pump to control signals is verified.
: c. Circulating water pump discharge valve operating times are recorded.
 
14.2.12.2.8.4  Acceptance Criteria
: a. The circulating water pumps operating characteristics
 
are within design specifications.
: b. The water box venting pumps operating characteristics
 
are within design specifications.
: c. The condenser drain pump operating characteristics are
 
within design specifications
: d. The condenser drain pump stops on receipt of a standpipe
 
low-level signal.
: e. Each circulating water pump trips on receipt of a two
 
out of three condenser pit high level signal.
 
14.2-131    Rev. 0 WOLF CREEK
: f. Low gland seal water pressure or low gland seal flow will prevent start of the circulating water pumps.
: g. The gland seal water flow to each circulating water pump
 
is within design specifications.
: h. The operating times of the circulating water pump
 
discharge valves are within design specifications.
 
14.2.12.2.9  Service Water System Preoperational Test (S-04EA01).
 
14.2.12.2.9.1  Objectives
: a. To demonstrate the capability of the service water
 
system and essential service water system to provide rated cooling water flow during the normal and normal-shutdown modes of operation to their respective loads.
: b. To  demonstrate the operating characteristics of the
 
Service Water (SW) Pumps.
: c. To verify proper operation of site service water system
 
controls and instrumentation.
 
14.2.12.2.9.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The essential service water system has been flow
 
balanced in the LOCA mode.
: d. Site system controls and instruments are calibrated.
: e. The SW system is available to receive flow from the SW
 
pumps.
 
14.2.12.2.9.3  Test Method
: a. Service water and essential service water system flows
 
are verified in the normal and normal-shutdown modes.
 
          (The service water pumps provide the motive force.)
: b. The SW pumps are operated and pump operating data is
 
recorded.
 
14.2-132    Rev. 0 WOLF CREEK 14.2.12.2.9.4  Acceptance Criteria
: a. Components supplied by the service water system and
 
essential service water system receive flows that are
 
within design specifications with the system operating in the normal and normal-shutdown modes.
: b. The SW pumps operating characteristics are within design
 
specifications.
 
14.2.12.2.10  Closed Cooling Water  System  Preoperational Test
 
              (S-04EB01)
 
14.2.12.2.10.1  Objectives
: a. To demonstrate the capability of the closed cooling water system to provide cooling water flow to its
 
associated components.
: b. To demonstrate the operating characteristics of the
 
closed cooling water pumps and to verify that the
 
associated instrumentation and controls are functioning
 
properly.
 
14.2.12.2.10.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
 
14.2.12.2.10.3  Test Method
 
Performance characteristics of the closed cooling water pumps and flow data to
 
supplied components are verified.
 
14.2.12.2.10.4  Acceptance Criteria
: a. The performance characteristics of each closed cooling
 
water pump are within design specifications.
: b. Flow to all components supplied by the closed cooling
 
water system is verified.
 
14.2-133    Rev. 0 WOLF CREEK 14.2.12.2.11  Fire Protection System  Preoperational  Test  (SU4-FP03)
 
14.2.12.2.11.1  Objectives
: a. To demonstrate the operating characteristics of the Fire
 
Protection (FP) system jockey pump, motor-driven fire
 
pump and the diesel-driven fire pump and verify the
 
operation of their associated control circuits.
: b. To demonstrate the operability of the diesel oil system,
 
including system instrumentation and controls.
 
14.2.12.2.11.2  Prerequisites
: a. Required component testing, instrument calibration, and system flushing/cleaning are completed.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2.12.2.11.3  Test Method
: a. The jockey pump, the motor-driven fire pump and the
 
diesel-driven fire pump are operated and operating data
 
are recorded.
: b. The response of the motor-driven fire pump and diesel-
 
driven fire pump to automatic start signals are
 
verified.
: c. With the diesel-driven fire pump operating at rated
 
capacity, the capacity of the diesel oil day tank is
 
verified.
 
14.2.12.2.11.4  Acceptance Criteria
: a. The FP pumps operating characteristics are within design
 
specifications.
: b. The motor-driven fire pump and the diesel-driven fire
 
pump automatically start upon receipt of their
 
associated decreasing fire protection system pressure
 
signal.
: c. With the diesel fire pump operating at rated capacity,
 
the capacity of the diesel oil day tank is within design
 
specifications.
 
14.2-134    Rev. 0 WOLF CREEK
: d. With the diesel fire pump operating at rated capacity and upon receipt of a diesel oil day tank low level
 
alarm, the remaining capacity of the diesel oil day tank
 
is within design specifications.
 
14.2.12.2.12  Radwaste Building HVAC System Preoperational Test
 
              (S-04GH01)
 
14.2.12.2.12.1  Objectives
: a. To verify the radwaste building supply and exhaust fans'
 
control circuits, including automatic transfer between
 
exhaust fans.
: b. To demonstrate the fan capacities of the radwaste building supply and exhaust fans, recycle evaporator room fan coil unit, waste evaporator room fan coil unit,
 
control room (solidification) fan coil unit, sample
 
laboratory fan  coil unit,  ground floor fan coil unit,
 
basement floor fan coil unit, SLWS evaporator fan coil
 
unit, and control room fan coil unit, and to verify that
 
the associated instrumentation and controls function
 
properly.
 
14.2.12.2.12.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system air balancing are complete.
: b. Required electrical power supplies and control circuits are operational.
 
14.2.12.2.12.3  Test Method
: a. The radwaste building system fans are operated, and fan
 
capacities are verified.
: b. Operability of the radwaste building supply and exhaust
 
fans' control circuits is verified.
 
14.2.12.2.12.4  Acceptance Criteria
: a. The radwaste building system fan capacities are within
 
design specifications.
: b. The radwaste building supply air unit will not operate
 
unless either radwaste exhaust fan is operating.
 
14.2-135    Rev. 0 WOLF CREEK
: c. A low flow on the operating radwaste building exhaust fan will cause the operating fan to stop and the standby
 
fan to start.
 
14.2.12.2.13  Local Containment Leak Rate Test (SU8-GP01)
 
14.2.12.2.13.1  Objectives
 
To determine the leakage rate of the containment penetrations and the leakage
 
rate of the containment isolation valves.
 
14.2.12.2.13.2  Prerequisites
: a. All containment isolation valves are closed by normal
 
actuation methods.
: b. Associated piping is drained, and vent paths for leakage
 
are established.
: c. Required instrument calibration is complete.
 
14.2.12.2.13.3  Test Method
 
The containment penetrations and containment isolation valves are leak tested
 
by performing type B and type C tests, in accordance with 10 CFR 50, Appendix
 
J.
 
14.2.12.2.13.4  Acceptance Criteria
 
The combined leakage from containment penetrations and containment isolation valves is within design limits.
 
14.2.12.2.14  Liquid Radwaste System Preoperational Test (S-
 
04HB01).
 
14.2.12.2.14.1  Objectives
: a. To demonstrate the operating characteristics of the
 
liquid radwaste system pumps and to verify the operation
 
of their associated control circuits.
: b. To demonstrate the operation of the liquid radwaste
 
system containment isolation valves, including their
 
response to a CIS.
: c. To determine by operational test that the liquid
 
radwaste system containment isolation valves' closure
 
times are within design specifications.
 
14.2-136    Rev. 0 WOLF CREEK 14.2.12.2.14.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The component cooling water system is available to
 
provide cooling water to the reactor coolant drain tank
 
heat exchanger.
 
14.2.12.2.14.3  Test Method
: a. The liquid radwaste system pumps are operated, and performance characteristics are recorded.
: b. The operability of the system pump and valve control
 
circuits is verified.
: c. The liquid radwaste system containment isolation valves
 
are operated under flow conditions, and operating times
 
are recorded.
 
14.2.12.2.14.4  Acceptance Criteria
: a. The performance characteristics of the liquid radwaste
 
system pumps are within design specifications.
: b. Each pump trips on receipt of a low-level signal from its respective tank.
: c. The liquid radwaste system containment isolation valves
 
close on receipt of a CIS.
: d. The liquid radwaste system containment isolation valves'
 
closure times are within design specifications.
: e. The liquid radwaste effluent discharge valve closes on a
 
high process radiation signal.
 
14.2.12.2.15  Waste Evaporator Preoperational Test (SU4-HB02)
 
14.2.12.2.15.1  Objectives
 
To demonstrate the operability of the waste evaporator and its associated
 
pumps, valves, and control circuits.
 
14.2-137    Rev. 0 WOLF CREEK 14.2.12.2.15.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. Cooling water is available to the waste evaporator.
: d. The auxiliary steam system is available to supply steam
 
to the waste evaporator.
: e. The waste evaporator condensate tank and the primary
 
evaporator bottoms tank are available to receive waste evaporator effluent.
 
14.2.12.2.15.3  Test Method
: a. The waste evaporator is operated, and performance data
 
is recorded.
: b. With the waste evaporator in operation, a low feed inlet
 
pressure signal is initiated, and the evaporator is
 
verified to shift to the recycle mode.
: c. The waste evaporator distillate pump is verified to trip
 
on a low evaporator condenser level.
 
14.2.12.2.15.4  Acceptance Criteria
: a. The waste evaporator process flow is within design
 
specifications.
: b. The waste evaporator goes into the recycle mode on low
 
feed inlet pressure.
: c. The waste evaporator distillate pump trips on a low
 
evaporator condenser level.
 
14.2.12.2.16  Solid Waste System Preoperational Test (S-04HC01)
 
14.2.12.2.16.1  Objectives
: a. To demonstrate the operating characteristics of the
 
solid waste system pumps and to verify the operation of
 
their associated control circuits.
 
14.2-138    Rev. 0 WOLF CREEK
: b. To demonstrate the ability of the decant station, drumming  station,  cement  filling station,  and the
 
solid radwaste bridge crane to process, solidify, and
 
handle waste and to verify the operation of their
 
associated control circuits.
: c. To demonstrate the ability of the dry waste compactors
 
to process compressible wastes and to verify the
 
operation of their associated control circuits.
 
14.2.12.2.16.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operable.
: c. Reactor makeup water is available to provide a source of
 
water to the decanting station.
 
14.2.12.2.16.3  Test Method
: a. The solid waste system pumps are operated, and the pump
 
operating data are recorded.
: b. The system component control circuits are verified, and
 
the ability of the solid radwaste system to process,
 
solidify, and handle waste is verified.
 
14.2.12.2.16.4. Acceptance Criteria
: a. The operating characteristics of the evaporator bottoms
 
tank pumps (primary and secondary) are within design
 
specifications.
: b. There are no free liquids present in the packaged waste.
: c. The evaporator bottoms tank pumps (primary and
 
secondary) trip on their respective tank low level
 
signal.
 
14.2.12.2.17  Solid Waste Filter Handling System Preoperational
 
Test (S-04HC02)
 
14.2.12.2.17.1  Objectives
 
To demonstrate the ability of the solid radwaste filter handling system to
 
remove, transfer, and install a spent resin sluice filter assembly.
 
14.2-139    Rev. 0 WOLF CREEK 14.2.12.2.17.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2.12.2.17.3  Test Method
: a. Operability of the solid radwaste monorail hoist and
 
handling cask winch and associated control circuits is
 
verified.
: b. The ability of the solid radwaste filter handling system to remove, transfer, and install a spent resin sluice filter assembly is verified.
 
14.2.12.2.17.4  Acceptance Criteria
 
The filter handling system functions in accordance with design specifications.
 
14.2.12.2.18  Resin Transfer Preoperational Test (SU4-HC03)
 
14.2.12.2.18.1  Objectives
: a. To demonstrate the ability to charge resins and
 
activated charcoal to those systems containing
 
potentially contaminated demineralizers or adsorbers.
 
The ability of the spent resin sluice pumps to  transfer resins and charcoal from demineralizers and adsorbers is also verified.
: b. To demonstrate the operating characteristics of the
 
spent resin sluice pumps, chemical addition metering
 
pumps, and chemical drain tank pumps.
: c. To demonstrate the operability of system valve and pump
 
control circuits.
 
14.2.12.2.18.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2-140    Rev. 0 WOLF CREEK
: c. Those systems containing potentially contaminated demineralizers and adsorbers are available to support
 
this test.
: d. The reactor makeup water system is available to provide a source of water for resin charging.
: e. A means of bulk disposal is available to receive waste
 
at the bulk disposal station.
 
14.2.12.2.18.3  Test Method
: a. Resins and charcoal are charged and transferred from
 
selected potentially contaminated demineralizers and
 
adsorbers.
: b. The spent resin sluice pumps, chemical addition metering
 
pumps, and chemical drain tank pumps are operated, and
 
performance characteristics are obtained.
: c. The response of the spent resin sluice pumps, chemical
 
addition metering pumps, and the chemical drain tank
 
pumps to a low-level trip signal from their respective
 
tanks is verified.
 
14.2.12.2.18.4  Acceptance Criteria
: a. The operating characteristics of the spent resin sluice
 
pumps, chemical addition metering pumps, and the
 
chemical drain tank pump  are within design specifications.
: b. The spent resin sluice pumps, chemical addition metering
 
pumps, and the chemical drain tank pump trip on receipt
 
of a low-level trip signal from their respective tanks.
 
14.2.12.2.19  Fire Protection System (Water) Preoperational Test
 
              (SU4-KC01A, SU4-KC01B)
 
14.2.12.2.19.1  Objectives
: a. To demonstrate the operability of the preaction
 
sprinkler system, wet-pipe sprinkler system, and the
 
automatic water spray system, including system
 
instrumentation, alarms, and interlocks.
: b. To demonstrate the operability of system valves,
 
including their response to safety signals.
 
14.2-141    Rev. 0 WOLF CREEK
: c. To verify spray to the applicable electrical system transformers.
 
14.2.12.2.19.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operable.
: c. The fire water pumps are available to provide a source
 
of water to the fire protection system headers.
 
14.2.12.2.19.3  Test Method
: a. Response of the preaction sprinkler system, wet-pipe
 
sprinkler system, and automatic water spray system to
 
fire detection signals is verified, including the
 
operability of associated alarms, instrumentation, and
 
interlocks.
: b. The fire protection system containment isolation valves
 
are operated under flow conditions and operating times
 
recorded.
: c. Response of the fire protection system containment
 
isolation valves to a CIS is verified.
: d. Spray to the applicable electrical transformers is verified.
 
14.2.12.2.19.4  Acceptance Criteria
: a. The preaction sprinkler system, wet-pipe sprinkler
 
system, automatic water spray system and associated
 
alarms, and instrumentation and interlocks operate in
 
accordance with system design specifications.
: b. The fire protection system containment isolation valves'
 
closure time is within design specifications.
: c. The fire protection system containment isolation valves
 
close on receipt of a CIS.
: d. The spray to applicable electrical transformers is
 
within design specifications.
 
14.2-142    Rev. 0 WOLF CREEK 14.2.12.2.20  Fire Protection System (Halon) Preoperational Test (S-04KC02)
 
14.2.12.2.20.1  Objectives
 
To demonstrate the operability of the halon system, including the associated
 
instrumentation, control circuits, and alarms.
 
14.2.12.2.20.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operable.
14.2.12.2.20.3  Test Method
 
The operability of the halon system, including the associated instrumentation
 
and alarms, is verified. System response to fire detection signals is also
 
verified.
 
14.2.12.2.20.4  Acceptance Criteria
 
The halon fire protection system operates in accordance with system design
 
specifications.
 
14.2.12.2.21  Fire Protection System Detection and Alarm
 
Preoperational Test (S-04KC03)
 
14.2.12.2.21.1  Objectives
 
To demonstrate the operability of the fire protection system detectors and
 
alarms not verified during the performance of the halon and water system
 
preoperational tests.
 
14.2.12.2.21.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operable.
 
14.2.12.2.21.3  Test Method
 
Actuation of system alarms upon receipt of fire detection signals is verified.
 
14.2-143    Rev. 0 WOLF CREEK 14.2.12.2.21.4  Acceptance Criteria
 
Fire protection system detectors and alarms operate in accordance with system
 
design specifications.
 
14.2.12.2.22  Oily Waste System Preoperational Test (S-04LE01)
 
14.2.12.2.22.1  Objectives
 
To demonstrate the sump pumps and miscellaneous condensate drain tank pumps'
 
operating characteristics and response to sump/tank, level signals. The
 
operation of system valves and associated control circuits and sump/tank level
 
alarms are also verified.
 
14.2.12.2.22.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The compressed air system is available to supply air to
 
system valves and pumps.
: d. A water source (fire system) and a collection receptacle
 
          (oil/water separator, main condenser) are available for
 
the testing of each sump/tank.
 
14.2.12.2.22.3  Test Method
: a. The sump pumps and miscellaneous condensate drain tank
 
pumps are operated, and performance characteristics are
 
verified.
: b. The response of each pump and associated alarms to sump/
 
tank high and low level signals is verified.
: c. The operability of system air-operated valves is
 
verified, including the response to a process radiation
 
signal.
 
14.2.12.2.22.4  Acceptance Criteria
: a. The performance characteristics of the system pumps are
 
within design specifications.
: b. The turbine building oily waste header discharge valve
 
closes on a high-radiation signal.
 
14.2-144    Rev. 0 WOLF CREEK 14.2.12.2.23  Floor and Equipment Drain System Preoperational Test (SU4-LF01)
 
14.2.12.2.23.1  Objectives
 
To demonstrate the sump pumps and hot machine shop oil interceptor pump's
 
capacities and response to sump/tank level signals. The operation of system
 
valves, their response to safety signals, and sump/tank level alarms are also
 
verified.
 
14.2.12.2.23.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The compressed air system is available to supply air to
 
system valves and pumps.
: d. A water source (fire system or ESW) and a collection
 
receptacle (holdup tank, radwaste system, etc.) are
 
available for the testing of each sump/tank.
 
14.2.12.2.23.3  Test Method
: a. The sump pumps and hot machine shop oil interceptor pumps
 
are operated, and their capacities are verified.
: b. The response of each system pump, system indication, and alarms, to sump/tank high and low level signals is
 
verified.
: c. The operability of system air- and motor-operated valves
 
is verified, including their response to safety signals.
 
14.2.12.2.23.4  Acceptance Criteria
: a. The capacities of the floor and equipment drain system
 
pumps are within design specifications.
: b. System valves properly respond to safety injection
 
signals and containment isolation signals.
: c. The valve response times are within design
 
specifications.
 
14.2-145    Rev. 0 WOLF CREEK 14.2.12.2.24  13.8-kV System Preoperational Test (S-04PA01)
 
14.2.12.2.24.1  Objectives
: a. To demonstrate that the 13.8-kV busses can be energized from the startup transformer.
: b. To demonstrate that automatic fast transfer of the
 
busses from the unit auxiliary source to the startup
 
source is within design specifications.
: c. To demonstrate that the unit auxiliary source or startup
 
source feeder breakers will trip on a stuck breaker
 
condition.
: d. To demonstrate proper operation of system instrumentation and controls.
 
14.2.12.2.24.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The 13.8-kV system has been energized.
 
14.2.12.2.24.3  Test Method
: a. The 13.8-kV busses are energized from the startup transformer, and bus voltages are recorded.
: b. Automatic fast transfer from the unit auxiliary source
 
to the startup source is verified.
: c. Stuck breaker conditions are simulated, and proper
 
operation of the 13.8-kV auxiliary source and startup
 
source feeder breakers is verified.
 
14.2.12.2.24.4  Acceptance Criteria
: a. The 13.8-kV bus voltages are within design
 
specifications, when energized from the startup
 
transformer.
: b. Automatic fast transfer of the busses from the unit
 
auxiliary source to the startup source is within design
 
specifications.
 
14.2-146    Rev. 0 WOLF CREEK
: c. The 13.8-kV auxiliary source and startup source feeder breakers trip on receipt of a stuck breaker signal.
 
14.2.12.2.25  4,160-V (Non-Class IE) System  Preoperational Test
 
              (S-04PB01)
 
14.2.12.2.25.1  Objectives
: a. To demonstrate that the 4,160-V busses can be energized
 
from their normal and alternate sources, and to verify
 
the operability of supply breaker and bus tie breaker
 
protective interlocks.
: b. To demonstrate that automatic transfer is achieved
 
through the tie breaker from the normal source to the alternate source in the event of an electrical fault.
: c. To demonstrate proper operation of system
 
instrumentation and controls.
 
14.2.12.2.25.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The 4,160-V (non-Class IE) system has been energized.
 
14.2.12.2.25.3  Test Method
: a. The 4,160-V non-Class IE busses are energized from their
 
normal and alternate source, and bus voltages are
 
recorded.
: b. System supply breakers and bus tie breakers are
 
operated, and breaker interlocks are verified.
: c. System electrical fault signals are simulated, and
 
automatic transfer is verified through the tie breaker
 
from the normal source to the alternate source for each
 
4,160-V bus.
 
14.2.12.2.25.4  Acceptance Criteria
: a. The voltage of each 4,160-V non-Class IE bus, when
 
supplied from its normal source and alternate source, is
 
within design specifications.
 
14.2-147    Rev. 0 WOLF CREEK
: b. System supply breaker and bus tie breaker interlocks operate in accordance with the system design.
: c. Automatic transfer is achieved through the tie breaker
 
from the normal source to the alternate source, for each 4,160-V bus, upon receipt of an electrical fault signal.
 
14.2.12.2.26  480-Volt (Non-Class IE) System Preoperational Test
 
              (S-04PG01)
 
14.2.12.2.26.1  Objectives
: a. To demonstrate that the 480-V non-Class IE load centers
 
can be energized from their normal sources and alternate
 
sources, as applicable, and verify the operability of feeder breaker and bus tie breaker protective interlocks.
: b. To demonstrate that the 480-V busses supplied by 4160-V
 
          (Class IE) source breakers are shed on receipt of a load
 
shed signal.
: c. To demonstrate proper operation of system
 
instrumentation and controls.
 
14.2.12.2.26.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The 480-V (non-Class IE and Class IE) systems have been
 
energized.
 
14.2.12.2.26.3  Test Method
: a. The 480-V non-Class IE load centers are energized from
 
their normal source and alternate source, as applicable
 
and voltages are recorded.
: b. System feeder breakers and bus tie breakers are
 
operated, and breaker interlocks verified.
: c. A load shed signal is simulated, and the 480-V busses
 
supplied by the 4,160-V (Class IE) source breakers are
 
verified to shed.
 
14.2-148    Rev. 0 WOLF CREEK 14.2.12.2.26.4  Acceptance Criteria
: a. The voltage for each 480-V non-Class IE load center,
 
when supplied from its normal source and alternate
 
source, as applicable, is within design specifications.
: b. System feeder breaker and bus tie breaker interlocks
 
operate in accordance with the system design.
: c. The 480-V busses supplied by the 4160-V (Class IE)
 
source breakers shed on receipt of a load shed signal.
 
14.2.12.2.27  250-V DC System Preoperational Test (S-04PJ01)
 
14.2.12.2.27.1  Objectives To demonstrate the ability of the battery and battery chargers to provide power
 
to the busses. The battery chargers' ability to recharge their respective
 
battery is also demonstrated. Proper operation of system instrumentation and
 
controls is also verified.
 
14.2.12.2.27.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. Ventilation for the battery room is available.
: d. The 250-V dc system has been energized.
 
14.2.12.2.27.3  Test Method
: a. The battery is discharged, using a test load at the
 
design duty cycle discharge rate.
: b. The battery is fully discharged to determine its
 
capacity factor.
: c. The ability of each battery charger to charge the
 
battery to normal conditions, after the battery has
 
undergone a design duty cycle, while simultaneously
 
supplying power at a rate equivalent to the largest
 
motor current load is verified.
: d. A load shed signal is initiated, and the battery charger
 
PJ31 ac supply breaker is verified to trip.
 
14.2-149    Rev. 0 WOLF CREEK 14.2.12.2.27.4  Acceptance Criteria
: a. The battery is capable of maintaining output voltage
 
above the design minimum, during a design duty cycle.
: b. The battery capacity factor is in accordance with design
 
requirements.
: c. The battery chargers are able to recharge the battery to
 
normal conditions, after the battery has undergone a
 
design duty cycle, while simultaneously supplying power
 
at a rate equivalent to the largest motor current load.
: d. Battery charger PJ31 ac supply breaker trips on receipt
 
of a load shed signal.
14.2.12.2.28  125-V (Non-Class IE) DC System Preoperational Test
 
              (S-04PK01, S-04PK02)
 
14.2.12.2.28.1  Objectives
 
To demonstrate the ability of the batteries and chargers to provide power to
 
the busses. The battery chargers' ability to recharge their respective battery
 
is also demonstrated. Proper operation of system instrumentation and controls
 
is also verified.
 
14.2.12.2.28.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. Ventilation for the battery room is available.
 
14.2.12.2.28.3  Test Method
: a. Each battery is discharged, using a test load at the
 
design duty cycle discharge rate.
: b. Each battery is fully discharged to determine its
 
capacity factor.
: c. The ability of each battery charger to charge its
 
respective battery to normal conditions, after the
 
battery has undergone a design duty cycle, while
 
simultaneously supplying power at a rate equivalent to
 
the design instrumentation loading.
 
14.2-150    Rev. 0 WOLF CREEK
: d. A safety injection load shed signal is initiated, and the battery charger PK21, PK22, PK23, and PK24 supply
 
breaker is verified to trip.
 
14.2.12.2.28.4  Acceptance Criteria
: a. Each battery is capable of maintaining output voltage
 
above the design minimum, during a design duty cycle.
: b. Each battery capacity factor is in accordance with
 
design requirements.
: c. The battery chargers are able to recharge the batteries
 
to normal conditions, after the battery has undergone a
 
design duty cycle, while simultaneously supplying power at a rate equivalent to the design load.
: d. Battery charger PK21, PK22, PK23, and PK24 supply
 
breaker trips on receipt of a safety injection load shed
 
signal.
 
14.2.12.2.29  Instrument AC (Non-Class IE) System Preoperational
 
Test (S-04PN01)
 
14.2.12.2.29.1  Objectives
 
To demonstrate that the 120-V non-Class IE ac distribution panels can be fed
 
from their associated supply transformers. Proper operation of system
 
instrumentation and controls is also verified.
 
14.2.12.2.29.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2.12.2.29.3  Test Method
 
The 120-V non-Class IE ac distribution panels are energized from their
 
associated supply transformers, and the panel voltages are recorded.
 
14.2.12.2.29.4  Acceptance Criteria
 
Each 120-V non-Class IE ac distribution panel voltage is within design
 
specifications.
 
14.2-151    Rev. 0 WOLF CREEK 14.2.12.2.30  Emergency Lighting System Preoperational Test (S-04QD01)
 
14.2.12.2.30.1  Objectives
 
To demonstrate the capability of the emergency lighting system to provide
 
adequate lighting. Proper operation of system instrumentation and controls is
 
also verified.
 
14.2.12.2.30.2  Prerequisites
 
Required electrical power supplies and control circuits are operable.
 
14.2.12.2.30.3  Test Method
 
The ability of the emergency lighting system to provide adequate lighting is verified. The operability of associated instrumentation and control circuits
 
is also verified.
 
14.2.12.2.30.4  Acceptance Criteria
 
The emergency lighting system operates in accordance with system design
 
specifications.
 
14.2.12.2.31  Public Address System Preoperational Test (S-04QF01)
 
14.2.12.2.31.1  Objectives
 
To demonstrate the capability of the public address system to provide adequate
 
intraplant communications and to verify the operability of the evacuation alarm system.
14.2.12.2.31.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operable.
 
14.2.12.2.31.3  Test Method
: a. The public address system is operated from all
 
locations, and adequate communications verified.
: b. Operability of the evacuation alarm system is verified.
 
14.2-152    Rev. 0 WOLF CREEK 14.2.12.2.31.4  Acceptance Criteria
: a. The evacuation alarm system operates in accordance with
 
system design specifications.
 
14.2.12.2.32  Heat Tracing Freeze Protection System Preoperational
 
Test (S-04QJ01)
 
14.2.12.2.32.1  Objectives
 
To demonstrate the ability of the freeze protection system to automatically
 
control the associated heat tracing circuits in accordance with system design. 
 
The operation of system instrumentation and controls is also verified.
 
14.2.12.2.32.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2.12.2.32.3  Test Method
 
Temperature signals are varied and the energization/ deenergization of the
 
associated heat tracing circuits is verified.
 
14.2.12.2.32.4  Acceptance Criteria
 
The freeze protection system automatically controls the associated heat tracing circuits, in accordance with system design.
 
14.2.12.2.33  Secondary Sampling System Preoperational Test
 
              (S-04RM01)
 
14.2.12.2.33.1  Objectives
: a. To demonstrate the operating characteristics of the
 
steam generator blowdown sample drain tank pump, sample
 
chiller pump, and the condenser sample pumps, and verify
 
the operability of their associated control circuits.
: b. To demonstrate that the system sample flows are within
 
design specifications.
 
14.2.12.2.33.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
 
14.2-153    Rev. 0 WOLF CREEK
: b. Required electrical power supplies and control circuits are operable.
: c. Plant conditions are established, and systems are
 
available, as necessary, to facilitate drawing samples from the sample points.
: d. The steam generator blowdown system is available to
 
receive effluent from the steam generator blowdown
 
sample drain tank.
: e. The closed cooling water system is available to provide
 
cooling water to the system sample coolers and chiller
 
package.
 
14.2.12.2.33.3  Test Method
: a. The steam generator blowdown sample drain tank pump,
 
sample chiller pump, and the condenser sample pumps are
 
operated, and pump performance data recorded.
 
Operability of their associated control circuits is also
 
verified.
: b. System samples are obtained, and flows are recorded.
 
14.2.12.2.33.4  Acceptance Criteria
: a. The steam generator blowdown sample drain tank pump,
 
sample chiller pump, and condenser sample pump
 
performance characteristics are within design specifications.
: b. Sample system flows are within design specifications.
 
14.2.12.2.34  Area Radiation Monitoring Preoperational Test
 
              (S-04SD01)
 
14.2.12.2.34.1  Objectives
 
To demonstrate the operation of the area radiation monitors and to verify that
 
a high radiation signal at each monitor will initiate an alarm.
 
14.2.12.2.34.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2-154    Rev. 0 WOLF CREEK 14.2.12.2.34.3  Test Method
 
A calibration source is utilized to actuate the area radiation monitors, and
 
their operability and associated alarms are verified.
 
14.2.12.2.34.4  Acceptance Criteria
 
Each area radiation monitor actuates the associated alarms, on receipt of a
 
high radiation signal.
 
14.2.12.2.35  Seismic Monitoring Instrumentation System
 
Preoperational Test (S-04SG01)
 
14.2.12.2.35.1  Objectives
 
To demonstrate the operability of the seismic triggers and switches and strong motion accelerometers, including their associated alarms and recording and
 
playback systems.
 
14.2.12.2.35.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2.12.2.35.3  Test Method
 
A test signal is initiated, and the operability of the seismic triggers and switches and strong motion accelerometers, including their associated alarms and recording and playback systems, is verified.
 
14.2.12.2.35.4  Acceptance Criteria
 
The seismic triggers and switches and strong motion accelerometers, including
 
their associated alarms and recording and playback systems, operate in
 
accordance with system design specifications.
 
14.2.12.2.36  Loose Parts Monitoring System Test (SU4-SQ02).
 
14.2.12.2.36.1  Objective
 
To demonstrate the operability of the accelerometers, signal conditioning
 
devices and diagnostic equipment, including associated alarms and recording and
 
playback systems.
 
14.2-155    Rev. 0 WOLF CREEK 14.2.12.2.36.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. Reactor coolant system is filled with water.
: d. Reactor coolant system is at normal operating
 
temperature and pressure with all reactor coolant pumps
 
running, and hot functional testing is in progress (for
 
those portions of the testing to be performed during hot
 
functional testing).
: e. Reactor coolant system is at normal operating
 
temperature and pressure with all reactor coolant pumps
 
running after fuel loading during startup testing (for
 
those portions of the testing to be performed during
 
startup testing).
 
14.2.12.2.36.3  Test Method
: a. Test signals are initiated and the operability of the
 
accelerometers, signal conditioners, and diagnostic
 
circuitry, including alarms and recording and playback
 
systems, is verified.
: b. Channel audio outputs are also recorded during hot functional testing and after fuel loading during startup testing to obtain a record of the reactor coolant system
 
noise "signature."
 
14.2.12.2.36.4  Acceptance Criteria
 
The accelerometers, signal conditioners, and diagnostic circuitry, including
 
alarms and recording and playback systems operate to detect loose parts as
 
specified in USAR Section 4.4.6.4.
 
14.2.12.2.37  Plant Performance Test (SU8-0007)
 
14.2.12.2.37.1  Objectives
: a. To monitor the balance-of-plant and electrical systems
 
under loaded conditions during hot functional and power
 
ascension testing. The ability of the ventilation
 
systems to maintain ambient temperatures within design
 
limits is also verified. To monitor the concrete
 
temperatures surrounding hot penetrations and to verify
 
evacuation alarm audibility in high noise areas.
 
14.2-156    Rev. 0 WOLF CREEK 14.2.12.2.37.2  Prerequisites
: a. Required component testing, instrument calibration, and
 
system flushing/cleaning are complete.
: b. Required HVAC systems have been balanced.
: c. Required electrical power supplies and control circuits
 
are operational.
 
14.2.12.2.37.3  Test Method
 
This procedure does not provide a test method. It provides a monitoring and
 
data collection function only, with the resultant datum evaluated against
 
provided design values, as applicable.
14.2.12.2.37.4  Acceptance Criteria
: a. Evacuation alarm audibility in high noise areas is
 
verified.
: b. The containment coolers maintain containment temperature
 
within design.
 
Note:  Each monitored point is evaluated throughout the test to verify that the
 
applicable system or component is functioning per design.
 
14.2.12.2.38  Electrical Distribution System Voltage Verification
 
Test (S-090023)
 
14.2.12.2.38.1  Objectives
 
To record actual loaded electrical distribution parameters during various
 
steady-state and transient conditions.
 
14.2.12.2.38.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
 
14.2.12.2.38.3  Test Method
 
The bus voltages and loadings of the electrical distribution system (down to
 
the Class lE 120/208 V ac system) are recorded for 
 
14.2-157    Rev. 0 WOLF CREEK various steady state configurations. Data is also recorded during the starting of the largest Class 1E and non-Class lE motors. All monitored busses are
 
loaded to at least 30 percent.
 
14.2.12.2.38.4  Acceptance Criteria
 
Not applicable.
 
Note:  The data obtained from this test procedure are used to verify electrical
 
system voltage analysis.
 
14.2.12.3  Startup Test Procedures The following sections are the test abstracts for each startup test. Table
 
14.2-3 provides an index of these tests.
 
14.2.12.3.1  Automatic Steam Generator Level Control (S-07AB01)
 
14.2.12.3.1.1  Objectives
: a. To verify the stability of the automatic steam generator
 
level control following simulated transients at low
 
power conditions and the proper operation of the
 
variable speed feature of the feedwater pumps.
: b. To demonstrate the performance characteristics of the steam generator feedwater pumps.
 
14.2.12.3.1.2  Prerequisites
: a. The steam generator level control system has been
 
checked and calibrated.
: b. Steam generator level instruments and set points have
 
been set and calibrated.
: c. Main feedwater is operational.
 
14.2.12.3.1.3  Test Method
: a. Induce simulated steam generator level transients to verify proper steam generator level control response.
: b. Verify the variable speed features of the steam
 
generator feedwater pumps by manipulation of controllers
 
and test input signals, and verify the performance
 
characteristics of the steam generator feedwater pumps.
 
14.2-158    Rev. 0 WOLF CREEK 14.2.12.3.1.4  Acceptance Criteria
: a. Automatic steam generator level control system response
 
must be in accordance with the vendor's technical
 
manual.
: b. The steam generator feedwater pump's performance
 
characteristics are within design specifications.
 
14.2.12.3.2  Dynamic Automatic Steam Dump Control (SU7-AB02)
 
14.2.12.3.2.1  Objectives
 
To verify automatic operation of the  T average steam dump control system,
 
demonstrate controller setpoint adequacy, and obtain final settings for steam pressure control of the condenser dump valves.
 
14.2.12.3.2.2  Prerequisites
: a. The reactor coolant system is at normal operating
 
pressure and temperature.
: b. The reactor is critical.
: c. The steam dump system has been checked and calibrated.
: d. Main feedwater and the condenser are operational.
 
14.2.12.3.2.3  Test Method
: a. Reactor power is increased by rod withdrawal and steam dump to condenser to demonstrate setpoint adequacy.
: b. Pressure controller setpoint is increased prior to
 
switching to  T average control, which will rapidly
 
modulate open condenser dump valves.
: c. Simulate turbine operating conditions with reactor at
 
power, then simulate turbine trip, resulting in the
 
rapid opening of the steam dump valves.
 
14.2.12.3.2.4  Acceptance Criteria
 
The steam dump system controllers must maintain stable reactor coolant system 
 
T average at the controllers set point with no divergent oscillations.
 
14.2.12.3.3  RTD Bypass Flow Measurement (S-07BB01)
 
14.2.12.3.3.1  Objectives
 
To determine the flow rate necessary to achieve the design reactor coolant 
 
transport  time  in  each resistance temperature detector 
 
14.2-159    Rev. 0 WOLF CREEK (RTD) bypass loop and to measure the flow rate in each RTD bypass loop to ensure that the transport times are acceptable.
 
14.2.12.3.3.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The reactor core is installed, and the plant is at
 
normal operating temperature and pressure with all
 
reactor coolant pumps running.
 
14.2.12.3.3.3  Test Method
 
The flow rate necessary to achieve the design reactor coolant transport time
 
for each hot and cold leg bypass loop is calculated, utilizing the hot and cold
 
leg RTD bypass loop piping lengths. Hot and cold RTD bypass loop flow data are
 
recorded.
 
14.2.12.3.3.4  Acceptance Criteria
 
The flow rate in each hot and cold leg RTD bypass loop, required to achieve the
 
design reactor coolant transport time, is within design specifications.
 
14.2.12.3.4  Pressurizer  Heater  and  Spray  Capability  Test
 
            (S-07BB02)
 
14.2.12.3.4.1  Objectives
 
To determine the rate of pressure reduction caused by fully opening the
 
pressurizer spray valves and the rate of pressure increase from the operation
 
of all pressurizer heaters.
 
14.2.12.3.4.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The reactor core is installed with the plant in the hot
 
shutdown condition at normal operating temperature and
 
pressure with all reactor coolant pumps running.
 
14.2-160    Rev. 0 WOLF CREEK
: d. The final setting of the continuous spray flow valves is complete.
: e. The reactor coolant system is borated to the value
 
required for fuel loading.
: f. This test is performed prior to initial criticality.
 
14.2.12.3.4.3  Test Method
: a. With the pressurizer spray valves closed, all
 
pressurizer heaters are energized, and the time to reach
 
a 2,300 psig system pressure is measured and recorded.
: b. With the pressurizer heaters deenergized, both spray valves are fully opened, and the time to reach a 2,000 psig system pressure is measured and recorded.
 
14.2.12.3.4.4  Acceptance Criteria
 
The pressurizer pressure response to the opening of the pressurizer spray
 
valves and to the actuation of all pressurizer heaters is within design limits.
 
14.2.12.3.5  Reactor Coolant System Flow Measurement (S-07BB03)
 
14.2.12.3.5.1  Objectives
: a. To confirm, after core installation but before initial
 
critical operation, that reactor coolant system (RCS)
 
flow rate as measured by loop elbow differential pressure readings is greater than or equal to 90 percent of the thermal design flow rate.
: b. To confirm during initial power operation that RCS flow
 
rate as computed from calorimetric data is greater than
 
or equal to the thermal design flow rate.
 
14.2.12.3.5.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The reactor core is installed, and the plant is at
 
normal operating temperature and pressure.
 
14.2-161    Rev. 0 WOLF CREEK 14.2.12.3.5.3  Test Method
: a. Before critical operation, loop elbow differential
 
pressure readings are taken with all reactor coolant
 
pumps running, and RCS flow rate is calculated.
: b. During initial power operation, calorimetric data are
 
taken from Procedure S-07SC03, "Thermal Power
 
Measurement and Statepoint Data Collection," and RCS
 
flow rate is calculated.
 
14.2.12.3.5.4  Acceptance Criteria
 
RCS flow rate by loop elbow differential pressure measurement is greater than
 
or equal to 90 percent of the thermal design value and by calculation from calorimetric data is greater than or equal to the thermal design value.
 
14.2.12.3.6  Reactor Coolant System Flow Coastdown Test (SU7-BB04)
 
14.2.12.3.6.1  Objectives
: a. To measure the rate at which reactor coolant flow
 
changes, subsequent to simultaneously tripping all
 
reactor coolant pumps.
: b. To determine that the reactor coolant system low-flow
 
delay time is less than or equal to the total low-flow
 
delay time assumed in the safety analysis for loss of
 
flow.
 
14.2.12.3.6.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The reactor core is installed, and the plant is at
 
normal operating temperature and pressure with all
 
reactor coolant pumps running.
 
14.2.12.3.6.3  Test Method
 
Flow coastdown stabilization and loss of coolant delay-time data are recorded
 
while tripping reactor coolant pumps.
 
14.2-162    Rev. 0 WOLF CREEK 14.2.12.3.6.4  Acceptance Criteria
: a. The rate of change of reactor coolant flow is within
 
design specifications.
: b. The reactor coolant system low-flow delay time is less
 
than or equal to the total low-flow delay time assumed
 
in the safety analysis for loss of flow.
 
14.2.12.3.7  Pressurizer  Continuous  Spray  Flow  Verification
 
            (S-07BB05)
 
14.2.12.3.7.1  Objectives
 
To establish a setting for the pressurizer continuous spray flow valves to obtain an optimum continuous spray flow.
 
14.2.12.3.7.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The reactor core is installed with the plant in the hot
 
shutdown condition at normal operating temperature and
 
pressure with all reactor coolant pumps running.
: d. The reactor coolant system is borated to the value required for fuel loading.
: e. This test shall be performed prior to initial
 
criticality.
: f. The preliminary setting of the continuous spray flow
 
valves has been completed during hot functional testing.
 
14.2.12.3.7.3  Test Method
 
Continuous spray flow valves are adjusted to establish the optimum continuous
 
spray flow, and the valve throttle positions are recorded.
 
14.2.12.3.7.4  Acceptance Criteria
 
The continuous spray flow valves are throttled to establish the optimum
 
continuous spray flow to keep the spray line warm and minimize normal steady-
 
state pressurizer heater loads.
 
14.2-163    Rev. 0 WOLF CREEK 14.2.12.3.8  RTD/TC Cross Calibration (S-07BB06)
 
14.2.12.3.8.1  Objectives
: a. To provide a functional checkout of the reactor coolant system resistance temperature detectors (RTDs) and
 
incore thermocouples and to generate isothermal cross-
 
calibration data for subsequent correction factors to
 
indicated temperatures.
 
NOTE This portion of the test need be performed only if the
 
data collected in S-03BB16, RTD/TC Cross Calibration,
 
during hot functional testing, so warrants.
: b. To provide a functional checkout of the core subcooling
 
monitor system including the detecting thermocouples.
 
14.2.12.3.8.2  Prerequisites
: a. Required component testing and instrument calibration
 
are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. Plant heatup, following core loading, is in progress,
 
and all reactor coolant pumps are operating.
 
14.2.12.3.8.3  Test Method
: a. At various temperature plateaus RTD and incore
 
thermocouple data are recorded. Isothermal
 
cross-calibration correction factors for individual
 
thermocouples and the installation corrections for
 
individual RTDs are determined.
: b. At normal operating temperature, the thermocouple core
 
subcooling monitors' operational and programmable functions are verified, including associated alarms, displays, and printouts.
 
14.2.12.3.8.4  Acceptance Criteria
: a. Individual RTD readings are within the design
 
specifications.
: b. The installation corrections of the RTDs are within
 
design specifications.
 
14.2-164    Rev. 0 WOLF CREEK
: c. The thermocouple core subcooling monitor alarms, displays, and printouts function in accordance with
 
design specifications.
 
14.2.12.3.9  Core Loading Instrumentation and Neutron Source Requirements (S-07SC01)
 
14.2.12.3.9.1  Objectives
 
To verify proper alignment, calibration, and neutron response of the temporary
 
core loading instrumentation prior to start of fuel- loading; to check the
 
neutron response of the nuclear instrumentation system (NIS) source range
 
channels prior to start of fuel-loading; and to check the neutron response of
 
the temporary and NIS source range instrumentation prior to resumption of fuel-
 
loading following any delay of 8 hours or more. To verify the signal to noise ratio is greater than 2.
 
14.2.12.3.9.2  Prerequisites
: a. Hot functional testing is completed.
: b. The nuclear instrumentation system is installed and
 
calibrated.
 
14.2.12.3.9.3  Test Method
: a. A portable neutron source (1-5 curie), plus preshipment
 
equipment checkout data, is used to verify proper
 
alignment, calibration, and neutron response of the
 
temporary core-loading instrumentation.
: b. A portable neutron source (1-5 curie) is used to check
 
the neutron response of the NIS source range detectors.
: c. A portable neutron source (1-5 curie) or movement of a
 
source-bearing fuel element to produce the desired
 
change in neutron level to verify the neutron response
 
of the temporary and NIS source range instrumentation
 
prior to resumption of fuel-loading following any delay
 
of 8 hours or more.
: d. Perform a statistical evaluation of 10 observations for
 
each channel, to verify operability of the equipment.
 
14.2.12.3.9.4  Acceptance Criteria
 
Neutron instrumentation is operational, calibrated, and indicates a
 
positive/negative change in count rate as the neutron level is increased and/or
 
decreased. The signal to noise ratio is greater than 2.
 
14.2-165    Rev. 0 WOLF CREEK 14.2.12.3.10  Thermal Power Measurement and Statepoint Data Collection (S-07SC03)
 
14.2.12.3.10.1  Objectives
 
To measure core thermal power and obtain data for instrumentation calibration.
 
14.2.12.3.10.2  Prerequisites
: a. Calorimetric instrumentation is installed.
: b. This test is performed at 30-percent, 50-percent, 75-
 
percent, 90-percent, and 100-percent power.
 
14.2.12.3.10.3  Test Method Collect data and calculate thermal power. Obtain statepoint data, compute the
 
average for each parameter measured, convert to the appropriate units, and
 
summarize the data for each RCS loop.
 
14.2.12.3.10.4  Acceptance Criteria
 
This test is for the collection of data.
 
14.2.12.3.11  Nuclear Instrumentation System Test (SU7-SE01)
 
14.2.12.3.11.1  Objectives
 
The purpose of this test is to verify that the nuclear instrumentation system
 
performs the required indications and control functions through the source, intermediate, and power ranges of operation prior to core loading.
 
14.2.12.3.11.2  Prerequisites
: a. The nuclear instrumentation system is installed,
 
calibrated, aligned, and operational for a period of at
 
least 4 hours.
: b. The plant is at ambient temperature and pressure.
 
14.2.12.3.11.3  Test Method
: a. The source and intermediate range channels are subjected
 
to various test signals to verify that the appropriate
 
indicators alarm, illuminate, or actuate, and the source
 
range local and remote speakers function.
 
14.2-166    Rev. 0 WOLF CREEK
: b. The power range channels are subjected to various test signals to observe proper meter reading and function of
 
the comparator and rate circuitry.
: c. The high voltage circuitry of the source and intermediate range channels is tested.
 
14.2.12.3.11.4  Acceptance Criteria
 
The control and indication functions and the reactor trip set points of the
 
nuclear instrumentation system source, intermediate, and power range channels
 
have been verified.
 
14.2.12.3.12  Operational  Alignment of Nuclear  Instrumentation
 
              (S-07SE02) 14.2.12.3.12.1  Objectives
 
To 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 prior to initial criticality to at
 
or near full reactor power.
 
14.2.12.3.12.2  Prerequisites
: a. The nuclear instrumentation system has been aligned.
: b. This test is conducted prior to criticality, during
 
power escalation, and at or near full power.
 
14.2.12.3.12.3  Test Method
: a. All functions are calibrated, tested, and verified,
 
utilizing permanently installed controls and adjustment
 
mechanisms.
: b. Operational modes of the source range, intermediate
 
range, and power range channels are set for their proper
 
functions, as per the test instructions.
 
14.2.12.3.12.4  Acceptance Criteria
 
The overlap between the source, intermediate, and power range channels must be
 
at least 1-1/2 decades, and the power range channels are capable of being
 
adjusted to agree with the results of plant calorimetric calculations.
 
14.2-167    Rev. 0 WOLF CREEK 14.2.12.3.13  Axial Flux Difference Instrumentation Calibration (S-07SE03)
 
14.2.12.3.13.1  Objectives
 
To derive calibration factors for overpower, overtemperature,  and
 
T setpoints, based on incore flux data, calorimetric data, and excore nuclear
 
instrumentation detector currents.
 
14.2.12.3.13.2  Prerequisites
: a. The axial flux difference instrumentation system has
 
been aligned.
: b. Data has been obtained from flux maps taken at 30-percent and 50-percent power.
 
14.2.12.3.13.3  Test Method
 
Collect data, as required by test instruction, at 50-percent and 75-percent power, perform FI calculations to calibration factors, and extrapolate results for use at the 100-percent power plateau.
 
14.2.12.3.13.4  Acceptance Criteria
 
Calibration factors agree with Technical Specifications.
 
14.2.12.3.14  Control Rod Drive Mechanism Operational Test (S-
 
07SF01)
 
14.2.12.3.14.1  Objectives
 
To demonstrate the proper operation of the rod drive mechanisms under both cold
 
and hot plant conditions and to provide verification of proper slave cycler
 
timing.
 
14.2.12.3.14.2  Prerequisites
: a. The control rod drive mechanisms are installed.
: b. The rod drive motor-generator sets are installed and
 
power is available.
: c. For the control rod drive mechanism timing test, the
 
core is installed, rod position indication is installed,
 
and the control rod driving mechanism cooling fans are
 
operational.
: d. Nuclear instrumentation channels operable and operating.
 
14.2-168    Rev. 0 WOLF CREEK
: e. A fast speed oscillograph (Visicorder or equivalent) to monitor test parameters is available.
 
14.2.12.3.14.3  Test Method
: a. With the reactor core installed and reactor in the cold
 
shutdown condition, confirm that the slave cycler
 
devices supply operating signals to the proper CRDM
 
stepping magnet coils.
: b. Verify proper operation of all CRDMs under both cold and
 
hot shutdown conditions. CRDM magnet coil currents and
 
audio noise signals are recorded.
 
14.2.12.3.14.4  Acceptance Criteria The control rod drive mechanisms conform to the requirements for proper
 
mechanism operation and timing as described in the magnetic control rod drive
 
mechanism instruction manual.
 
14.2.12.3.15  Rod Control System (S-07SF02)
 
14.2.12.3.15.1  Objectives
 
To demonstrate and document that the rod control system performs the required
 
control and indication functions just prior to initial criticality. To
 
demonstrate operation of the rod inhibit functions.
 
14.2.12.3.15.2  Prerequisites
: a. The reactor coolant system is at normal operating pressure and temperature.
: b. The rod control system is installed and aligned.
: c. The source range nuclear instruments are operable.
: d. The rods are capable of withdrawal.
: e. The rod position indication system is operable.
 
14.2.12.3.15.3  Test Method
: a. With the reactor at no load operating temperature and
 
pressure, and just prior to initial criticality, the
 
control is checked for each applicable position of the
 
bank selector switch for proper operation.
 
14.2-169    Rev. 0 WOLF CREEK
: b. Status lights, alarms, and indicators are verified.
 
14.2.12.3.15.4  Acceptance Criteria
 
The control and indication functions in accordance with the rod position indication system and rod control system manuals. Rod motion is inhibited upon
 
application of an inhibit function.
 
14.2.12.3.16  Rod Drop Time Measurement (SU7-SF03)
 
14.2.12.3.16.1  Objectives
 
To determine the rod drop time of each rod cluster control assembly under no-
 
flow and full-flow conditions, with the reactor in the cold shutdown condition
 
and at normal operating temperature and pressure.
14.2.12.3.16.2  Prerequisites
: a. Initial core loading is completed.
: b. Rod control system is installed and tested.
: c. Individual rod position indication is installed and
 
checked.
 
14.2.12.3.16.3  Test Method
 
Withdraw each rod cluster control assembly, interrupt the electrical power to
 
the associated rod drive mechanism, and measure and record the rod drop time. 
 
This test is performed with the reactor at cold and hot conditions and at no-flow and full- flow.
 
14.2.12.3.16.4  Acceptance Criteria
 
The rod drop times are acceptable in accordance with plant technical
 
specifications.
 
14.2.12.3.17  Rod Position Indication System (SU7-SF04)
 
14.2.12.3.17.1  Objectives
 
To verify that the rod position indication system satisfactorily performs
 
required indication functions for each individual rod and that each rod
 
operates satisfactorily over its entire range of travel.
 
14.2-170    Rev. 0 WOLF CREEK 14.2.12.3.17.2  Prerequisites
: a. Plant system conditions are established as follows:
: 1. Test performed at T avg <200&deg;F, nominal RCS pressure for T avg noted          2. Test results verified at T avg nominally 557&deg;F, RCS pressure nominally 2235 psig and at least one reactor coolant pump in service.
 
14.2.12.3.17.3  Test Method
: a. All shutdown rod banks are fully withdrawn by bank
 
stopping at 18,210 and 228 steps to record the rod
 
position, the Digital Rod Position Indication display
 
          (DRPI), and the group step position indication.
: b. All control rod banks are fully withdrawn by bank in 24
 
step increments while recording rod position as
 
indicated by the plant control room DRPI readout, and
 
the group step position indication.
: c. In addition, the pulse-to-analog converter chassis bank
 
position digital readout is recorded for all control rod
 
banks.
 
14.2.12.3.17.4  Acceptance Criteria
 
The rod position indication system performs the required indication functions,
 
and each rod operates over its entire range of travel within the limits of the
 
rod position indication instruction manual and the plant precautions,
 
limitations,setpoints manual, and WCGS Technical Specifications.
 
14.2.12.3.18  Automatic Reactor Control System (S-07SF05)
 
14.2.12.3.18.1  Objectives
 
To demonstrate the capability of the reactor control system to respond properly
 
to input signals and to transmit proper control signals to other plant control
 
systems and components.
 
14.2.12.3.18.2  Prerequisites
: a. The reactor is at approximately 30-percent power.
 
14.2-171    Rev. 0 WOLF CREEK
: b. Pressurizer level and pressure, steam dump, steam generator level, and main feed pump speed control
 
systems are in automatic.
 
14.2.12.3.18.3  Test Method
 
T average will be successively varied  from the  T ref set point to verify the transient recovery capabilities of the auto reactor control system.
 
14.2.12.3.18.4  Acceptance Criteria
: a. No manual intervention should be required to bring the
 
plant conditions to equilibrium values following
 
initiation of a 6 F temperature transient.
: b. T avg should return to within +
1.5 F of T ref following initiation of a 6 F temperature transient.
: c. Rod motion is inhibited by application of the
 
appropriate inhibit inputs.
 
14.2.12.3.19  Incore Flux Mapping (S-07SR01, S-07SR02)
 
14.2.12.3.19.1  Objectives
 
To obtain core power and temperature profiles for evaluating core performance.
 
14.2.12.3.19.2  Prerequisites
: a. The incore monitoring system has been functionally
 
tested.
: b. This test is performed at low power, 30-, 50-, 75-, 90-,
 
and 100-percent power.
: c. The reactor is stabilized prior to taking a map.
 
14.2.12.3.19.3  Test Method
 
The movable detectors are inserted into the core, data is obtained, and
 
thermocouples are monitored while at a stable power. The obtained data is
 
retained for evaluation.
 
14.2.12.3.19.4  Acceptance Criteria
 
Flux and temperature data is obtained at the various power levels.
 
14.2-172    Rev. 0 WOLF CREEK 14.2.12.3.20  Incore Instrumentation Test (S-07SR03, S-07SR04)
 
14.2.12.3.20.1  Objectives
 
To set up and demonstrate operation of the incore instrumentation system.
 
14.2.12.3.20.2  Prerequisites
: a. The incore instrumentation system is installed.
: b. Proper rotation and limit switch operation has been
 
verified.
: c. Testing is performed at cold shutdown and hot standby.
 
14.2.12.3.20.3  Test Method
 
At cold shutdown a dummy cable is inserted into each thimble, and proper
 
rotation and limit switch operation is verified. At hot standby the detectors
 
are inserted into the thimbles to demonstrate performance in all operational
 
modes.
 
14.2.12.3.20.4  Acceptance Criteria
 
The incore instrumentation system is capable of taking a flux map.
 
14.2.12.3.21  Operational Alignment of Process Temperature
 
Instrumentation (S-07SF06)
 
14.2.12.3.21.1  Objectives To align T and  Tavg process instrumentation under isothermal conditions, prior to criticality and at power.
 
14.2.12.3.21.2  Prerequisites
: a. This alignment is performed prior to initial criticality
 
and again at 75-percent power. Alignment is checked at
 
100-percent power.
: b. All reactor coolant pumps shall be operating.
 
14.2.12.3.21.3  Test Method
: a. Align T and Tavg per test instructions under isothermal conditions prior to criticality and at approximately 75
 
14.2-173    Rev. 0 WOLF CREEK percent power. Extrapolate the 75-percent power data to determine T and Tavg values for the 100-percent power plateau.
: b. At or near full power, check the alignment of the T          and T avg channels for agreement with the results of thermal power measurement. Realign any channels, as necessary, to meet test specifications.
 
14.2.12.3.21.4  Acceptance Criteria
 
The 100 percent power indications for T and Tavg channels must be within the maximum design values as specified in vendor design documents.
14.2.12.3.22  Startup  Adjustments of  Reactor  Control  System (S-07SF07)
 
14.2.12.3.22.1  Objectives
 
To obtain the optimum plant efficiency.
 
14.2.12.3.22.2  Prerequisites
: a. The reactor coolant system is at normal operating
 
pressure and temperature.
: b. Plant instrumentation shall have been aligned according
 
to Operational Alignment of Process Temperature
 
Instrumentation.
: c. The turbine control system shall have been aligned.
 
14.2.12.3.22.3  Test Method
: a. Obtain system temperature and steam pressure data at
 
steady-state conditions for zero power and at hold
 
points during power escalations.
: b. Evaluation of these data will provide the basis for
 
adjustments to the reactor control system.
 
14.2.12.3.22.4  Acceptance Criteria
 
The Tavg controller must be capable of maintaining full load steam pressure
 
within turbine pressure limitations specified in the vendor's technical manual.
 
14.2-174    Rev. 0 WOLF CREEK 14.2.12.3.23  RCCA or Bank Worth Measurement at Zero Power (S-07SF08)
 
14.2.12.3.23.1  Objectives
 
To determine the differential and integral reactivity worth of a rod cluster
 
control bank (RCC) or an individual rod cluster control assembly (RCCA).
 
14.2.12.3.23.2  Prerequisites
: a. The reactor is critical with the neutron flux level
 
within the range established for zero power physics
 
testing.
: b. The reactor coolant system is at normal operating pressure and temperature.
 
14.2.12.3.23.3  Test Method
 
RCC and RCCA worth are validated by constant addition and/or dilution of boron
 
in the reactor coolant system, causing rod movement to compensate for the boron
 
addition and/or dilution. This rod movement will cause step changes in
 
reactivity which are used to compute the worths.
 
14.2.12.3.23.4  Acceptance Criteria
 
The integral reactivity worth of the RCC or RCCA over its entire range of
 
travel agrees with acceptance criteria given in the Nuclear Design Report
 
within tolerance values specified in vendor design documents.
 
14.2.12.3.24  RCCA or Bank Worth Measurement at Power (SU7-SF09)
 
14.2.12.3.24.1  Objectives
: a. To measure RCCA worth for a rod ejected from the HFP rod
 
insertion limit position.
: b. To determine in-core response resulting from a dropped
 
rod with all other control rods near fully withdrawn.
 
14.2-175    Rev. 0 WOLF CREEK 14.2.12.3.24.2  Prerequisites
 
Testing will be performed at 30-percent power with the reactor stable.
* 14.2.12.3.24.3  Test Method
: a. Ejected rod - Compute the change in reactivity
 
associated with the change in RCCA position.
: b. Dropped rod - Determine the quadrant power tilt ratio
 
and hot channel factors by use of the in-core flux
 
mapping system.
 
14.2.12.3.24.4  Acceptance Criteria
: a. Ejected rod - The rod worth of the ejected rod is within tolerance values specified in vendor design documents.
: b. Dropped rod - The peaking factors are within the limits
 
specified in vendor design documents.
 
14.2.12.3.25  Reactor Systems Sampling for Core Load (S-07SJ01)
 
14.2.12.3.25.1  Objectives
 
To verify uniform boron concentration, prior to core load, in the reactor
 
coolant system and directly connected auxiliary systems.
 
14.2.12.3.25.2  Prerequisites
: a. Boric acid tanks, pumps, and transfer lines are all filled with 4 percent boric acid solution.
: b. Reactor coolant system is filled with reactor grade
 
water which has been borated to a concentration as
 
specified in the technical specifications.
 
14.2.12.3.25.3  Test Method
: a. Filling and circulating the reactor coolant system with
 
borated water should be accomplished, utilizing normal
 
flow paths as much as possible.
 
_______________________
* This test was performed at 50 percent power at Callaway.
 
Callaway has the same core and Nuclear Instrumentation System
 
as Wolf Creek. Wolf Creek Core parameters measured prior to
 
the pseudo rod drop test were compared with the corresponding
 
results for Callaway to verify that the plant response was the
 
same. This exemption was approved in a July 3, 1985 letter
 
from the NRC.
 
14.2-176    Rev. 0 WOLF CREEK
: b. Collect and analyze four samples taken at equidistant depths in the reactor vessel simultaneously with one
 
sample from the operating residual heat removal loop to
 
check uniform boron concentration.
 
14.2.12.3.25.4  Acceptance Criteria
 
Boron concentration of the samples obtained from the designated sample points
 
must be within a 30-ppm range of values.
 
14.2.12.3.26  Initial Core Loading (SU7-0001)
 
14.2.12.3.26.1  Objectives
: a. To load fuel in a controlled manner.
: b. To measure boron concentration.
 
14.2.12.3.26.2  Prerequisites
: a. Sufficient preoperational testing has been completed to
 
ensure the necessary equipment and attendant
 
instrumentation is functional.
: b. Required technical specification surveillance is
 
completed and the necessary systems are operable.
 
14.2.12.3.26.3  Test Method
 
Instruction includes a core-loading sequence which specifies the loading in a step-by-step fashion with the appropriate data collection records.
 
14.2.12.3.26.4  Acceptance Criteria
 
A permanent record of the final as-loaded core configuration has been made, and
 
the configuration is consistent with the fuel assembly core loading plan. 
 
Boron concentration is as specified in the Technical Specifications.
 
14.2.12.3.27  Inverse Count Rate Ratio Monitoring For Core Loading
 
              (S-070002)
 
14.2.12.3.27.1  Objectives
: a. To obtain nuclear monitoring data during initial core
 
loading.
: b. To prevent criticality during core loading.
 
14.2-177    Rev. 0 WOLF CREEK 14.2.12.3.27.2  Prerequisites
: a. Temporary and plant source range nuclear instrumentation
 
has been operational for a minimum of 4 hours to achieve
 
stable operation.
: b. Plant is prepared for initial core loading.
 
14.2.12.3.27.3  Test Method
 
Data from the nuclear monitoring channels is used to assess the safety with
 
which core loading operations may be conducted. Inverse count rate ratio is
 
plotted and evaluated to prevent any unexpected deviation from subcriticality. 
 
The core is monitored and maintained in a subcritical configuration throughout
 
the core loading.
14.2.12.3.27.4  Acceptance Criteria
 
The core is loaded without achieving criticality.
 
14.2.12.3.28  Inverse Count Rate Ratio Monitoring for Approach to
 
Initial Criticality (S-070003)
 
14.2.12.3.28.1  Objectives
: a. To obtain nuclear monitoring data during initial
 
criticality.
: b. To anticipate and determine criticality.
 
14.2.12.3.28.2  Prerequisites
: a. Both source range and intermediate range nuclear
 
channels alarm, trip functions, and indicating devices
 
have been checked out and calibrated.
: b. Both source range and intermediate range nuclear
 
channels have been energized a minimum of 4 hours to
 
insure stable operation.
 
14.2.12.3.28.3  Test Method
: a. Obtain base line count rates prior to rod withdrawal and
 
boron dilution. After each increment of rod withdrawal,
 
and periodically during boron dilution, count rates are
 
obtained, and inverse count rate ratio is evaluated.
: b. Core reactivity is monitored during the approach to
 
criticality.
 
14.2-178    Rev. 0 WOLF CREEK 14.2.12.3.28.4  Acceptance Criteria
 
To determine criticality.
 
14.2.12.3.29  Initial Criticality (S-070004)
 
14.2.12.3.29.1  Objectives
 
To achieve initial criticality in a controlled manner.
 
14.2.12.3.29.2  Prerequisites
: a. Initial core loading is completed.
: b. Required technical specification surveillance is completed and the necessary systems operable.
: c. Sufficient post-core loading precritical testing has
 
been completed to ensure the necessary equipment and
 
attendant instrumentation is functional.
 
14.2.12.3.29.3  Test Method
: a. At preselected points during rod withdrawal and/or boron
 
dilution, data is taken and inverse count rate plots
 
made to enable extrapolation to be carried out to the
 
expected critical point.
: b. Initial criticality is achieved by boron dilution or, if
 
desired, by withdrawing control rods.
14.2.12.3.29.4  Acceptance Criteria
 
The reactor is critical with the flux level established at approximately 1 x 10-8 amps on the intermediate range nuclear channels.
14.2.12.3.30  Determination of Core Power Range for Physics
 
Testing (S-070005)
 
14.2.12.3.30.1  Objectives
 
To determine the reactor power level at which effects from fuel heating is
 
detectable and to establish the range of neutron flux in which zero power
 
reactivity measurements are to be performed.
 
14.2.12.3.30.2  Prerequisites
: a. The reactor is critical and stable in the intermediate
 
range.
 
14.2-179    Rev. 0 WOLF CREEK
: b. Control rods are sufficiently deep in the core to allow positive reactivity insertion by rod withdrawal.
: c. Reactor coolant temperature is established at a value
 
that minimizes the moderator temperature coefficient reactivity feedback.
 
14.2.12.3.30.3  Test Method
: a. Withdraw control rod bank and allow the neutron flux
 
level to increase until nuclear heating effects are
 
indicated by the reactivity computer.
: b. Record the reactivity computer picoammeter flux level
 
and, if possible, the corresponding IR channel currents at which nuclear heating occurs, to obtain zero power testing range.
 
14.2.12.3.30.4  Acceptance Criteria
 
The power level at which zero power testing is conducted is determined.
 
14.2.12.3.31  Boron Endpoint Determination (S-070006)
 
14.2.12.3.31.1  Objectives
 
To determine the critical reactor coolant system boron concentration
 
appropriate to an endpoint configuration (RCC configuration).
 
14.2.12.3.31.2  Prerequisites
: a. The reactor is critical within the range for zero power
 
testing and stable.
: b. The reactor coolant is at normal operating pressure and
 
temperature.
: c. Rods are at the approximate end point configuration.
 
14.2.12.3.31.3  Test Method
 
Boron endpoints are measured by determining the boron concentration of the
 
reactor coolant system with the rods close to or at the desired configuration. 
 
If not, the rods are then quickly moved to the desired configuration with no
 
boron adjustment. The change in reactivity is measured, and this reactivity is
 
converted to an equal amount of boron to yield the endpoint at that particular
 
rod configuration.
 
14.2-180    Rev. 1 WOLF CREEK 14.2.12.3.31.4  Acceptance Criteria
 
The results of the boron endpoint calculations meet the requirements of the
 
Nuclear Design Report within tolerance values specified in vendor design
 
documents.
 
14.2.12.3.32  Isothermal  Temperature  Coefficient  Measurement
 
              (S-070007)
 
14.2.12.3.32.1  Objectives
 
To determine isothermal temperature coefficient, then derive the moderator
 
temperature coefficient from the isothermal data.
 
14.2.12.3.32.2  Prerequisites
: a. The reactor is critical within the range for zero power
 
testing and stable.
: b. The reactor coolant is at normal operating pressure and
 
temperature.
: c. Control rods are at the approximate end point
 
configuration.
 
14.2.12.3.32.3  Test Method
 
The isothermal temperature coefficient is determined by heating/cooling the
 
reactor coolant system at a constant rate and plotting temperature versus
 
reactivity. The moderator temperature coefficient may be derived from isothermal data, if desired.
 
14.2.12.3.32.4  Acceptance Criteria
 
The average of the measured values of the isothermal and, if desired, the
 
derived moderator temperature coefficient agrees with acceptance criteria given
 
in the Nuclear Design Report within tolerance values specified in vendor design
 
documents.
 
14.2.12.3.33  Power Coefficient Determination (S-070008)
 
14.2.12.3.33.1  Objectives
 
To verify the power coefficient of reactivity.
 
14.2.12.3.33.2  Prerequisites
: a. Reactor power level, reactor coolant temperature and
 
pressures, and RCCA and RCC bank configuration are as
 
follows:
 
14.2-181    Rev. 1 WOLF CREEK
: 1. RCS pressure - nominal 2235 psig
: 2. RCCA, RCC bank configuration - nominally all rods
 
out, D at bite position
: 3. Reactor power level - nominally 30, 50, 75, and 90
 
percent RTP
: 4. T avg - consistent with the nominal value corresponding to the T avg program at the identified nominal power levels.
: b. All subsystems which affect overall plant transient
 
response should be in automatic mode of operation with
 
the exception of the rod control system and automatic makeup. The CVCS demineralizer shall be bypassed.
 
14.2.12.3.33.3  Test Method
: a. As generator electrical load is changed, the primary side
 
is permitted to freely respond without any control rod
 
motion.
: b. The power coefficient verification factor is calculated
 
by measuring the change in RCS temperature and the
 
corresponding change in core power.
 
14.2.12.3.33.4  Acceptance Criteria
 
The average value of the measured verification factor agrees with that obtained
 
from design predictions of the isothermal temperature coefficient and doppler
 
power coefficient. This agreement is within limits given in the test
 
instructions.
 
14.2.12.3.34  Load Swing Tests (S-070009)
 
14.2.12.3.34.1  Objectives
 
To verify proper nuclear plant transient response, including automatic control
 
system performance, when load changes are introduced at the turbine generator.
 
14.2.12.3.34.2  Prerequisites
 
Step load changes are initiated from steady state conditions at approximately
 
30-, 75-, and 100-percent power.
 
14.2-182    Rev. 1 WOLF CREEK 14.2.12.3.34.3  Test Method
: a. Manually reduce the turbine generator output as rapidly
 
as possible to achieve an approximate 10-percent load
 
decrease/increase.
: b. Plant variables are recorded, along with values observed
 
on the normal plant instrumentation, during the load
 
transient for those parameters required.
 
14.2.12.3.34.4  Acceptance Criteria
 
The following acceptance criteria are to be used to determine successful test
 
completion. Failure to meet these criteria does not constitute a need for
 
stopping the test program, but correction of any deficiences should be accomplished, as required, consistent with the current plant schedule.
: a. Reactor and turbine must not trip.
: b. Safety injection is not initiated.
: c. Neither steam generator atmospheric relief valves nor safety  valves shall lift.
: d. Neither pressurizer relief valves nor safety valves shall
 
lift.
: e. No manual intervention shall be required to bring plant conditions to steady state.
: f. Nuclear power overshoot (undershoot) must be less than 3
 
percent for load increase (decrease).
 
14.2.12.3.35  Large Load Reduction Test (S-070010)
 
14.2.12.3.35.1  Objectives
 
To demonstrate satisfactory plant transient response to various specified load changes, to monitor the reactor control systems during these transients, and, if necessary, optimize the reactor control system setpoints.
 
14.2.12.3.35.2  Prerequisites
 
Step load reduction changes of 50 percent are initiated from steady state
 
conditions at approximately 75- and 100-percent power.
 
14.2-183 Rev. 13 WOLF CREEK 14.2.12.3.35.3  Test Method
: a. Manually reduce the turbine generator output to achieve
 
an approximate 50-percent load reduction.
: b. Monitor plant response during the transient and record
 
plant variables, as required.
: c. If necessary, adjust the reactor control system setpoints
 
until optimal response is obtained.
 
14.2.12.3.35.4  Acceptance Criteria
 
The following acceptance criteria are to be used to determine successful test  
 
completion. Failure to meet these criteria does not constitute a need for stopping the test program, but correction of any deficiencies should be accomplished, as required, consistent with the current plant schedule.  
: a. Reactor and turbine must not trip.  
: b. Safety injection is not initiated.  
: c. Steam generator safety valves shall not lift.  
: d. Pressurizer safety valves shall not lift.  
: d. Pressurizer safety valves shall not lift.  
: e. No manual intervention shall be required to bring plant conditions to steady state.  
: e. No manual intervention shall be required to bring plant  
 
conditions to steady state.  
 
14.2.12.3.36  Plant Trip From 100 Percent Power (S-070011) 14.2.12.3.36.1  Objectives
 
To verify the ability of the plant automatic control systems to sustain a trip
 
from 100 percent and to bring the plant to stable conditions following the
 
transient, to determine the overall response time of the hot leg resistance
 
temperature detectors, and to evaluate the data resulting from the trip to
 
determine if changes in the control system setpoints are warranted to improve
 
transient response based on actual plant operations.
 
14.2.12.3.36.2  Prerequisites
: a. The rod control system, steam generator level,
 
pressurizer pressure and level, and the steam dump system
 
are in the automatic control mode.
: b. The plant is operating at normal steady state full power.
: c. Diesel generators in standby idling condition.
 
14.2-184 Rev. 1 WOLF CREEK 14.2.12.3.36.3  Test Method
: a. Initiate a plant trip by opening the main generator
 
output breaker, monitor plant response, and record plant
 
variables, as required.
: b. If necessary, adjust the control system setpoints to
 
obtain optimal response.
 
14.2.12.3.36.4  Acceptance Criteria
 
The system parameters must stay within the limitations specified in the
 
vendor's design transient analysis document.
 
14.2.12.3.37  Rods Drop and Plant Trip (S-070012) 14.2.12.3.37.1  Objectives
 
To demonstrate that the negative rate trip circuit will trip the reactor and to
 
monitor plant response.
 
14.2.12.3.37.2  Prerequisites
: a. The rod control system, steam generator level,
 
pressurizer pressure and level, and the feedwater pump
 
speed control are in the automatic control mode. Steam
 
dump control system is in the Tavg mode.
: b. The plant is operating at a steady state power of 30 to
 
50 percent.
: c. The rod group and the selected rods to be dropped have
 
been identified.
 
14.2.12.3.37.3  Test Method
: a. Drop two RCCAs from a common group which, because of
 
their worth and location, are the most difficult to
 
detect by the nuclear instrumentation system (NIS).
: b. Monitor systems behavior and plant response to trip from
 
an intermediate power level prior to the plant trip test
 
from full power.
 
14.2.12.3.37.4  Acceptance Criteria
 
The following acceptance criteria are to be used to determine successful test
 
completion:
 
14.2-185    Rev. 1 WOLF CREEK
: a. The reactor shall have tripped as a result of the negative rate trip.
: b. All RCCAs shall release and bottom on receipt of a trip
 
signal.
: c. The pressurizer safety valves shall not lift.
: d. Steam generator safety valves shall not lift.
: e. Safety injection is not initiated.
 
14.2.12.3.38  Shutdown and Maintenance of Hot Standby External to
 
the Control Room (S-070014)
 
14.2.12.3.38.1  Objectives
 
To demonstrate, using a plant procedure, that the plant can be taken from >
10 percent power to hot standby conditions, and verify that the plant can be maintained in hot standby for at least 30 minutes with a minimum shift crew,
 
using controls and instrumentation external to the control room.
 
14.2.12.3.38.2  Prerequisites
: a. Required component testing and instrument calibration are
 
complete.
: b. Required electrical power supplies and control circuits
 
are operational.
: c. The  plant  is  at  normal  operating  conditions  at >
10          percent power.
: d. The authority and responsibility of the control room
 
observers has been established and is specified in this procedure.
 
14.2.12.3.38.3  Test Method
: a. The plant is taken from >
10 percent power to hot standby conditions, using a plant procedure, minimum shift crew, and controls and instrumentation external to the control
 
room.
: b. Hot standby conditions are maintained for at least 30
 
minutes.
 
14.2-186    Rev. 1 WOLF CREEK
: c. All actions performed by the control room observers is documented within this procedure for use in evaluating
 
their impact on the test results.
 
14.2.12.3.38.4  Acceptance Criteria
 
The plant can be taken from  >
10 percent power to hot standby conditions which are maintained for >
30 minutes, using a plant procedure, minimum shift crew, and controls and instrumentation external to the control room.
 
14.2.12.3.39  Power Ascension Thermal Expansion and Dynamic Test (S-070015)
 
14.2.12.3.39.1  Objectives
: a. To demonstrate during specified power ascension
 
transients that the systems' monitored points respond in
 
accordance with design.
: b. To demonstrate during the heatup to full power
 
temperature that the systems' piping can expand without obstruction and that the expansion is in accordance with design. Also, during the subsequent cooldown to ambient
 
temperature, the piping returns to its cold position in
 
accordance with system design.
 
14.2.12.3.39.2  Prerequisites
: a. Reference points for measurement of the systems are
 
established.
: b. Power ascension testing is in progress.
: c. All subject systems are available for the specified
 
dynamic operations.
: d. Required instrument calibration is complete.
: e. A preservice inspection of the associated piping snubbers
 
has been completed within 6 months.
 
14.2.12.3.39.3  Test Method
: a. Record cold baseline data.
: b. Obtain measurement data at various specified temperature
 
plateaus.
 
14.2-187    Rev. 1 WOLF CREEK
: c. The systems are aligned for the specified dynamic operation.
: d. The specified dynamic event of pump operation, valve
 
operation, etc., is initiated, and the system is monitored for response.
: e. On completion of cooldown to ambient temperature, obtain
 
measurement data.
 
14.2.12.3.39.4  Acceptance Criteria
: a. There shall be no evidence of blocking of the thermal
 
expansion of any piping or components, other than by
 
design.
: b. The total stresses shall not exceed applicable code
 
limits.
: c. Spring hanger movement must remain within the hot and
 
cold set points, snubber swing clearance remains
 
satisfactory., and snubbers must not become fully
 
retracted or expanded.
: d. Piping and components must return to their baseline
 
position on cooldown in accordance with system design.
: e. The measured thermal movement shall be within 25 percent
 
of the analytical value or +
0.25 inch, whichever is greater.
 
14.2.12.3.40  Biological Shield Testing (S-070016)
 
14.2.12.3.40.1  Objectives
: a. To measure and record the neutron and gamma ray radiation
 
levels in accessible areas of the plant where radiation
 
levels above background are anticipated.
: b. To determine locations if any, where shielding is
 
deficient.
: c. To ensure that plant personnel are not subjected to overexposure from radiation as a result of inadequate shielding.
 
14.2.12.3.40.2  Prerequisites
: a. Required instrument calibration is complete.
 
14.2-188    Rev. 1 
 
WOLF CREEK
: b. Appropriate reactor power levels are attained.
 
14.2.12.3.40.3  Test Method
 
Neutron and gamma ray surveys are conducted in each of the following reactor power level ranges.
 
Test                                % Reactor Power Range Preoperational Shield Tests                    <
0 Low Power Tests                              0-5
 
Intermediate Power Tests                      5-50 
 
High Power Tests                            50-100
 
14.2.12.3.40.4  Acceptance Criteria
 
Neutron and gamma ray radiation surveys in all accessible areas of the plant
 
where radiation levels above background are anticipated reveal no shielding
 
deficiencies; or identify and implement appropriate administrative controls in
 
accordance with 10 CFR 20 for the areas determined to be radiation areas.
 
14.2.12.3.41  Loss of Heater Drain Pump Test (S-070017)*
 
14.2.12.3.41.1  Objectives To verify proper nuclear plant response to a loss of heater drain pump
 
accident.
 
14.2.12.3.41.2  Prerequisites
 
The plant is operating at steady state conditions at 90-percent power.
 
14.2.12.3.41.3  Test Method
 
The heater drain pumps are tripped and plant variables are recorded, along with
 
values observed on the normal plant instrumentation, during the transient for
 
those parameters required.
 
_______________________
* This test was performed at Callaway only, with the consent of
 
the NRC, as Callaway and Wolf Creek have identical Heater Drain
 
Systems.
 
14.2-189 Rev. 1 WOLF CREEK 14.2.12.3.41.4  Acceptance Criteria
 
The following acceptance criteria are to be used to determine successful test
 
completion. Failure to meet these criteria does not constitute a need for
 
stopping the test program, but correction of any deficiencies should be accomplished as required, consistent with the current plant schedule.
: a. Reactor and turbine must not trip.
: b. Safety injection is not initiated.
: c. Neither steam generator atmospheric relief valves nor safety  valves shall lift.
: d. Neither pressurizer relief valves nor safety valves shall
 
lift.
: e. No manual intervention shall be required to bring plant conditions to steady state.
 
14.2.12.3.42  Calibration of Steam and Feedwater Flow
 
Instrumentation at Power Test (S-070018)
 
14.2.12.3.42.1  Objectives
: a. To calibrate the steam flow transmitters against feed-
 
water flow.
: b. To perform a cross-check verification of all signals indicating feedwater and steam flow.
 
14.2.12.3.42.2  Prerequisites
: a. Test equipment, including transmitters, has been
 
calibrated for expected ranges of plant conditions.
: b. The plant shall be at steady state conditions for each
 
power level at which testing is performed.
 
14.2.12.3.42.3  Test Method
 
At 30 and 50 percent power, perform Step a if the steam flow/ feedwater flow
 
mismatch alarm actuates. At 75 and 100 percent power, perform Steps a and b.
: a. Verify calibration of the steam flow by comparing steam
 
flow signal to referenced feedwater flow.
 
14.2-190 Rev. 13 WOLF CREEK
: b. Compare, using plots, the steam and feedwater flow values to determine if recalibration is necessary prior to the
 
next power escalation.
 
14.2.12.3.42.4  Acceptance Criteria
: a. Steam flow/feedwater flow mismatch alarm does not actuate
 
at 30, 50, 75, and 100 percent power.
: b. Steam flow indication should be within +
4 percent of feedwater flow panel indicator at 75 and 100 percent power.
: c. The test feedwater flow instrument versus plant feed-water flow instrument and plant steam flow instrument
 
curves should be within +
2.5 percent and +
3.0 percent of their respective ideal curves at 75 and 100 percent power.
 
14.2.12.3.43  Natural Circulation Test (S-090024)*
 
14.2.12.3.43.1  Objectives
 
To demonstrate the length of time required to stabilize natural circulation; to
 
demonstrate core flow distribution during natural circulation using incore
 
thermocouples.
 
14.2.12.3.43.2  Prerequisites
: a. Required low power physics testing has been completed.
: b. Required instrumentation is installed and calibration
 
complete.
: c. The  plant  is operating at steady state conditions at 3
 
percent power.
 
14.2.12.3.43.3  Test Method
 
All reactor coolant pumps are simultaneously tripped while at 3 percent rated
 
power. The transients are monitored and establishment of natural circulation
 
verified.
* Due to similar plant design for Callaway and Wolf Creek, the
 
NRC allowed WCGS to use Callaway Natural Circulation test data
 
and pertinent results.
 
14.2-191    Rev. 1 WOLF CREEK 14.2.12.3.43.4  Acceptance Criteria Natural circulation has been demonstrated. The measured core T as a function of core power under natural circulation conditions is no greater than the
 
limiting reactor coolant system T based on design requirements.
 
14.2-192    Rev. 1 
 
WOLF CREEK TABLE 14.2-1 SAFETY-RELATED PREOPERATIONAL TEST PROCEDURES Test Abstract Test Number Title USAR Section S-03AB01    Steam Dump System Preoperational Test      14.2.12.1.1
 
SU3-AB02    Main Steam Safety Valve Test                14.2.12.1.2
 
S-03AB03    Main Steam Line Isolation Valve Test        14.2.12.1.3 S-03AB04    Main Steam System Preoperational Test      14.2.12.1.4 S-03AE01    Main Feedwater System Preoperational
 
Test                                    14.2.12.1.5 S-03AE02    Steam Generator Level Control Test          14.2.12.1.6 S-03AL01    Auxiliary Feedwater Motor-Driven Pump
 
and Valve Preoperational Test            14.2.12.1.7 SU3-AL02    Auxiliary Feedwater Turbine-Driven Pump and Valve Preoperational Test      14.2.12.1.8
 
SU3-AL03    Auxiliary Feedwater Motor-Driven Pump Endurance Test                          14.2.12.1.9 S-03AL04    Auxiliary Feedwater System Water
 
Hammer Test                              14.2.12.1.10 SU3-AL05    Auxiliary Feedwater Turbine-Driven Pump Endurance Test                          14.2.12.1.11
 
S-03BB01    Reactor Coolant Pump Initial Operation      14.2.12.1.12 SU3-BB02    PRT Cold Preoperational Test                14.2.12.1.13 SU3-BB03    RTD Bypass Flow Measurement                14.2.12.1.14
 
S-03BB04    Pressurizer Pressure Control Test          14.2.12.1.15 S-03BB05    Reactor Coolant System Hot Preoperational Test                                    14.2.12.1.16
 
S-03BB06    Thermal Expansion                          14.2.12.1.17 d-03BB07    Pressurizer Level Control Test              14.2.12.1.18 SU3-BB08    Pressurizer Heater and Spray Capability
 
Test                                    14.2.12.1.19 SU3-BB09    Reactor Coolant System Flow Measurement Test                                    14.2.12.1.20
 
SU3-BB10    Reactor Coolant System Flow Coastdown Test                                    14.2.12.1.21 S-03BB11    Reactor Coolant System Hydrostatic Test    14.2.12.1.22
 
SU3-BB12    Pressurizer Continuous Spray Flow Verification Test                        14.2.12.1.23 S-03BB13    Pressurizer Relief Valve and PRT Hot


14.2.12.3.36  Plant Trip From 100 Percent Power (S-070011)  14.2.12.3.36.1  Objectives
Preoperational Test                      14.2.12.1.24 S-03BB14    Reactor Coolant Loop Vibration Surveillance Test                        14.2.12.1.25


To verify the ability of the plant automatic control systems to sustain a trip from 100 percent and to bring the plant to stable conditions following the transient, to determine the overall response time of the hot leg resistance temperature detectors, and to evaluate the data resulting from the trip to determine if changes in the control system setpoints are warranted to improve transient response based on actual plant operations.  
SU3-BB15A    Leak Detection System Preoperational Test                                    14.2.12.1.26 SU3-BB15B    Leak Detection System Preoperational


14.2.12.3.36.2 Prerequisites
Test                                    14.2.12.1.27 S-03BB16    RTD/TC Cross Calibration                    14.2.12.1.28            Rev. 0 WOLF CREEK TABLE 14.2-1 (Sheet 2)
: a. The rod control system, steam generator level, pressurizer pressure and level, and the steam dump system are in the automatic control mode.  
Test Number Title USAR Section S-03BG01    Chemical and Volume Control System Major Component Test                    14.2.12.1.29 SU3-BG02    Seal Injection Preoperational Test          14.2.12.1.30 SU3-BG03    Charging System Preoperational Test        14.2.12.1.31 SU3-BG04    Boron Thermal Regeneration System Preoperational Test                      14.2.12.1.32
: b. The plant is operating at normal steady state full power.  
: c. Diesel generators in standby idling condition.  


14.2-184 Rev. 1 WOLF CREEK 14.2.12.3.36.3  Test Method 
SU3-BG05    Boric Acid Blending System Preopera-tional Test                              14.2.12.1.33 S-03BG06    Chemical and Volume Control System
: a. Initiate a plant trip by opening the main generator output breaker, monitor plant response, and record plant variables, as required. 
: b. If necessary, adjust the control system setpoints to obtain optimal response.


14.2.12.3.36.4  Acceptance Criteria
Hot Preoperational Test                  14.2.12.1.34 SU3-EC01    Fuel Pool Cooling and Cleanup System Preoperational Test                        14.2.12.1.35


The system parameters must stay within the limitations specified in the vendor's design transient analysis document.  
S-03EC02    Spent Fuel Pool Leak Test                  14.2.12.1.36 SU3-EF01    Essential Service Water System Pre-operational Test                        14.2.12.1.37


14.2.12.3.37 Rods Drop and Plant Trip (S-070012)  14.2.12.3.37.1  Objectives
SU3-EF02    Essential Service Water Pump Preopera-tional Test                              14.2.12.1.37 S-03EG01    Component Cooling Water System Pre-


To demonstrate that the negative rate trip circuit will trip the reactor and to monitor plant response.  
operational Test                        14.2.12.1.38 SU3-EJ01    Residual Heat Removal System Cold Pre-operational Test                        14.2.12.1.39


14.2.12.3.37.2  Prerequisites
SU3-EJ02    Residual Heat Removal System Hot Preoperational Test                      14.2.12.1.40 SU3-EM01    Safety Injection System Cold Pre-
: a. The rod control system, steam generator level, pressurizer pressure and level, and the feedwater pump speed control are in the automatic control mode. Steam dump control system is in the Tavg mode.
: b. The plant is operating at a steady state power of 30 to 50 percent.      c. The rod group and the selected rods to be dropped have been identified.  


14.2.12.3.37.3  Test Method
operational Test                        14.2.12.1.41 SU3-EM02    Safety Injection Flow Verification Test    14.2.12.1.42 SU3-EM03    Safety Injection Check Valve Test           14.2.12.1.43 SU3-EM04    Boron Injection Tank and Recirculation Pump Test                                14.2.12.1.44 S-03EN01    Containment Spray System Nozzle Air Test                                    14.2.12.1.45 SU3-EN02    Containment Spray System Preoperational Test                                    14.2.12.1.46
: a. Drop two RCCAs from a common group which, because of their worth and location, are the most difficult to detect by the nuclear instrumentation system (NIS).  
: b. Monitor systems behavior and plant response to trip from an intermediate power level prior to the plant trip test from full power.  


14.2.12.3.37.4  Acceptance Criteria
S-03EP01    Accumulator Testing                        14.2.12.1.47 SU3-FC01    Auxiliary Feedwater Pump Turbine Preoperational Test                      14.2.12.1.48


The following acceptance criteria are to be used to determine successful test completion:
SU3-GD01    Essential Service Water Pumphouse HVAC Preoperational Test                14.2.12.1.49 SU3-GF01    Miscellaneous Building HVAC System


14.2-185    Rev. 1 WOLF CREEK      a. The reactor shall have tripped as a result of the          negative rate trip.
SU3-GF02        Preoperational Tests SU3-GF03                                                14.2.12.1.50 S-03GG01    Fuel Building HVAC System Preoperational
: b. All RCCAs shall release and bottom on receipt of a trip signal. 
: c. The pressurizer safety valves shall not lift.
: d. Steam generator safety valves shall not lift.
: e. Safety injection is not initiated.  


14.2.12.3.38  Shutdown and Maintenance of Hot Standby External to the Control Room (S-070014) 14.2.12.3.38.1 Objectives To demonstrate, using a plant procedure, that the plant can be taken from >10 percent power to hot standby conditions, and verify that the plant can be maintained in hot standby for at least 30 minutes with a minimum shift crew, using controls and instrumentation external to the control room.
Test                                    14.2.12.1.51 SU3-GK01    Control Building HVAC System Preopera-tional Test                              14.2.12.1.52
14.2.12.3.38.2  Prerequisites
: a. Required component testing and instrument calibration are complete.
: b. Required electrical power supplies and control circuits are operational.
: c. The  plant  is  at  normal  operating  conditions  at >10          percent power. 
: d. The authority and responsibility of the control room observers has been established and is specified in this          procedure.  


14.2.12.3.38.3  Test Method
SU3-GL01    Auxiliary Building HVAC System Pre-operational Test                        14.2.12.1.53 S-03GM01    Diesel Generator Building HVAC Pre-
: a. The plant is taken from >10 percent power to hot standby          conditions, using a plant procedure, minimum shift crew,          and controls and instrumentation external to the control room.
: b. Hot standby conditions are maintained for at least 30 minutes.  


14.2-186    Rev. 1 WOLF CREEK     c. All actions performed by the control room observers is          documented within this procedure for use in evaluating their impact on the test results.  
operational Test                        14.2.12.1.54            Rev. 3 WOLF CREEK TABLE 14.2-1 (Sheet 3)
Test Number Title USAR Section SU3-GN01    Containment Cooling System Preoperational Test                                    14.2.12.1.55 S-03GN02    CRDM Cooling Preoperational Test            14.2.12.1.56 SU3-GP01    Integrated Containment Leak Rate Test                                    14.2.12.1.57 SU3-GP02    Reactor Containment Structural Integ-


14.2.12.3.38.4  Acceptance Criteria The plant can be taken from  > 10 percent power to hot standby conditions which are maintained for >30 minutes, using a plant procedure, minimum shift crew, and controls and instrumentation external to the control room.  
rity Acceptance Test                    14.2.12.1.58 S-03GS01    Post-Accident Hydrogen Removal System Preoperational Test                      14.2.12.1.59


14.2.12.3.39  Power Ascension Thermal Expansion and Dynamic Test              (S-070015)
S-03GT01    Containment Purge System HVAC Pre-operational Test                        14.2.12.1.60 S-03HA01    Gaseous Radwaste System Preoperational


14.2.12.3.39.1 Objectives
Test                                    14.2.12.1.61 S-03JE01    Emergency Fuel Oil System Preoperational Test                                    14.2.12.1.62
: a. To demonstrate during specified power ascension transients that the systems' monitored points respond in accordance with design.  
: b. To demonstrate during the heatup to full power temperature that the systems' piping can expand without          obstruction and that the expansion is in accordance with          design. Also, during the subsequent cooldown to ambient temperature, the piping returns to its cold position in accordance with system design.  


14.2.12.3.39.2 Prerequisites
SU3-KE01    Spent Fuel Pool Crane Preoperational Test                                    14.2.12.1.63 SU3-KE02    New Fuel Elevator Preoperational Test      14.2.12.1.64
: a. Reference points for measurement of the systems are established.
: b. Power ascension testing is in progress.
: c. All subject systems are available for the specified dynamic operations.
: d. Required instrument calibration is complete. 
: e. A preservice inspection of the associated piping snubbers has been completed within 6 months.  


14.2.12.3.39.3  Test Method
SU3-KE03    Fuel Handling and Storage Preoperational Test                                    14.2.12.1.65 SU3-KE04    Fuel Transfer System Preoperational
: a. Record cold baseline data.
: b. Obtain measurement data at various specified temperature plateaus.  


14.2-187    Rev. 1 WOLF CREEK      c. The systems are aligned for the specified dynamic          operation.  
Test                                    14.2.12.1.66 SU3-KE05    Refueling Machine and RCC Change Fixture Preoperational Test              14.2.12.1.67
: d. The specified dynamic event of pump operation, valve operation, etc., is initiated, and the system is          monitored for response.
: e. On completion of cooldown to ambient temperature, obtain measurement data.  


14.2.12.3.39.4  Acceptance Criteria
S-03KE06    Refueling Machine Indexing Test            14.2.12.1.68 SU3-KE07    Fuel Handling System Integrated Preoperational Test                      14.2.12.1.69
: a. There shall be no evidence of blocking of the thermal expansion of any piping or components, other than by design.      b. The total stresses shall not exceed applicable code limits.
: c. Spring hanger movement must remain within the hot and cold set points, snubber swing clearance remains satisfactory., and snubbers must not become fully retracted or expanded.
: d. Piping and components must return to their baseline position on cooldown in accordance with system design.
: e. The measured thermal movement shall be within 25 percent of the analytical value or +0.25 inch, whichever is          greater.
14.2.12.3.40  Biological Shield Testing (S-070016) 14.2.12.3.40.1 Objectives
: a. To measure and record the neutron and gamma ray radiation levels in accessible areas of the plant where radiation levels above background are anticipated.
: b. To determine locations if any, where shielding is deficient.
: c. To ensure that plant personnel are not subjected to          overexposure from radiation as a result of inadequate          shielding.  


14.2.12.3.40.2  Prerequisites
S-03KJ01    Diesel Generator Mechanical Preopera-tional Test                              14.2.12.1.70 S-03NB01    4160-V (Class IE) System Preoperational
: a. Required instrument calibration is complete.  


14.2-188    Rev. 1 WOLF CREEK      b. Appropriate reactor power levels are attained.
Test                                    14.2.12.1.71 S-03NE01    Diesel Generator Electrical Preopera-tional Test                              14.2.12.1.72
14.2.12.3.40.3  Test Method


Neutron and gamma ray surveys are conducted in each of the following reactor power level ranges.  
SU3-NF01    Integrated Control Logic Test              14.2.12.1.73 S-03NF02    LOCA Sequencer Preoperational Test          14.2.12.1.74 S-03NF03    Shutdown Sequencer Preoperational Test      14.2.12.1.75


Test                                % Reactor Power Range  Preoperational Shield Tests                    <0 Low Power Tests                              0-5 Intermediate Power Tests                      5-50 High Power Tests                            50-100 14.2.12.3.40.4  Acceptance Criteria
S-03NG01    480-V (Class IE) System Preoperational Test                                    14.2.12.1.76 SU3-NG02    480-V Class IE System (ESW) Preopera-


Neutron and gamma ray radiation surveys in all accessible areas of the plant where radiation levels above background are anticipated reveal no shielding deficiencies; or identify and implement appropriate administrative controls in accordance with 10 CFR 20 for the areas determined to be radiation areas.  
tional Test                              14.2.12.1.77 S-03NK01    125-V (Class IE) DC System Preopera-tional Test                              14.2.12.1.78


14.2.12.3.41  Loss of Heater Drain Pump Test (S-070017)*
S-03NN01    Instrument AC System (Class IE) Pre-operational Test                        14.2.12.1.79 SU3-SA01    Engineered Safeguards (NSSS) Preopera-  


14.2.12.3.41.1 Objectives  To verify proper nuclear plant response to a loss of heater drain pump accident.  
tional Test                              14.2.12.1.80            Rev. 0 WOLF CREEK TABLE 14.2-1 (Sheet 4)
Test Number Title USAR Section SU3-SA02    Engineered Safeguards (BOP) Pre-operational Test                        14.2.12.1.81 SU3-SA03    Engineered Safeguards Verification Test    14.2.12.1.82 S-03SB01    Reactor Protection System Logic Test        14.2.12.1.83 S-03SJ01    Primary Sampling System Preoperational Test                                    14.2.12.1.84


14.2.12.3.41.2  Prerequisites
S-03SP01    Process Radiation Monitoring System Preoperational Test                      14.2.12.1.85 SU3-0004    Power conversion and ECCS Systems


The plant is operating at steady state conditions at 90-percent power.  
Thermal Expansion Test                  14.2.12.1.86 S-030005    Power Conversion and ECCS Systems Dynamic Test                            14.2.12.1.87


14.2.12.3.41.3  Test Method
SU3-0006    HEPA Filter Test                            14.2.12.1.88 S-030008    Cooldown from Hot Standby External to the Control Room                        14.2.12.1.89


The heater drain pumps are tripped and plant variables are recorded, along with values observed on the normal plant instrumentation, during the transient for those parameters required.  
S-030009    Compressed Gas Accumulator Testing          14.2.12.1.90            Rev. 0 WOLF CREEK TABLE 14.2-2 NONSAFETY-RELATED PREOPERATIONAL TESTS Test Number                      Title USAR Section S-04AC02    Turbine Trip Test                          14.2.12.2.1 S-04AC03    Turbine System Cold Test                    14.2.12.2.2 S-04AD01    Condensate System Preoperational Test      14.2.12.2.3 S-04AF01    Secondary Vent and Drain System Pre-operational Test                        14.2.12.2.4 S-04AQ01    Condensate and Feedwater Chemical Feed System Preoperational Test              14.2.12.2.5 S-04BL01    Reactor Makeup Water System Preopera-tional Test                              14.2.12.2.6 S-04CG01    Condenser Air Removal System Pre-operational Test                        14.2.12.2.7


_______________________
SU4-DA01    Circulating Water System Preoperational Test                                    14.2.12.2.8 S-04EA01    Service Water System Preoperational Test    14.2.12.2.9 S-04EB01    Closed Cooling Water System Preopera-tional Test                              14.2.12.2.10 SU4-FP03    Fire Protection System Preoperational Test                                    14.2.12.2.11 S-04GH01    Radwaste Building HVAC System Pre-operational Test                        14.2.12.2.12 SU8-GP01    Local Containment Leak Rate Test            14.2.12.2.13 S-04HB01    Liquid Radwaste System Preoperational Test                                    14.2.12.2.14
* This test was performed at Callaway only, with the consent of the NRC, as Callaway and Wolf Creek have identical Heater Drain Systems.  


14.2-189 Rev. 1 WOLF CREEK 14.2.12.3.41.4  Acceptance Criteria The following acceptance criteria are to be used to determine successful test completion. Failure to meet these criteria does not constitute a need for stopping the test program, but correction of any deficiencies should be accomplished as required, consistent with the current plant schedule.  
SU4-HB02    Waste Evaporator Preoperational Test        14.2.12.2.15 S-04HC01    Solid Waste System Preoperational Test      14.2.12.2.16 S-04HC02    Solid Waste Filter Handling System Preoperational Test                      14.2.12.2.17 SU4-HC03    Resin Transfer Preoperational Test          14.2.12.2.18 SU4-KC01A    Fire Protection System (Water) Pre-
: a. Reactor and turbine must not trip.  
: b. Safety injection is not initiated.  
: c. Neither steam generator atmospheric relief valves nor safety  valves shall lift.       d. Neither pressurizer relief valves nor safety valves shall lift.  
: e. No manual intervention shall be required to bring plant          conditions to steady state.  


14.2.12.3.42  Calibration of Steam and Feedwater Flow Instrumentation at Power Test (S-070018)
SU4-KC01B      operational Test                        14.2.12.2.19 S-04KC02    Fire Protection System (Halon) Pre-operational Test                        14.2.12.2.20 S-04KC03    Fire Protection System Detection and Alarm Preoperational Test               14.2.12.2.21 S-04LE01    Oily Waste System Preoperational Test      14.2.12.2.22


14.2.12.3.42.1  Objectives
SU4-LF01    Floor and Equipment Drain System Pre-operational Test                        14.2.12.2.23 S-04PA01    13.8-kV System Preoperational Test          14.2.12.2.24
: a. To calibrate the steam flow transmitters against feed-water flow.  
: b. To perform a cross-check verification of all signals          indicating feedwater and steam flow.  


14.2.12.3.42.2 Prerequisites
S-04PB01    4,160-V (Non-Class IE) System Pre-operational Test                        14.2.12.2.25 S-04PG01    480-Volt (Non-Class IE) System Pre-
: a. Test equipment, including transmitters, has been calibrated for expected ranges of plant conditions.
: b. The plant shall be at steady state conditions for each power level at which testing is performed.


14.2.12.3.42.3  Test Method
operational Test                        14.2.12.2.26 Rev. 0 WOLF CREEK TABLE 14.2-2 (Sheet 2)
Test Number                      Title USAR Section S-04PJ01    250-V DC System Preoperational Test         14.2.12.2.27 S-04PK01    125-V (Non-Class IE) DC System Pre-


At 30 and 50 percent power, perform Step a if the steam flow/ feedwater flow mismatch alarm actuates. At 75 and 100 percent power, perform Steps a and b.       a. Verify calibration of the steam flow by comparing steam flow signal to referenced feedwater flow.  
S-04PK02        operational Test                        14.2.12.2.28 S-04PN01    Instrument AC (Non-Class IE) System Pre-operational Test                        14.2.12.2.29 S-04QD01    Emergency Lighting System Preopera-tional Test                              14.2.12.2.30 S-04QF01    Public Address System Preoperational Test                                    14.2.12.2.31 S-04QJ01    Heat Tracing Freeze Protection System Preoperational Test                      14.2.12.2.32 S-04RM01    Secondary Sampling System Preoperational Test                                    14.2.12.2.33 S-04SD01    Area Radiation Monitoring Preoperational Test                                    14.2.12.2.34 S-04SG01    Seismic Monitoring Instrumentation System Preoperational Test              14.2.12.2.35 SU4-SQ02    Loose Parts Monitoring System Test          14.2.12.2.36 SU8-0007    Plant Performance Test                      14.2.12.2.37 S-090023    Electrical Distribution System Voltage


14.2-190 Rev. 13 WOLF CREEK     b. Compare, using plots, the steam and feedwater flow values          to determine if recalibration is necessary prior to the next power escalation.  
Verification Test                        14.2.12.2.38 Rev. 0 WOLF CREEK TABLE 14.2-3 INITIAL STARTUP TEST Test Number                      Title USAR Section S-07AB01    Automatic Steam Generator Level Control    14.2.12.3.1 SU7-AB02    Dynamic Automatic Steam Dump Control        14.2.12.3.2 S-07BB01    RTD Bypass Flow Measurement                14.2.12.3.3 S-07BB02    Pressurizer Heater and Spray Capability Test                                    14.2.12.3.4 S-07BB03    Reactor Coolant System Flow Measurement    14.2.12.3.5 SU7-BB04    Reactor Coolant System Flow Coastdown Test                                    14.2.12.3.6 S-07BB05    Pressurizer Contiuous Spray Flow Verification                            14.2.12.3.7 S-07BB06    RTD/TC Cross Calibration                    14.2.12.3.8


14.2.12.3.42.4  Acceptance Criteria 
S-07SC01    Core Loading Instrumentation and Neutron Source Requirements                      14.2.12.3.9 S-07SC03    Thermal Power Measurement and Statepoint Data Collection                          14.2.12.3.10 SU7-SE01    Nuclear Instrumentation System Test        14.2.12.3.11 S-07SE02    Operational Alignment of Nuclear Instru-mentation                                14.2.12.3.12 S-07SE03    Axial Flux Difference Instrumentation Calibration                              14.2.12.3.13 S-07SF01    Control Rod Drive Mechanism Operational Test                                    14.2.12.3.14 S-07SF02    Rod Control System                          14.2.12.3.15
: a. Steam flow/feedwater flow mismatch alarm does not actuate at 30, 50, 75, and 100 percent power.  
: b. Steam flow indication should be within +4 percent of         feedwater flow panel indicator at 75 and 100 percent          power.  
: c. The test feedwater flow instrument versus plant feed-         water flow instrument and plant steam flow instrument curves should be within +2.5 percent and +3.0 percent of          their respective ideal curves at 75 and 100 percent          power.  


14.2.12.3.43  Natural Circulation Test (S-090024)*
SU7-SF03    Rod Drop Time Measurement                  14.2.12.3.16 SU7-SF04    Rod Position Indication System              14.2.12.3.17 S-07SF05    Automatic Reactor Control System            14.2.12.3.18 S-07SR01/    Incore Flux Mapping S-07SR02                                                14.2.12.3.19 S-07SR03/    Incore Instrumentation Test
14.2.12.3.43.1  Objectives


To demonstrate the length of time required to stabilize natural circulation; to demonstrate core flow distribution during natural circulation using incore thermocouples.  
S-07SR04                                                14.2.12.3.20 S-07SF06    Operational Alignment of Process Temperature Instrumentation              14.2.12.3.21 S-07SF07    Startup Adjustments of Reactor Control System                          14.2.12.3.22 S-07SF08    RCCA or Bank Worth Measurement at


14.2.12.3.43.2 Prerequisites
Zero Power                              14.2.12.3.23 SU7-SF09    RCCA or Bank Worth Measurement at Power                                    14.2.12.3.24
: a. Required low power physics testing has been completed.      b. Required instrumentation is installed and calibration complete.
: c. The  plant  is operating at steady state conditions at 3 percent power.  


14.2.12.3.43.3 Test Method
S-07SJ01    Reactor Systems Sampling for Core Load                                    14.2.12.3.25 SU7-0001    Initial Core Loading                        14.2.12.3.26


All reactor coolant pumps are simultaneously tripped while at 3 percent rated power. The transients are monitored and establishment of natural circulation verified.
S-070002    Inverse Count Rate Ratio Monitoring for Core Loading                        14.2.12.3.27 Rev. 0 WOLF CREEK TABLE 14.2-3 (Sheet 2)
* Due to similar plant design for Callaway and Wolf Creek, the NRC allowed WCGS to use Callaway Natural Circulation test data and pertinent results.  
Test Number                      Title USAR Section S-070003    Inverse Count Rate Ratio Monitoring for Approach to Initial Criticality      14.2.12.3.28


14.2-191    Rev. 1 WOLF CREEK 14.2.12.3.43.4  Acceptance Criteria  Natural circulation has been demonstrated. The measured core T as a function of core power under natural circulation conditions is no greater than the limiting reactor coolant system T based on design requirements.  
S-070004    Initial Criticality                        14.2.12.3.29 S-070005    Determination of Core Power Range for Physics Testing                          14.2.12.3.30 S-070006    Boron Endpoint Determination                14.2.12.3.31 S-070007    Isothermal Temperature Coefficient Measurement                              14.2.12.3.32 S-070008    Power Coefficient Determination            14.2.12.3.33 S-070009    Load Swing Tests                            14.2.12.3.34 S-070010    Large Load Reduction Test                  14.2.12.3.35 S-070011    Plant Trip from 100 Percent Power          14.2.12.3.36 S-070012    Rods Drop and Plant Trip                    14.2.12.3.37 S-070014    Shutdown and Maintenance of Hot Standby External to the Control Room            14.2.12.3.38 S-070015    Power Ascension Thermal Expansion and Dynamic Test                        14.2.12.3.39 S-070016    Biological Shield Testing                  14.2.12.3.40 S-070017    Loss of Heater Drain Pump Test              14.2.12.3.41 S-070018    Calibration of Steam and Feedwater


14.2-192    Rev. 1 WOLF CREEK TABLE 14.2-1              SAFETY-RELATED PREOPERATIONAL TEST PROCEDURES                                                          Test Abstract Test Number                      Title                  USAR SectionS-03AB01    Steam Dump System Preoperational Test      14.2.12.1.1 SU3-AB02    Main Steam Safety Valve Test                14.2.12.1.2 S-03AB03    Main Steam Line Isolation Valve Test        14.2.12.1.3 S-03AB04    Main Steam System Preoperational Test      14.2.12.1.4 S-03AE01    Main Feedwater System Preoperational Test                                    14.2.12.1.5 S-03AE02    Steam Generator Level Control Test          14.2.12.1.6 S-03AL01    Auxiliary Feedwater Motor-Driven Pump and Valve Preoperational Test            14.2.12.1.7 SU3-AL02    Auxiliary Feedwater Turbine-Driven                Pump and Valve Preoperational Test      14.2.12.1.8 SU3-AL03    Auxiliary Feedwater Motor-Driven Pump                Endurance Test                          14.2.12.1.9 S-03AL04    Auxiliary Feedwater System Water Hammer Test                              14.2.12.1.10 SU3-AL05    Auxiliary Feedwater Turbine-Driven Pump                Endurance Test                          14.2.12.1.11 S-03BB01    Reactor Coolant Pump Initial Operation      14.2.12.1.12 SU3-BB02    PRT Cold Preoperational Test                14.2.12.1.13 SU3-BB03    RTD Bypass Flow Measurement                14.2.12.1.14 S-03BB04    Pressurizer Pressure Control Test          14.2.12.1.15 S-03BB05    Reactor Coolant System Hot Preoperational                Test                                    14.2.12.1.16 S-03BB06    Thermal Expansion                          14.2.12.1.17 d-03BB07    Pressurizer Level Control Test              14.2.12.1.18 SU3-BB08    Pressurizer Heater and Spray Capability Test                                    14.2.12.1.19 SU3-BB09    Reactor Coolant System Flow Measurement                Test                                    14.2.12.1.20 SU3-BB10    Reactor Coolant System Flow Coastdown                Test                                    14.2.12.1.21 S-03BB11    Reactor Coolant System Hydrostatic Test    14.2.12.1.22 SU3-BB12    Pressurizer Continuous Spray Flow                Verification Test                        14.2.12.1.23 S-03BB13    Pressurizer Relief Valve and PRT Hot Preoperational Test                      14.2.12.1.24 S-03BB14    Reactor Coolant Loop Vibration                Surveillance Test                        14.2.12.1.25 SU3-BB15A    Leak Detection System Preoperational                Test                                    14.2.12.1.26 SU3-BB15B    Leak Detection System Preoperational Test                                    14.2.12.1.27 S-03BB16    RTD/TC Cross Calibration                    14.2.12.1.28            Rev. 0 WOLF CREEK                        TABLE 14.2-1 (Sheet 2) Test Number                      Title                  USAR SectionS-03BG01    Chemical and Volume Control System                Major Component Test                    14.2.12.1.29 SU3-BG02    Seal Injection Preoperational Test          14.2.12.1.30 SU3-BG03    Charging System Preoperational Test        14.2.12.1.31 SU3-BG04    Boron Thermal Regeneration System                Preoperational Test                      14.2.12.1.32 SU3-BG05    Boric Acid Blending System Preopera-                tional Test                              14.2.12.1.33 S-03BG06    Chemical and Volume Control System Hot Preoperational Test                  14.2.12.1.34 SU3-EC01    Fuel Pool Cooling and Cleanup System              Preoperational Test                        14.2.12.1.35 S-03EC02    Spent Fuel Pool Leak Test                  14.2.12.1.36 SU3-EF01    Essential Service Water System Pre-                operational Test                        14.2.12.1.37 SU3-EF02    Essential Service Water Pump Preopera-                tional Test                              14.2.12.1.37 S-03EG01    Component Cooling Water System Pre-operational Test                        14.2.12.1.38 SU3-EJ01    Residual Heat Removal System Cold Pre-                operational Test                        14.2.12.1.39 SU3-EJ02    Residual Heat Removal System Hot                Preoperational Test                      14.2.12.1.40 SU3-EM01    Safety Injection System Cold Pre-operational Test                        14.2.12.1.41 SU3-EM02    Safety Injection Flow Verification Test    14.2.12.1.42SU3-EM03    Safety Injection Check Valve Test          14.2.12.1.43 SU3-EM04    Boron Injection Tank and Recirculation                Pump Test                                14.2.12.1.44 S-03EN01    Containment Spray System Nozzle Air                Test                                    14.2.12.1.45 SU3-EN02    Containment Spray System Preoperational                Test                                    14.2.12.1.46 S-03EP01    Accumulator Testing                        14.2.12.1.47 SU3-FC01    Auxiliary Feedwater Pump Turbine                Preoperational Test                      14.2.12.1.48 SU3-GD01    Essential Service Water Pumphouse                HVAC Preoperational Test                14.2.12.1.49 SU3-GF01    Miscellaneous Building HVAC System SU3-GF02        Preoperational Tests SU3-GF03                                                14.2.12.1.50 S-03GG01    Fuel Building HVAC System Preoperational Test                                    14.2.12.1.51 SU3-GK01    Control Building HVAC System Preopera-                tional Test                              14.2.12.1.52 SU3-GL01    Auxiliary Building HVAC System Pre-                operational Test                        14.2.12.1.53 S-03GM01    Diesel Generator Building HVAC Pre-operational Test                        14.2.12.1.54            Rev. 3 WOLF CREEK                        TABLE 14.2-1 (Sheet 3) Test Number                      Title                  USAR SectionSU3-GN01    Containment Cooling System Preoperational                Test                                    14.2.12.1.55 S-03GN02    CRDM Cooling Preoperational Test            14.2.12.1.56 SU3-GP01    Integrated Containment Leak Rate                Test                                    14.2.12.1.57 SU3-GP02    Reactor Containment Structural Integ-rity Acceptance Test                    14.2.12.1.58 S-03GS01    Post-Accident Hydrogen Removal System                Preoperational Test                      14.2.12.1.59 S-03GT01    Containment Purge System HVAC Pre-                operational Test                        14.2.12.1.60 S-03HA01    Gaseous Radwaste System Preoperational Test                                    14.2.12.1.61 S-03JE01    Emergency Fuel Oil System Preoperational                Test                                    14.2.12.1.62 SU3-KE01    Spent Fuel Pool Crane Preoperational                Test                                    14.2.12.1.63 SU3-KE02    New Fuel Elevator Preoperational Test      14.2.12.1.64 SU3-KE03    Fuel Handling and Storage Preoperational                Test                                    14.2.12.1.65 SU3-KE04    Fuel Transfer System Preoperational Test                                    14.2.12.1.66 SU3-KE05    Refueling Machine and RCC Change                Fixture Preoperational Test              14.2.12.1.67 S-03KE06    Refueling Machine Indexing Test            14.2.12.1.68 SU3-KE07    Fuel Handling System Integrated                Preoperational Test                      14.2.12.1.69 S-03KJ01    Diesel Generator Mechanical Preopera-                tional Test                              14.2.12.1.70 S-03NB01    4160-V (Class IE) System Preoperational Test                                    14.2.12.1.71 S-03NE01    Diesel Generator Electrical Preopera-                tional Test                              14.2.12.1.72 SU3-NF01    Integrated Control Logic Test              14.2.12.1.73 S-03NF02    LOCA Sequencer Preoperational Test          14.2.12.1.74 S-03NF03    Shutdown Sequencer Preoperational Test      14.2.12.1.75 S-03NG01    480-V (Class IE) System Preoperational                Test                                    14.2.12.1.76 SU3-NG02    480-V Class IE System (ESW) Preopera-tional Test                              14.2.12.1.77 S-03NK01    125-V (Class IE) DC System Preopera-                tional Test                              14.2.12.1.78 S-03NN01    Instrument AC System (Class IE) Pre-                operational Test                        14.2.12.1.79 SU3-SA01    Engineered Safeguards (NSSS) Preopera-tional Test                              14.2.12.1.80            Rev. 0 WOLF CREEK                        TABLE 14.2-1 (Sheet 4) Test Number                      Title                  USAR SectionSU3-SA02    Engineered Safeguards (BOP) Pre-                operational Test                        14.2.12.1.81 SU3-SA03    Engineered Safeguards Verification Test    14.2.12.1.82 S-03SB01    Reactor Protection System Logic Test        14.2.12.1.83 S-03SJ01    Primary Sampling System Preoperational                Test                                    14.2.12.1.84 S-03SP01    Process Radiation Monitoring System                Preoperational Test                      14.2.12.1.85 SU3-0004    Power conversion and ECCS Systems Thermal Expansion Test                  14.2.12.1.86 S-030005    Power Conversion and ECCS Systems                Dynamic Test                            14.2.12.1.87 SU3-0006    HEPA Filter Test                            14.2.12.1.88 S-030008    Cooldown from Hot Standby External to                the Control Room                        14.2.12.1.89 S-030009    Compressed Gas Accumulator Testing          14.2.12.1.90            Rev. 0 WOLF CREEK                            TABLE 14.2-2                NONSAFETY-RELATED PREOPERATIONAL TESTSTest Number                      Title                  USAR SectionS-04AC02    Turbine Trip Test                          14.2.12.2.1S-04AC03    Turbine System Cold Test                    14.2.12.2.2S-04AD01    Condensate System Preoperational Test      14.2.12.2.3S-04AF01    Secondary Vent and Drain System Pre-                operational Test                        14.2.12.2.4S-04AQ01    Condensate and Feedwater Chemical Feed                System Preoperational Test              14.2.12.2.5S-04BL01    Reactor Makeup Water System Preopera-                tional Test                              14.2.12.2.6S-04CG01    Condenser Air Removal System Pre-                operational Test                        14.2.12.2.7 SU4-DA01    Circulating Water System Preoperational                Test                                    14.2.12.2.8S-04EA01    Service Water System Preoperational Test    14.2.12.2.9S-04EB01    Closed Cooling Water System Preopera-                tional Test                              14.2.12.2.10SU4-FP03    Fire Protection System Preoperational                Test                                    14.2.12.2.11S-04GH01    Radwaste Building HVAC System Pre-                operational Test                        14.2.12.2.12SU8-GP01    Local Containment Leak Rate Test            14.2.12.2.13S-04HB01    Liquid Radwaste System Preoperational                Test                                    14.2.12.2.14 SU4-HB02    Waste Evaporator Preoperational Test        14.2.12.2.15S-04HC01    Solid Waste System Preoperational Test      14.2.12.2.16S-04HC02    Solid Waste Filter Handling System                Preoperational Test                      14.2.12.2.17SU4-HC03    Resin Transfer Preoperational Test          14.2.12.2.18SU4-KC01A    Fire Protection System (Water) Pre-SU4-KC01B      operational Test                        14.2.12.2.19S-04KC02    Fire Protection System (Halon) Pre-                operational Test                        14.2.12.2.20S-04KC03    Fire Protection System Detection and                Alarm Preoperational Test                14.2.12.2.21S-04LE01    Oily Waste System Preoperational Test      14.2.12.2.22 SU4-LF01    Floor and Equipment Drain System Pre-                operational Test                        14.2.12.2.23S-04PA01    13.8-kV System Preoperational Test          14.2.12.2.24 S-04PB01    4,160-V (Non-Class IE) System Pre-                operational Test                        14.2.12.2.25S-04PG01    480-Volt (Non-Class IE)  System Pre-operational Test                        14.2.12.2.26Rev. 0 WOLF CREEK                        TABLE 14.2-2 (Sheet 2)Test Number                      Title                  USAR SectionS-04PJ01    250-V DC System Preoperational Test        14.2.12.2.27S-04PK01    125-V (Non-Class IE) DC System Pre-S-04PK02        operational Test                        14.2.12.2.28S-04PN01    Instrument AC (Non-Class IE) System Pre-                operational Test                        14.2.12.2.29S-04QD01    Emergency Lighting System Preopera-                tional Test                              14.2.12.2.30S-04QF01    Public Address System Preoperational                Test                                    14.2.12.2.31S-04QJ01    Heat Tracing Freeze Protection System                Preoperational Test                      14.2.12.2.32S-04RM01    Secondary Sampling System Preoperational                Test                                    14.2.12.2.33S-04SD01    Area Radiation Monitoring Preoperational                Test                                    14.2.12.2.34S-04SG01    Seismic Monitoring Instrumentation                System Preoperational Test              14.2.12.2.35SU4-SQ02    Loose Parts Monitoring System Test          14.2.12.2.36SU8-0007    Plant Performance Test                      14.2.12.2.37S-090023    Electrical Distribution System Voltage Verification Test                        14.2.12.2.38Rev. 0 WOLF CREEK                            TABLE 14.2-3                        INITIAL STARTUP TESTTest Number                      Title                  USAR SectionS-07AB01    Automatic Steam Generator Level Control    14.2.12.3.1SU7-AB02    Dynamic Automatic Steam Dump Control        14.2.12.3.2S-07BB01    RTD Bypass Flow Measurement                14.2.12.3.3S-07BB02    Pressurizer Heater and Spray Capability                Test                                    14.2.12.3.4S-07BB03    Reactor Coolant System Flow Measurement    14.2.12.3.5SU7-BB04    Reactor Coolant System Flow Coastdown                Test                                    14.2.12.3.6S-07BB05    Pressurizer Contiuous Spray Flow                Verification                            14.2.12.3.7S-07BB06    RTD/TC Cross Calibration                    14.2.12.3.8 S-07SC01    Core Loading Instrumentation and Neutron                Source Requirements                      14.2.12.3.9S-07SC03    Thermal Power Measurement and Statepoint                Data Collection                          14.2.12.3.10SU7-SE01    Nuclear Instrumentation System Test        14.2.12.3.11S-07SE02    Operational Alignment of Nuclear Instru-                mentation                                14.2.12.3.12S-07SE03    Axial Flux Difference Instrumentation                Calibration                              14.2.12.3.13S-07SF01    Control Rod Drive Mechanism Operational                Test                                    14.2.12.3.14S-07SF02    Rod Control System                          14.2.12.3.15 SU7-SF03    Rod Drop Time Measurement                  14.2.12.3.16SU7-SF04    Rod Position Indication System              14.2.12.3.17S-07SF05    Automatic Reactor Control System            14.2.12.3.18S-07SR01/    Incore Flux MappingS-07SR02                                                14.2.12.3.19S-07SR03/    Incore Instrumentation Test S-07SR04                                                14.2.12.3.20S-07SF06    Operational Alignment of Process                Temperature Instrumentation              14.2.12.3.21S-07SF07    Startup Adjustments of Reactor                Control System                          14.2.12.3.22S-07SF08    RCCA or Bank Worth Measurement at Zero Power                               14.2.12.3.23SU7-SF09    RCCA or Bank Worth Measurement at                Power                                    14.2.12.3.24 S-07SJ01    Reactor Systems Sampling for Core                Load                                    14.2.12.3.25SU7-0001    Initial Core Loading                        14.2.12.3.26 S-070002    Inverse Count Rate Ratio Monitoring                for Core Loading                        14.2.12.3.27Rev. 0 WOLF CREEK                        TABLE 14.2-3 (Sheet 2)Test Number                      Title                  USAR SectionS-070003    Inverse Count Rate Ratio Monitoring                for Approach to Initial Criticality      14.2.12.3.28 S-070004    Initial Criticality                        14.2.12.3.29S-070005    Determination of Core Power Range for                Physics Testing                          14.2.12.3.30S-070006    Boron Endpoint Determination                14.2.12.3.31S-070007    Isothermal Temperature Coefficient                Measurement                              14.2.12.3.32S-070008    Power Coefficient Determination            14.2.12.3.33S-070009    Load Swing Tests                            14.2.12.3.34S-070010    Large Load Reduction Test                  14.2.12.3.35S-070011    Plant Trip from 100 Percent Power          14.2.12.3.36S-070012    Rods Drop and Plant Trip                    14.2.12.3.37S-070014    Shutdown and Maintenance of Hot Standby                External to the Control Room            14.2.12.3.38S-070015    Power Ascension Thermal Expansion                and Dynamic Test                        14.2.12.3.39S-070016    Biological Shield Testing                  14.2.12.3.40S-070017    Loss of Heater Drain Pump Test              14.2.12.3.41S-070018    Calibration of Steam and Feedwater Flow Instrumentation at Power Test      14.2.12.3.42S-090024    Natural Circulation Test                    14.2.12.3.43Rev. 0}}
Flow Instrumentation at Power Test       14.2.12.3.42 S-090024    Natural Circulation Test                    14.2.12.3.43 Rev. 0}}

Revision as of 19:56, 29 June 2018

Wolf Creek Revision 30 to Updated Final Safety Analysis Report, Chapter 14.0, Initial Test Program
ML17151B013
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 03/09/2017
From:
Wolf Creek
To:
Office of Nuclear Reactor Regulation
Shared Package
ML17151A982 List: ... further results
References
WO 17-0045
Download: ML17151B013 (204)
v • d • e


Text

WOLF CREEK CHAPTER 14.0 TABLE OF CONTENTS INITIAL TEST PROGRAM

Section Title Page

14.1 SPECIFIC INFORMATION TO BE INCLUDED 14.1-1 IN THE PSAR

14.2 INITIAL TEST PROGRAM 14.2-1

14.2.1 SUMMARY OF TEST PROGRAM AND OBJECTIVES 14.2-1

14.2.1.1 Preoperational Test Program 14.2-1

14.2.1.2 Initial Startup Test Program 14.2-2

14.2.2 ORGANIZATION AND STAFFING 14.2-3 14.2.2.1 General Description 14.2-3

14.2.2.2 Startup Organization 14.2-4

14.2.2.3 Operating Staff 14.2-6

14.2.2.4 Major Participating Organizations 14.2-6 14.2.2.5 Quality Assurance 14.2-8 14.2.2.6 Qualifications of Key Personnel 14.2-8

14.2.3 TEST PROCEDURES 14.2-8

14.2.3.1 Startup Test Procedures 14.2-8 14.2.3.2 Procedure Review and Approval 14.2-10

14.2.4 CONDUCT OF TEST PROGRAM 14.2-12

14.2.4.1 Administrative Procedures 14.2-12

14.2.4.2 Turnover From Construction to KG&E 14.2-13 Startup 14.2.4.3 Component and Prerequisite Testing 14.2-14

14.2.4.4 Preoperational Testing 14.2-14

14.2.4.5 Initial Startup Testing 14.2-14

14.2.4.6 Test Prerequisites 14.2-15 14.2.4.7 Test Evaluation 14.2-15 14.2.4.8 Design Modifications 14.2-15

14.2.5 REVIEW, EVALUATION, AND APPROVAL OF 14.2-15

TEST RESULTS 14.2.6 TEST RECORDS 14.2-16

14.2.7 CONFORMANCE OF TEST PROGRAMS WITH 14.2-16

REGULATORY GUIDES

14.2.8 UTILIZATION OF REACTOR OPERATING AND 14.2-16 TESTING EXPERIENCE IN DEVELOPMENT

OF TEST PROGRAMS

14.2.9 TRIAL USE OF PLANT OPERATING AND EMERGENCY 14.2-18 PROCEDURES

14.0-i Rev. 29 WOLF CREEK TABLE OF CONTENTS (CONTINUED)

Section Title Page 14.2.10 INITIAL FUEL LOADING CRITICALITY AND POWER 14.2-18

ASCENSION

14.2.10.1 Fuel Loading 14.2-19 14.2.10.2 Initial Criticality 14.2-22 14.2.10.3 Low Power Testing 14.2-23

14.2.10.4 Power Level Ascension 14.2-23

14.2.11 TEST PROGRAM SCHEDULE 14.2-24 14.2.12 INDIVIDUAL TEST DESCRIPTIONS 14.2-25

14.2.12.1 Safety-Related Preoperational Test 14.2-25

Procedures

14.2.12.2 Nonsafety-related Preoperational Test 14.2-121 Procedures

14.2.12.3 Startup Test Procedures 14.2-158

14.0-ii Rev. 29 WOLF CREEK TABLE OF CONTENTS (CONTINUED)

LIST OF TABLES Table No. Title

14.2-1 Safety-Related Preoperational Test Procedures 14.2-2 Non-Safety-Related Preoperational Test Procedures

14.2-3 Initial Startup Test

14.0-iii Rev. 0

WOLF CREEK CHAPTER 14.0 INITIAL TEST PROGRAM

14.1 SPECIFIC INFORMATION TO BE INCLUDED IN PRELIMINARY SAFETY ANALYSIS REPORTS This section is not applicable to a USAR.

14.1-1 Rev. 1 WOLF CREEK CHAPTER 14.0 INITIAL TEST PROGRAM 14.2 INITIAL TEST PROGRAM 14.2.1 SUMMARY OF TEST PROGRAM AND OBJECTIVES

The Initial Test Program encompassed the scope of events following completion of construction and construction-related inspections and tests and terminating

with Power Ascension Testing. The Initial Test Program was conducted in two

separate and sequential subprograms: the Preoperational Test Program and the

Initial Startup Test Program. At the conclusion of these subprograms, the

plant was ready for normal power operation. Testing during the Initial Test

Program was accomplished in four sequential phases:

Preoperational Test Program

Phase I - Preoperational Testing Initial Startup Test Program

Phase II - Initial Fuel Loading and Zero Power Testing

Phase III - Low Power Physics Testing

Phase IV - Power Ascension Testing

Prior to preoperational testing of a particular system, certain prerequisite

and construction tests were conducted in order to verify the integrity, proper

installation, cleanliness, and functional operability of the system components.

14.2.1.1 Preoperational Test Program The Preoperational Test Program is defined as that part of the Initial Test

Program that commences with the completion of construction and construction-

related inspections and tests and terminates with commencement of nuclear fuel loading.

The Preoperational Test Program included both safety-related and nonsafety-

related preoperational tests. The Preoperational Test Program used a graded

approach to determine the extent of testing to be performed. The safety-

related preoperational tests (Table 14.2-1) demonstrated the capability of

safety-related structures, systems, and components to meet performance

requirements and to satisfy design criteria. The nonsafety-related

preoperational tests (Table 14.2-2) were conducted on nonsafety-related systems

and components to satisfy reliability and availability. Preoperational tests were conducted on those systems that:

14.2-1 Rev. 0 WOLF CREEK

a. Are 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. Are 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. Are relied upon for establishing conformance with safety

limits or limiting conditions for operations that are

included in the technical specifications;

d. Are classified as engineered safety features actuation systems or are relied upon to support or ensure

operation of engineered safety features actuation

systems within design limits;

e. Are assumed to function during an accident or for which

credit is taken in the accident analysis;

f. Are used to process, store, control, or limit the

release of radioactive materials.

The objectives of the Preoperational Test Program were to:

a. Verify that plant components and systems, including

alarms and indications, are constructed and fulfill their design intent;

b. Demonstrate, to the extent practicable, proper

system/component response to postulated accidents;

c. Familiarize plant staff operating, technical, and

maintenance personnel with plant operation.

The completion of preoperational testing constituted the completion of Phase I

of the Initial Test Program.

14.2.1.2 Initial Startup Test Program The Initial Startup Test Program is defined as that part of the Initial Test

Program that commences with the start of nuclear fuel loading and terminates

with the completion of power ascension testing. The initial startup tests (Table 14.2-3) ensured that fuel loading was accomplished in a safe manner,

confirmed the

14.2-2 Rev.0 WOLF CREEK design basis, demonstrated, where practical, that the plant operates and responds properly to anticipated transients and postulated accidents, and

ensured that the plant can be safely brought to rated capacity and sustained

power operation.

The objectives of the Initial Startup Test Program were to:

a. Accomplish a controlled, orderly, and safe initial core

loading;

b. Accomplish a controlled, orderly, and safe initial

criticality;

c. Conduct low power testing sufficient to ensure that

design parameters are satisfied and safety analysis assumptions are conservative;

d. Perform a controlled, orderly, and safe power ascension

with testing terminating at plant rated conditions;

e. Provide sufficient testing of transient and accident

conditions to verify safe operation during transient or

accident conditions.

The completion of initial startup testing constituted the completion of Phases

II, III, and IV of the Initial Test Program.

14.2.2 ORGANIZATION AND STAFFING

14.2.2.1 General Description The Operating Agent, as defined in Section 1.4, was responsible for the overall

administration and technical direction of the WCGS startup program. In

recognition of this responsibility, the Director of Nuclear Operations, under the direction of the Vice President - Nuclear, established a startup

organization to coordinate and direct the comprehensive planning, development,

implementation and performance of the test program. The Startup Organization

was headed by the Startup Manager who reported to the Plant Manager both

administratively and technically.

During the preoperational startup program, the Startup Manager acted to

coordinate activities between the Startup Organization, the construction staff,

and the operating staff.

Prior to commencing preoperational testing activities, a Joint Test Group (JTG) as described in Section 14.2.3.2.2 was formed to review and recommend for

approval startup administrative procedures, preoperational test procedures, and

preoperational test

14.2-3 Rev. 0 WOLF CREEK results. A Plant Safety Review Committee (PSRC) as described in Section 14.2.3.2.3 was organized with the Plant Manager acting as chairman and it

reviewed and recommended for approval initial startup test procedures and

results.

14.2.2.2 Startup Organization

The Startup Organization was directly responsible for the conduct of the WCGS

preoperational test program. The duties and responsibilities of the startup

organization also included:

a. Familiarization of support personnel with specific

tests.

b. Direction to support personnel and others during performance of tests including appropriate interface with station operators.
c. Authority to disallow or terminate testing due to

conditions which could endanger personnel or equipment.

d. Identification of deficiencies that could adversely

affect test performance.

e. Assembly of test data and preparation of test reports

for evaluation of test results by others.

The Startup Organization was composed of system startup engineers, technicians,

planners, craft labor, and other support personnel. The Operating Agent

provided these personnel and used contractors to supply manpower for those positions that it could not staff. The staffing level for the Startup Organization increased as the test program progressed and construction

activities decreased. Typical schedules for the test program are given in

Section 14.2.11. Staffing and training of personnel involved in testing at

WCGS were planned to provide sufficient manpower to support the testing

schedule.

The Startup Organization reported administratively and technically to the

Startup Manager; the duties performed by key individuals within the Startup

Organization are summarized below.

14.2.2.2.1 Startup Manager

The Startup Manager had the authority and responsibility, as delegated by the

Plant Manager, for the overall direction and administration of the functions

and activities required to conduct the Startup Program. The responsibilities

and duties of the Startup Manager also included:

14.2-4 Rev. 0 WOLF CREEK

a. Development of plans and schedules regarding the status of the startup program.
b. Review and approval of administrative and technical test

procedures and results.

c. Continuing analysis of construction and equipment

installation schedules for compatibility with testing

schedules and recommendations for corrective actions to

minimize conflict.

d. Review and submittal of design related problems

requiring engineering resolution, encountered by the

Startup Organization in accordance with the appropriate

Startup Administrative Procedures.

e. Maintaining liaison with all organizations supporting

Startup and coordinating their activities.

14.2.2.2.2 Startup Section

The Startup Section was comprised primarily of the System Test Group, the

Electrical Test Group and the Instrumentation and Control Group which had

primary responsibility within the Startup Organization to perform testing.

This section also reviewed and recommended the acceptance of system or

subsystem turnover documentation from Construction and coordinated system

turnover and any subsequent system rework. It was responsible for preparing the

test procedures, conducting the tests, and reporting the test results. For

preoperational testing, this section documented the test results and presented

them before the Joint Test Group for its review and recommendation for approval.

14.2.2.2.3 Operations Technical Support Section

The Operations Technical Support Section was responsible for providing

technical support to the Startup Section during testing. The areas in which

this support was given were instrumentation and control, chemistry, computer,

health physics and reactor engineering.

This section was a permanent part of the WCGS operating staff until these functions were incorporated into other sections. They were involved in training, procedure preparation, and general preparation for support of plant operations.

14.2.2.2.4 Startup Scheduling Section

The Startup Scheduling Section prepared and updated the Startup Schedule, utilizing input from cognizant system startup engineers and the construction

organizations.

14.2-5 Rev.7 WOLF CREEK 14.2.2.2.5 Quality Control Section

The Quality Control Section formulated and implemented the Startup Quality

Control Program. This program monitored the conduct of the Startup

Organization's testing activities by reviewing administrative and technical test procedures, by witnessing major evolutions and selected flushes, hydros,

and preoperational tests and by reviewing turnover packages. The Quality

Control Section was under the direction of the Director - Quality. They

provided support to the Startup Manager.

14.2.2.2.6 Startup Technical Support Section

The Startup Technical Support Section was responsible for providing technical

support to the Startup Organization during the conduct of the Startup Program.

Their responsibilities included test procedure and test results review and approval, technical planning of major milestone activities, startup organization training and startup program compliance to FSAR commitments.

14.2.2.3 Operating Staff The WCGS operating staff was involved in the startup program in several

capacities throughout preoperational and initial startup testing. This

involvement included review of test procedures and results and the direct participation in test activities. Operating staff personnel were utilized by

the startup organization as required for performance of testing under the

direction of system startup engineers. Station operators assisted system

startup engineers in performing tests and in the routine operations of systems.

The operating staff directed the fuel loading and was responsible for plant

operation during initial startup testing.

The operating staff was divided into sections headed by the Superintendent

Operations, Superintendent of Maintenance, Superintendent of Plant Support, Superintendent of Technical Support, Nuclear Training Manager and Superintendent Regulatory Quality and Administrative Services. These section

superintendents reported administratively and technically to the Plant Manager.

The duties and responsibilities of the operating staff during plant operations

are described in Chapter 13.0.

14.2.2.4 Major Participating Organizations 14.2.2.4.1 Bechtel

Bechtel provided engineering input into the startup program. Bechtel was contacted to provide personnel experienced in nuclear plant startup to augment

the startup organization for WCGS. Bechtel employees were assigned consistent

with the startup program schedules.

14.2-6 Rev. 12 WOLF CREEK 14.2.2.4.2 Daniel International Corporation (DIC)

DIC, as contractor for WCGS, was responsible for the construction completion,

and orderly release of components and turnover of systems to KG&E consistent

with the startup program schedules. This responsibility included:

a. Certification that documentation for components, systems

and structures, as required by purchase and installation

specifications, is complete and available; and the

maintenance of these certification files which provide

the documentary evidence, and

b. Provision of dedicated craft manpower support as

required for performance of the startup program.

14.2.2.4.3 Westinghouse Electric Corporation

Westinghouse, as the Nuclear Steam Supply System (NSSS) supplier, was

responsible for providing technical assistance to KG&E during preoperational

and initial startup testing performed on the NSSS equipment and systems.

Technical assistance is defined as technical guidance, advice and counsel based

on current engineering, installation, and testing practices. Westinghouse

employees were assigned consistent with the Startup Program schedules. This

responsibility included:

a. Assignment of personnel to provide advice and assistance

to KG&E for test and operation of all equipment and

systems in the Westinghouse area of responsibility.

b. Supportive engineering services, including special assistance during the initial fuel loading.
c. Providing test procedure outlines and technical

assistance for tests of Westinghouse furnished

components and systems.

14.2.2.4.4 General Electric (GE)

GE is the supplier and installer of the turbine generator. GE supplied

technical support for the startup and testing of the turbine generator. Some

of the prerequisite testing (i.e., turbine oil flush) was performed by the GE

personnel. GE has supplied recommended procedures for starting, operating, and

shutting down equipment in their technical manuals for the turbine generator.

14.2-7 Rev. 0 WOLF CREEK 14.2.2.5 Quality Assurance The KG&E Quality Branch was responsible for assuring the quality of

construction, plant testing, and operations activities in accordance with the

WCGS Quality Program which is described in the Quality Program Manual.

14.2.2.6 Qualifications of Key Personnel

The qualifications for key plant operating personnel are described in Chapter

13.0.

The qualification requirements for startup personnel involved in the WCGS

startup program conformed to capability levels per ANSI N45.2.6 and Regulatory

Guide 1.8 recommendations.

All test personnel were indoctrinated in the startup administrative procedures,

methods and controls.

14.2.3 TEST PROCEDURES

The Initial Test Program was conducted in accordance with detailed preoperational and initial startup test procedures. KG&E maintained the overall responsibility for test procedure preparation, review, and approval

during the preparational stages. KG&E was responsible for final procedure

revision, review, and approval. These activities were completed in a timely

fashion to ensure that the approved procedures for satisfying FSAR testing

equipment commitments were available for review approximately 60 days prior to

scheduled implementation or fuel load for preoperational and initial startup

tests, respectively. Preoperational and initial start-up testing commitments

not available for review approximately 60 days prior to scheduled

implementation or fuel load, respectively, were handled on a case- by-case

basis.

The following sections describe the general methods employed to control

procedure development and review, and they also describe the responsibilities

of the various organizations which participated in this process. The detailed controls and methods were described in the startup administrative procedures.

14.2.3.1 Procedure Preparation Test procedures for the powerblock systems and components were developed by

Westinghouse and Bechtel. Bechtel also prepared test procedures for the site

safety-related systems and components. Test procedures for the site nonsafety-related systems and components were developed by various entities as

coordinated by KG&E.

14.2-8 Rev. 21 WOLF CREEK The format and content of the test procedures developed for the standard plant and safety-related site systems and components reflected the guidance provided

in Regulatory Guide 1.68. The procedures contained as a minimum the following

sections:

1.0 Objectives

The objectives section identified the general results to

be accomplished by the test.

2.0 Acceptance Criteria

The acceptance criteria section clearly defined

quantitative and/or qualitative criteria against which

the success or failure of the test procedure is judged.

3.0 References

The references section identified those FSAR sections,

vendor manuals, drawings, etc. that were pertinent to

the performance and/or development of the test

procedure.

4.0 Test Equipment

The test equipment section identified temporary

equipment required to conduct the test procedure and/or

collect data.

5.0 Notes and Precautions The notes and precautions sections listed limitations

and precautions necessary to ensure personnel and

equipment safety. Additional instructions needed to

clarify the test procedure were also listed in this

section.

6.0 Prerequisites

The prerequisites section identified those prerequisite

tests and initial conditions that had to be completed

and/or satisfied prior to the performance of the test

procedure.

7.0 Test Procedure

The test procedure section provided a detailed step-by-

step test method and instructions for data collection.

All nonstandard arrangements required by the test

procedure section were restored either in the test

procedure section or the system restoration section.

14.2-9 Rev. 0 WOLF CREEK 8.0 Test Data Sheets

The test data sheet section provided specific forms for

data collection. Additional instructions, if necessary,

were also identified for each data sheet.

9.0 System Restoration

The system restoration section returned the system to a

safe operating or standby condition. Instructions for

the removal and/or return of system temporary

modifications required by the prerequisite and/or test

procedure sections were clearly defined.

The procedural sections included, as applicable, appropriate requirements for initials and/or signatures to control the performance and sequencing of the test.

The test procedures were prepared using the latest design information available

and functional requirements provided by the design engineers. This information

was utilized in developing the detailed test methods which verified the ability

of systems and components to function within their design specifications. The

procedure preparation efforts were started more than 2 years before the first

procedure to be performed. This early start allows for an orderly development

of the test procedure program and of the test procedures.

The test procedures were reviewed by the cognizant design organization to

ensure that the test procedure objectives and acceptance criteria are

consistent with current design document requirements. Subsequent changes to

test procedure objectives or acceptance criteria during the preparational stage were based on approved changes to design documents with the design organization's concurrence.

14.2.3.2 Procedure Review and Approval Following initial procedure preparation, and prior to submittal to the JTG for

review and approval recommendation, the test procedures were reviewed by the

SNUPPS utilities (KG&E and Union Electric). Review comments were resolved between the SNUPPS utilities and the writing organization.

A final revision was made by the writing organization, incorporating all

applicable design changes, and was submitted to the utilities for their review

and approval.

14.2-10 Rev. 0 WOLF CREEK Each utility had various organizations, groups, and committees, such as a startup organization, initial test group, and a plant safety review committee,

comprised of individuals having appropriate technical backgrounds and

experience. Individuals within these organizations, groups, and committees

were responsible for:

a. Reviewing procedures for accuracy and technical content;
b. Verifying that the procedure has been revised to

incorporate known design changes;

c. Verifying procedure compatibility with field

installation of equipment;

d. Verifying procedure conformance with FSAR requirements and plant operating technical specifications;
e. Reviewing procedures against reactor operating and

testing experiences of similar power plants.

14.2.3.2.2 Joint Test Group (JTG)

A subcommittee of the PSRC, the JTG was organized by the Operating Agent to

review preoperational test procedures and preoperational test results.

The primary JTG functions were to:

a. Review preoperational test procedures and recommend

their approval by the Startup Manager.

b. Evaluate and authorize changes to preoperational test procedures as detailed in the Startup Administrative

Manual.

c. Evaluate preoperational test procedure results and

recommend their approval to the Startup Manager and

Plant Manager.

d. Review safety-related aspects of the startup

administrative procedures.

Membership in the JTG included the following personnel or their designated

representatives:

a. Superintendent Operations - Chairman
b. Superintendent of Plant Support

14.2-11 Rev. 12 WOLF CREEK

c. Superintendent of Regulatory, Quality and Administrative Services
d. Startup Technical Support Supervisor
e. Assistant Startup Manager
f. Operations Quality Assurance (non-voting member)
g. Bechtel Power Corporation-Engineering (non-voting

member)

h. Westinghouse-Engineering (non-voting member)

Others were requested to provide technical support to the JTG. This support was based on the procedure being reviewed, required technical expertise or other applicable factors. Participation in the JTG meeting was with the concurrence

of the JTG and was limited to technical input only.

14.2.3.2.3 Plant Safety Review Committee (PSRC)

The PSRC was organized by the Operating Agent to ensure effective coordination

of the engineering, construction, and operations activities affecting the

startup program.

The appropriate PSRC members ensured sufficient review of initial startup test

procedures and results.

The primary PSRC startup functions were:

a. Review all initial startup test procedures and make recommendations to the Plant Manager.
b. Evaluation and authorization of changes to initial

startup test procedures.

c. Evaluation of initial startup test procedure results.

Membership in the PSRC is given in the Quality Program Manual.

14.2.4 CONDUCT OF TEST PROGRAM

14.2.4.1 Administrative Procedures

The conduct of the preoperational startup program was controlled by

administrative procedures. The preparation, maintenance, and implementation

of these procedures was the responsibility of the Startup Manager. The startup administrative procedures prescribed controls for startup activities such as:

14.2-12 Rev. 21 WOLF CREEK

a. Organization and interfaces;
b. Indoctrination and training;
c. Preparation, review, approval, and modification of test procedures;
d. Format and content of test procedures;
e. Tagging procedures;
f. Test scheduling and test conduct;
g. Test deficiencies and resolution;
h. Startup quality control; and
i. Startup document control.

14.2.4.2 Turnover from Construction to KG&E Startup Construction completion was scheduled in accordance with engineered system or

subsystem boundaries. As systems or sub- systems were completed to support

Startup testing, a turnover of the system or subsystem to KG&E Startup was processed. Turnover was conducted in accordance with established

administrative procedures.

As part of the turnover process, each safety-related system or subsystem

received physical walkdowns to provide assurance of readiness for Startup

testing and verification that installation requirements had been met.

Walkdowns were performed jointly by KG&E Startup and KG&E Construction

personnel under the direction of the KG&E Construction Manager. Discrepancies

identified during the walkdowns were tracked and resolved in accordance with

established administrative and quality procedures.

The system or subsystem Turnover Package prepared by the constructor was

reviewed by KG&E Construction and KG&E Startup personnel for accuracy,

completeness and acceptability for Startup testing. In conjunction with the

Turnover Package review, Startup personnel verified that the system or

subsystem procurement and installation documentation review had been performed

by Construction, and that discrepancies had been addressed. Acceptance of the

Turnover Package by Startup followed satisfactory completion of the Turnover

Package review. The Startup Manager was responsible for the approval and

acceptance of the system or subsystem and the associated Turnover Package.

14.2-13 Rev. 0 WOLF CREEK Individual components could be released to Startup for calibration, testing or temporary operation prior to turnover.

All components released in this manner were incorporated into the scope of a

subsequent system or subsystem turnover.

14.2.4.3 Component and Prerequisite Testing Upon Startup acceptance of a turned-over system, subsystem, or released

component, prerequisite-type testing was performed to demonstrate proper

operability and functional ability in support of, and prior to, the performance of preoperational testing. Local containment leak rate testing, as described in

Section 14.2.12.2.13, was performed at WCGS as part of the prerequisite test

program.

Administrative procedures were established to ensure that all prerequisites

were met before testing was initiated. Upon completion of all prerequisite

tests applicable to a system or subsystem, a documented review was conducted by

Startup personnel to verify that appropriate documentation was able and that

required prerequisite tests had been satisfactorily completed. All deficiencies

which would prevent performance of preoperational tests or generate negative test results were identified and dispositioned prior to implementation of the preoperational tests.

14.2.4.4 Preoperational Testing Technical direction and administration, including test execution and data

recording, of the preoperational testing were the responsibility of the startup

organization. The system startup engineers were responsible for the performance of tests and providing appropriate interface with station

operators. The Startup Manager was responsible for the administration and

surveillance of all testing activities during the preoperational test program.

14.2.4.5 Initial Startup Testing During the initial startup testing phase, the Plant Manager had overall

authority and responsibility for the startup program. The Startup Organization

provided support to the plant operating staff which had responsibility for performing equipment operations and maintenance in accordance with the

provisions of the plant operating license. The WCGS operating staff was also

responsible for ensuring that the conduct of testing did not place the plant in

an unsafe condition at any time.

The shift supervisors had the authority to terminate or disallow testing at any

time.

14.2-14 Rev. 0 WOLF CREEK 14.2.4.6 Test Prerequisites Each test procedure contained a set of prerequisites and initial conditions as

prescribed by the startup administrative procedures. The system startup

engineer ensured that all specified prerequisites were met prior to performing the test. The format for test procedures is described in Section 14.2.3.1.

14.2.4.7 Test Evaluation Upon completion of system preoperational testing, the test results were

submitted to the JTG for its review and subsequent recommendation for approval

to the Startup Manager and Plant Manager.

Between each major phase of the initial startup test program, the test results

for all tests that were performed were reviewed by the PSRC. This review

ensured that all required systems were tested satisfactorily and that test

results were approved before proceeding to the next stage of testing.

These reviews are described in Section 14.2.5.

14.2.4.8 Design Modifications Modifications to the design of the equipment during the test program could be

initiated in order to correct deficiencies discovered as a result of testing.

Any such modifications were either developed by the original design organization or other designated organizations. Modifications made to

components or systems after completion of preoperational or initial startup

testing were reviewed for retesting requirements on affected portions of the

system.

14.2.5 REVIEW, EVALUATION, AND APPROVAL OF TEST RESULTS

The responsibility for review, evaluation, and recommendation for approval of

test results from all preoperational tests rested with the JTG. In the case of

all initial start-up tests, it rested with the PSRC.

Following completion of a preoperational test, the responsible system startup

engineer assembled the test data package for submittal to the members of the

JTG for evaluation. Each test data package was reviewed to ensure that the

test has been performed in accordance with the approved procedure and that all

required data, checks, and signatures were properly recorded and that system

performance met the approved acceptance criteria.

14.2-15 Rev. 0 WOLF CREEK Members of the JTG reviewed the evaluation findings and recommended corrective action to be taken to resolve any outstanding deficiencies. If the

deficiencies were not resolved to the satisfaction of the JTG, then appropriate

retesting was required. If the evaluation indicated that deficiencies in the

test method were responsible for unsatisfactory test results, the test procedure was revised accordingly before retesting was initiated. The review

and approval process for procedure revisions was carried out in the manner

described in Section 14.2.3. Whenever an evaluation of test results indicated

deficiencies in system performance, the JTG referred the problem to the

responsible engineering organization for evaluation.

If the test documentation and system performance were acceptable, the JTG

recommended approval of the test by the Startup Manager and the Plant Manager.

Following each major phase of the initial startup test program, the PSRC verified that all required tests were performed and that the test results were approved. This verification ensured that all required systems were operating

properly and that testing for the next major phase was conducted in a safe and

efficient manner. This type of review was performed to the extent required

before major initial startup test phases such as fuel load, initial

criticality, and power ascension. During the power ascension phase, review and

approval of initial startup test procedure results was completed as described

in KMLNRC-84-235.

14.2.6 TEST RECORDS

Test procedures and test data relating to preoperational and initial startup

testing are retained in accordance with the measures described in the Quality Program Manual.

14.2.7 CONFORMANCE OF TEST PROGRAMS WITH REGULATORY GUIDES

The regulatory guides applicable to the test program are listed, with

positions, in Appendix 3A, Conformance to NRC Regulatory Guides.

14.2.8 UTILIZATION OF REACTOR OPERATING AND TESTING EXPERIENCE IN

DEVELOPMENT OF TEST PROGRAMS

Available information on reactor operating experiences was utilized in the

development of the Initial Test Program, as follows:

14.2-16 Rev. 21 WOLF CREEK

a. Bechtel reviewed and distributed pertinent Licensee Event Reports for use in the development of

preoperational test procedures as follows:

1. The Licensee Event Summary Reports and other pertinent information were reviewed on a periodic

basis, and those reports deemed to be useful for

updating test procedures and items of a generic

nature were cataloged. A summary of these reports

was distributed within Bechtel.

2. Copies of the specific reports were then made and

distributed for use in the preparation of

procedures. In addition, these reports were coded

and filed in a computer retrieval system.

b. The operating experience assessment for Wolf Creek

Generating Station Unit No. 1 (WCGS) was conducted by

the nuclear divisions and plant staff who possess the

appropriate experience in the area of concern. The

sources of operating experience information included the

use of the NETWORK and the INPO/NSAC SEEIN system. An

administrative system which controlled the flow of

information from NETWORK, INPO/NSAC SEEIN, etc., to the

cognizant organizations including the Independent Safety

Engineering Group (ISEG) was developed and functioning

prior to fuel load.

The Licensing Section was responsible for coordinating

the review of the NRC Information and Enforcement (IE)

Bulletins, Circulars, and Information Notices.

The Startup Group reviewed information provided by the

other KG&E Nuclear Divisions and information provided by

Bechtel and Westinghouse to determine its effect on the

Wolf Creek Initial Test Program, making revisions to

test and administrative procedures as required.

An instrumented auxiliary feedwater water-hammer test was performed only at

Wolf Creek. (This test was not required to be performed. It was being

performed for the purpose of gathering engineering data only.) Procedure S-

O3AL04, Auxiliary Feedwater System Water Hammer Test, required a visual and

audible water hammer test and was completed prior to the issuance of an

operating license. See new Section 14.2.12.1.10.

Procedure S-070017, Loss of Heater Drain Pump Test, was performed on Callaway

only. This test was conducted to verify analytical assumptions. No

additional loss of heater drain pump tests are

14.2-17 Rev. 0 WOLF CREEK required, since the data obtained from the first unit test is equally valid for subsequent units. See Section 14.2.12.3.41.

Procedure S-07SF09 RCCA or Bank Worth Measurement at Power, was performed at 50

percent power only at Callaway. Wolf Creek and Callaway have the same core and Nuclear instrumentation system design and the test at Callaway is considered a

prototypical test for Wolf Creek. This position was accepted by the NRC in a

July 3, 1985 letter to KG&E.

A natural circulation test was performed at Callaway only to demonstrate the

length of time to stabilize natural circulation, core flow distribution, and

the ability to establish and maintain natural circulation. Operators

participating in the tests were able to recognize when natural circulation had

stabilized and were able to control saturation margin, RCS pressure, and heat

removal rate without exceeding specified operating limits. These tests were conducted insofar as possible to include all available licensed operators.

Licensed operators were trained in these same areas on the simulator. The

simulator has full capability of simulating natural circulation, using

Westinghouse data initially. When the above tests were accomplished on the

Callaway plant, actual data was incorporated into the Wolf Creek simulator

program. See Chapter 18, item I.G.1, and Section 14.2.12.3.43.

14.2.9 TRIAL USE OF PLANT OPERATING AND EMERGENCY PROCEDURES

The plant operating procedures were utilized, where applicable during the test

program, to support testing, maintain plant conditions, and facilitate

training. The trial use of operating procedures served to familiarize

operating personnel with systems and plant operation during the testing phase

and also served to ensure the adequacy of the procedures under actual or

simulated operating conditions before plant operation begins. The emergency procedures were verified during startup as plant conditions, testing, and training warrant. Surveillance tests were performed as conditions warrant

during the testing program, to demonstrate their adequacy.

Plant operating procedures were developed in approximately the same time frame

as the preparation of preoperational and initial startup tests. The operating

procedures were revised as necessary to reflect experience gained during the

testing program.

14.2.10 INITIAL FUEL LOADING, CRITICALITY, AND POWER

ASCENSION

Prior to the commencement of fuel loading, required preoperational test

procedures were evaluated, and appropriate remedial action

14.2-18 Rev. 0 WOLF CREEK was taken if the acceptance criteria was not satisfied. At the completion of fuel loading, the reactor upper internals and pressure vessel head were

installed, and additional mechanical and electrical tests were performed to

prepare the plant for nuclear operation. After final precritical tests,

nuclear operation of the reactor began. This phase of testing included initial criticality, low power testing, and power level ascension. The purpose of

these tests was to establish the operational characteristics of the unit and

core, to acquire data for the proper calibration of setpoints, and to ensure

that operation is within license requirements. Section 14.2.12.3 summarizes

the tests which are performed from fuel load to rated power. The fuel loading

and post loading tests are described below.

14.2.10.1 Fuel Loading The Plant Manager or his designated representative with technical assistance

provided by Westinghouse, was responsible for the coordination of initial core

loading. The overall process of initial core loading was, in general, directed from the operating floor of the containment structure by a licensed senior

reactor operator. The licensed senior reactor operator had no additional

responsibilities other than core load operations.

The core configuration was specified as part of the core design studies

conducted well in advance of fuel loading. In the event mechanical damage was

sustained during core loading operations to a fuel assembly of a type for which

no spare was available onsite, an alternate core loading scheme could have been

determined. Any such changes would have been approved by the appropriate

Westinghouse personnel.

Core loading procedures specified the condition of fluid systems to prevent

inadvertent changes in boron concentration of the reactor coolant; the movement

of fuel to preclude the possibility of mechanical damage; the conditions under

which loading could proceed; and the responsibility and authority for

continuous and complete fuel and core component accountability.

The following conditions were met prior to core loading:

a. The reactor containment structure was complete and

containment integrity had been demonstrated.

b. Fuel handling tools and equipment were checked out and

operators familiarized in the use and operation of

equipment. Inspections of fuel assemblies, rod cluster control assemblies, and reactor vessel were satisfactorily completed.

14.2-19 Rev. 0 WOLF CREEK

c. The reactor vessel and associated components were in a state of readiness to receive fuel. The water level was

maintained above the bottom of the nozzles and

recirculation maintained to ensure the required boron

concentration could be increased via the recirculation path or directly to the open vessel.

Criteria for safe loading required that loading operations stop immediately if

any of the following conditions occur.

a. An unanticipated increase in the neutron count rates by a

factor of two occurs on all responding nuclear channels

during any single loading step after the initial nucleus

of eight fuel assemblies is loaded.

b. An unanticipated increase in the count rate by a factor of five on any individual responding nuclear channel

during any single loading step after the initial nucleus

of eight fuel assemblies is loaded.

c. An unanticipated decrease in boron concentration greater

than 20 ppm is determined from two successive samples of

the reactor coolant.

Loading operations could not be restarted until the situation was evaluated.

An alarm in the containment and main control room was coupled to the source

range channels with a setpoint equal to or less than five times the current

count rate. This alarm automatically alerts the loading operation personnel of

high count rate, and an immediate stop of all operations would be required

until the situation was evaluated. In the event the evacuation alarm was actuated during core loading and after it has been determined that no hazards to personnel exist, preselected personnel would be permitted to reenter the

containment to evaluate the cause and determine future action.

The core was assembled in the reactor vessel and submerged in the reactor grade

water containing sufficient dissolved boric acid to maintain a calculated core

effective multiplication factor of 0.95 or lower. The refueling pool could be

wet or dry during initial core loading. Core moderator, chemistry conditions

(particularly boron concentration) were prescribed in the core loading

procedure document and verified by chemical analysis of moderator samples taken

prior to and during core loading operations.

At least two artificial neutron sources were introduced into the core at

specified points in the core during the loading program to ensure a detector

response of at least 2 counts per second attributable to neutrons.

14.2-20 Rev. 0 WOLF CREEK Core loading instrumentation consisted of two permanently installed source range (pulse type) nuclear channels and two temporary incore source range

channels. A third temporary channel could also be used as a spare. The

permanent channels, when responding, were monitored in the main control room,

and the temporary channels were installed and monitored in the containment. At least one permanent channel was equipped with an audible count rate indicator.

Both plant channels have the capability of displaying the neutron flux level on

a strip chart recorder. The temporary channels indicated on scalers, and a

minimum of one channel was recorded on a strip chart recorder. Normally minimum

count rates of two counts per second attributable to core neutrons were

required on at least two of the four (i.e. two temporary and two permanent

source range detectors) available nuclear source channels at all times

following installation of the initial nucleus of eight fuel assemblies. A

response check of nuclear instruments to a neutron source was performed within

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to loading of the core, or upon resumption of loading if delay was for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Fuel assemblies, together with inserted components (control rod assemblies,

burnable, poison assemblies, source spider, or thimble plugging devices) were

placed in the reactor vessel one at a time, according to a previously

established and approved sequence developed to provide reliable core monitoring

with minimum possibility of core mechanical damage. The core loading procedure

documents prescribed the successive movements of each fuel assembly and its

specified inserts from its initial position in the storage racks to its final

position in the core. Fuel assembly status boards were maintained throughout

the core loading operation.

An initial nucleus of eight fuel assemblies, one containing a neutron source,

is the minimum source-fuel nucleus which permitted subsequent meaningful

inverse count rate monitoring. This initial nucleus was determined by calculation to be markedly subcritical (K eff 0.95) under the required conditions of loading.

Each subsequent fuel addition was accompanied by detailed neutron count rate

monitoring to determine that the just-loaded fuel assembly did not excessively

increase the count rate and that the extrapolated inverse count rate ratio was

behaving as expected. These results for each loading step were evaluated before

the next fuel assembly was loaded. The final, as loaded, core configuration

was subcritical (K eff < 0.95) under the required loading conditions.

14.2-21 Rev. 0 WOLF CREEK 14.2.10.2 Initial Criticality Prior to initial criticality, the following tests were performed and the

results evaluated.

a. At the completion of core loading, the reactor upper

internals and pressure vessel head were installed. A

pressure test was conducted after filling, and venting

was completed to check the leaktightness of the vessel

head installation.

b. Mechanical and electrical tests were performed on the

control rod drive mechanisms. These tests included a

complete operational checkout of the mechanisms and

calibration of the individual rod position indicators.

c. Tests were performed on the reactor trip circuits to

test manual trip operation, and actual control rod

assembly drop times were measured for each control rod

assembly. At all times that the control rod drive

mechanisms were being tested, the boron concentration in

the coolant was maintained so that the shutdown margin

requirements specified in the Technical Specifications

were met. During individual RCCA or RCC bank motion,

source range instrumentation was monitored for

unexpected changes in core reactivity.

d. The reactor control and reactor protection systems were

checked with simulated inputs to produce trip signals

for various trip conditions.

e. A functional electrical and mechanical check was made of

the incore nuclear flux mapping system near normal

operating temperature and pressure.

Initial criticality was achieved by a combination of shutdown and control bank

withdrawal and reactor coolant system boron concentration dilution. The plant

conditions, precautions, and specific instructions for the approach to

criticality were specified by approved procedures.

Initially, the shutdown and control banks of control rods were withdrawn

incrementally in the normal withdrawal sequence, leaving the last withdrawn

control bank partially inserted in the core to provide effective control when

criticality was achieved. The boron concentration in the reactor coolant

system was reduced and criticality achieved by boron dilution or by subsequent

rod withdrawal following boron dilution. Throughout this period, samples of

the primary coolant were obtained and analyzed for boron concentration.

14.2-22 Rev. 0 WOLF CREEK Inverse count rate ratio monitoring using data from the normal plant source range instrumentation was used as an indication of the proximity and rate of

approach to criticality. Inverse count rate ratio data was plotted as a

function of rod bank position during rod motion and as a function of reactor

makeup water addition during reactor coolant system boron concentration reduction.

14.2.10.3 Low Power Testing Following initial criticality, a program of reactor physics measurements was

undertaken to verify that the basic static and kinetic characteristics of the

core were as expected and that the values of the kinetic coefficients assumed in the safeguards analysis were conservative.

Procedures specified the sequence of tests and measurements to be conducted and

the conditions under which each was performed in order to ensure both safety of

operation and the validity and consistency of the results obtained. If test

results deviated significantly from design predictions, if unacceptable

behavior had been revealed, or if unexplained anomalies had developed, the

plant would have been brought to a safe stable condition and the situation

reviewed to determine the course of subsequent plant operation.

These measurements were made at low power and primarily at or near normal operating temperature and pressure. Measurements were made in order to verify

the calculated values of control rod bank reactivity worths, the isothermal

temperature coefficient under various core conditions, differential boron

concentration reactivity worth, and critical boron concentrations as functions

of control rod configuration. In addition, measurements of the relative power

distributions were made, and concurrent tests were conducted on the

instrumentation, including source and intermediate range nuclear channels.

Gamma and neutron radiation surveys were performed at selected points

throughout the station. Periodic sampling was performed to verify chemical and

radio-chemical analysis of the reactor coolant.

14.2.10.4 Power Level Ascension After the operating characteristics of the reactor were verified by low power

testing, a program of power level ascension brought the unit to its full rated

power level in successive stages. At each successive stage, hold points were provided to evaluate and approve test results prior to proceeding to the next

stage. The minimum test requirements for each successive stage of power

ascension were specified in the initial startup test procedures.

14.2-23 Rev. 0 WOLF CREEK Measurements were made to determine the relative power distribution in the core as functions of power level and control assembly bank position.

Secondary system heat balance measurements ensured that the indications of

power level were consistent and provide bases for calibration of the power range nuclear channels. The ability of the reactor coolant system to respond

effectively to signals from primary and secondary instrumentation under a

variety of conditions encountered in normal operations was verified.

At prescribed power levels, the dynamic response characteristics of the primary

and secondary systems were evaluated. System response characteristics were

measured for design step load changes, rapid load reduction, and plant trips.

Adequacy of radiation shielding was verified by gamma and neutron radiation

surveys at selected points throughout the station at various power levels.

Periodic sampling was performed to verify the chemical and radio-chemical analysis of the reactor coolant.

14.2.11 TEST PROGRAM SCHEDULE

Detailed schedules for testing were prepared, reviewed, and revised on a

continuing basis as plant construction progressed.

Preoperational tests which were not performed according to schedule were

reviewed on a case-by-case basis. Administrative procedures were established

to ensure that all prerequisites were met before testing was initiated. Upon

completion of all prerequisite tests applicable to a system or subsystem, a

documented review was conducted by Start-up personnel to verify that

appropriate documentation was available and that required prerequisite tests

were satisfactorily completed. All deficiencies which would have prevented performance of preoperational tests or generated negative test results were identified and dispositioned prior to implementation of the preoperational

tests.

Preoperational testing was scheduled to commence approximately 18 months prior

to fuel loading. The preoperational tests were performed and sequenced during

this period as a function of system turnover, system interrelationships, and

acceptance for testing.

Initial startup testing was scheduled to be conducted over a period of

approximately 3 to 5 months, commencing with fuel loading. The sequential

schedule for initial startup tests ensured, insofar as practicable, that test

requirements were completed

14.2-24 Rev. 0 WOLF CREEK prior to exceeding 25-percent power for all plant structures, systems, and components that are relied upon to prevent, limit, or mitigate the consequences

of postulated accidents.

The development of the test procedures was an ongoing process consisting of preparation, review, and revision. Preoperational test procedures were

available for NRC review approximately 60 days prior to the performance of an

individual test. If an individual test procedure was not available 60 days

prior to the test, the NRC was notified of the test date and the date the test

procedure was available. Initial startup test procedures were available for

NRC review at least 60 days prior to fuel loading.

14.2.12 INDIVIDUAL TEST DESCRIPTIONS

Test abstracts were provided for both safety-related and selected nonsafety-related preoperational tests. The abstracts included test prerequisites and summaries of test methods, objectives, and acceptance criteria.

14.2.12.1 Safety-Related Preoperational Test Procedures The following sections contain test abstracts used for safety- related

preoperational tests. Table 14.2-1 provides an index of these tests.

The preoperational test procedures were designated SO3 (Safety- Related/Common

to WCGS and Callaway), SU3 (Safety-Related/WCGS Specific), SO4 thru SO9

(Nonsafety-Related/Common to WCGS and Callaway) and SU4 thru SU9 (Nonsafety-

Related/WCGS Specific) as appropriate.

14.2.12.1.1 Steam Dump System Preoperational Test (S-03AB01)

14.2.12.1.1.1 Objectives

a. To demonstrate the operability of the steam dump control system control circuits in both the average temperature and steam pressure modes of operation.
b. To demonstrate the operation of the main steam dump

valves and main steam cooldown valves, including valve

response to safety signals.

c. To verify the operation of the main steam line drain

valves' control circuits, including valve response to a

turbine trip signal.

14.2-25 Rev. 0 WOLF CREEK

d. To verify the operation of the main steam to turbine-driven feedwater pump supply valves' control logics,

including valve response to an auxiliary feedwater

actuation signal (AFAS).

e. To verify the operation of the main steam atmospheric relief valves' control circuits.

14.2.12.1.1.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are completed.

b. Required electrical power supplies and control circuits

are operational.

14.2.12.1.1.3 Test Method

a. Operability of the steam dump control system control

circuits is verified in both the average temperature and

steam pressure modes.

b. Operability of the main steam dump valves' and main steam cooldown valves' control circuits is verified,

including valve response to turbine impulse low

pressure, low-low average temperature, and condenser

shell high pressure signals.

c. Operability of the main steam line drain valves' control

circuits is verified, including valve response to a

turbine trip signal.

d. Operability of the main steam to turbine-driven

auxiliary feedwater pump supply valves' control logics

is verified, including valve response to an AFAS.

e. Operability of the main steam atmospheric relief valves' control circuits is verified.

14.2.12.1.1.4 Acceptance Criteria

a. The response of the main steam dump valves and the main steam cooldown valves to the associated turbine impulse

low pressure, low-low average temperature, and condenser

shell high pressure signals is in accordance with system

design.

b. The main steam line drain valves open on receipt of a

turbine trip signal.

14.2-26 Rev. 13 WOLF CREEK

c. The main steam to turbine-driven auxiliary feedwater pump supply valves open on receipt of an AFAS.
d. The response of the main steam atmospheric relief valves to pressure signals is in accordance with system

design.

14.2.12.1.2 Main Steam Safety Valve Test (SU3-AB02)

14.2.12.1.2.1 Objectives

To verify the pressure relief setpoints of the main steam

safety valves.

NOTE: This objective may be accomplished either by bench

testing or with a pneumatic test device.

14.2.12.1.2.2 Prerequisites

The following prerequisites apply when a pneumatic test device is used.

a. Required instrument calibration is complete.
b. Hot Functional Testing is in progress.
c. A Source of compressed air is available to provide air

to the air set pressure device installed on the valve

under test.

The following prerequisites apply when bench testing is

performed.

a. Bench testing facility is available.
b. An approved WCGS procedure is available to accomplish

bench testing.

c. A source of compressed gas is available to provide

pressure to the valve under test.

14.2.12.1.2.3 Test Method

The following test method applied when a pneumatic test

device is used.

Main steam pressure is adjusted within the required range,

and air is admitted to the air set pressure device on the

safety valve under test. Actual lift pressure is calculated,

using the steam pressure and converted air pressure at the

time of lift.

14.2-27 Rev. 13 WOLF CREEK The following test applies when bench testing is performed.

With the main steam safety valve mounted on the bench test

facility, the spring assembly is preheated and the safety

valve is pressurized with compressed gas. Actual set pressure is determined at the time of lift.

14.2.12.1.2.4 Acceptance Criteria

Each main steam safety valve lifts within its respective

setpoint tolerance.

14.2.12.1.3 Main Steam Line Isolation Valve Test (S-03AB03)

14.2.12.1.3.1 Objectives

a. To verify the response of the main steam bypass, drain,

and auxiliary feedwater turbine warmup valves to steam

line isolation signals.

b. To demonstrate the operability of the main steam

isolation valve control circuits, including control

circuit response to a steam line isolation signal

(SLIS).

14.2.12.1.3.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits are operational.
c. The main steam line isolation valve accumulators are

charged, and the associated hydraulic systems are

operational.

14.2.12.1.3.3 Test Method

An SLIS is initiated, and the response of the main steam bypass, main steam

drain, and auxiliary feedwater turbine warmup valves is verified.

14.2.12.1.3.4 Acceptance Criteria

a. The main steam bypass, drain, and auxiliary feedwater

turbine warmup valves close on receipt of an SLIS.

14.2.12.1.4 Main Steam System Preoperational Test (S-03AB04)

14.2-28 Rev. 0 WOLF CREEK 14.2.12.1.4.1 Objectives

a. To determine, during hot functional testing, the

operating times of the main steam isolation valves,

main steam bypass valves, main steam dump valves, main steam cooldown valves, and the main steam atmospheric relief valves.

b. To verify the response of the main steam isolation

valves to steam line isolation signals.

14.2.12.1.4.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. Hot functional testing is in progress.
d. The condenser is available to receive steam from the main steam system.

14.2.12.1.4.3 Test Method

a. The main steam isolation valves, main steam bypass

valves, main steam dump valves, main steam cooldown

valves, and the main steam atmospheric relief valves are operated, and operating times are recorded.

b. An SLIS is initiated, and the response of the main steam

isolation valves is verified.

14.2.12.1.4.4 Acceptance Criteria

a. The operating times of the main steam isolation valves,

main steam dump valves, main steam bypass valves, main

steam cooldown valves, and the main steam atmospheric relief valves are within design specifications.

b. The main steam isolation valves close on receipt of a

steam line isolation signal.

14.2.12.1.5 Main Feedwater System Preoperational Test (S-03AEO1)

14.2.12.1.5.1 Objectives

a. To demonstrate the operation of the feedwater system

valves and to verify the response of the feedwater

system valves to a feedwater isolation signal (FIS).

14.2-29 Rev. 13 WOLF CREEK

b. To perform the initial operation of the steam generator feedwater pumps (SGFP).

14.2.12.1.5.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The closed cooling water system is available to provide

cooling water to the SGFP lube oil coolers.

d. The compressed air system is available to provide air to system air-operated valves.
e. The steam seal system is available to provide seal steam

and packing exhaust for the SGFPs.

f. The main turbine is available for turning gear

operation.

g. The condensate system is available to supply suction for

the SGFPs.

h. The main condenser is available to receive SGFP turbine

exhaust.

i. The auxiliary steam system is available to provide steam flow to the SGFP turbines.

14.2.12.1.5.3 Test Method

a. Feedwater system valves are operated, and the proper

response of required system valves to an FIS is

verified.

b. The turbine-driven SGFPs are operated as limited by

steam, and operating data are recorded.

c. The motor-driven SGFP is operated, and operating data

are recorded.

14.2.12.1.5.4 Acceptance Criteria

a. The feedwater control valves, steam generator feedwater

isolation valves, feedwater chemical injection isolation

valves, and feedwater bypass control valves close on

receipt of an FIS.

14.2-30 Rev. 0 WOLF CREEK

b. The closing time of the feedwater isolation valves is within design specifications.
c. The performance of the motor-driven SGFP is within

design specifications.

14.2.12.1.6 Steam Generator Level Control Test (S-03AE02)

14.2.12.1.6.1 Objectives

a. To demonstrate the operability of the feedwater control

valves (FWCVs).

b. To demonstrate the operability of the FWCV bypass

valves.

c. To demonstrate the response of the FWCVs and bypass

valves to signals generated by the steam generator level

control system.

14.2.12.1.6.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2.12.1.6.3 Test Method

a. The FWCVs are operated from their respective controllers, and the FWCVs' response to feedwater flow,

steamline flow, and steam generator level is verified.

b. The FWCV bypass valves are operated from their

respective controllers, and their response to steam

generator level and neutron flux signal is verified.

14.2.12.1.6.4 Acceptance Criteria

a. The response of the FWCVs to feedwater flow, steamline

flow, and steam generator level is in accordance with

system design.

b. The response of the FWCV bypass valves to steam

generator level and neutron flux signal is in accordance

with system design.

14.2-31 Rev. 0 WOLF CREEK 14.2.12.1.7 Auxiliary Feedwater Motor-Driven Pump and Valve Preoperational Test (S-03ALOl)

14.2.12.1.7.1 Objectives

To demonstrate the operability of the motor-driven auxiliary feedwater pumps,

determine by flow test their ability to supply water to the steam generators,

and verify their response to safety signals. The operation of system motor-

operated valves, including their response to safety signals, is also verified.

14.2.12.1.7.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits are operational.
c. The condensate storage tank contains an adequate supply

of demineralized water for the performance of this test.

d. The steam generators are available to receive water from

the auxiliary feedwater system.

14.2.12.1.7.3 Test Method

a. Performance characteristics of the motor-driven

auxiliary feedwater pumps are verified while discharging

to the steam generators.

b. System component control circuits are verified, including the operation of the motor-driven auxiliary

feedwater pumps and system valves on receipt of safety

signals.

14.2.12.1.7.4 Acceptance Criteria

a. Motor-driven auxiliary feedwater pump performance

characteristics must be within design specifications.

b. Motor-driven auxiliary feedwater pumps automatically

start on receipt of an engineered safety features

actuation signal (ESFAS) in the absence of an SIS signal

and a Class IE 4.16 kV bus undervoltage signal.

c. Auxiliary feedwater suction valves from essential

service water system open, and suction valves from

condensate storage tank close, on condensate storage

tank low-suction-pressure signals, coincident with an

auxiliary feedwater pump ESFAS.

14.2-32 Rev. 0 WOLF CREEK 14.2.12.1.8 Auxiliary Feedwater Turbine-Driven Pump and Valve Preoperational Test (SU3-AL02)

14.2.12.1.8.1 Objectives

a. To verify the auxiliary feedwater pump turbine

mechanical trip and throttle valve automatic operation

on an auxiliary feedwater actuation signal (AFAS).

b. To perform the initial coupled operation of the turbine-

driven auxiliary feedwater pump. Full flow

characteristics of the turbine-driven pump will be

demonstrated during hot functional testing.

c. To perform five consecutive, successful, cold starts of the turbine-driven auxiliary feedwater pumps.

14.2.12.1.8.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b Required electrical power supplies and control circuits

are operational.

c. The steam generators are available to receive water from

the auxiliary feedwater pumps.

d. The steam generator blowdown system is available to

maintain the normal operating levels in the steam generators during auxiliary feedwater pump operation.

e. The auxiliary steam system is available to supply steam

to the auxiliary feedwater pump turbine.

f. For the performance characteristic test of this pump,

hot functional testing (HFT) is in progress.

14.2.12.1.8.3 Test Method

a. An AFAS is simulated, and opening of the mechanical trip

and throttle valve is verified.

b. The turbine-driven auxiliary feedwater pump is operated

during HFT, and performance characteristics are

recorded.

c. The ability of the turbine-driven auxiliary feedwater

pumps to start successfully five consecutive times from

cold conditions is verified.

14.2-33 Rev. 0 WOLF CREEK 14.2.12.1.8.4 Acceptance Criteria

a. The auxiliary feedwater pump mechanical trip and

throttle valve opens automatically on an AFAS.

b. Operating characteristics of the turbine-driven

auxiliary feedwater pump are in accordance with design.

c. The turbine driven auxiliary feedwater pump starts

successfully five consecutive times from a cold start.

14.2.12.1.9 Auxiliary Feedwater Motor-Driven Pump Endurance Test

(SU3-AL03)

14.2.12.1.9.1 Objectives

a. To demonstrate that the motor-driven auxiliary feedwater

pumps can operate for 48 continuous hours without

exceeding any of their limiting design specifications.

b. To demonstrate that the motor-driven auxiliary feedwater

pumps can operate for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after a cooldown from the

48-hour test.

c. To demonstrate that the room environmental conditions

are not exceeded during the 48-hour test.

14.2.12.1.9.2 Prerequisites

a. Required component testing, instrument calibration and system flushing/cleaning are complete.
b. Required electrical power supplies and control circuits

are operational.

c. The appropriate auxiliary feedwater pump room coolers

are operational.

d. The condensate storage tank is available as a water

source and to receive recirculation flow.

14.2.12.1.9.3 Test Method

Each motor-driven pump is started and operated for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching

rated speed and rated discharge pressure and flow, or a greater pressure and

less flow. During the endurance run, pump- operating data and the pump room

environmental conditions are recorded. At the completion of each endurance

test, the pump is cooled for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and until pump data returns to within 20 F

of the original pretest data. The pump is then started and operated for 1

hour.

14.2-34 Rev. 0 WOLF CREEK 14.2.12.1.9.4 Acceptance Criteria

a. The operating parameters (vibration, bearing

temperatures, etc.) of each motor-driven auxiliary

feedwater pump do not exceed the design specifications.

b. The environmental conditions of each motor-driven

auxiliary feedwater pump room do not exceed the design

specifications.

14.2.12.1.10 Auxiliary Feedwater System Water Hammer Test (S-

03AL04)

14.2.12.1.10.1 Objectives

To demonstrate that the injection of auxiliary feedwater at rated flow into a steam generator at or near normal operating temperatures will not cause

damaging water hammer to the steam generators and/or feedwater system.

14.2.12.1.10.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The steam generators are at or near normal operating

temperature.

d. The condensate storage tank is available as a water source.

14.2.12.1.10.3 Test Method

Auxiliary feedwater is injected into each steam generator. The feedwater system

piping and the steam generators are monitored visually and audibly to verify

that no damaging water hammer occurs.

14.2.12.1.10.4 Acceptance Criteria

No damaging water hammer occurs.

14.2.12.1.11 Auxiliary Feedwater Turbine-Driven Pump Endurance

Test (SU3-AL05)

14.2.12.1.11.1 Objectives

14.2-35 Rev. 0 WOLF CREEK

a. To demonstrate that the turbine-driven auxiliary feedwater pump can operate for 48 continuous hours

without exceeding any of its limiting design

specifications.

b. To demonstrate that the turbine-driven auxiliary

feedwater pump can operate for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after a cool down

from the 48-hour test.

c. To demonstrate that the room environmental conditions

are not exceeded during the 48-hour test.

14.2.12.1.11.2 Prerequisites

a. Required component testing, instrument calibration and system flushing/cleaning are complete.
b. Required electrical power supplies and control circuits

are operational.

c. The appropriate auxiliary feedwater pump room coolers

are operational.

d. The condensate storage tank is available as a water

source and to receive recirculation flow.

e. A steam source is available.

14.2.12.1.11.3 Test Method

The pump is started and operated for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching rated speed and rated discharge pressure and flow, or a greater pressure and less flow. The

turbine-driven auxiliary feedwater pump operating steam is as close to normal

operating temperature as possible and is at least 400 F. During the endurance

run, pump-operating data and the pump room environmental conditions are

recorded. At the completion of the endurance test, the pump is cooled for 8

hours and until pump data returns to within 20 F of the original pretest data.

The pump is then started and operated for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

14.2.12.1.11.4 Acceptance Criteria

a. The operating parameters (vibration, bearing

temperatures, etc.) do not exceed the design

specifications.

b. The environmental conditions of the turbine-driven

auxiliary feedwater pump room do not exceed the design

specifications.

14.2-36 Rev. 0 WOLF CREEK 14.2.12.1.12 Reactor Coolant Pump Initial Operation (S-03BB01)

14.2.12.1.12.1 Objectives

To demonstrate the operating characteristics of the reactor coolant pumps and verify the operation of their associated oil lift pumps.

14.2.12.1.12.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The chemical and volume control system is available to provide seal water to the reactor coolant pump seals.
d. The component cooling water system is available to

supply cooling water to the reactor coolant pumps.

14.2.12.1.12.3 Test Method

The reactor coolant pumps and associated oil lift pumps are operated, and pump

operating data are recorded.

14.2.12.1.12.4 Acceptance Criteria

Reactor coolant pump and oil lift pump operating characteristics are within

design specifications.

14.2.12.1.13 Pressurizer Relief Tank Cold Preoperational Test

(SU3-BB02)

14.2.12.1.13.1 Objectives

To demonstrate that the reactor makeup water system can supply design

pressurizer relief tank (PRT) spray flow against design backpressure. The

operation of the PRT nitrogen isolation valves, including their response to a

containment isolation signal, is also verified.

14.2.12.1.13.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2-37 Rev. 0 WOLF CREEK

c. The reactor makeup water system is available to supply water to the PRT.
d. The service gas system is available to pressurize the

PRT.

14.2.12.1.13.3 Test Method

a. With a design backpressure in the PRT, a reactor makeup

water pump is operated to obtain the spray flow to the

PRT.

b. The response of the PRT nitrogen isolation valves to a

containment isolation signal is verified.

14.2.12.1.13.4 Acceptance Criteria

a. The reactor makeup water system supplies the design

spray flow to the PRT with design backpressure in the

PRT.

b. PRT nitrogen isolation valves close on receipt of a

containment isolation signal. Valve closure times are

within design specifications.

14.2.12.1.14 RTD Bypass Flow Measurement (SU3-BB03)

At WCGS, test S-07BB01 (USAR Section 14.2.12.3.3) was used to satisfy the

requirement for verification of design specifications.

14.2.12.1.15 Pressurizer Pressure Control Test (S-03BB04)

14.2.12.1.15.1 Objectives

To demonstrate the stability and response of the pressurizer pressure control

system, including the verification of pressurizer pressure alarm and control

functions.

14.2.12.1.15.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The plant is at normal operating temperature and

pressure with all reactor coolant pumps running, and hot

functional testing is in progress.

14.2-38 Rev. 0 WOLF CREEK 14.2.12.1.15.3 Test Method

a. Pressurizer pressure is varied, and the ability of the

pressurizer pressure control system to automatically

control and stabilize pressurizer pressure is verified.

b. Pressurizer pressure is varied, and pressurizer pressure

control system alarm and control setpoints are verified.

14.2.12.1.15.4 Acceptance Criteria

a. The pressurizer pressure control system responds, in

accordance with system design, to an increase and

decrease in system pressure.

b. Pressurizer pressure control system alarm and control setpoints are within design specifications.

14.2.12.1.16 Reactor Coolant System Hot Preoperational Test

(S-03BB05)

14.2.12.1.16.1 Objectives

a. To operate the reactor coolant system at full flow

conditions for a minimum of 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> to provide the

necessary vibration cycles on the vessel's internal

components prior to their inspection at core loading.

b. To provide coordination and initial conditions necessary

for the conduct of those preoperational tests to be performed during heatup, normal operating temperature and pressure, and cooldown of the reactor coolant

system.

14.2.12.1.16.2 Prerequisites

a. The reactor coolant system cold hydrostatic test is

complete.

b. The reactor vessel internals and head are installed, and

the vessel is available to support this test.

c. All systems and components required to support heatup,

operations at normal temperature and pressure, and

cooldown of the reactor coolant system are available.

d. Required instrument calibration is complete.

14.2-39 Rev. 0 WOLF CREEK

e. The examination of the reactor internals in accordance with Section 3.9(N).2.4, is complete

14.2.12.1.16.3 Test Method

a. The reactor coolant system is operated at full flow

conditions for a minimum of 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />.

b. Those preoperational tests required to be performed

during heatup, normal operating temperature and

pressure, and cooldown of the reactor coolant system are

completed, as coordinated by this test.

14.2.12.1.16.4 Acceptance Criteria

The reactor coolant system has operated at full flow conditions for a minimum of 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />.

Notes: 1. The acceptance criteria for individual systems are a

part of the individual test procedures sequenced by

this procedure.

2. A post-hot functional examination of the reactor

internals is performed as described in Section

3.9(N).2.4.

14.2.12.1.17 Thermal Expansion (S-03BB06)

14.2.12.1.17.1 Objectives

To verify that during heatup and cooldown of the reactor coolant system the associated components, piping, support, and restraint deflections are

unobstructed and within design specifications.

14.2.12.1.17.2 Prerequisites

a. This test is conducted in conjunction with hot

functional testing.

b. Supports, restraints, and hangers are installed and

reference points and predicted movements established.

c. Required instrument calibration is complete.

14.2.12.1.17.3 Test Method

During the reactor coolant system heatup and cooldown, deflection data are

recorded.

14.2-40 Rev. 0 WOLF CREEK 14.2.12.1.17.4 Acceptance Criteria

a. Unrestricted expansion and movements are verified to be

within design specifications.

b. Components, piping, supports, and restraints return to

their baseline cold position in accordance with system

design.

14.2.12.1.18 Pressurizer Level Control Test (S-03BB07)

14.2.12.1.18.1 Objectives

To demonstrate the stability and response of the pressurizer level control

system, including the verification of pressurizer level alarm and control functions.

14.2.12.1.18.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The letdown and charging portions of the chemical and

volume control system are available to vary pressurizer

level.

d. The plant is at normal operating temperature and pressure, and hot functional testing is in progress.

14.2.12.1.18.3 Test Method

a. Pressurizer level is varied and the ability of the

pressurizer level control system to automatically

control and stabilize pressurizer level is verified.

b. Pressurizer level is varied, and pressurizer level

control system alarm and control setpoints are verified.

14.2.12.1.18.4 Acceptance Criteria

a. The response and stability of the pressurizer level

control system are within design specifications.

b. The pressurizer level control system alarm and control

functions are within design specifications.

14.2-41 Rev. 0 WOLF CREEK 14.2.12.1.19 Pressurizer Heater and Spray Capability Test (SU3-BB08)

14.2.12.1.19.1 Objectives

To determine the electrical capacity of the pressurizer heaters, and the rate

of pressure increase from the operation of all pressurizer heaters.

14.2.12.1.19.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The plant is at normal operating temperature and

pressure with all reactor coolant pumps running, and hot

functional testing is in progress.

14.2.12.1.19.3 Test Method

a. Pressurizer heaters are energized, and heater capacity

is calculated.

b. With the pressurizer spray valves closed, all

pressurizer heaters are energized, and the time to reach

a 2,300 psig system pressure is measured and recorded.

14.2.12.1.19.4 Acceptance Criteria

a. The capacity of the pressurizer heaters is within design

limits.

b. The pressurizer pressure response to the actuation of

all pressurizer heaters is within design limits.

14.2.12.1.20 Reactor Coolant System Flow Measurement Test

(SU3-BB09)

At WCGS, Test S-07BB03 (USAR Section 14.2.12.3.5) is used to satisfy the

requirements for verification of design specifications.

14.2.12.1.21 Reactor Coolant System Flow Coastdown Test

(SU3-BB10)

14.2-42 Rev. 0 WOLF CREEK At WCGS, Test S-07BB04 (USAR Section 14.2.12.3.6) is used to satisfy the requirements for verification of design specifications.

14.2.12.1.22 Reactor Coolant System Hydrostatic Test (S-03BBll)

14.2.12.1.22.1 Objectives

To verify the integrity and leaktightness of the reactor coolant system and the

high-pressure portions of associated systems.

14.2.12.1.22.2 Prerequisites

a. Required system flushing/cleaning are complete.
b. The reactor coolant pumps are available to support this test.
c. The reactor vessel's lower internals, upper internals,

filter assembly, and the closure head are installed.

The studs are tensioned to design value for the

associated hydrostatic test pressure

d. Temporary temperature instrumentation is installed for

measuring the temperature of the steam generator tube

sheets, the bottom of the pressurizer, and the closure

flange of the reactor vessel.

e. A charging pump or test pump is available to pressurize

the system.

f. Required instrument calibration is complete.

14.2.12.1.22.3 Test Method

The minimum temperature for pressurizing the system is established. The

reactor coolant pumps are operated as required to establish the required

temperature. The system is then pressurized to test pressure, and system

welds, flanges, piping, and components are monitored for leakage.

14.2.12.1.22.4 Acceptance Criteria

The reactor coolant system and associated high-pressure systems are verified

leaktight in accordance with the requirements of the ASME Boiler and Pressure

Vessel Code,Section III, "Nuclear Components," through the Winter 1975

Addenda.

14.2.12.1.23 Pressurizer Continuous Spray Flow Verification Test

(SU3-BB12)

14.2-43 Rev. 0 WOLF CREEK At WCGS, Test S-07BB05 (USAR Section 14.2.12.3.7) was used to satisfy the requirements for verification of design specifications.

14.2.12.1.24 Pressurizer Relief Valve and PRT Hot Preoperational

Test (S-03BB13)

14.2.12.1.24.1 Objectives

To demonstrate that the operating times of the pressurizer power- operated

relief valves are within design specifications. The ability of the reactor

coolant drain tank portion of the liquid radwaste system to cool down the

pressurizer relief tank (PRT) at the design rate is also verified.

14.2.12.1.24.2 Prerequisites

a. Required component testing and instrument calibration are complete.
b. Required electrical power supplies and control circuits

are operational.

c. The PRT is at a normal operating level and is aligned

for normal operation.

d. The liquid radwaste system is available to cool down the

PRT via the reactor coolant drain tank heat exchanger.

e. The plant is at normal operating temperature and pres-

sure, and hot functional testing is in progress.

14.2.12.1.24.3 Test Method

a. Pressurizer power-operated relief valves are operated,

and opening times recorded.

b. Following the operation of the pressurizer power-

operated relief valves, the PRT is cooled down via the

reactor coolant drain tank heat exchanger, and the

cooldown rate is calculated and recorded.

14.2.12.1.24.4 Acceptance Criteria

a. Power-operated relief valve operating times are within

design specifications.

14.2-44 Rev. 0 WOLF CREEK

b. The reactor coolant drain tank portion of the liquid radwaste system cools down the PRT at a rate within

design specifications.

14.2.12.1.25 Reactor Coolant Loop Vibration Surveillance Test (S-03BB14)

14.2.12.1.25.1 Objectives

To verify that the dynamic effects experienced during reactor coolant loop

steady flow and reactor coolant loop pump transients as measured during hot

functional testing (HFT) do not exceed acceptance criteria for the primary loop

piping and components.

14.2.12.1.25.2 Prerequisites

a. Hot functional testing is in progress.
b. Reference points for vibrational measurement of the

reactor coolant piping and components are established.

c. All subject systems are available for the specified

dynamic operation.

d. Required instrument calibration is complete.

14.2.12.1.25.3 Test Method

a. The systems are aligned for the specified dynamic

operation.

b. The specified dynamic event is initiated and the reactor

coolant piping and component responses are monitored.

14.2.12.1.25.4 Acceptance Criteria

The measured deflections for each of the test measurement points are within a

specified percent of the calculated reference deflections.

14.2.12.1.26 Leak Detection System Preoperational Test

(SU3-BB15A)

14.2.12.1.26.1 Objectives

a. To determine, during hot functional testing, the amount

of identified and unidentified leakage from the reactor

coolant system and verify that the leakage is within

design limits.

14.2-45 Rev. 0 WOLF CREEK

b. To demonstrate the ability to detect an increase in reactor coolant system leakage.

14.2.12.1.26.2 Prerequisites

a. Required instrument calibration is complete.
b. Hot functional testing is in progress, and the reactor

coolant system is at normal operating temperature and

pressure.

c. The volume control tank contains an adequate supply of

water to support this test.

d. The reactor coolant drain tank and associated pumps are available to support this test.

14.2.12.1.26.3 Test Method

a. The reactor coolant system identified and unidentified

leakage rates are determined by monitoring the reactor

coolant system water inventory.

b. A known leakage rate is initiated, and the ability to

detect an increase in leakage is verified.

14.2.12.1.26.4 Acceptance Criteria

a. Reactor coolant system identified and unidentified

leakage is within design limits.

b. The ability to detect an increase in reactor coolant

system leakage is verified.

14.2.12.1.27 Leak Detection System Preoperational Test

(SU3-BB15B)

14.2.12.1.27.1 Objectives

a. To demonstrate the operation of the leak detection

system and to verify the ability of the system to detect

leakage within the required time limit as specified by

design.

b. The operation of the containment particulate and

radioactive gas monitoring portions of the Leak

Detection System are verified in SU4-SP01, Process

Radiation Monitoring System Preoperational Test.

14.2-46 Rev. 0 WOLF CREEK 14.2.12.1.27.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. The containment normal sumps, instrument tunnel sump,

floor drain tank, auxiliary building sump and associated

pumps are available to support this test.

14.2.12.1.27.3 Test Method

a. A known simulated leakage is initiated, and the ability

of the system to detect the leakage within the design

time is verified.

14.2.12.1.27.4 Acceptance Criteria

a. The ability of the leak detection system to detect a

leak within the design time is verified.

14.2.12.1.28 RTD/TC Cross Calibration (S-03BB16)

14.2.12.1.28.1 Objectives

To provide a functional checkout of the reactor coolant system resistance

temperature detectors (RTDs) and incore thermocouples and to generate

isothermal cross-calibration data for subsequent correction factors to

indicated temperatures.

14.2.12.1.28.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. Initial plant heatup, during hot functional testing, is

in progress, and all reactor coolant pumps are

operating.

14.2.12.1.28.3 Test Method

At various temperature plateaus, RTD and incore thermocouple data are recorded.

Isothermal cross-calibration correction factors for individual thermocouples

and the installation corrections for individual RTDs are determined.

14.2-47 Rev. 0 WOLF CREEK 14.2.12.1.28.4 Acceptance Criteria

a. Individual RTD readings are within the design

specifications.

b. The installation corrections of the RTDs are within

design specifications.

14.2.12.1.29 Chemical and Volume Control System Major Component

Test (S-03BG01)

14.2.12.1.29.1 Objectives

To demonstrate the operation of the centrifugal charging pumps and associated minimum flow valves, including their response to safety signals.

14.2.12.1.29.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The refueling water storage tank contains an adequate

supply of demineralized water for the performance of

this test.

d. The component cooling water system is available to provide cooling water to the centrifugal charging pump oil coolers.

14.2.12.1.29.3 Test Method

a. Centrifugal charging pumps are operated, and performance

characteristics are verified.

b. Centrifugal charging pump and minimum flow valve control

logics are verified, including their response to safety

signals.

14.2.12.1.29.4 Acceptance Criteria

a. Centrifugal charging pump performance characteristics

are within design specifications.

b. Each centrifugal charging pump receives a start signal

from the load sequencer.

14.2-48 Rev. 0 WOLF CREEK

c. If a safety injection signal is present, a centrifugal charging pump minimum flow valve will open if the

associated pump flow is low and will close if the

associated pump flow is above the minimum flow

requirement of the pump.

14.2.12.1.30 Seal Injection Preoperational Test (SU3-BG02)

14.2.12.1.30.1 Objective

To demonstrate the ability of the chemical and volume control system to supply

adequate seal water injection flow to the reactor coolant pumps and verify the

operation of the seal water return containment isolation valves, including

their response to a CIS.

14.2.12.1.30.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The volume control tank contains an adequate supply of

demineralized water for the performance of this test.

d. Cooling water is available to the charging pumps.

14.2.12.1.30.3 Test Method

a. With a charging pump in operation, seal water throttle valves are adjusted to maintain the required flow to

each reactor coolant pump.

b. Seal water return containment isolation valves control

logics are verified, including their response to a CIS.

14.2.12.1.30.4 Acceptance Criteria

a. Seal water injection flow to each reactor coolant pump

is within design specifications.

b. Seal water return containment isolation valves close on

receipt of a CIS. Valve closure times are within design

specifications.

14.2-49 Rev. 0 WOLF CREEK 14.2.12.1.31 Charging System Preoperational Test (SU3-BG03)

14.2.12.1.31.1 Objective

To demonstrate positive displacement charging pump (replaced by the normal charging pump per DCP 04590) operating characteristics and to verify the operation of the regenerative heat exchanger inlet isolation valves and the

letdown isolation valves, including their response to a safety injection signal

(SIS).

14.2.12.1.31.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The volume control tank contains an adequate supply of

demineralized water for the performance of this test.

d. Cooling water is available to the positive displacement charging pump (replaced by the normal charging pump per DCP 04590).
e. The reactor coolant system is available to receive

charging system flow.

14.2.12.1.31.3 Test Method

a. The positive displacement charging pump (replaced by the normal charging pump per DCP 04590)is operated, and pump operating data are recorded.
b. Regenerative heat exchanger inlet isolation valve and

letdown system isolation valve control circuits are

verified, including valve response to safety injection signals.

14.2.12.1.31.4 Acceptance Criteria

a. Positive displacement charging pump (replaced by the normal charging pump per DCP 04590)operating characteristics are within design specifications.
b. Charging pump to regenerative heat exchanger inlet

isolation valves close on receipt of an SIS. Valve

closure times are within design specifications.

c. The letdown line containment isolation valves close on

receipt of a containment isolation signal. Valve

closure times are within design specifications.

14.2-50 Rev. 12 WOLF CREEK 14.2.12.1 32 Boron Thermal Regeneration System Preoperational Test (SU3-BG04)

14.2.12.1.32.1 Objective

To verify the operation of the boron thermal regeneration system, and

associated control circuits. Performance characteristics of the chemical and

volume control system chiller pumps are also verified.

14.2.12.1.32.2 Prerequisites

a. Required component testing, instrument calibration and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits are operational.
c. The volume control tank contains an adequate supply of

demineralized water for the performance of this test.

d. The chemical and volume control system chiller surge

tank contains an adequate supply of demineralized water

for the performance of this test.

14.2.12.1.32.3 Test Method

a. The chemical and volume control system chiller pumps are

operated and performance characteristics are verified.

b. Boron thermal regeneration system component control circuits are verified.

14.2.12.1.32.4 Acceptance Criteria

a. The chemical and volume control system chiller pumps'

operating characteristics are within design

specifications.

b. The chemical and volume control system chiller pumps

start automatically when the boron thermal regeneration

system is placed in the borate or dilute mode of

operation.

14.2.12.1.33 Boric Acid Blending System Preoperational Test (SU3-

BG05)

14.2.12.1.33.1 Objectives

a. To demonstrate the operating characteristics of boron

injection makeup and boric acid transfer pumps and

14.2-51 Rev. 0 WOLF CREEK verify the ability of the boric acid blending system to make up at design flow rates to the chemical and volume

control system (CVCS).

b. To verify the operation of system component control circuits in all modes of operation.
c. To demonstrate by flow test the ability of the reactor

makeup water system to supply water to the boric acid

blender.

d. To demonstrate by flow test the ability of the boric

acid system to supply an emergency boration flow to the

charging pump suction.

e. To verify the operation of volume control tank valves and associated control circuits, including valve

response to safety signals.

14.2.12.1.33.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The reactor makeup water system is available to supply

water to the boric acid blender and boric acid batching

tank.

d. A charging pump is available to receive and discharge

flow from the boric acid transfer pumps.

e. The volume control tank (VCT) contains an adequate

supply of demineralized water for the performance of

this test.

14.2.12.1.33.3 Test Method

a. The boron injection makeup and boric acid pumps are

operated, performance data recorded, and the ability of

the system to make up to the CVCS at design flow rates

is verified.

b. System component control circuits are verified in all

modes of operation.

14.2-52 Rev. 0 WOLF CREEK

c. With a reactor makeup water pump in operation, flow is verified to the boric acid blender and boric acid

batching tank.

d. With both boric acid transfer pumps in operation and a charging pump taking a suction from the VCT and

discharging to the reactor coolant loops, the emergency

boration flow rate from the transfer pumps to the

charging pump suction is recorded.

e. The emergency boration flow rate via gravity feed from

the boric acid tanks to the charging pump suction is

recorded.

f. Proper operation of the reactor makeup water system is verified when the reactor makeup control system (RMCS) is operated in the manual, dilute, alternate dilute, and

automatic modes.

g. The operation of the VCT outlet valves control circuits

is verified, including their response to a safety

injection signal.

14.2.12.1.33.4 Acceptance Criteria

a. The boron injection makeup and boric acid transfer pump

operating characteristics are within design

specifications.

b. The flow rate to the boric acid blender from the reactor makeup water system is within design specifications.
c. The emergency boration flow rates to the charging pump

suction are within design specifications.

d. The boric acid transfer pumps and the reactor makeup

water pumps start automatically on a low level in the

volume control tank when the RMCS is in the automatic

mode.

e. VCT outlet valves close on receipt of a safety injection

signal when the associated charging pump supply valve

from the refueling water storage tank is open.

f. Refueling water storage tank to charging pump suction

valves open on receipt of a safety injection signal.

g. The boric acid transfer pumps stop on receipt of a load

shed signal.

14.2-53 Rev. 0 WOLF CREEK

h. The boric acid filter to charging pump valve supply breaker trips open on receipt of a load shed signal.

14.2.12.1.34 Chemical and Volume Control System Hot

Preoperational Test (S-03BG06)

14.2.12.1.34.1 Objectives

a. To determine by flow test that all letdown and cleanup

flow rates are within design specifications.

b. To determine, by comparison of boron concentrations,

that boric acid addition to the reactor coolant system

has occurred, using the normal and emergency flow paths.

c. To determine by flow test the ability of the chemical and volume control system (CVCS) to make up at design

flow rates and boron concentrations to the reactor

coolant system in all modes of operation.

d. To determine by operational test that the letdown

containment isolation valve closure times are within

design specifications.

e. To demonstrate the ability of the pump room coolers to

maintain room temperatures within design limits.

14.2.12.1.34.2 Prerequisites

a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
b. Required electrical power supplies and control circuits

are operational.

c. The plant is at normal operating temperature and

pressure, and hot functional testing is in progress.

d. The CVCS pump rooms are closed, and their associated

pump room coolers are operational.

14.2.12.1.34.3 Test Method

a. The letdown throttle valves are adjusted to establish

letdown flow within design specifications.

b. Boric acid addition to the reactor coolant system is

verified, using the normal and emergency flow paths, by

comparing the change in boron concentrations.

14.2-54 Rev. 0 WOLF CREEK

c. With a charging pump in operation, the ability of the CVCS, in all modes of operation, to make up at design

flow rates and boron concentrations to the reactor

coolant system is verified.

d. With letdown flow established, the letdown containment

isolation valves are operated, and operating times are

recorded.

e. During CVCS pump operation, pump room temperature data

are recorded.

14.2.12.1.34.4 Acceptance Criteria

a. All letdown and cleanup flow rates are within design specifications
b. The boric acid addition system is capable of adding

boron to the reactor coolant system via both the normal

and emergency flow paths.

c. The CVCS makeup flow rates and boron additions to the

reactor coolant system are within design specifications

in all modes of operation.

d. The letdown containment isolation valves' closure times

are within design specifications.

e. The CVCS pump room coolers maintain the room temperature

within design limits.

f. The boron thermal regeneration system (BTRS) can vary

the reactor coolant boron concentration as required for

daily load cycle at 85 percent core life.

14.2.12.1.35 Fuel Pool Cooling and Cleanup System Preoperational

Test (SU3-EC01)

14.2.12.1.35.1 Objectives

a. To demonstrate the operating characteristics of the fuel

pool cooling, fuel pool cleanup, and pool skimmer pumps

and to verify that the associated instrumentation and

controls are functioning properly.

b. To verify that the fuel pool cleanup pump refueling

water storage tank (RWST) suction isolation valves close

on receipt of a safety injection signal (SIS).

14.2-55 Rev. 0 WOLF CREEK

c. To verify that each fuel pool cooling pump room cooler starts when the associated fuel pool cooling pump

starts.

14.2.12.1.35.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. Cooling water is available to the fuel pool cooling and

cleanup system heat exchangers.

d. The liquid radwaste system is available to drain the refueling pool to the RWST.
e. The essential service water system is available to

provide cooling water to the spent fuel pool pump room

coolers.

f. The spent fuel pool and fuel transfer canals are filled

to their normal operating levels.

14.2.12.1.35.3 Test Method

a. The fuel pool cooling, fuel pool cleanup, and pool

skimmer pumps are operated in their various modes, and

pump operating data are recorded.

b. System component control circuits are verified,

including the operation of system pumps and valves on

receipt of safety signals.

c. The ability of each fuel pool cooling pump room cooler

to start when the associated fuel pool cooling pump

starts is verified.

14.2.12.1.35.4 Acceptance Criteria

a. The operating characteristics of the fuel pool cooling,

fuel pool cleanup, and pool skimmer pumps are within

design specifications.

b. The fuel pool cleanup pumps RWST suction isolation

valves close on receipt of an SIS.

14.2-56 Rev. 0 WOLF CREEK

c. Each fuel pool cooling pump trips on a low spent fuel pool level signal.
d. Each fuel pool cooling pump trips on receipt of a load

shed signal.

e. Each fuel pool cooling pump room cooler starts when the

associated fuel pool cooling pump starts.

14.2.12.1.36 Spent Fuel Pool Leak Test (S-03EC02)

14.2.12.1.36.1 Objectives

a. To demonstrate the integrity of the spent fuel pool,

cask loading pit, and fuel transfer canal.

b. To demonstrate the leaktightness of the cask loading pit

gate and the fuel transfer canal gate.

14.2.12.1.36.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The spent fuel pool is filled to the normal operating

level.

d. The cask loading pit level is below the level of the fuel pool gate.
e. The fuel transfer canal level is below the level of the

fuel pool gate.

f. The reactor makeup water system is available to provide

demineralized water to the spent fuel pool.

g. A source of compressed air is available to pressurize

the system standpipes.

14.2.12.1.36.3 Test Method

The cask loading pit gate and fuel transfer canal gate are visually inspected

for leakage. A leak test is performed on the spent fuel pool, cask loading

pit, and fuel transfer canal, using the associated leak chase standpipes.

14.2-57 Rev. 0 WOLF CREEK 14.2.12.1.36.4 Acceptance

No leakage is observed from the spent fuel pool, cask loading pit, fuel

transfer canal, cask loading pit gate, and fuel transfer canal gate.

14.2.12.1.37 Essential Service Water System Preoperational Test

(SU3-EF01)

Test SU3-EF02 combined with Test SU3-EF01, Essential

Service Water System Preoperational Test.

14.2.12.1.37.1 Objectives

a. To demonstrate the capability of the essential service

water system to provide cooling water flow during the LOCA mode of operation. The operation and response of system valves to align the system in the LOCA flow mode

on safety injection signals, load sequence signals, and

low suction pressure signals are also verified.

b. To demonstrate the operating characteristics of the

essential service water (ESW) pumps and verify their

response to safety signals.

c. To demonstrate the operability of the backpressure

control valves, including their response to safety

signals.

14.2.12.1.37.2 Prerequisites

a. Required component testing, instrument calibration, and system flushing/cleaning are complete.
b. Required electrical power supplies and control circuits

are operational.

c. The compressed air system is available to the system

air-operated valves.

14.2.12.1.37.3 Test Method

a. System operating characteristics are verified in the

LOCA mode of operation.

b. Safety signals are simulated, and the responses of the

system valves and the ESW pumps are verified.

c. The ESW pumps are operated and pump operating data are

recorded.

14.2-58 Rev. 0 WOLF CREEK

d. The operability of the backpressure control valves, including their response to safety signals is verified.

14.2.12.1.37.4 Acceptance Criteria

a. Components supplied by the essential service water

system receive flows that are within design

specifications in the LOCA mode of system operation.

b. System valve operation in response to safety signals is

within design requirements.

c. System valve operating times are within design

specifications.

d. The ESW pumps' operating characteristics are within design specifications.
e. Each ESW pump responds properly to load sequence and

load shed signals.

f. The time required for each ESW pump to reach rated flow

is within design specifications.

g. System backpressure valves close upon receipt of a LOCA

sequencer or safety injection signal.

h. An auxiliary feedwater pump low suction pressure signal

will close the ESW pump breakers if a zero sequencer

signal is not present.

14.2.12.1.38 Component Cooling Water System Preoperational Test

(S-03EG01)

14.2.12.1.38.1 Objectives

a. To demonstrate the capability of the component cooling

water system to provide cooling water during the normal,

shutdown, and post-LOCA modes of operation.

b. To demonstrate the operating characteristics of the

component cooling water pumps and to verify that the

associated instrumentation and controls are functioning

properly, including system response to safety signals.

14.2.12.1.38.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

14.2-59 Rev. 0 WOLF CREEK

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

14 2.12.1.38.3 Test Method

a. System operating characteristics are verified in the

normal, shutdown, and post-LOCA modes of operation.

b. Safety signals are simulated, and the response of system

pumps and valves is verified.

14.2.12.1.38.4 Acceptance Criteria

a. The performance characteristics of each component

cooling water pump are within design specifications.

b. Components supplied by the component cooling water

system receive flows that are within design

specifications with the system operating in the normal,

shutdown, and post-LOCA modes.

c. Component cooling water pump and valve responses to load

sequence, containment isolation, and safety injection

signals are within design specifications.

d. Closure times for the component cooling water supply and

return valves to the reactor coolant system are within

design specifications.

e. Component cooling water pump response to centrifugal charging pump start signals is in accordance with system design.

14.2.12.1.39 Residual Heat Removal System Cold Preoperational

Test (SU3-EJ01)

14.2.12.1.39.1 Objective

To demonstrate the operability of the Residual Heat Removal (RHR) pumps,

demonstrate by flow test their ability to supply water at rated pressure and

flow, and verify their response to safety signals. The operation of system

motor-operated valves, including their response to safety signals, are also

verified. The RWST control and alarm circuits are also verified.

14.2.12.1.39.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

14.2-60 Rev. 0 WOLF CREEK

b. Required electrical power supplies and control circuits are operational.
c. The reactor vessel head is removed and the water level

is above the nozzles.

d. The refueling water storage tank contains an adequate

supply of demineralized water for the performance of

this test.

e. Cooling water is available to the RHR pumps and heat

exchangers.

f. The instrument air system is available to supply air to

system air-operated valves.

14.2.12.1.39.3 Test Method

a. Performance characteristics of the RHR pumps are

verified during discharge to the reactor coolant hot and

cold loops and test recirculation.

b. RWST and RHR system component control circuits are

verified, including the operation of the RHR pumps and

system valves on receipt of safety signals.

14.2.12.1.39.4 Acceptance Criteria

a. RHR pump performance characteristics are within design

specifications.

b. RHR system components align or actuate in accordance

with system design to safety injection, containment

isolation, load sequencing, load shed, and tank level

signals.

c. The time required for each RHR pump to reach rated speed

is within design specifications.

d. RHR system motor-operated valve closure times are within

design specifications.

14.2.12.1.40 Residual Heat Removal System Hot Preoperational Test

(S-U3-EJ02)

14.2.12.1.40.1 Objectives

a. To demonstrate the ability of the residual heat removal

(RHR) system to cool down the reactor coolant system

(RCS) at its design rate.

14.2-61 Rev. 0 WOLF CREEK

b. To demonstrate the ability of the RHR pump room coolers to maintain room temperature within design limits.

14.2.12.1.40.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The component cooling water system is supplying water to

each RHR heat exchanger.

d. The RCS is being cooled down during hot functional testing.
e. The RHR pump rooms are closed, and their associated pump

room coolers are operational.

14.2.12.1.40.3 Test Method

a. While the RCS is being cooled down with the RHR system,

the heat transfer is obtained by performing a heat

balance across each RHR heat exchanger.

b. When RHR pump room temperatures have stabilized, room

temperature data is recorded.

14.2.12.1.40.4 Acceptance Criteria

a. The RHR system is capable of cooling down the reactor

coolant system at its design rate.

b. The RHR pump room coolers can maintain room temperature

within design limits.

14.2.12.1.41 Safety Injection System Cold Preoperational Test

(SU3-EM01)

14.2.12.1.41.1 Objectives

To demonstrate the response of the safety injection pumps and associated valves

to safety signals.

14.2.12.1.41.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete

14.2-62 Rev. 0 WOLF CREEK

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

14.2.12.1.41.3 Test Method

The response of the safety injection pumps and associated valves to safety

signals is verified

14.2.12.1.41.4 Acceptance Criteria

a. The safety injection pumps and associated valves align

or actuate in accordance with system design to

containment isolation signals, load shedding signals,

and load sequencing signals.

14.2.12.1.42 Safety Injection Flow Verification Test (SU3-EM02)

14.2.12.1.42.1 Objectives

a. To demonstrate the operating characteristics of the

safety injection pumps and the centrifugal charging

pumps.

b. To demonstrate the capability of the safety injection

pumps to provide balanced flow to the reactor coolant

system and prevent runout flow in the cold leg and hot

leg injection modes.

c. To demonstrate the capability of the charging pumps to

provide balanced flow to the reactor coolant system and prevent runout flow in the boron injection mode.

d. To demonstrate the capability of the residual heat

removal pumps to provide required net positive suction

head to the safety injection pumps and the centrifugal

charging pumps.

e. To demonstrate that the safety injection and centrifugal

charging pump room coolers maintain room temperature

within design limits.

f. To demonstrate that associated system valve operating

times are within specified limits.

14.2.12.1.42.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

14.2-63 Rev. 0 WOLF CREEK

b. Required electrical power supplies and control circuits are operational.
c. The CVCS is available to supply rated flow to the

reactor coolant system via the boron injection path, while simultaneously supplying other required loads.

d. The residual heat removal system is available to supply

adequate suction head to the safety injection and

centrifugal charging pumps during required injection

modes.

e. The borated refueling water storage tank contains an

adequate supply of demineralized water for this test.

f. The reactor vessel is available to receive water, and the temporary reactor vessel pumpdown system is

operational (if required).

g. The auxiliary building HVAC system is available to cool

the pump rooms and verify associated pump interlocks.

h. The accumulator safety injection system piping from the

safety injection system to the reactor coolant system is

available, and an accumulator tank is capable of

receiving water.

i. Cooling water is available to required pumps and heat

exchangers.

j. The compressed air system is available to supply air to associated system valves.
k. The residual heat removal system hot leg and cold leg

flow orifices have been sized for required flow.

14.2.12.1.42.3 Test Method

a. The safety injection pumps are operated in the cold leg

flow mode to verify pump performance characteristics and

to identify the weaker pump.

b. The safety injection cold leg branch lines are balanced

using the weaker safety injection pump and the balance

checked with the stronger pump. The balance is

performed so that injection flow is maximized while

preventing pump runout.

14.2-64 Rev. 0 WOLF CREEK

c. The safety injection hot leg branch lines are balanced, using their respective safety injection pump. The

balance is performed so that injection flow is maximized

while preventing pump runout.

d. The centrifugal charging pumps are operated in the boron

injection mode to determine pump performance

characteristics and to identify the weaker pump.

e. The boron injection branch lines are balanced, using the

weaker centrifugal charging pump and the balance checked

with the stronger pump. The balance is performed such

that injection flow is maximized while preventing pump

runout.

f. Each residual heat removal pump is operated in series with the centrifugal charging pumps and safety injection

pumps to verify that the residual heat removal pumps can

supply adequate suction head.

g. With each centrifugal charging pump and safety injection

pump operating, pump room temperatures are allowed to

stabilize, and room temperature data are recorded.

14.2.12.1.42.4 Acceptance Criteria

a. The safety injection and centrifugal charging pump

response times and valve operating times are within

design specifications.

b. The safety injection pump room coolers start with their respective pump.
c. The NPSH provided by the residual heat removal pumps to

the centrifugal charging pumps and safety injection

pumps is within system design specifications.

d. Safety injection cold leg, hot leg, and safety injection

pump flows are within design specifications.

e. Boron injection and centrifugal charging pump flows are

within design specifications.

f. The safety injection and centrifugal charging pump room

coolers can maintain room temperature within design

limits.

14.2-65 Rev. 0 WOLF CREEK 14.2.12.1.43 Safety Injection Check Valve Test (SU3-EM03)

14.2.12.1.43.1 Objectives

To demonstrate the integrity of accumulator outlet line and loop safety injection line check valves and backup check valves by performing backleakage

tests. The operability of the various safety injection line check valves under

their design pressure conditions is also verified.

14.2.12.1.43.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits are operational.
c. The reactor coolant system is at normal operating

pressure.

14.2.12.1.43.3 Test Method

a. Check valve leak testing is performed with the reactor

coolant system at normal operating pressure.

b. Check valve operability is performed by verifying flow

through the check valves at reduced reactor coolant

pressure.

14.2.12.1.43.4 Acceptance Criteria

a. Check valve leakage rates are within limits established

by Technical Specifications Section 3.4.6.2f.

b. Injection line check valve operability is demonstrated

by verification of flow through the check valves in each

of the safety injection lines to the reactor coolant

system.

14.2.12.1.44 Boron Injection Tank and Recirculation Pump Test

(SU3-EM04)

This test has been deleted at Wolf Creek since the boron injection requirements

have been eliminated due to the decrease in required boron concentration.

14.2-66 Rev. 0 WOLF CREEK 14.2.12.1.45 Containment Spray System Nozzle Air Test (S-03EN01)

14.2.12.1.45.1 Objectives

To demonstrate that the spray nozzles in the containment spray header are clear of obstructions.

14.2.12.1.45.2 Prerequisites

A source of compressed air is available to pressurize the spray headers.

14.2.12.1.45.3 Test Method

Air flow is initiated through the containment spray headers, and unobstructed

flow is verified through each nozzle.

14.2.12.1.45.4 Acceptance Criteria

All containment spray nozzles are clear and unobstructed, as evidenced by air

passing through each nozzle.

14.2.12.1.46 Containment Spray System Preoperational Test

(SU3-EN02)

14.2.12.1.46.1 Objectives

a. To demonstrate the operation of system components,

including their response to safety signals, and verify

that the associated instrumentation and controls are

functioning properly. System flow characteristics in the test and simulated accident modes are also verified.

b. To demonstrate the ability of the pump room coolers to

maintain room temperatures within design limits.

14.2.12.1.46.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The refueling water storage tank contains an adequate

supply of demineralized water for the performance of

this test.

d. The auxiliary building HVAC system is available to cool

the pump rooms and verify associated pump interlocks.

14.2-67 Rev. 0 WOLF CREEK

e. The containment spray pump rooms are closed.

14.2.12.1.46.3 Test Method

a. Performance characteristics of the containment spray pumps are verified in the test mode, recirculating to

the refueling water storage tank, and in the simulated

accident mode.

b. System component control circuits are verified,

including the operation of system pumps and valves on

receipt of load sequence/shedder and CSAS/CIS signals,

respectively.

c. During system operations, spray additive eductor operating characteristics are verified.
d. During containment spray pump operation, pump room

temperature data are recorded.

14.2.12.1.46.4 Acceptance Criteria

a. Containment spray pump performance characteristics are

within design specifications for the tested modes of

operation.

b. Containment spray pump and valve response to load

sequence/shedder and CSAS/CIS is verified, and the

associated response times are within design

specifications.

c. Spray additive eductor operating characteristics are

within design specifications.

d. The containment spray pump room coolers maintain the

room temperature within design limits.

14.2.12.1.47 Accumulator Testing (S-03EP01)

14.2.12.1.47.1 Objectives

To determine the operability of each safety injection accumulator and obtain,

by flow test, each accumulator's discharge line resistance to flow. The

ability of the accumulator discharge line isolation valves to open under

maximum differential pressure conditions is verified, as is the response of

accumulator system valves to safety signals.

14.2-68 Rev. 0 WOLF CREEK 14.2.12.1.47.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The reactor vessel head and reactor internals are not

installed, and the vessel is available to receive water.

d. A source of compressed air and nitrogen is available.
e. The refueling water storage tank contains an adequate

supply of demineralized water for the performance of this test.

14.2.12.1.47.3 Test Method

a. Each accumulator is filled and partially pressurized with

the discharge valves closed. The discharge valves are

opened, discharging the accumulators to the reactor

vessel, and performance data are recorded.

b. Each accumulator discharge line isolation valve is

operated under maximum differential pressure conditions

of normal accumulator precharge pressure and zero reactor

coolant pressure, and the valve operating times are

recorded.

c. Accumulator system valve control circuits are verified, including their response to safety injection and

containment isolation signals.

14.2.12.1.47.4 Acceptance Criteria

a. Each accumulator's discharge line resistance to flow

(L/D) is in accordance with design specifications.

b. Each accumulator's discharge line isolation valve

opening time under maximum differential pressure

conditions is within design specifications.

c. The accumulator system nitrogen supply containment

isolation valve closes on receipt of a containment

isolation signal. Valve closure time is within design

specifications.

d. Each accumulator discharge isolation valve opens on

receipt of a safety injection signal.

14.2-69 Rev. 0 WOLF CREEK 14.2.12.1.48 Auxiliary Feedwater Pump Turbine Preoperational Test (SU3-FC01)

14.2.12.1.48.1 Objectives

a. To demonstrate the operation of the auxiliary feedwater

pump (AFWP) turbine and its support equipment, while

uncoupled from the pump.

b. To demonstrate control of the AFWP turbine from the

control room as well as the auxiliary shutdown panel.

14.2.12.1.48.2 Prerequisites

a. Required component testing, instrument calibration and system flushing/cleaning are complete.
b. Steam is available to the AFWP turbine.

14.2.12.1.48.3 Test Method

a. AFWP turbine system valves are operated and required

response to various signals is verified.

b. The turbine is operated and proper control is verified

from the control room as well as the auxiliary shutdown

panel, and operating data are recorded.

c. The turbine is brought to high speed at which time the

mechanical and electronic overspeed trips are verified.

14.2.12.1.48.4 Acceptance Criteria

a. The AFWP turbine can be controlled from the control room

panel and the auxiliary shutdown panel.

b. The mechanical and electronic overspeed trips actuate to

shut down the turbine in accordance with the design.

14.2.12.1.49 Essential Service Water Pumphouse HVAC

Preoperational Test (SU3-GD01)

14.2.12.1.49.1 Objectives

a. To demonstrate the capacity of the essential service

water (ESW) pumproom supply fans.

b. To demonstrate ESW pumproom unit heater response to a

load shed signal.

14.2-70 Rev. 0 WOLF CREEK 14.2.12.1.49.2 Prerequisites

a. Required component testing and instrument calibration

are completed.

b. Required electrical power supplies and control circuits

are operational.

c. The ESW pumphouse HVAC system is air balanced.

14.2.12.1.49.3 Test Methods

a. The ESW pumphouse supply fans are operated and flow data

are recorded.

b. Response of the ESW pumproom unit heaters to load shed signal is verified.

14.2.12.1.49.4 Acceptance Criteria

a. The ESW pumphouse supply fan capacities are within

design specification.

b. A load shed signal will trip the ESW pumproom unit

heaters' circuit breaker.

14.2.12.1.50 Miscellaneous Building HVAC System Preoperational

Tests (SU3-GF01, SU3-GF02, SU3-GF03)

14.2.12.1.50.1 Objectives To demonstrate the capacity of; 1) the auxiliary feedwater pump room cooler

fans, 2) the main steam enclosure building supply and exhaust fans and 3) the

tendon access gallery transfer fans and to verify that the associated

instrumentation and controls are functioning properly. The responses of the

main steam enclosure building dampers and tendon access gallery dampers to

safety signals are also verified.

(At Wolf Creek Generating Station, this test was performed in three independent

parts. In addition, the auxiliary boiler room fan was treated as part of

preoperational test SU4-GF01.)

14.2.12.1.50.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2-71 Rev. 0 WOLF CREEK

c. The miscellaneous building HVAC system is air balanced.

14.2.12.1.50.3 Test Method

a. Flow data are recorded while the fans are operating.
b. The response of system dampers to a safety injection

signal (SIS) is verified.

14.2.12.1.50.4 Acceptance Criteria

a. System fan capacities are within design specifications.
b. The main steam enclosure building and tendon access

gallery dampers close on receipt of a SIS.

14.2.12.1.51 Fuel Building HVAC System Preoperational Test

(S-03GG01)

14.2.12.1.51.1 Objectives

To demonstrate that the emergency exhaust fans are capable of maintaining a

negative pressure in the fuel building or the auxiliary building during

accident conditions with the buildings isolated. To demonstrate the capacities

of the fuel building supply unit fans, emergency exhaust fans, and the spent

fuel pool pump room cooler fans. The operability of system instrumentation and

controls, including the components' response to safety signals, is also

verified.

14.2.12.1.51.2 Prerequisites

a. Required component testing, instrument calibration, and

system air balancing are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The compressed air system is available to supply the

air-operated dampers in the fuel building.

d. Required portions of the auxiliary building HVAC system

have been air balanced and are available to support this

test.

14.2.12.1.51.3 Test Method

a. With the fuel building closed, the system is operated in

its normal configuration, and the fuel building supply

14.2-72 Rev. 0 WOLF CREEK unit fan and spent fuel pool pump room cooler fan capacities are verified.

b. With a fuel building isolation signal (FBIS) present,

the emergency exhaust fan capacities and negative fuel building pressures are verified.

c. With a safety injection signal (SIS) present and the

auxiliary building isolated, the emergency exhaust fan

capacities and negative auxiliary building pressures are

verified.

14.2.12.1.51.4 Acceptance Criteria

a. The auxiliary building and fuel building pressures maintained by the emergency exhaust fans are within design specifications.
b. The fuel building supply fans, emergency exhaust fans,

and spent fuel pool pump room cooler fans' capacities

are within design specifications.

c. The fuel building ventilation system fans and dampers

properly respond to FBIS and SIS, in accordance with

system design.

14.2.12.1.52 Control Building HVAC System Preoperational Test

(SU3-GK01)

14.2.12.1.52.1 Objectives To demonstrate the capacities of the control building supply air unit, control

building exhaust fans, access control exhaust fans, control room pressurization

fans, control room filtration fans, control room air conditioning units, access

control fan coil units, counting room fan coil unit, and Class IE electrical

equipment ac units. To demonstrate that the control room pressurization fans

are capable of maintaining a positive pressure in the control room following a

control room ventilation isolation signal (CRVIS). The system instrumentation

and controls, including the components' responses to safety signals, are also

verified. To demonstrate that the ventilation to battery rooms 1 through 4 is

in accordance with system design.

14.2.12.1.52.2 Prerequisites

a. Required component testing, instrument calibration, and

system air balancing are complete.

14.2-73 Rev. 0 WOLF CREEK

b. Required electrical power supplies and control circuits are operational.
c. The compressed air system is available to supply air to

system air-operated dampers.

14.2.12.1.52.3 Test Method

a. The control building system fans are operated, and fan

capacities are verified.

b. Proper response of system components to control room

ventilation isolation signals (CRVIS) and safety

injection signals (SIS) is verified.

c. With a CRVIS present, the ability of each control room pressurization fan to maintain the control room at a

positive pressure is verified.

d. The air flow to battery rooms 1 through 4 is verified.

14.2.12.1.52.4 Acceptance Criteria

a. The control building HVAC system fan capacities are

within design specifications.

b. The control building HVAC system fans and dampers

properly respond to CRVIS and SIS in accordance with

system design.

c. The control room pressure maintained by the control room pressurization fans is within design specification.
d. The air flow to battery rooms 1 through 4 is in

accordance with system design.

14.2.12.1.53 Auxiliary Building HVAC System Preoperational Test

(SU3-GL01)

14.2.12.1.53.1 Objectives

To demonstrate the capacities of the auxiliary building supply unit fans,

auxiliary/fuel building normal exhaust fans, the auxiliary building fan coil

units, pump room coolers, penetration room coolers, decon tank exhaust scrubber

fans, access tunnel transfer fan, and penetration cooling fan. The system

instrumentation and controls, including components' response to safety and fire

signals, are also verified.

14.2-74 Rev. 0 WOLF CREEK 14.2.12.1.53.2 Prerequisites

a. Required component testing, instrument calibration, and

system air balancing are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The compressed air system is available to supply the

air-operated dampers in the auxiliary building.

d. The fuel building HVAC system has been air balanced, and

is available to support this test.

14.2.12.1.53.3 Test Method

a. The system is operated in its normal configuration, and

the system fan capacities are verified.

b. Proper responses of system components to safety

injection and fire signals are verified.

14.2.12.1.53.4 Acceptance Criteria

a. The auxiliary building fan capacities are within design

specifications.

b. The auxiliary building fans and dampers properly respond

to safety injection and fire signals, in accordance with

system design.

14.2.12.1.54 Diesel Generator Building HVAC Preoperational Test

(S-03GM01)

14.2.12.1.54.1 Objectives

To demonstrate the capacities of the diesel generator room supply fans and to

verify that the system instrumentation and controls function properly,

including the response of fans and associated dampers to a diesel generator run

signal and room temperature signals.

14.2.12.1.54.2 Prerequisites

a. Required component testing and instrument calibration

are completed.

b. Required electrical power supplies and control circuits

are operational.

14.2-75 Rev. 0 WOLF CREEK

c. The diesel generator building HVAC system is air balanced.
d. The respective diesel generator is not operating while

the room is under test.

14.2.12.1.54.3 Test Method

a. Flow data are recorded, while the diesel generator room

supply fans are operating.

b. The responses of the diesel generator room supply fans

and exhaust dampers to a diesel generator run signal and

to room temperature signals are verified.

14.2.12.1.54.4 Acceptance Criteria

a. The capacities of the diesel generator room supply fans

are within design specifications.

b. The diesel generator room exhaust dampers open on

receipt of a diesel generator run signal.

c. The diesel generator room supply fans start on a high

room temperature signal and stop on a low room

temperature signal.

14.2.12.1.55 Containment Cooling System Preoperational Test

(SU3-GN01)

14.2.12.1.55.1 Objectives

To demonstrate the capacities of the hydrogen mixing, containment cooling, and

pressurizer cooling fans and verify their associated instrumentation and

controls function properly, including fan response to safety signals.

14.2.12.1.55.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The essential service water system is available to

supply water to the containment coolers.

d. The containment cooling system has been air balanced.

14.2-76 Rev. 0 WOLF CREEK 14.2.12.1.55.3 Test Method

a. The hydrogen mixing, containment cooling, and

pressurizer cooling fans are operated, flow data

recorded, and fan capacities calculated.

b. The response of the hydrogen mixing and containment

cooling fans to safety signals is verified.

14.2.12.1.55.4 Acceptance Criteria

a. The capacities of the hydrogen mixing, containment

cooling, and pressurizer cooling fans are within design

specifications.

b. The hydrogen mixing and containment cooling fans align or actuate in response to safety injection, shutdown

sequencer, and LOCA sequencer signals, in accordance

with system design.

14.2.12.1.56 CRDM Cooling Preoperational Test (S-03GN02)

14.2.12.1.56.1 Objectives

To demonstrate the operating characteristics of the cavity cooling, control rod

drive mechanism (CRDM), and the elevator machine room exhaust fans and verify

their associated instrumentation and controls, including their response to

safety signals.

14.2.12.1.56.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The CRDM and cavity cooling portions of the containment

cooling system are air balanced.

14.2.12.1.56.3 Test Method

a. The cavity cooling, elevator machine room exhaust, and

CRDM fans are operated, flow data recorded, and fan

capacities calculated.

b. The response of the CRDM fans to a safety injection

signal is verified.

14.2-77 Rev. 0 WOLF CREEK 14.2.12.1.56.4 Acceptance Criteria

a. The capacities of the cavity cooling, elevator machine

room exhaust, and CRDM fans are within design

specifications.

b. The appropriate CRDM fans supply breakers open on

receipt of a safety injection signal.

14.2.12.1.57 Integrated Containment Leak Rate Test (SU3-GP01)

14.2.12.1.57.1 Objective

To demonstrate that the total leakage from the containment does not exceed the

maximum allowable leakage rate at the calculated peak containment internal pressure. The operability of the containment cooling fans at design accident pressure is also verified.

14.2.12.1.57.2 Prerequisites

a. The containment penetration leakage rate tests (type B

tests) and containment isolation valve leakage tests

(type C tests) are complete and the containment has been

pressurized to 115 percent of the design pressure.

b. All containment isolation valves are closed by normal

actuation methods.

c. Containment penetrations, including equipment hatches

and personnel airlocks, are closed.

d. Portions of fluid systems that are part of the

containment boundary, that may be opened directly to the

containment or outside atmosphere under post-accident

conditions, are opened or vented to the appropriate

atmosphere to place the containment in as close to post-

accident conditions as possible.

e. Required instrument calibration is complete.

14.2.12.1.57.3 Test Method

a. The integrated containment leak rate test (type A test)

is conducted, using the absolute method, described in

the ANSI/ANS 56.8-1981 Containment System Leakage

Testing Requirements. Measurements of containment

atmosphere dry-bulb temperature, dew point and pressure

are taken to calculate the leakage rate. A standard

14.2-78 Rev. 0 WOLF CREEK statistical analysis of data is conducted, using a linear least squares fit regression analysis to

calculate the leakage rate.

b. On completion of the leak rate test, a verification test is conducted to confirm the capability of the data

acquisition and reduction system to satisfactorily

determine the calculated integrated leakage rate. The

verification test is accomplished by imposing a known

leakage rate on the containment, or by pumping back a

known quantity of air into the containment through a

calibrated flow measurement device.

c. While at the design accident pressure, data is recorded

for the containment cooling fans.

14.2.12.1.57.4 Acceptance Criteria

The containment integrated leakage does not exceed the maximum allowable

leakage rate at a calculated peak containment internal pressure, as defined in

10 CFR 50, Appendix J.

The containment cooling fan operation at design accident pressure is in

accordance with design.

14.2.12.1.58 Reactor Containment Structural Integrity Acceptance

Test (SU3-GP02)

14.2.12.1.58.1 Objectives

To demonstrate the structural integrity of the reactor containment building.

14.2.12.1.58.2 Prerequisites

a. Containment penetrations are installed, and penetration

leak tests are completed.

b. Containment penetrations, including equipment hatches

and personnel airlocks, are closed.

c. Required instrument calibration is complete.

14.2.12.1.58.3 Test Method

The containment is pressurized at 115 percent of the design pressure, and

deflection measurements and concrete crack inspections are made to determine

that the actual structural response is within the limits predicted by the

design analyses.

14.2-79 Rev. 0 WOLF CREEK 14.2.12.1.58.4 Acceptance Criteria

The containment structural response is within the limits predicted by design

analyses.

14.2.12.1.59 Post-Accident Hydrogen Removal System

Preoperational Test (S-03GS01)

14.2.12.1.59.1 Objectives

a. To demonstrate that the hydrogen recombiner performance

characteristics are within design specifications.

b. To determine the operation of system dampers and valves,

including the response of hydrogen purge and hydrogen monitoring containment isolation valves to a CIS.

c. To demonstrate the operability of the hydrogen analyzers

and their ability to sample the containment atmosphere.

14.2.12.1.59.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2.12.1.59.3 Test Method

a. Performance characteristics are recorded, while the hydrogen recombiners are operating.
b. System valve and damper control circuits are verified,

including the response of hydrogen purge and hydrogen

monitoring containment isolation valves to a CIS.

c. The hydrogen analyzers are operated, and performance

data recorded.

14.2.12.1.59.4 Acceptance Criteria

a. Hydrogen recombiner performance characteristics are

within design specifications.

b. Hydrogen purge and hydrogen monitoring containment

isolation valves close on receipt of a CIS. Valve

closure times are within design specifications.

14.2-80 Rev. 0 WOLF CREEK 14.2.12.1.60 Containment Purge System HVAC Preoperational Test (S-03GT01)

14.2.12.1.60.1 Objectives

To demonstrate the capacities of the containment minipurge supply and exhaust,

shutdown purge supply and exhaust, and containment atmospheric control fans.

The operation of system instrumentation and controls, including the response of

system fans and dampers to safety signals, is also verified.

14.2.12.1.60.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits are operational.
c. The containment purge HVAC system has been air balanced.
d. The compressed air system is available to supply air to

system valves and dampers.

14.2.12.1.60.3 Test Method

a. The containment minipurge supply and exhaust, shutdown

purge supply and exhaust, and containment atmospheric

control fans are operated, flow data recorded, and fan

capacities calculated.

b. The response of system fans and dampers to safety signals is verified.

14.2.12.1.60.4 Acceptance Criteria

a. The capacities of the containment minipurge supply and

exhaust, shutdown purge supply and exhaust, and

containment atmospheric control fans are within design

specifications.

b. System fans and dampers align or actuate in response to

containment purge isolation and safety injection

signals, in accordance with system design. Damper

closure times are within design specifications.

14.2-81 Rev. 0 WOLF CREEK 14.2.12.1.61 Gaseous Radwaste System Preoperational Test (S-03HA01)

14.2.12.1.61.1 Objectives

a. To demonstrate the performance characteristics of the

gas decay tank drain pump, waste gas compressors, and

catalytic hydrogen recombiners, including their response

to safety signals.

b. To verify the operability of system valves, including

the response of the waste gas discharge valve to a high-

radiation signal.

c. To verify that system instrumentation and controls function properly.

14.2.12.1.61.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The component cooling water system is available to

supply cooling water to the waste gas compressors and

catalytic hydrogen recombiners.

d. The service gas system is available to provide nitrogen, hydrogen, and oxygen to the catalytic hydrogen recombiners.
e. The reactor makeup water system is available to provide

water to the waste gas compressors, catalytic hydrogen

recombiners, and the waste gas decay tank drain header.

14.2.12.1.61.3 Test Method

a. Performance characteristics of the gas decay tank drain

pump, and waste gas compressors are verified.

b. Hydrogen is introduced to the system and the catalytic

hydrogen recombiners performance are verified.

c. System component control circuits are verified,

including component response to safety signals.

14.2.12.1.61.4 Acceptance Criteria

a. Performance characteristics of the gas decay tank drain

pump, waste gas compressors, and catalytic hydrogen

recombiners are within design specifications.

14.2-82 Rev. 0 WOLF CREEK

b. The waste gas discharge valve automatically closes on a high-radiation signal.
c. The waste gas compressors trip on a high-high or low-low

moisture separator level, high or low moisture separator pressure, low compressor suction pressure, or low

component cooling water flow.

d. The hydrogen recombiner oxygen feed valve closes on

high-high hydrogen concentration in the recombiner feed,

high-high oxygen concentration in the recombiner

discharge, high cooler-condenser discharge temperature,

high-high recombiner discharge temperature, low-low

recombiner flow, and high-high recombiner reactor inlet

temperature.

e. The hydrogen recombiner oxygen feed valve signal is

blocked on high oxygen concentration in the recombiner

feed and high catalyst bed temperature.

f. The volume control tank vent valve closes on a hydrogen

recombiner trip, low volume control tank pressure, and

low waste gas compressor suction pressure.

14.2.12.1.62 Emergency Fuel Oil System Preoperational Test

(S-03JE01)

14.2.12.1.62.1 Objectives

To demonstrate the capability of the system to provide an adequate fuel supply to the emergency diesel generator fuel oil day tanks and verify that the associated instrumentation and controls are functioning properly.

14.2.12.1.62.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2.12.1.62.3 Test Method

a. Fuel oil is transferred from the fuel oil storage tank

to the fuel oil day tanks by means of the transfer

pumps. Flow and pressure characteristics are recorded.

b. Fuel oil day tank levels are varied to verify the

transfer pump automatic operations.

14.2-83 Rev. 0 WOLF CREEK

c. Response to fire and emergency diesel generator start signals are verified.

14.2.12.1.62.4 Acceptance Criteria

a. The transfer pump flow capacity is verified for later

comparison to the fuel consumption rate (S-03NF02).

b. Control circuit automatic operation from fuel oil day

tank levels, fire signals, and diesel generator start

signals is within design specifications.

14.2.12.1.63 Spent Fuel Pool Crane Preoperational Test

(SU3-KE01)

14.2.12.1.63.l Objectives

a. To demonstrate proper operation of the spent fuel pool

bridge crane control circuits and associated interlocks.

b. To document the data obtained during testing of the

spent fuel pool bridge crane at 125 percent of rated

load.

c. To verify the ability of the spent fuel pool bridge

crane and associated fuel handling tools to transfer a

dummy fuel assembly.

14.2.12.1.63.2 Prerequisites

a. Required component testing and instrument calibration are completed.
b. Required electrical power supplies and control circuits

are operational.

c. A dummy fuel assembly is available.

14.2.12.1.63.3 Test Method

a. Operability of the spent fuel pool bridge crane control

circuits and associated interlocks is verified.

b. Ability of the spent fuel pool bridge crane and

associated fuel handling tools to transfer a dummy fuel

assembly is verified.

14.2-84 Rev. 0 WOLF CREEK 14.2.12.1.63.4 Acceptance Criteria

a. The spent fuel pool bridge crane electric and manual

hoists support 125 percent of their rated load.

b. The spent fuel pool bridge crane monorail center span

deflection at rated load is within design

specifications.

c. The spent fuel pool crane bridge, trolley and hoist

speeds at rated loads are within design specifications.

d. All control circuits and interlocks associated with the

spent fuel pool bridge crane operate in accordance with

system design.

e. While transferring a dummy fuel assembly, the spent fuel

pool bridge crane and associated fuel handling tools

operate in accordance with system design.

14.2.12.1.64 New Fuel Elevator Preoperational Test (SU3-KE02)

14.2.12.1.64.1 Objectives

a. To demonstrate proper operation of the new fuel elevator

control circuits and associated interlocks.

b. To verify the ability of the new fuel elevator to raise

and lower a dummy fuel assembly.

14.2.12.1.64.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. A dummy fuel assembly is available.

14.2.12.1.64.3 Test Method

Operability of the new fuel elevator including control circuits and associated

interlocks is verified.

14.2.12.1.64.4 Acceptance Criteria

a. All control circuits and interlocks associated with the

new fuel elevator operate in accordance with system

design.

14.2-85 Rev. 0 WOLF CREEK

b. While raising and lowering a dummy fuel assembly, the new fuel elevator operates in accordance with system

design.

14.2.12.1.65 Fuel Handling and Storage Preoperational Test (SU3-KE03)

14.2.12.1.65.1 Objectives

a. To verify the ability of the spent fuel cask handling

crane, and associated fuel handling tools to transfer a

dummy fuel assembly.

b. To demonstrate proper operation of the spent fuel cask

handling crane control circuits and associated interlocks.

c. To document the data obtained during testing of the

spent fuel cask handling crane at 125 percent of rated

load.

14.2.12.1.65.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. A dummy fuel assembly is available.

14.2.12.1.65.3 Test Method

a. During the transfer of a dummy fuel assembly, the

operability of the spent fuel cask handling crane and

associated fuel handling tools is verified.

b. Operability of the spent fuel cask handling crane

control circuits and associated interlocks is verified.

14.2.12.1.65.4 Acceptance Criteria

a. While transferring a dummy fuel assembly, the spent fuel

cask handling crane and associated fuel handling tools

operate in accordance with system design.

b. All control circuits and interlocks associated with the

spent fuel cask handling crane operate in accordance

with system design.

14.2-86 Rev. 0 WOLF CREEK

c. The spent fuel cask handling crane hoist supports 125 percent of rated load.
d. The spent fuel cask handling crane bridge center span

deflection at rated load is within design specifications.

e. The spent fuel cask handling crane bridge, trolley and

hoist speeds at rated loads are within design

specifications.

14.2.12.1.66 Fuel Transfer System Preoperational Test

(SU3-KE04)

14.2.12.1.66.l Objectives

a. To demonstrate proper operation of the fuel transfer

system control circuits and associated interlocks.

b. To verify the ability of the fuel transfer system and

associated handling tools to transfer a dummy fuel

assembly.

14.2.12.1.66.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. A dummy fuel assembly is available.

14.2.12.1.66.3 Test Method

a. Operability of the fuel transfer system control circuits

and associated interlocks is verified.

b. During the transfer of a dummy fuel assembly, the

operability of the fuel transfer system and associated

handling tools is verified.

14.2.12.1.66.4 Acceptance Criteria

a. All control circuits and interlocks associated with the

fuel transfer system operate in accordance with system

design.

14.2-87 Rev. 0 WOLF CREEK

b. While transferring a dummy fuel assembly, the fuel transfer system and associated handling tools operate in

accordance with system design.

14.2.12.1.67 Refueling Machine and RCC Change Fixture Preoperational Test (SU3-KE05)

14.2.12.1.67.1 Objectives

a. To demonstrate proper operation of the refueling

machine, rod cluster control change fixture and

containment building polar crane control circuits and

associated interlocks.

b. To document the data obtained during testing of the containment building polar crane at 125 percent of rated load.
c. To verify the ability of the refueling machine to

transfer a dummy fuel assembly.

14.2.12.1.67.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. A dummy fuel assembly is available.
d. A dummy control rod assembly is available.

14.2.12.1.67.3 Test Method

a. Operability of the refueling machine and rod cluster

control change fixture control circuits and associated

bridge, trolley, hoist and gripper interlocks is

verified.

b. Operability of the containment building polar crane

control circuits and associated interlocks is verified.

14.2.12.1.67.4 Acceptance Criteria

a. All control circuits and interlocks associated with the

refueling machine and rod cluster control change fixture

operate in accordance with system design.

14.2-88 Rev. 0 WOLF CREEK

b. The control circuits and interlocks associated with the containment building polar crane operate in accordance

with system design.

c. The containment polar crane main and auxiliary hoists support 125 percent of their rated load.
d. The containment polar crane bridge center span

deflection at rated load is within design

specifications.

e. The containment polar crane bridge, trolley, and hoist

speeds at rated loads are within design specifications.

f. While transferring a dummy fuel assembly, the refueling machine operates in accordance with system design.

14.2.12.1.68 Refueling Machine Indexing Test (S-03KE06)

14.2.12.1.68.1 Objectives

a. To verify the indexing of the refueling machine and

establish bridge rail reference points for future

operations.

b. To demonstrate the ability to transfer the dummy fuel

assembly to the reactor vessel.

14.2.12.1.68.2 Prerequisites

a. Required component testing and instrument calibration are complete.
b. Required electrical power supplies and control circuits

are operational.

c. A dummy fuel assembly is available.

14.2.12.1.68.3 Test Method

a. While transferring a dummy fuel assembly with the

refueling machine, the bridge rail is marked at key

transfer points.

14.2.12.1.68.4 Acceptance Criteria

a. The refueling machine can load a dummy fuel assembly in

each of the reactor vessel fuel loading locations.

14.2.12.1.69 Fuel Handling System Integrated Preoperational Test

(SU3-KE07)

14.2-89 Rev. 0 WOLF CREEK 14.2.12.1.69.1 Objective

To verify the ability of the refueling machine, new fuel elevator, fuel

transfer system, spent fuel bridge crane, spent fuel cask handling crane and

associated fuel handling tools to transfer a dummy fuel assembly.

14.2.12.1.69.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The reactor vessel, refueling pool, refueling canal and spent fuel pool are filled with demineralized water.
d. A dummy fuel assembly is available.

14.2.12.1.69.3 Test Method

During the transfer of a dummy fuel assembly, the operability of the refueling

machine, new fuel elevator, fuel transfer system, spent fuel bridge crane,

spent fuel cask handling crane and associated fuel handling tools is verified.

14.2.12.1.69.4 Acceptance Criteria

While transferring a dummy fuel assembly, the refueling machine, new fuel

elevator, fuel transfer system, spent fuel bridge crane, spent fuel cask

handling crane and associated fuel handling tools operate in accordance with system design.

14.2.12.1.70 Diesel Generator Mechanical Preoperational Test

(S-03KJ01)

14.2.12.1.70.1 Objectives

a. To demonstrate the performance characteristics of the

diesel generators and associated auxiliaries, and verify

that each diesel reaches rated speed within the required

time.

b. To verify the operability of all control circuits

associated with the diesel generator and diesel

auxiliaries, including the control circuits response to

safety signals.

14.2-90 Rev. 0 WOLF CREEK

c. To demonstrate the capability of each air storage tank to provide five diesel cranking cycles without being

recharged.

14.2.12.1.70.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The essential service water system is available to

provide cooling water to the diesel engine intercooler

heat exchanger.

d. The emergency fuel oil system is available to provide

fuel oil to the diesel generators.

e. The fire protection system is available to support this

test.

14.2.12.1.70.3 Test Method

a. The diesel generators are started, and the time required

to reach rated speed is recorded.

b. With the diesel generators and associated auxiliaries

operating, performance characteristics are verified.

c. The operability of all control circuits associated with the diesel generator and diesel auxiliaries, including

the control circuits' response to safety signals, is

verified.

d. The ability of each air storage tank to provide five

diesel cranking cycles, without being recharged, is

verified.

14.2.12.1.70.4 Acceptance Criteria

a. The time required for each diesel generator to reach

rated speed is within design specifications.

b. The performance characteristics of the diesel generators

and associated auxiliaries are within design

specifications.

c. Each diesel generator starts automatically on receipt of

a safety injection signal or a bus under-voltage signal.

14.2-91 Rev. 0 WOLF CREEK

d. Each diesel generator trips automatically on receipt of each of the following signals:

Lube oil pressure low

Jacket coolant temperature high Crankcase pressure high

Start failure

Engine overspeed

Diesel generator ground overcurrent

Diesel generator differential current

e. The diesel generator neutral ground overcurrent trip

signal is bypassed when the diesel generator is

operating in the emergency mode.

f. Each air storage tank is capable of providing five diesel cranking cycles, without being recharged.
g. Each starting air compressor has the ability to charge

its respective air tank from minimum to normal pressure

within the required time.

14.2.12.1.71 4160-V (Class IE) System Preoperational Test

(S-03NB01)

14.2.12.1.71.1 Objectives

a. To demonstrate that the 4,160-V Class IE busses can be

energized from their normal and alternate sources.

b. To verify that a 4,160-V Class IE bus digital undervoltage signal trips the associated incoming feeder

breakers.

c. To verify that a degraded bus voltage condition will

trip the associated incoming feeder breakers.

d. To verify proper operation of system instrumentation and

alarms.

14.2.12.1.71.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2-92 Rev. 0 WOLF CREEK 14.2.12.1.71.3 Test Method

a. The 4,160-V Class IE busses are energized from their

normal source, and bus voltages are recorded.

b. The 4,160-V Class IE busses are energized from their

alternate source, and bus voltages are recorded.

c. 4,160-V Class IE bus undervoltage signals are simulated,

and proper operation of the 4,160-V Class IE feeder

breakers is verified.

14.2.12.1.71.4 Acceptance Criteria

a. The voltage of each 4,160-V Class IE bus, when supplied from its normal source, is within design specifications.
b. The voltage of each 4,160-V Class IE bus, when supplied

from its alternate source, is within design

specifications.

c. A 4,160-V Class IE bus digital undervoltage signal will

trip the appropriate bus incoming feeder breakers.

d. A degraded voltage condition on either 4,160-V Class IE

bus will cause an alarm and, if it continues, trip the

appropriate bus incoming feeder breakers.

e. A degraded voltage condition on either 4,160-V Class IE

bus coincident with a safety injection actuation signal will immediately trip the bus incoming feeder breakers.

14.2.12.1.72 Diesel Generator Electric Preoperational Test

(S-03NE01)

14.2.12.1.72.1 Objectives

a. To demonstrate that each diesel generator is capable of

35 consecutive valid starts with no failure.

b. To demonstrate the ability of each diesel generator to

carry the design load for the time required to reach

equilibrium temperature plus l hour, without exceeding

design limits.

c. To demonstrate the ability of each diesel generator to

attain and stabilize frequency and voltage within the

design limits and time.

14.2-93 Rev. 0 WOLF CREEK

d. To demonstrate the capability of each diesel generator to withstand a full-load rejection without exceeding

speeds or voltages that cause tripping or damage.

e. To demonstrate the operability of each diesel generator feeder breaker and associated interlocks.
f. To demonstrate the ability of the diesel cooling water

system to maintain the diesel temperature within design

specifications, while the diesel generators are

operating at full load.

g. To demonstrate the ability of each diesel generator to

start and shed the largest single motor while supplying

all other sequenced loads, maintaining voltage and frequency within design limits.

14.2.12.l.72.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The essential service water system is available to

provide cooling water to the diesel generator

intercooler heat exchanger.

d. The emergency fuel oil system is available to provide fuel oil to the diesel generators.
e. The fire protection system is available to support this

test.

f. The 4.16-kV busses are available for loading to support

this test.

14.2.12.1.72.3 Test Method

a. The ability of each diesel generator to undergo 35

consecutive starts with no failure is verified.

b. The ability of each diesel generator to carry the design

load for the time required to reach equilibrium

temperature, plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, without exceeding design

limits, is verified.

14.2-94 Rev. 0 WOLF CREEK

c. The ability of each diesel generator to attain and stabilize frequency and voltage within the design limits

and time is verified.

d. The ability of each diesel generator to withstand a full-load rejection, without exceeding speeds or

voltages that cause tripping, is verified.

e. The operability of each diesel generator feeder breaker

and associated interlocks is verified.

f. While operating each diesel generator at full-load

conditions, the ability of the diesel cooling water

system to maintain diesel temperatures within design

specifications is verified.

g. The ability of each diesel generator to start and shed

the largest fully loaded single motor while supplying

all other sequenced loads and maintain voltage and

frequency within design limits is verified.

14.2.12.1.72.4 Acceptance Criteria

a. Each diesel generator is capable of carrying the design

load for the time required to reach equilibrium

temperature, plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, without exceeding design

limits.

b. Each diesel generator can attain and stabilize frequency

and voltage within design limits and time.

c. Each diesel generator is capable of withstanding a full-

load rejection without exceeding speeds or voltages that

cause tripping.

d. When a diesel generator is operating in the nonemergency

(test) mode, the associated diesel generator feeder

breaker trips on receipt of any of the following

signals:

Generator overcurrent

Reverse power

Loss of field

Underfrequency

e. The diesel generator stops and the associated diesel

generator feeder breaker trips on receipt of any of the

following signals:

Generator differential current

Neutral ground overcurrent

14.2-95 Rev. 0 WOLF CREEK

f. When a diesel generator is operating in the emergency mode, the following trip signals are bypassed:

Neutral ground overcurrent

Generator overcurrent Reverse power

Loss of field

Underfrequency

g. Each diesel generator cooling water system, with the

diesel generators operating at full-load, maintains the

diesel temperatures within design specifications.

h. Each diesel generator has the capability of starting and

shedding the largest fully loaded single motor while supplying all other sequenced loads, maintaining voltage and frequency within design limits.

i. Diesel generators are capable of 35 consecutive valid

starts with no failure.

14.2.12.1.73 Integrated Control Logic Test (SU3-NF01)

14.2.12.1.73.1 Objectives

a. To demonstrate that the actuation of the LOCA sequencer,

shutdown sequencer, safety-related load shed, and

nonsafety-related load shed circuits on receipt of the

appropriate undervoltage, safety injection, containment

spray actuation, diesel generator breaker position, and normal and alternate 4,160-V feeder breaker position signals is in accordance with system design.

b. To demonstrate that the LOCA sequencer, shutdown

sequencer, safety-related load shed, and nonsafety-

related load shed circuits shed and sequence loads in

accordance with system design.

14.2.12.1.73.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2.12.1.73.3 Test Method

a. Undervoltage, safety injection, containment spray

actuation, diesel generator breaker position, and

normal and

14.2-96 Rev. 0 WOLF CREEK alternate 4,160-V feeder breaker position signals are initiated, and the actuation of the LOCA sequencer,

shutdown sequencer, safety-related load shed, and

nonsafety-related load shed circuits is verified.

b. Signals are initiated to actuate the LOCA sequencer,

shutdown sequencer, safety-related load shed, and

nonsafety-related load shed circuits, and proper load

shed and load sequencing are verified.

14.2.12.1.73.4 Acceptance Criteria

a. Actuation of the LOCA sequencer, shutdown sequencer,

safety-related load shed, and nonsafety-related load

shed circuits on receipt of under-voltage, safety injection, containment spray actuation, diesel generator breaker position, and normal and alternate 4,160-V

feeder breaker position signals is in accordance with

system design.

b. The LOCA sequencer, shutdown sequencer, safety-related

load shed, and nonsafety-related load shed circuits shed

and sequence loads in accordance with system design.

14.2.12.1.74 LOCA Sequencer Preoperational Test (S-03NF02)

14.2.12.1.74.1 Objectives

a. To demonstrate that initiation of a safety injection

signal (SIS) will shed the nonsafety-related loads, start the diesel generator, and sequence the associated equipment. The ability of each 4,160-V Class IE load

group to supply the sequenced loads while maintaining

voltage within design specifications is also verified.

b. To demonstrate that a loss of offsite power concurrent

with SIS will shed the safety-related loads, start the

diesel generator, close the diesel generator feeder

breaker, and sequence the associated equipment. The

ability of each diesel generator to supply the sequenced

loads while maintaining voltage and frequency within

design specifications is also verified.

c. To demonstrate the ability of each diesel generator to

carry the short-time rating load for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and the

continuous rated load for 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />, without exceeding

design limits.

d. To demonstrate that each diesel generator, following

operation for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at the short-time rated load and

14.2-97 Rev. 0 WOLF CREEK 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> at the continuous rated load, will start automatically on a loss of ac voltage concurrent with an

SIS, attain voltage and frequency within design limits

and time, and accept the LOCA sequenced loads, while

maintaining voltage and frequency within design limits.

c. To demonstrate the ability of the diesel cooling water

system to maintain the diesel temperature within design

specifications, while the diesel generators are

operating for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at the short-time rating load and

22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> at the continuous rating load.

f. To determine the fuel oil consumption of each diesel,

while operating for 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> at the continuous rating

load.

g. To demonstrate the ability of the 125 V dc system to

perform its design functions while at minimum voltage.

h. To demonstrate the independence between the redundant on

ac and dc power sources.

14.2.12.1.74.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Each diesel generator and its associated auxiliaries are

available.

c. All components actuated by the LOCA sequencer and safety-related and nonsafety-related load shed circuits

are available.

14.2.12.1.74.3 Test Method

a. A train A SIS is initiated, and the following are

verified:

1. Group l nonsafety-related loads are shed.
2. Group 1 diesel generator starts.
3. Group 1 LOCA sequencer is actuated, and associated

components are sequenced. The times for sequenced

pumps to reach full flow are verified.

4. With bus NB01 supplying the sequenced loads from its

normal source, bus voltage is recorded.

14.2-98 Rev. 0 WOLF CREEK

b. With group 2 dc load group isolated from its power source and group 1 dc load group voltage set to minimum,

a loss of offsite power is initiated concurrent with a

train A SIS, and the following are verified:

1. Safety-related group 1 loads are shed.
2. Group 1 diesel generator starts, and its feeder

breaker closes.

3. Group 1 LOCA sequencer is actuated, and associated

components are sequenced. The times for sequenced

pumps to reach full flow are verified.

4. With the group 1 diesel generator supplying the sequenced loads, bus voltage and frequency are recorded.
5. The group 2 ac and dc busses are monitored to

verify the absence of voltage on these busses and

loads, indicating no interconnection at load

groups.

c. The ability of the group 1 diesel generator to carry the

short-time rating load for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> without exceeding

design limits is verified.

d. The ability of the group 1 diesel generator to carry the

continuous rated load for 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> without exceeding

design limits is verified. Group l diesel fuel oil consumption is also determined.

e. Following group 1 diesel generator operation for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

at the short-time rated load and 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> at the

continuous rated load, the group 1 diesel generator is

shutdown, a loss of group 1 ac voltage is initiated

concurrent with a train A SIS, and the ability of the

group l diesel generator to start, attain voltage and

frequency within design limits and time, and accept the

loads resulting from the design accident loading

sequence while maintaining voltage and frequency within

design limits is verified. If this test is not

satisfactorily completed, it is not necessary to repeat

the tests of items c and d prior to rerunning this

test. Instead, prior to rerunning this test, the diesel

generator may be operated at the continuous rated load

for l hour or until operating temperature has

stabilized.

14.2-99 Rev. 0 WOLF CREEK

f. A train B SIS is initiated, and the following are verified:
1. Group 2 nonsafety-related loads are shed.
2. Group 2 diesel generator starts.
3. Group 2 LOCA sequencer is actuated, and associated

components are sequenced. The times for sequenced

pumps to reach full flow are verified.

4. With Bus NB02 supplying the sequenced loads from

its normal source, bus voltage is recorded.

g. With group 1 dc load group isolated from its power source and group 2 dc load group voltage set to minimum, a loss of offsite power is initiated concurrent with a

train B SIS, and the following are verified:

1. Safety-related group 2 loads are shed.
2. Group 2 diesel generator starts, and its feeder

breaker closes.

3. Group 2 LOCA sequencer is actuated, and associated

components are sequenced. The times for sequenced

pumps to reach full flow are verified.

4. With the group 2 diesel generator supplying the

sequenced loads, bus voltage and frequency are recorded.

5. The group l ac and dc busses are monitored to

verify the absence of voltage on these busses and

loads, indicating no interconnection of load

groups.

h. The ability of the group 2 diesel generator to carry the

short-time rating load for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> without exceeding

design limits is verified.

i. The ability of the group 2 diesel generator to carry the

continuous rated load for 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> without exceeding

design limits is verified. Group 2 diesel fuel oil

consumption is also determined.

14.2-100 Rev. 0 WOLF CREEK

j. Following group 2 diesel generator operation for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at the short-time rated load and 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> at the

continuous rated load, the group 2 diesel generator is

shutdown, a loss of group 2 ac voltage is initiated

concurrent with a train B SIS, and the ability of the group 2 diesel generator to start, attain voltage and

frequency within design limits and time, and accept the

LOCA sequenced loads, while maintaining voltage and

frequency within design limits, is verified. If this

test is not satisfactorily completed, it is not necessary

to repeat the tests of items h and i prior to rerunning

this test. Instead, prior to rerunning this test, the

diesel generator may be operated at the continuous rated

load for l hour or until operating temperature has

stabilized.

k. The ability of the diesel cooling water system to

maintain the diesel temperature within design

specifications, while the diesel generators are operating

for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at the short-time rating load and 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> at

the continuous rating load, is verified.

14.2.12.1.74.4 Acceptance Criteria

a. A train A SIS initiates the following, in accordance

with system design:

1. Group 1 nonsafety-related loads are shed.
2. Group 1 diesel generator starts.
3. Group l LOCA sequencer actuates, and the associated

components are sequenced. Sequenced pumps reach

full flow within the required times.

b. Bus NB01, while powered from its normal source, supplies

the sequenced loads while maintaining voltage within

design specifications.

c. With the group 2 dc load group isolated from its power

source and the group 1 dc load group voltage at minimum,

a loss of offsite power concurrent with a train A SIS

initiates the following, in accordance with system

design:

1. Safety-related group 1 loads are shed.
2. Group 1 diesel generator starts, and its feeder

breaker closes.

14.2-101 Rev. 0 WOLF CREEK

3. Group l LOCA sequencer actuates, and the associated components are sequenced. Sequenced pumps reach

full flow within design times.

d. Group l diesel generator supplies the sequenced loads, while maintaining voltage and frequency within design

specifications.

e. With load group 1 supplying loads following a loss of

offsite power concurrent with a train A SIS, the group 2

ac and dc busses are verified de-energized, indicating

no interconnection of load groups.

f. Following group 1 diesel generator operation for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

at the short-time rated load and 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> at the continuous rated load, the group 1 diesel generator starts, attains voltage and frequency within design

limits and time, and accepts the LOCA sequenced loads

while maintaining voltage and frequency within design

limits, on loss of group 1 ac voltage concurrent with a

train A SIS.

g. A train B SIS initiates the following, in accordance

with the system design:

1. Group 2 nonsafety-related loads are shed.
2. Group 2 diesel generator starts.
3. Group 2 LOCA sequencer actuates, and the associated components are sequenced. Sequenced pumps reach full flow within design times.
h. Bus NB02, while powered from its normal source, supplies

the required loads while maintaining the voltage within

design specifications.

i. With the group 1 dc load group isolated from its power

source and the group 2 dc load group voltage at minimum,

a loss of offsite power concurrent with a train B SIS

initiates the following, in accordance with system

design:

1. Safety-related group 2 loads are shed.
2. Group 2 diesel generator starts, and its feeder

breaker closes.

14.2-102 Rev. 0 WOLF CREEK

3. Group 2 LOCA sequencer actuates, and the associated components are sequenced. Sequenced pumps reach

full flow within design times.

j. Group 2 diesel generator supplies the required loads, while maintaining voltage and frequency within design

specifications.

k. With load group 2 supplying loads following a loss of

offsite power concurrent with a train B SIS, the group 1

ac and dc busses are verified de-energized, indicating

no interconnection of load groups.

l. Following group 2 diesel generator operation for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

at the short-time rated load and 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> at continuous rated load, group 2 diesel generator starts, attains voltage and frequency within design limits and time, and

accepts the LOCA sequenced loads while maintaining

voltage and frequency within design limits, on loss of

group 2 ac voltage concurrent with a train B SIS.

m. Each diesel generator is capable of carrying the short-

time rating load for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and the continuous rated

load for 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />, without exceeding design limits.

n. Fuel oil consumption of each diesel, while operating at

the continuous rated load, is within design

specifications.

o. Each diesel generator cooling water system, with the diesel generators operating for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at the short-time rating load and 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> at the continuous rating

load, maintains the diesel temperatures within design

specifications.

p. The controls required for the loss of offsite power

concurrent with a SIS (shedding, sequencing, etc.)

function with minimum dc voltage available.

14.2.12.1.75 Shutdown Sequencer Preoperational Test (S-03NF03)

14.2.12.1.75.1 Objectives

a. To demonstrate that de-energization of either 4,160-V

Class IE load group will start the associated diesel

generator, close the diesel generator feeder breaker,

actuate the associated group load shed, and actuate the

shutdown sequencer. All sequenced components are

verified to start within required design times.

14.2-103 Rev. 0 WOLF CREEK

b. To demonstrate that each diesel generator will maintain voltage and frequency within design specifications while

supplying the design shutdown loads.

c. To demonstrate the ability of the emergency 4.16-kV loads to start at maximum and minimum design voltages.

14.2.12.1.75.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. Each diesel generator and its associated auxiliaries are available.
d. All components actuated by the shutdown sequencer are

available.

14.2.12.1.75.3 Test Method

a. Class IE 4,160-V load group 1 is de-energized and the

following are verified:

1. Group 1 load shedder actuates.
2. Group 1 diesel generator starts, and its feeder

breaker closes.

3. Group 1 shutdown sequencer is actuated, and

associated components are sequenced. Components

are verified to actuate within the required design

times.

b. Class IE 4,160-V load group 2 is de-energized and the

following are verified:

1. Group 2 load shedder actuates.
2. Group 2 diesel generator starts, and its feeder

breaker closes.

3. Group 2 shutdown sequencer is actuated, and

associated components are sequenced. Components

are verified to actuate within the required design

times.

14.2-104 Rev. 0 WOLF CREEK

c. Emergency 4.16-kV loads are started while their respective diesel generators are supplying:
1. Minimum rated voltage
2. Maximum rated voltage
d. The ability of each diesel generator to maintain voltage

and frequency within the design specifications while

supplying the design shutdown loads is verified.

14.2.12.1.75.4 Acceptance Criteria

a. De-energization of Class IE 4,160-V load group 1

initiates the following, in accordance with system design:

1. Group 1 diesel generator starts, and its feeder

breaker closes.

2. Group 1 shutdown sequencer actuates, and associated

components are sequenced. Components actuate

within required design times.

3. Group 1 load shedder actuates.
b. De-energization of Class IE 4,160-V load group 2

initiates the following, in accordance with system

design:

1. Group 2 diesel generator starts, and its feeder breaker closes.
2. Group 2 shutdown sequencer actuates, and associated

components are sequenced. Components actuate

within required design times.

3. Group 2 load shedder actuates.
c. The emergency 4.16-kV loads start and reach rated speed

within design times, with minimum and maximum design

voltage.

d. Each diesel generator maintains voltage and frequency

within design specifications, while supplying the design

shutdown loads.

14.2.12.1.76 480-V (Class IE) System Preoperational Test

(S-03NG01)

14.2.12.1.76.1 Objectives

To demonstrate that the 480-V Class IE load centers can be energized from

their normal and alternate sources and verify the

14.2-105 Rev. 0 WOLF CREEK operability of system breaker protective interlocks. Proper operation of system instrumentation and controls is also verified.

14.2.12.1.76.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2.12.1.76.3 Test Method

a. The 480-V Class IE load centers are energized from their

normal source, and voltages are recorded.

b. The 480-V Class IE load centers are energized from their

alternate source, and voltages are recorded.

c. System breakers are operated, and breaker interlocks

verified.

14.2.12.1.76.4 Acceptance Criteria

a. The voltage for each 480-V Class IE load center, when

supplied from its normal source, is within design

specifications.

b. The voltage for each 480-V Class IE load center, when

supplied from its alternate source, is within design specifications.

c. System breaker interlocks operate in accordance with the

system design.

14.2.12.1.77 480-V Class IE System (ESW) Preoperational Test

(SU3-NG02).

14.2.12.1.77.1 Objectives

To demonstrate that the nonpower block 480-V Class IE MCC can be energized from

their normal source and to verify their bus voltage phase sequence. Proper

operation of system instrumentation and controls is also verified.

14.2.12.1.77.2 Prerequisites

a. Required component testing and instrument calibration

are completed.

14.2-106 Rev. 0 WOLF CREEK

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

14.2.12.1.77.3 Test Method

The nonpower block 480-V Class IE MCC are energized, voltages are recorded, and

phase sequence is verified.

14.2.12.1.77.4 Acceptance Criteria

a. The voltage for each nonpower block 480-V Class IE MCC

is within design specification.

b. The bus voltage phase sequence of the nonpower block

480-V Class IE MCC is in accordance with design.

14.2.12.1.78 125-V (Class IE) DC System Preoperational Test

(S-03NK01)

14.2.12.1.78.1 Objectives

To demonstrate the ability of the batteries and chargers to provide power

during normal operations and the battery to provide power during abnormal

conditions. The battery chargers' ability to recharge their respective battery

is also demonstrated. Proper operation of the system instrumentation and

controls is also verified.

14.2.12.1.78.2 Prerequisites

a. Required component testing and instrument calibration are complete.
b. Required electrical power supplies and control circuits

are operational.

c. Ventilation for the battery rooms is available.

14.2.12.1.78.3 Test Method

a. Each battery is discharged, using a test load at the

design duty cycle discharge rate.

b. Each battery is fully discharged to determine its

capacity factor.

c. Each battery charger will charge its respective battery

to normal conditions, after the battery has undergone a

design duty cycle, while simultaneously supplying power

at a rate equivalent to the design emergency loading.

14.2-107 Rev. 0 WOLF CREEK 14.2.12.1.78.4 Acceptance Criteria

a. Each battery is capable of maintaining output voltage

above the design minimum, during a design duty cycle.

b. Each battery has a capacity factor greater than or equal

to design.

c. The battery chargers are able to recharge the batteries

to normal conditions, after the battery has undergone a

design duty cycle, while simultaneously supplying power

at a rate equivalent to the design emergency loading.

14.2.12.1.79 Instrument AC System (Class IE) Preoperational Test

(S-03NN01) 14.2.12.1.79.1 Objectives

To demonstrate that the 120-V Class IE ac distribution panel- boards can be fed

from their normal source inverters and from their backup source transformers by

manual transfer. The operability of system instrumentation and controls,

including breaker protective interlocks, is also verified.

14.2.12.1.79.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2.12.1.79.3 Test Method

a. The 120-V Class IE ac distribution panelboards are

energized from their normal source inverters, and

panelboard voltages are recorded.

b. The 120-V Class IE ac distribution panelboards are

energized from their backup source transformers by

manual transfer, and panelboard voltages are recorded.

c. The system breakers are operated, and breaker interlocks

are verified.

14.2.12.1.79.4 Acceptance Criteria

a. Each 120-V Class IE ac distribution panelboard voltage,

when supplied from the normal source inverters of the

panelboards, is within design specifications.

14.2-108 Rev. 0 WOLF CREEK

b. Each 120-V Class IE ac distribution panelboard voltage, when supplied from the backup source transformers, is

within design specifications.

c. System breaker interlocks operate in accordance with system design.

14.2.12.1.80 Engineered Safeguards (NSSS) Preoperational Test

(SU3-SA01)

14.2.12.1.80.1 Objectives

a. To demonstrate the ability of the NSSS to initiate

safety injection, containment isolation, containment

spray actuation, main feedwater isolation, and steam line isolation signals on receipt of the associated input signals.

b. To verify NSSS ESFAS loop response times.
c. To demonstrate the ability of each solid-state

protection system test panel to adequately test the

associated NSSS ESFAS and reactor protection logic

trains.

d. To demonstrate the coincidence and redundancy of the

NSSS ESFAS.

e. To verify the operability of ESFAS block and permissive

interlocks.

14.2.12.1.80.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies are operational.

14.2.12.1.80.3 Test Method

a. The ability of the NSSS ESFAS to actuate safety

injection, containment isolation, containment spray

actuation, main feedwater isolation, and steam line

isolation signals on receipt of the required coincidence

of the following input signals for each redundant

channel is verified:

. High steam line pressure rate

. Low steam line pressure

. Low pressurizer pressure

14.2-109 Rev. 0 WOLF CREEK

. High containment pressure (Hi-1, Hi-2, and Hi-3)

. High-high steam generator level

. Low Tavg

. Low-low steam generator water level

b. Input signals are initiated, and loop response times are

verified.

c. The ability of each solid-state protection system test

panel to test the NSSS ESFAS logic trains is verified.

d. ESFAS block and permissive interlocks are verified.

14.2.12.1.80.4 Acceptance Criteria

a. The NSSS ESFAS actuates safety injection, containment isolation, containment spray actuation, main feedwater

isolation, and steam line isolation signals when their

associated input signals are received from the following

signals for each applicable channel:

. High steam line pressure rate

. Low steam line pressure

. Low pressurizer pressure

. High containment pressure (Hi-1, Hi-2, and Hi-3)

. High-high steam generator level

. Low Tavg

. Low-low steam generator water level

b. NSSS ESFAS loop response times are within design specifications.
c. ESFAS block and permissive interlocks operate in

accordance with system design.

14.2.12.1.81 Engineered Safeguards (BOP) Preoperational Test

(SU3-SA02)

14.2.12.1.81.1 Objectives

a. To demonstrate the operability of the BOP ESFAS to

initiate containment purge isolation, control room

ventilation isolation, fuel building ventilation

isolation, auxiliary feedwater pump actuation, auxiliary

feedwater suction valve switchover to essential service

water (ESW), and steam generator blowdown and sample

isolation signals on receipt of the associated input

signals.

14.2-110 Rev. 0 WOLF CREEK

b. To verify BOP ESFAS loop response times.
c. To demonstrate the ability of the BOP ESFAS test panel

to adequately test the associated BOP ESFAS logic

trains.

d. To demonstrate the coincidence and redundancy of the BOP

ESFAS.

14.2.12.1.81.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies are operational.

14.2.12.1.81.3 Test Method

a. The ability of the BOP ESFAS to actuate containment

purge isolation, control room ventilation isolation,

fuel building ventilation isolation, auxiliary feedwater

pump actuation, auxiliary feedwater suction valve

switchover to ESW, and steam generator blowdown and

sample isolation signals on receipt of the required

coincidence of the following input signals for each

redundant channel is verified.

o Containment isolation (phase A)

o High atmospheric radiation

o High chlorine concentration o Loss of main feedwater flow o Low-low steam generator level

o Loss of offsite power

o Low feedwater pump suction pressure

o Safety injection

b. Input signals are initiated, and loop response times are

verified.

c. The ability of the BOP ESFAS test panel to test the BOP

ESFAS logic trains is verified.

14.2.12.1.81.4 Acceptance Criteria

a. The BOP ESFAS actuates containment purge isolation,

control room ventilation isolation, fuel building

ventilation isolation, auxiliary feedwater pump

actuation, auxiliary feedwater suction valve switchover

to ESW, and

14.2-111 Rev. 0 WOLF CREEK steam generator blowdown and sample isolation signals

when their associated input signals are received from

the following signals for each applicable channel:

o Containment isolation (phase A)

o High atmospheric radiation

o High chlorine concentration

o Loss of main feedwater flow

o Low-low steam generator level

o Loss of offsite power

o Low feedwater pump suction pressure

o Safety injection

b. BOP ESFAS loop response times are within design specifications.

14.2.12.1.82 Engineered Safeguards Verification Test (SU3-SA03)

14.2.12.1.82.1 Objectives

To demonstrate the proper response of actuated components resulting from the

following safety signals: Safety injection, containment spray actuation, main

feedwater isolation, steam line isolation, containment isolation, containment

purge isolation, control room ventilation isolation, fuel building ventilation

isolation, auxiliary feedwater pump actuation, auxiliary feedwater suction

valve switch over to ESW, and steam generator blowdown and sample isolation.

14.2.12.1.82.2 Prerequisites

a. Required component testing and instrument calibration are complete.
b. Required electrical power sources and control circuits

are operational.

c. Components actuated by the NSSS and BOP ESFAS are

available.

14.2.12.1.82.3 Test Method

NSSS and BOP ESFAS signals are initiated manually and the proper response and

response times of the actuated components are verified.

14.2-112 Rev. 0 WOLF CREEK 14.2.12.1.82.4 Acceptance Criteria

Components required to actuate on receipt of safety signals respond properly in

accordance with design specifications and within the times specified by design

requirements.

14.2.12.1.83 Reactor Protection System Logic Test (S-03SB01)

14.2.12.1.83.1 Objectives

a. To demonstrate the ability of the reactor protection

system to initiate a reactor trip on input of the

associated input signals.

b. To verify reactor protection loop response times.
c. To verify the operability of the reactor protection

system block and permissive interlocks.

d. To demonstrate the coincidence, redundancy, and fail

safe (power loss) design of the reactor protection

system.

14.2.12.1.83.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2.12.1.83.3 Test Method

a. The ability of the reactor protection system to initiate

a reactor trip on receipt of the proper coincidence of

the following trip signals for each redundant channel is

verified:

o Source range high neutron flux

o Intermediate range high neutron flux

o Power range high neutron flux (low setpoint and

high setpoint)

o Power range high positive neutron flux rate

o Power range high negative neutron flux rate o Overtemperature T o Overpower T o Low primary coolant flow o Reactor coolant pump bus undervoltage

o Reactor coolant pump bus underfrequency

14.2-113 Rev. 0 WOLF CREEK o High pressurizer pressure o Low pressurizer pressure

o High pressurizer level

o Safety injection signal

o Turbine trip signal

b. Loop response times are measured for the above listed

trip signals.

c. Reactor protection system block and permissive

interlocks are verified.

d. Power is isolated from the system, and the safe failure

of the system is verified.

14.2.12.1.83.4 Acceptance Criteria

a. The reactor protection system initiates a reactor trip

on receipt of the proper coincidence of the following

signals for each applicable channel:

o Source range high neutron flux

o Intermediate range high neutron flux

o Power range high neutron flux (low setpoint and

high setpoint)

o Power range high positive neutron flux rate

o Power range high negative neutron flux rate o Overtemperature T o Overpower T o Low primary coolant flow o Reactor coolant pump bus undervoltage o Reactor coolant pump bus underfrequency

o High pressurizer pressure

o Low pressurizer pressure

o High pressurizer level

o Safety injection signal

o Turbine trip signal

b. Loop response times for the following trip signals are

within design limits.

o Power range high neutron flux (low setpoint and

high setpoint)

o Power range high negative neutron flux rate o Overtemperature T o Overpower T o Low primary coolant flow o Reactor coolant pump bus undervoltage

o Reactor coolant pump bus underfrequency

14.2-114 Rev. 0 WOLF CREEK o High pressurizer pressure o Low pressurizer pressure

c. Reactor protection system block and permissive

interlocks operate in accordance with system design.

d. The reactor protection system functions in accordance

with system design on a loss of power.

14.2.12.1.84 Primary Sampling System Preoperational Test

(S-03SJ01)

14.2.12.1.84.1 Objectives

a. To set sample panels' flow rates and to verify the operability of the sample system containment isolation valves. Proper operation of system instrumentation and

controls is also verified.

b. To verify that the post-accident sampling system (PASS)

containment isolation valves operate properly.

14.2.12.1.84.2 Prerequisites

a. Required component testing instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operable.

c. Plant conditions are established, and systems are available, as necessary, to facilitate drawing samples

from the sample points.

d. The component cooling water system is available to

provide cooling water to the auxiliary building sample

station.

e. The chemical and volume control system is available to

receive discharge from the nuclear sampling station.

f. The chemical and detergent waste system is available to

receive discharge from the nuclear sampling station.

14.2.12.1.84.3 Test Method

a. Sample panel flows are adjusted, and flow data are

recorded.

14.2-115 Rev. 0 WOLF CREEK

b. Operability of the sample containment isolation valves is verified, including their response to an isolation

signal. Valve operating times are recorded.

14.2.12.1.84.4 Acceptance Criteria

a. The sample containment isolation valves close on receipt

of an isolation signal.

b. The sample containment isolation valves' closure times

are within design specifications.

14.2.12.1.85 Process Radiation Monitoring System Preoperational

Test (S-03SP01)

14.2.12.1.85.1 Objectives

To demonstrate the operation of the process radiation monitors and to verify

the ability of the process radiation monitoring system to provide alarm and

isolation signals, as applicable, upon receipt of high radiation signals.

Operability of the radioactivity monitoring control room microprocessor is also

verified.

14.2.12.1.85.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operable.

14.2.12.1.85.3 Test Method

a. The check source for each monitor is remotely

positioned, and the actuation of each monitor and the

operability of its associated alarms and isolation

signals are verified.

b. Operability of the radioactivity monitoring control room

microprocessor is verified.

14.2.12.1.85.4 Acceptance Criteria

The process radiation monitoring system provides alarm and isolation signals,

in accordance with system design specifications.

14.2-116 Rev. 0 WOLF CREEK 14.2.12.1.86 Power Conversion and ECCS Thermal Expansion Test (SU3-0004)

14.2.12.1.86.1 Objective

To demonstrate snubber operability on all safety-related systems whose

operating temperature exceeds 250 F.

14.2.12.1.86.2 Prerequisites

a. Preservice examinations as specified in the Tedesco

letter to KG&E dated 2/10/81 have been completed on the

systems being checked within the last 6 months.

b. Other required component testing and instrument calibration are completed.
c. Required electrical power supplies and control circuits

are operational.

d. Preoperational testing is in progress.

14.2.12.1.86.3 Test Method

a. During initial system heatup and cooldown, at specified

temperature intervals, verify the expected snubber

movement for any system which attains operating

temperature.

b. For those systems which do not attain operating temperature, verify by observation and/or calculation that the snubber will accommodate the projected thermal

movement.

c. Observe snubber swing clearances at specified heat-up

and cooldown intervals.

14.2.12.1.86.4 Acceptance Criteria

a. The expected snubber movement for any system that

attains operating temperature is within design

specifications.

b. The expected snubber movement determined by observation

and/or calculation for any system that does not attain

operating temperature is within design specifications.

c. Snubber swing clearance observed at specified heatup and

cooldown intervals is within design specifications.

14.2-117 Rev. 0 WOLF CREEK 14.2.12.1.87 Power Conversion and ECCS Systems Dynamic Test (S-030005)

14.2.12.1.87.1 Objectives

To demonstrate during specified transients that the systems' monitored points

respond in accordance with design.

14.2.12.1.87.2 Prerequisites

a. Reference points for measurement of the systems are

established.

b. Hot functional testing is in progress.
c. All subject systems are available for the specified dynamic operations.
d. Required instrument calibration is complete.

14.2.12.1.87.3 Test Method

a. The systems are aligned for the specified dynamic

operation.

b. The specified dynamic event of pump operation, valve

operation, etc., is initiated, and the system is

monitored for response.

14.2.12.1.87.4 Acceptance Criteria

a. The total stress shall not exceed applicable code

limits.

14.2.12.1.88 HEPA Filter Test (SU3-0006).

14.2.12.1.88.1 Objectives

To demonstrate the leaktightness and particulate removal efficiency of all HEPA

filters and to verify the leaktightness of their associated charcoal adsorbers.

14.2.12.1.88.2 Prerequisites

a. The ventilation systems containing HEPA filters and

charcoal adsorbers have been air balanced and are

operational and available to support this test.

14.2-118 Rev. 0 WOLF CREEK

b. Required electrical power supplies and control circuits are operational.
c. Required instrument calibration is complete.

14.2.12.1.88.3 Test Method

a. HEPA filters are inplace tested with cold poly-dispersed

DOP, in accordance with the procedures set forth in ANSI

N510.

b. Charcoal adsorbers are inplace tested with a suitable

refrigerant, in accordance with the procedures set forth

in ANSI N510.

14.2.12.1.88.4 Acceptance Criteria

a. The airflow of each filter adsorber unit is equal to the

design flow.

b. Air flow distribution downstream of each HEPA filter is

within 20 percent of the average velocity through the

unit.

c. HEPA DOP penetration is less than one percent at the

design air flow.

d. Charcoal adsorber bypass leakage is less than .05

percent at the design air flow.

14.2.12.1.89 Cooldown from Hot Standby External to the Control Room (S-030008)

14.2.12.1.89.1 Objectives

To demonstrate, using a plant procedure, the potential capability to cooldown

the plant from the hot standby to the cold shutdown condition, using

instrumentation and controls external to the control room verifying that:

a. The reactor coolant temperature and pressure can be

lowered to permit the operation of the residual heat

removal (RHR) system.

b. The RHR system can be operated and controlled.
c. The reactor coolant temperature can be reduced 50 F, using the RHR system, without exceeding technical specification limits.

14.2-119 Rev. 0 WOLF CREEK 14.2.12.1.89.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The plant is in a hot standby condition.
d. The authority and responsibility of the control room

observers has been established and is specified in this

procedure.

14.2.12.1.89.3 Test Method

a. The plant is cooled from hot standby, RHR is initiated,

and a >

50°F cooldown is performed with the RHR system transferring heat to the ultimate heat sink, using instrumentation and controls external to the control room.

b. All actions performed by the control room observers are documented within this procedure for use in evaluating

their impact on the test results.

14.2.12.1.89.4 Acceptance Criteria

The following actions are capable of being performed, external to the control

room:

a. The reactor coolant temperature and pressure can be

lowered to permit the operation of the RHR system.

b. The reactor coolant temperature can be reduced 50 F, using the RHR system, without exceeding technical specification limits.

14.2.12.1.90 Compressed Gas Accumulator Testing (S-030009)

14.2.12.1.90.1 Objectives

To demonstrate the ability of the auxiliary feedwater control valve/mainsteam

atmospheric relief valve and main feedwater control valve accumulators to

provide the design backup supply of compressed gas for continued design valve

operation following a loss of the normal motive source.

14.2-120 Rev. 0 WOLF CREEK 14.2.12.1.90.2 Prerequisites

Required component testing, instrument calibration and system flushing/cleaning

are complete.

14.2.12.1.90.3 Test Method

The accumulators are isolated from the compressed gas supply header and the

associated valves are operated to demonstrate the ability of the accumulators

to provide design motive force for the required valve cycles.

14.2.12.1.90.4 Acceptance Criteria

The auxiliary feedwater control valve/mainsteam atmospheric relief valve, and

main feedwater control valve accumulators provide the design backup supply of compressed gas to their associated valves.

14.2.12.2 Nonsafety-Related Preoperational Test Procedures The following sections are the test abstract for each nonsafety- related

preoperational test. Table 14.2-2 provides an index of these tests.

14.2.12.2.1 Turbine Trip Test (S-04AC02)

14.2.12.2.1.1 Objectives

a. To demonstrate the ability of the turbine trip and

monitoring system to initiate a turbine trip on input of

the associated input signals.

b. To demonstrate the response of the moisture separator

reheater drain valves, feedwater heater extraction check valves, turbine main stop valves, turbine main stop valve above seat drain valves, turbine control valves,

turbine control valve above seat drain valves,

intermediate stop valves, main steamline drain valves,

startup drain valves, and intercept valves to a turbine

trip signal.

c. To demonstrate that a turbine trip signal initiates a

reactor trip signal.

d. To demonstrate that the turbine main stop valves

operating times are within design specifications.

14.2-121 Rev. 0

WOLF CREEK 14.2.12.2.1.2 Prerequisites

a. Required component testing and instrument calibration is

complete.

b. Required electrical power supplies and control circuits

are operational.

c. The main turbine control oil and lube oil systems are

available to provide oil to the turbine auxiliaries.

d. The compressed air system is available to provide air to

system air-operated valves.

14.2.12.2.1.3 Test Method

a. The ability of the turbine trip and monitoring system to

initiate a turbine trip signal on receipt of each of the

following input signals is verified:

o Manual trip pushbutton depressed

o Manual trip handle pulled

o Generator trip (EHC vital trip)

o Generator trip (unit trip)

o Reactor trip

o Loss of stator coolant

o Low lube oil pressure

o Loss of EHC 125 V dc power with turbine speed

below 75 percent

o High turbine vibration o High exhaust hood temperature o Low hydraulic fluid pressure

o Moisture separator high level

o Low bearing oil pressure

o Low condenser vacuum

o Excessive thrust bearing wear

o Backup overspeed (Electrical)

o Loss of EHC 24-volt dc power

b. A turbine trip signal is initiated, and the response of

the following valves is verified:

o Moisture separator reheater drain valves

o Feedwater heater extraction check valves

o Turbine main stop valves

o Turbine control valves

o Intermediate stop valves

o Turbine intercept valves

o Startup drain valves

o Main steam line drain valves

14.2-122 Rev. 0 WOLF CREEK o Turbine main stop valve above seat drain valves o Turbine control valve above seat drain valves

c. A turbine trip signal is initiated, and a reactor trip

input signal is verified.

14.2.12.2.1.4 Acceptance Criteria

a. The turbine trip and monitoring system initiates a

turbine trip on receipt of each of the following

signals:

o Manual trip pushbutton depressed

o Manual trip handle pulled

o Generator trip (EHC vital trip) o Generator trip (unit trip) o Reactor trip

o Loss of stator coolant

o Low lube oil pressure

o Loss of EHC 125 V dc power with turbine speed

below 75 percent

o High turbine vibration

o High exhaust hood temperature

o Low hydraulic fluid pressure

o Moisture separator high level

o Low bearing oil pressure

o Low condenser vacuum

o Excessive thrust bearing wear

o Backup overspeed (electrical)

o Loss of EHC 24-volt dc power

b. The following valves open on receipt of a turbine trip

signal:

o Turbine main stop valve above seat drain valves

o Turbine control valve above seat drain valves

o Main steam line drain valves

o Moisture separator reheater drain valves

o Startup drain valves

c. The following valves close on receipt of a turbine trip

signal:

o Low pressure heater extraction check valves

o Main stop valves

o Turbine control valves

o Intercept valves

o Intermediate stop valves

14.2-123 Rev. 0 WOLF CREEK

d. A turbine trip signal initiates a reactor trip signal.
e. The turbine main stop valves operating times are within

design specifications.

14.2.12.2.2 Turbine System Cold Test (S-04AC03)

14.2.12.2.2.1 Objectives

a. To demonstrate the operability of the turning gear and

associated control circuits.

b. To demonstrate the operability of the electro-hydraulic

control system.

14.2.12.2.2.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The main turbine control oil and lube oil systems are

available to supply the turbine auxiliaries.

14.2.12.2.2.3 Test Method

a. The operability of the turning gear and associated

control circuits is verified.

b. A turbine simulator is utilized to verify the ability of

the electro-hydraulic control system to perform its

control functions.

14.2.12.2.2.4 Acceptance Criteria

a. The turning gear motor trips on loss of bearing oil

pressure, loss of all bearing lift pumps, or closure of

the main transformer switchyard breaker.

b. The turbine control and intercept valves close on a

power load unbalance signal.

c. The turbine load set is run back on a reactor overtemperature T signal when in the manual mode.
d. The turbine load set is run back on a reactor overpower T signal when in the manual mode.

14.2-124 Rev. 0 WOLF CREEK

e. The turbine load is set back on a loss of circulating water pump signal.
f. Turbine loading is inhibited on a C-16 control interlock

signal.

14.2.12.2.3 Condensate System Preoperational Test (S-04ADOl)

14.2.12.2.3.1 Objectives

To demonstrate the condensate pumps' operating characteristics and verify the

operation of system valves and associated control circuits. The operability of

the condensate storage and transfer system and associated components is also

verified.

14.2.12.2.3.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The feedwater system is available to receive flow from

the condensate pump discharge header.

d. The demineralized water system is available to provide

water to the condensate pump seals and a source of

makeup to the condensate storage tank.

e. The condensate storage tank is available to provide makeup to the condenser hotwell.
f. The closed cooling water system is available to provide

cooling water to the condensate pump motor bearing oil

coolers.

14.2.12.2.3.3 Test Method

a. Condensate pumps are operated, and performance

characteristics are verified.

b. The response of each condensate pump to a condenser low-

low level trip signal is verified.

c. The operability of the condensate pump recirculation

valves is verified.

14.2-125 Rev. 0 WOLF CREEK 14.2.12.2.3.4 Acceptance Criteria

a. The operating characteristics of the condensate pumps

are within design specifications.

b. Each condensate pump will receive a trip signal on a 2/3

condenser low-low level signal.

c. Each condensate pump recirculation valve operates in

accordance with design specifications.

14.2.12.2.4 Secondary Vent and Drain System Preoperational

Test (S-04AF01)

14.2.12.2.4.1 Objectives

a. To demonstrate the operating characteristics of the

heater drain pumps.

b. To demonstrate the operability of system valve and pump

control circuits.

14.2.12.2.4.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The compressed air system is available to the system air-operated valves.
d. The closed cooling water system is available to supply

cooling water to the heater drain pumps.

14.2.12.2.4.3 Test Method

a. The heater drain pumps are operated, and performance

characteristics are verified.

b. The operability of system valve and pump control

circuits is verified.

14.2.12.2.4.4 Acceptance Criteria

The operating characteristics of the heater drain pumps are within design

specifications.

14.2-126 Rev. 0 WOLF CREEK 14.2.12.2.5 Condensate and Feedwater Chemical Feed System Preoperational Test (S-04AQ01)

14.2.12.2.5.1 Objectives

a. To demonstrate the operating characteristics of the

condensate oxygen control chemical addition pumps, condensate pH control chemical addition pumps, condensate oxygen control chemical circulating pumps, condensate pH control chemical circulating pumps, feedwater chemical addition pumps, and feedwater chemical addition circulating pump and verify the operation of the associated control circuits.

b. To demonstrate the operability of the drum dispensing

pumps.

14.2.12.2.5.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The demineralized water storage and transfer system is

available to provide a source of demineralized water to the oxygen and pH control chemical supply and mixing tanks.

d. The compressed air system is available to provide air to

the drum dispensing pumps.

e. The service gas system is available to provide a source

of nitrogen to the oxygen and pH control chemical supply, measuring, and mixing tanks.

14.2.12.2.5.3 Test Method

a. System pumps are operated, and performance characteristics are verified.
b. The response of the condensate oxygen control chemical circulating pumps, condensate pH control chemical circulating pumps, and the feedwater chemical addition feed pumps to a low level in their associated tank is verified.

14.2-127 Rev. 12 WOLF CREEK 14.2.12.2.5.4 Acceptance Criteria

a. The operating characteristics of the condensate

oxygen control chemical addition pumps, condensate pH control chemical addition pumps, condensate oxygen control chemical circulating pumps, condensate ph control chemical circulating pumps, feedwater chemical addition pumps, feedwater chemical addition circulating pump, and the drum dispensing pumps are within design specifications.

b. The condensate oxygen control chemical circulating pumps, condensate pH control chemical circulating pumps, feedwater

chemical addition feed pumps, and the feedwater chemical addition circulating pump trip on a low level signal from their associated tanks.

14.2.12.2.6 Reactor Makeup Water System Preoperational Test

(S-04BL01)

14.2.12.2.6.1 Objectives

a. To demonstrate the operating characteristics of the

reactor makeup water transfer pumps and verify that the

associated control circuits are functioning properly.

b. To demonstrate the operation of the system automatic

valves, including the response of the reactor makeup

water system containment supply valve to a CIS.

14.2.12.2.6.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The demineralized water storage and transfer system is

available to provide a source of water to the reactor

makeup water storage tank.

14.2.12.2.6.3 Test Method

a. The reactor makeup water transfer pumps are operated, and pump operating data are recorded.
b. Reactor makeup water transfer pumps and system automatic

valves control logics are verified, including their

response to safety signals.

14.2-128 Rev. 12 WOLF CREEK

c. The reactor makeup water containment supply valve is operated under flow conditions and operating times

recorded.

14.2.12.2.6.4 Acceptance Criteria

a. The operating characteristics of the reactor makeup

water transfer pumps are within design specifications.

b. Each reactor makeup water transfer pump trips on receipt

of a reactor makeup water storage tank low level signal.

c. Each reactor makeup water transfer pump starts, after a

time delay, with the other pump running and the receipt

of a low header pressure signal.

d. The reactor makeup water containment supply valve

closure time is within design specifications.

e. The reactor makeup containment supply valve closes on

receipt of a CIS.

14.2.12.2.7 Condenser Air Removal System Preoperational Test

(S-04CG01)

14.2.12.2.7.1 Objectives

a. To demonstrate the operation of the condenser air

removal portion of the turbine building HVAC system

motoroperated dampers, including automatic operation on a safety injection signal.

b. To demonstrate the capacities of the condenser air

removal filtration fans and verify the operation of

their associated control circuits.

c. To demonstrate the operability of the condenser air

removal system vacuum pumps, control valves, and their

associated control circuits.

14.2.12.2.7.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2-129 Rev. 0 WOLF CREEK

c. The condenser air removal filtration system portion of the turbine building HVAC system is available to support

this test.

d. The condensate storage tank is available to provide a source of water to the vacuum pump seal water

reservoirs.

e. The service water system is available to provide cooling

water to the mechanical vacuum pump seal water coolers.

14.2.12.2.7.3 Test Method

a. The condenser air removal filtration fans are operated,

and fan capacities are verified.

b. Operation of the condenser air removal filtration

dampers is verified, including their response to a

safety injection signal.

c. The ability of the mechanical vacuum pumps to reduce

condenser pressure during startup operation is verified.

d. Operability of the mechanical vacuum pumps and their

associated control valves' control circuits is verified,

including their response to a low condenser vacuum

signal.

14.2.12.2.7.4 Acceptance Criteria

a. The condenser air removal filtration fans' capacities are within design specifications.
b. The condenser air removal filtration dampers close on

receipt of a safety injection signal.

c. The rate at which the mechanical vacuum pumps reduce

condenser pressure is within design specifications.

d. The mechanical vacuum pumps start automatically on

receipt of a low condenser vacuum signal.

14.2.12.2.8 Circulating Water System Preoperational Test (SU4-

DA01)

14.2.12.2.8.1 Objective

a. To demonstrate the operating characteristics of the

circulating water pumps, water box venting pumps, and

14.2-130 Rev. 0 WOLF CREEK the condenser drain pump and verify the operation of their associated control circuits.

b. To demonstrate by operational test that the circulating

water pump discharge valves operating times are within design specifications.

c. To demonstrate that the gland water system flow to the

circulating water pumps is within design specifications.

14.2.12.2.8.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are completed.

b. Required electrical power supplies and control circuits are operational.
c. The circulatng water system and condenser are available

to receive flow from the circulating water pumps.

14.2.12.2.8.3 Test Method

a. The circulating water pumps, water box venting pumps,

and the condenser drain pump are operated and pump

operating data is recorded.

b. The response of the circulating water pumps and the

condenser drain pump to control signals is verified.

c. Circulating water pump discharge valve operating times are recorded.

14.2.12.2.8.4 Acceptance Criteria

a. The circulating water pumps operating characteristics

are within design specifications.

b. The water box venting pumps operating characteristics

are within design specifications.

c. The condenser drain pump operating characteristics are

within design specifications

d. The condenser drain pump stops on receipt of a standpipe

low-level signal.

e. Each circulating water pump trips on receipt of a two

out of three condenser pit high level signal.

14.2-131 Rev. 0 WOLF CREEK

f. Low gland seal water pressure or low gland seal flow will prevent start of the circulating water pumps.
g. The gland seal water flow to each circulating water pump

is within design specifications.

h. The operating times of the circulating water pump

discharge valves are within design specifications.

14.2.12.2.9 Service Water System Preoperational Test (S-04EA01).

14.2.12.2.9.1 Objectives

a. To demonstrate the capability of the service water

system and essential service water system to provide rated cooling water flow during the normal and normal-shutdown modes of operation to their respective loads.

b. To demonstrate the operating characteristics of the

Service Water (SW) Pumps.

c. To verify proper operation of site service water system

controls and instrumentation.

14.2.12.2.9.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits are operational.
c. The essential service water system has been flow

balanced in the LOCA mode.

d. Site system controls and instruments are calibrated.
e. The SW system is available to receive flow from the SW

pumps.

14.2.12.2.9.3 Test Method

a. Service water and essential service water system flows

are verified in the normal and normal-shutdown modes.

(The service water pumps provide the motive force.)

b. The SW pumps are operated and pump operating data is

recorded.

14.2-132 Rev. 0 WOLF CREEK 14.2.12.2.9.4 Acceptance Criteria

a. Components supplied by the service water system and

essential service water system receive flows that are

within design specifications with the system operating in the normal and normal-shutdown modes.

b. The SW pumps operating characteristics are within design

specifications.

14.2.12.2.10 Closed Cooling Water System Preoperational Test

(S-04EB01)

14.2.12.2.10.1 Objectives

a. To demonstrate the capability of the closed cooling water system to provide cooling water flow to its

associated components.

b. To demonstrate the operating characteristics of the

closed cooling water pumps and to verify that the

associated instrumentation and controls are functioning

properly.

14.2.12.2.10.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

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

14.2.12.2.10.3 Test Method

Performance characteristics of the closed cooling water pumps and flow data to

supplied components are verified.

14.2.12.2.10.4 Acceptance Criteria

a. The performance characteristics of each closed cooling

water pump are within design specifications.

b. Flow to all components supplied by the closed cooling

water system is verified.

14.2-133 Rev. 0 WOLF CREEK 14.2.12.2.11 Fire Protection System Preoperational Test (SU4-FP03)

14.2.12.2.11.1 Objectives

a. To demonstrate the operating characteristics of the Fire

Protection (FP) system jockey pump, motor-driven fire

pump and the diesel-driven fire pump and verify the

operation of their associated control circuits.

b. To demonstrate the operability of the diesel oil system,

including system instrumentation and controls.

14.2.12.2.11.2 Prerequisites

a. Required component testing, instrument calibration, and system flushing/cleaning are completed.
b. Required electrical power supplies and control circuits

are operational.

14.2.12.2.11.3 Test Method

a. The jockey pump, the motor-driven fire pump and the

diesel-driven fire pump are operated and operating data

are recorded.

b. The response of the motor-driven fire pump and diesel-

driven fire pump to automatic start signals are

verified.

c. With the diesel-driven fire pump operating at rated

capacity, the capacity of the diesel oil day tank is

verified.

14.2.12.2.11.4 Acceptance Criteria

a. The FP pumps operating characteristics are within design

specifications.

b. The motor-driven fire pump and the diesel-driven fire

pump automatically start upon receipt of their

associated decreasing fire protection system pressure

signal.

c. With the diesel fire pump operating at rated capacity,

the capacity of the diesel oil day tank is within design

specifications.

14.2-134 Rev. 0 WOLF CREEK

d. With the diesel fire pump operating at rated capacity and upon receipt of a diesel oil day tank low level

alarm, the remaining capacity of the diesel oil day tank

is within design specifications.

14.2.12.2.12 Radwaste Building HVAC System Preoperational Test

(S-04GH01)

14.2.12.2.12.1 Objectives

a. To verify the radwaste building supply and exhaust fans'

control circuits, including automatic transfer between

exhaust fans.

b. To demonstrate the fan capacities of the radwaste building supply and exhaust fans, recycle evaporator room fan coil unit, waste evaporator room fan coil unit,

control room (solidification) fan coil unit, sample

laboratory fan coil unit, ground floor fan coil unit,

basement floor fan coil unit, SLWS evaporator fan coil

unit, and control room fan coil unit, and to verify that

the associated instrumentation and controls function

properly.

14.2.12.2.12.2 Prerequisites

a. Required component testing, instrument calibration, and

system air balancing are complete.

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

14.2.12.2.12.3 Test Method

a. The radwaste building system fans are operated, and fan

capacities are verified.

b. Operability of the radwaste building supply and exhaust

fans' control circuits is verified.

14.2.12.2.12.4 Acceptance Criteria

a. The radwaste building system fan capacities are within

design specifications.

b. The radwaste building supply air unit will not operate

unless either radwaste exhaust fan is operating.

14.2-135 Rev. 0 WOLF CREEK

c. A low flow on the operating radwaste building exhaust fan will cause the operating fan to stop and the standby

fan to start.

14.2.12.2.13 Local Containment Leak Rate Test (SU8-GP01)

14.2.12.2.13.1 Objectives

To determine the leakage rate of the containment penetrations and the leakage

rate of the containment isolation valves.

14.2.12.2.13.2 Prerequisites

a. All containment isolation valves are closed by normal

actuation methods.

b. Associated piping is drained, and vent paths for leakage

are established.

c. Required instrument calibration is complete.

14.2.12.2.13.3 Test Method

The containment penetrations and containment isolation valves are leak tested

by performing type B and type C tests, in accordance with 10 CFR 50, Appendix

J.

14.2.12.2.13.4 Acceptance Criteria

The combined leakage from containment penetrations and containment isolation valves is within design limits.

14.2.12.2.14 Liquid Radwaste System Preoperational Test (S-

04HB01).

14.2.12.2.14.1 Objectives

a. To demonstrate the operating characteristics of the

liquid radwaste system pumps and to verify the operation

of their associated control circuits.

b. To demonstrate the operation of the liquid radwaste

system containment isolation valves, including their

response to a CIS.

c. To determine by operational test that the liquid

radwaste system containment isolation valves' closure

times are within design specifications.

14.2-136 Rev. 0 WOLF CREEK 14.2.12.2.14.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The component cooling water system is available to

provide cooling water to the reactor coolant drain tank

heat exchanger.

14.2.12.2.14.3 Test Method

a. The liquid radwaste system pumps are operated, and performance characteristics are recorded.
b. The operability of the system pump and valve control

circuits is verified.

c. The liquid radwaste system containment isolation valves

are operated under flow conditions, and operating times

are recorded.

14.2.12.2.14.4 Acceptance Criteria

a. The performance characteristics of the liquid radwaste

system pumps are within design specifications.

b. Each pump trips on receipt of a low-level signal from its respective tank.
c. The liquid radwaste system containment isolation valves

close on receipt of a CIS.

d. The liquid radwaste system containment isolation valves'

closure times are within design specifications.

e. The liquid radwaste effluent discharge valve closes on a

high process radiation signal.

14.2.12.2.15 Waste Evaporator Preoperational Test (SU4-HB02)

14.2.12.2.15.1 Objectives

To demonstrate the operability of the waste evaporator and its associated

pumps, valves, and control circuits.

14.2-137 Rev. 0 WOLF CREEK 14.2.12.2.15.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. Cooling water is available to the waste evaporator.
d. The auxiliary steam system is available to supply steam

to the waste evaporator.

e. The waste evaporator condensate tank and the primary

evaporator bottoms tank are available to receive waste evaporator effluent.

14.2.12.2.15.3 Test Method

a. The waste evaporator is operated, and performance data

is recorded.

b. With the waste evaporator in operation, a low feed inlet

pressure signal is initiated, and the evaporator is

verified to shift to the recycle mode.

c. The waste evaporator distillate pump is verified to trip

on a low evaporator condenser level.

14.2.12.2.15.4 Acceptance Criteria

a. The waste evaporator process flow is within design

specifications.

b. The waste evaporator goes into the recycle mode on low

feed inlet pressure.

c. The waste evaporator distillate pump trips on a low

evaporator condenser level.

14.2.12.2.16 Solid Waste System Preoperational Test (S-04HC01)

14.2.12.2.16.1 Objectives

a. To demonstrate the operating characteristics of the

solid waste system pumps and to verify the operation of

their associated control circuits.

14.2-138 Rev. 0 WOLF CREEK

b. To demonstrate the ability of the decant station, drumming station, cement filling station, and the

solid radwaste bridge crane to process, solidify, and

handle waste and to verify the operation of their

associated control circuits.

c. To demonstrate the ability of the dry waste compactors

to process compressible wastes and to verify the

operation of their associated control circuits.

14.2.12.2.16.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits are operable.
c. Reactor makeup water is available to provide a source of

water to the decanting station.

14.2.12.2.16.3 Test Method

a. The solid waste system pumps are operated, and the pump

operating data are recorded.

b. The system component control circuits are verified, and

the ability of the solid radwaste system to process,

solidify, and handle waste is verified.

14.2.12.2.16.4. Acceptance Criteria

a. The operating characteristics of the evaporator bottoms

tank pumps (primary and secondary) are within design

specifications.

b. There are no free liquids present in the packaged waste.
c. The evaporator bottoms tank pumps (primary and

secondary) trip on their respective tank low level

signal.

14.2.12.2.17 Solid Waste Filter Handling System Preoperational

Test (S-04HC02)

14.2.12.2.17.1 Objectives

To demonstrate the ability of the solid radwaste filter handling system to

remove, transfer, and install a spent resin sluice filter assembly.

14.2-139 Rev. 0 WOLF CREEK 14.2.12.2.17.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2.12.2.17.3 Test Method

a. Operability of the solid radwaste monorail hoist and

handling cask winch and associated control circuits is

verified.

b. The ability of the solid radwaste filter handling system to remove, transfer, and install a spent resin sluice filter assembly is verified.

14.2.12.2.17.4 Acceptance Criteria

The filter handling system functions in accordance with design specifications.

14.2.12.2.18 Resin Transfer Preoperational Test (SU4-HC03)

14.2.12.2.18.1 Objectives

a. To demonstrate the ability to charge resins and

activated charcoal to those systems containing

potentially contaminated demineralizers or adsorbers.

The ability of the spent resin sluice pumps to transfer resins and charcoal from demineralizers and adsorbers is also verified.

b. To demonstrate the operating characteristics of the

spent resin sluice pumps, chemical addition metering

pumps, and chemical drain tank pumps.

c. To demonstrate the operability of system valve and pump

control circuits.

14.2.12.2.18.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2-140 Rev. 0 WOLF CREEK

c. Those systems containing potentially contaminated demineralizers and adsorbers are available to support

this test.

d. The reactor makeup water system is available to provide a source of water for resin charging.
e. A means of bulk disposal is available to receive waste

at the bulk disposal station.

14.2.12.2.18.3 Test Method

a. Resins and charcoal are charged and transferred from

selected potentially contaminated demineralizers and

adsorbers.

b. The spent resin sluice pumps, chemical addition metering

pumps, and chemical drain tank pumps are operated, and

performance characteristics are obtained.

c. The response of the spent resin sluice pumps, chemical

addition metering pumps, and the chemical drain tank

pumps to a low-level trip signal from their respective

tanks is verified.

14.2.12.2.18.4 Acceptance Criteria

a. The operating characteristics of the spent resin sluice

pumps, chemical addition metering pumps, and the

chemical drain tank pump are within design specifications.

b. The spent resin sluice pumps, chemical addition metering

pumps, and the chemical drain tank pump trip on receipt

of a low-level trip signal from their respective tanks.

14.2.12.2.19 Fire Protection System (Water) Preoperational Test

(SU4-KC01A, SU4-KC01B)

14.2.12.2.19.1 Objectives

a. To demonstrate the operability of the preaction

sprinkler system, wet-pipe sprinkler system, and the

automatic water spray system, including system

instrumentation, alarms, and interlocks.

b. To demonstrate the operability of system valves,

including their response to safety signals.

14.2-141 Rev. 0 WOLF CREEK

c. To verify spray to the applicable electrical system transformers.

14.2.12.2.19.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operable.

c. The fire water pumps are available to provide a source

of water to the fire protection system headers.

14.2.12.2.19.3 Test Method

a. Response of the preaction sprinkler system, wet-pipe

sprinkler system, and automatic water spray system to

fire detection signals is verified, including the

operability of associated alarms, instrumentation, and

interlocks.

b. The fire protection system containment isolation valves

are operated under flow conditions and operating times

recorded.

c. Response of the fire protection system containment

isolation valves to a CIS is verified.

d. Spray to the applicable electrical transformers is verified.

14.2.12.2.19.4 Acceptance Criteria

a. The preaction sprinkler system, wet-pipe sprinkler

system, automatic water spray system and associated

alarms, and instrumentation and interlocks operate in

accordance with system design specifications.

b. The fire protection system containment isolation valves'

closure time is within design specifications.

c. The fire protection system containment isolation valves

close on receipt of a CIS.

d. The spray to applicable electrical transformers is

within design specifications.

14.2-142 Rev. 0 WOLF CREEK 14.2.12.2.20 Fire Protection System (Halon) Preoperational Test (S-04KC02)

14.2.12.2.20.1 Objectives

To demonstrate the operability of the halon system, including the associated

instrumentation, control circuits, and alarms.

14.2.12.2.20.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operable.

14.2.12.2.20.3 Test Method

The operability of the halon system, including the associated instrumentation

and alarms, is verified. System response to fire detection signals is also

verified.

14.2.12.2.20.4 Acceptance Criteria

The halon fire protection system operates in accordance with system design

specifications.

14.2.12.2.21 Fire Protection System Detection and Alarm

Preoperational Test (S-04KC03)

14.2.12.2.21.1 Objectives

To demonstrate the operability of the fire protection system detectors and

alarms not verified during the performance of the halon and water system

preoperational tests.

14.2.12.2.21.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operable.

14.2.12.2.21.3 Test Method

Actuation of system alarms upon receipt of fire detection signals is verified.

14.2-143 Rev. 0 WOLF CREEK 14.2.12.2.21.4 Acceptance Criteria

Fire protection system detectors and alarms operate in accordance with system

design specifications.

14.2.12.2.22 Oily Waste System Preoperational Test (S-04LE01)

14.2.12.2.22.1 Objectives

To demonstrate the sump pumps and miscellaneous condensate drain tank pumps'

operating characteristics and response to sump/tank, level signals. The

operation of system valves and associated control circuits and sump/tank level

alarms are also verified.

14.2.12.2.22.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The compressed air system is available to supply air to

system valves and pumps.

d. A water source (fire system) and a collection receptacle

(oil/water separator, main condenser) are available for

the testing of each sump/tank.

14.2.12.2.22.3 Test Method

a. The sump pumps and miscellaneous condensate drain tank

pumps are operated, and performance characteristics are

verified.

b. The response of each pump and associated alarms to sump/

tank high and low level signals is verified.

c. The operability of system air-operated valves is

verified, including the response to a process radiation

signal.

14.2.12.2.22.4 Acceptance Criteria

a. The performance characteristics of the system pumps are

within design specifications.

b. The turbine building oily waste header discharge valve

closes on a high-radiation signal.

14.2-144 Rev. 0 WOLF CREEK 14.2.12.2.23 Floor and Equipment Drain System Preoperational Test (SU4-LF01)

14.2.12.2.23.1 Objectives

To demonstrate the sump pumps and hot machine shop oil interceptor pump's

capacities and response to sump/tank level signals. The operation of system

valves, their response to safety signals, and sump/tank level alarms are also

verified.

14.2.12.2.23.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required electrical power supplies and control circuits are operational.
c. The compressed air system is available to supply air to

system valves and pumps.

d. A water source (fire system or ESW) and a collection

receptacle (holdup tank, radwaste system, etc.) are

available for the testing of each sump/tank.

14.2.12.2.23.3 Test Method

a. The sump pumps and hot machine shop oil interceptor pumps

are operated, and their capacities are verified.

b. The response of each system pump, system indication, and alarms, to sump/tank high and low level signals is

verified.

c. The operability of system air- and motor-operated valves

is verified, including their response to safety signals.

14.2.12.2.23.4 Acceptance Criteria

a. The capacities of the floor and equipment drain system

pumps are within design specifications.

b. System valves properly respond to safety injection

signals and containment isolation signals.

c. The valve response times are within design

specifications.

14.2-145 Rev. 0 WOLF CREEK 14.2.12.2.24 13.8-kV System Preoperational Test (S-04PA01)

14.2.12.2.24.1 Objectives

a. To demonstrate that the 13.8-kV busses can be energized from the startup transformer.
b. To demonstrate that automatic fast transfer of the

busses from the unit auxiliary source to the startup

source is within design specifications.

c. To demonstrate that the unit auxiliary source or startup

source feeder breakers will trip on a stuck breaker

condition.

d. To demonstrate proper operation of system instrumentation and controls.

14.2.12.2.24.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The 13.8-kV system has been energized.

14.2.12.2.24.3 Test Method

a. The 13.8-kV busses are energized from the startup transformer, and bus voltages are recorded.
b. Automatic fast transfer from the unit auxiliary source

to the startup source is verified.

c. Stuck breaker conditions are simulated, and proper

operation of the 13.8-kV auxiliary source and startup

source feeder breakers is verified.

14.2.12.2.24.4 Acceptance Criteria

a. The 13.8-kV bus voltages are within design

specifications, when energized from the startup

transformer.

b. Automatic fast transfer of the busses from the unit

auxiliary source to the startup source is within design

specifications.

14.2-146 Rev. 0 WOLF CREEK

c. The 13.8-kV auxiliary source and startup source feeder breakers trip on receipt of a stuck breaker signal.

14.2.12.2.25 4,160-V (Non-Class IE) System Preoperational Test

(S-04PB01)

14.2.12.2.25.1 Objectives

a. To demonstrate that the 4,160-V busses can be energized

from their normal and alternate sources, and to verify

the operability of supply breaker and bus tie breaker

protective interlocks.

b. To demonstrate that automatic transfer is achieved

through the tie breaker from the normal source to the alternate source in the event of an electrical fault.

c. To demonstrate proper operation of system

instrumentation and controls.

14.2.12.2.25.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The 4,160-V (non-Class IE) system has been energized.

14.2.12.2.25.3 Test Method

a. The 4,160-V non-Class IE busses are energized from their

normal and alternate source, and bus voltages are

recorded.

b. System supply breakers and bus tie breakers are

operated, and breaker interlocks are verified.

c. System electrical fault signals are simulated, and

automatic transfer is verified through the tie breaker

from the normal source to the alternate source for each

4,160-V bus.

14.2.12.2.25.4 Acceptance Criteria

a. The voltage of each 4,160-V non-Class IE bus, when

supplied from its normal source and alternate source, is

within design specifications.

14.2-147 Rev. 0 WOLF CREEK

b. System supply breaker and bus tie breaker interlocks operate in accordance with the system design.
c. Automatic transfer is achieved through the tie breaker

from the normal source to the alternate source, for each 4,160-V bus, upon receipt of an electrical fault signal.

14.2.12.2.26 480-Volt (Non-Class IE) System Preoperational Test

(S-04PG01)

14.2.12.2.26.1 Objectives

a. To demonstrate that the 480-V non-Class IE load centers

can be energized from their normal sources and alternate

sources, as applicable, and verify the operability of feeder breaker and bus tie breaker protective interlocks.

b. To demonstrate that the 480-V busses supplied by 4160-V

(Class IE) source breakers are shed on receipt of a load

shed signal.

c. To demonstrate proper operation of system

instrumentation and controls.

14.2.12.2.26.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits are operational.
c. The 480-V (non-Class IE and Class IE) systems have been

energized.

14.2.12.2.26.3 Test Method

a. The 480-V non-Class IE load centers are energized from

their normal source and alternate source, as applicable

and voltages are recorded.

b. System feeder breakers and bus tie breakers are

operated, and breaker interlocks verified.

c. A load shed signal is simulated, and the 480-V busses

supplied by the 4,160-V (Class IE) source breakers are

verified to shed.

14.2-148 Rev. 0 WOLF CREEK 14.2.12.2.26.4 Acceptance Criteria

a. The voltage for each 480-V non-Class IE load center,

when supplied from its normal source and alternate

source, as applicable, is within design specifications.

b. System feeder breaker and bus tie breaker interlocks

operate in accordance with the system design.

c. The 480-V busses supplied by the 4160-V (Class IE)

source breakers shed on receipt of a load shed signal.

14.2.12.2.27 250-V DC System Preoperational Test (S-04PJ01)

14.2.12.2.27.1 Objectives To demonstrate the ability of the battery and battery chargers to provide power

to the busses. The battery chargers' ability to recharge their respective

battery is also demonstrated. Proper operation of system instrumentation and

controls is also verified.

14.2.12.2.27.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. Ventilation for the battery room is available.
d. The 250-V dc system has been energized.

14.2.12.2.27.3 Test Method

a. The battery is discharged, using a test load at the

design duty cycle discharge rate.

b. The battery is fully discharged to determine its

capacity factor.

c. The ability of each battery charger to charge the

battery to normal conditions, after the battery has

undergone a design duty cycle, while simultaneously

supplying power at a rate equivalent to the largest

motor current load is verified.

d. A load shed signal is initiated, and the battery charger

PJ31 ac supply breaker is verified to trip.

14.2-149 Rev. 0 WOLF CREEK 14.2.12.2.27.4 Acceptance Criteria

a. The battery is capable of maintaining output voltage

above the design minimum, during a design duty cycle.

b. The battery capacity factor is in accordance with design

requirements.

c. The battery chargers are able to recharge the battery to

normal conditions, after the battery has undergone a

design duty cycle, while simultaneously supplying power

at a rate equivalent to the largest motor current load.

d. Battery charger PJ31 ac supply breaker trips on receipt

of a load shed signal.

14.2.12.2.28 125-V (Non-Class IE) DC System Preoperational Test

(S-04PK01, S-04PK02)

14.2.12.2.28.1 Objectives

To demonstrate the ability of the batteries and chargers to provide power to

the busses. The battery chargers' ability to recharge their respective battery

is also demonstrated. Proper operation of system instrumentation and controls

is also verified.

14.2.12.2.28.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. Ventilation for the battery room is available.

14.2.12.2.28.3 Test Method

a. Each battery is discharged, using a test load at the

design duty cycle discharge rate.

b. Each battery is fully discharged to determine its

capacity factor.

c. The ability of each battery charger to charge its

respective battery to normal conditions, after the

battery has undergone a design duty cycle, while

simultaneously supplying power at a rate equivalent to

the design instrumentation loading.

14.2-150 Rev. 0 WOLF CREEK

d. A safety injection load shed signal is initiated, and the battery charger PK21, PK22, PK23, and PK24 supply

breaker is verified to trip.

14.2.12.2.28.4 Acceptance Criteria

a. Each battery is capable of maintaining output voltage

above the design minimum, during a design duty cycle.

b. Each battery capacity factor is in accordance with

design requirements.

c. The battery chargers are able to recharge the batteries

to normal conditions, after the battery has undergone a

design duty cycle, while simultaneously supplying power at a rate equivalent to the design load.

d. Battery charger PK21, PK22, PK23, and PK24 supply

breaker trips on receipt of a safety injection load shed

signal.

14.2.12.2.29 Instrument AC (Non-Class IE) System Preoperational

Test (S-04PN01)

14.2.12.2.29.1 Objectives

To demonstrate that the 120-V non-Class IE ac distribution panels can be fed

from their associated supply transformers. Proper operation of system

instrumentation and controls is also verified.

14.2.12.2.29.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2.12.2.29.3 Test Method

The 120-V non-Class IE ac distribution panels are energized from their

associated supply transformers, and the panel voltages are recorded.

14.2.12.2.29.4 Acceptance Criteria

Each 120-V non-Class IE ac distribution panel voltage is within design

specifications.

14.2-151 Rev. 0 WOLF CREEK 14.2.12.2.30 Emergency Lighting System Preoperational Test (S-04QD01)

14.2.12.2.30.1 Objectives

To demonstrate the capability of the emergency lighting system to provide

adequate lighting. Proper operation of system instrumentation and controls is

also verified.

14.2.12.2.30.2 Prerequisites

Required electrical power supplies and control circuits are operable.

14.2.12.2.30.3 Test Method

The ability of the emergency lighting system to provide adequate lighting is verified. The operability of associated instrumentation and control circuits

is also verified.

14.2.12.2.30.4 Acceptance Criteria

The emergency lighting system operates in accordance with system design

specifications.

14.2.12.2.31 Public Address System Preoperational Test (S-04QF01)

14.2.12.2.31.1 Objectives

To demonstrate the capability of the public address system to provide adequate

intraplant communications and to verify the operability of the evacuation alarm system.

14.2.12.2.31.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operable.

14.2.12.2.31.3 Test Method

a. The public address system is operated from all

locations, and adequate communications verified.

b. Operability of the evacuation alarm system is verified.

14.2-152 Rev. 0 WOLF CREEK 14.2.12.2.31.4 Acceptance Criteria

a. The evacuation alarm system operates in accordance with

system design specifications.

14.2.12.2.32 Heat Tracing Freeze Protection System Preoperational

Test (S-04QJ01)

14.2.12.2.32.1 Objectives

To demonstrate the ability of the freeze protection system to automatically

control the associated heat tracing circuits in accordance with system design.

The operation of system instrumentation and controls is also verified.

14.2.12.2.32.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2.12.2.32.3 Test Method

Temperature signals are varied and the energization/ deenergization of the

associated heat tracing circuits is verified.

14.2.12.2.32.4 Acceptance Criteria

The freeze protection system automatically controls the associated heat tracing circuits, in accordance with system design.

14.2.12.2.33 Secondary Sampling System Preoperational Test

(S-04RM01)

14.2.12.2.33.1 Objectives

a. To demonstrate the operating characteristics of the

steam generator blowdown sample drain tank pump, sample

chiller pump, and the condenser sample pumps, and verify

the operability of their associated control circuits.

b. To demonstrate that the system sample flows are within

design specifications.

14.2.12.2.33.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

14.2-153 Rev. 0 WOLF CREEK

b. Required electrical power supplies and control circuits are operable.
c. Plant conditions are established, and systems are

available, as necessary, to facilitate drawing samples from the sample points.

d. The steam generator blowdown system is available to

receive effluent from the steam generator blowdown

sample drain tank.

e. The closed cooling water system is available to provide

cooling water to the system sample coolers and chiller

package.

14.2.12.2.33.3 Test Method

a. The steam generator blowdown sample drain tank pump,

sample chiller pump, and the condenser sample pumps are

operated, and pump performance data recorded.

Operability of their associated control circuits is also

verified.

b. System samples are obtained, and flows are recorded.

14.2.12.2.33.4 Acceptance Criteria

a. The steam generator blowdown sample drain tank pump,

sample chiller pump, and condenser sample pump

performance characteristics are within design specifications.

b. Sample system flows are within design specifications.

14.2.12.2.34 Area Radiation Monitoring Preoperational Test

(S-04SD01)

14.2.12.2.34.1 Objectives

To demonstrate the operation of the area radiation monitors and to verify that

a high radiation signal at each monitor will initiate an alarm.

14.2.12.2.34.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2-154 Rev. 0 WOLF CREEK 14.2.12.2.34.3 Test Method

A calibration source is utilized to actuate the area radiation monitors, and

their operability and associated alarms are verified.

14.2.12.2.34.4 Acceptance Criteria

Each area radiation monitor actuates the associated alarms, on receipt of a

high radiation signal.

14.2.12.2.35 Seismic Monitoring Instrumentation System

Preoperational Test (S-04SG01)

14.2.12.2.35.1 Objectives

To demonstrate the operability of the seismic triggers and switches and strong motion accelerometers, including their associated alarms and recording and

playback systems.

14.2.12.2.35.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2.12.2.35.3 Test Method

A test signal is initiated, and the operability of the seismic triggers and switches and strong motion accelerometers, including their associated alarms and recording and playback systems, is verified.

14.2.12.2.35.4 Acceptance Criteria

The seismic triggers and switches and strong motion accelerometers, including

their associated alarms and recording and playback systems, operate in

accordance with system design specifications.

14.2.12.2.36 Loose Parts Monitoring System Test (SU4-SQ02).

14.2.12.2.36.1 Objective

To demonstrate the operability of the accelerometers, signal conditioning

devices and diagnostic equipment, including associated alarms and recording and

playback systems.

14.2-155 Rev. 0 WOLF CREEK 14.2.12.2.36.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. Reactor coolant system is filled with water.
d. Reactor coolant system is at normal operating

temperature and pressure with all reactor coolant pumps

running, and hot functional testing is in progress (for

those portions of the testing to be performed during hot

functional testing).

e. Reactor coolant system is at normal operating

temperature and pressure with all reactor coolant pumps

running after fuel loading during startup testing (for

those portions of the testing to be performed during

startup testing).

14.2.12.2.36.3 Test Method

a. Test signals are initiated and the operability of the

accelerometers, signal conditioners, and diagnostic

circuitry, including alarms and recording and playback

systems, is verified.

b. Channel audio outputs are also recorded during hot functional testing and after fuel loading during startup testing to obtain a record of the reactor coolant system

noise "signature."

14.2.12.2.36.4 Acceptance Criteria

The accelerometers, signal conditioners, and diagnostic circuitry, including

alarms and recording and playback systems operate to detect loose parts as

specified in USAR Section 4.4.6.4.

14.2.12.2.37 Plant Performance Test (SU8-0007)

14.2.12.2.37.1 Objectives

a. To monitor the balance-of-plant and electrical systems

under loaded conditions during hot functional and power

ascension testing. The ability of the ventilation

systems to maintain ambient temperatures within design

limits is also verified. To monitor the concrete

temperatures surrounding hot penetrations and to verify

evacuation alarm audibility in high noise areas.

14.2-156 Rev. 0 WOLF CREEK 14.2.12.2.37.2 Prerequisites

a. Required component testing, instrument calibration, and

system flushing/cleaning are complete.

b. Required HVAC systems have been balanced.
c. Required electrical power supplies and control circuits

are operational.

14.2.12.2.37.3 Test Method

This procedure does not provide a test method. It provides a monitoring and

data collection function only, with the resultant datum evaluated against

provided design values, as applicable.

14.2.12.2.37.4 Acceptance Criteria

a. Evacuation alarm audibility in high noise areas is

verified.

b. The containment coolers maintain containment temperature

within design.

Note: Each monitored point is evaluated throughout the test to verify that the

applicable system or component is functioning per design.

14.2.12.2.38 Electrical Distribution System Voltage Verification

Test (S-090023)

14.2.12.2.38.1 Objectives

To record actual loaded electrical distribution parameters during various

steady-state and transient conditions.

14.2.12.2.38.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

14.2.12.2.38.3 Test Method

The bus voltages and loadings of the electrical distribution system (down to

the Class lE 120/208 V ac system) are recorded for

14.2-157 Rev. 0 WOLF CREEK various steady state configurations. Data is also recorded during the starting of the largest Class 1E and non-Class lE motors. All monitored busses are

loaded to at least 30 percent.

14.2.12.2.38.4 Acceptance Criteria

Not applicable.

Note: The data obtained from this test procedure are used to verify electrical

system voltage analysis.

14.2.12.3 Startup Test Procedures The following sections are the test abstracts for each startup test. Table

14.2-3 provides an index of these tests.

14.2.12.3.1 Automatic Steam Generator Level Control (S-07AB01)

14.2.12.3.1.1 Objectives

a. To verify the stability of the automatic steam generator

level control following simulated transients at low

power conditions and the proper operation of the

variable speed feature of the feedwater pumps.

b. To demonstrate the performance characteristics of the steam generator feedwater pumps.

14.2.12.3.1.2 Prerequisites

a. The steam generator level control system has been

checked and calibrated.

b. Steam generator level instruments and set points have

been set and calibrated.

c. Main feedwater is operational.

14.2.12.3.1.3 Test Method

a. Induce simulated steam generator level transients to verify proper steam generator level control response.
b. Verify the variable speed features of the steam

generator feedwater pumps by manipulation of controllers

and test input signals, and verify the performance

characteristics of the steam generator feedwater pumps.

14.2-158 Rev. 0 WOLF CREEK 14.2.12.3.1.4 Acceptance Criteria

a. Automatic steam generator level control system response

must be in accordance with the vendor's technical

manual.

b. The steam generator feedwater pump's performance

characteristics are within design specifications.

14.2.12.3.2 Dynamic Automatic Steam Dump Control (SU7-AB02)

14.2.12.3.2.1 Objectives

To verify automatic operation of the T average steam dump control system,

demonstrate controller setpoint adequacy, and obtain final settings for steam pressure control of the condenser dump valves.

14.2.12.3.2.2 Prerequisites

a. The reactor coolant system is at normal operating

pressure and temperature.

b. The reactor is critical.
c. The steam dump system has been checked and calibrated.
d. Main feedwater and the condenser are operational.

14.2.12.3.2.3 Test Method

a. Reactor power is increased by rod withdrawal and steam dump to condenser to demonstrate setpoint adequacy.
b. Pressure controller setpoint is increased prior to

switching to T average control, which will rapidly

modulate open condenser dump valves.

c. Simulate turbine operating conditions with reactor at

power, then simulate turbine trip, resulting in the

rapid opening of the steam dump valves.

14.2.12.3.2.4 Acceptance Criteria

The steam dump system controllers must maintain stable reactor coolant system

T average at the controllers set point with no divergent oscillations.

14.2.12.3.3 RTD Bypass Flow Measurement (S-07BB01)

14.2.12.3.3.1 Objectives

To determine the flow rate necessary to achieve the design reactor coolant

transport time in each resistance temperature detector

14.2-159 Rev. 0 WOLF CREEK (RTD) bypass loop and to measure the flow rate in each RTD bypass loop to ensure that the transport times are acceptable.

14.2.12.3.3.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The reactor core is installed, and the plant is at

normal operating temperature and pressure with all

reactor coolant pumps running.

14.2.12.3.3.3 Test Method

The flow rate necessary to achieve the design reactor coolant transport time

for each hot and cold leg bypass loop is calculated, utilizing the hot and cold

leg RTD bypass loop piping lengths. Hot and cold RTD bypass loop flow data are

recorded.

14.2.12.3.3.4 Acceptance Criteria

The flow rate in each hot and cold leg RTD bypass loop, required to achieve the

design reactor coolant transport time, is within design specifications.

14.2.12.3.4 Pressurizer Heater and Spray Capability Test

(S-07BB02)

14.2.12.3.4.1 Objectives

To determine the rate of pressure reduction caused by fully opening the

pressurizer spray valves and the rate of pressure increase from the operation

of all pressurizer heaters.

14.2.12.3.4.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The reactor core is installed with the plant in the hot

shutdown condition at normal operating temperature and

pressure with all reactor coolant pumps running.

14.2-160 Rev. 0 WOLF CREEK

d. The final setting of the continuous spray flow valves is complete.
e. The reactor coolant system is borated to the value

required for fuel loading.

f. This test is performed prior to initial criticality.

14.2.12.3.4.3 Test Method

a. With the pressurizer spray valves closed, all

pressurizer heaters are energized, and the time to reach

a 2,300 psig system pressure is measured and recorded.

b. With the pressurizer heaters deenergized, both spray valves are fully opened, and the time to reach a 2,000 psig system pressure is measured and recorded.

14.2.12.3.4.4 Acceptance Criteria

The pressurizer pressure response to the opening of the pressurizer spray

valves and to the actuation of all pressurizer heaters is within design limits.

14.2.12.3.5 Reactor Coolant System Flow Measurement (S-07BB03)

14.2.12.3.5.1 Objectives

a. To confirm, after core installation but before initial

critical operation, that reactor coolant system (RCS)

flow rate as measured by loop elbow differential pressure readings is greater than or equal to 90 percent of the thermal design flow rate.

b. To confirm during initial power operation that RCS flow

rate as computed from calorimetric data is greater than

or equal to the thermal design flow rate.

14.2.12.3.5.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The reactor core is installed, and the plant is at

normal operating temperature and pressure.

14.2-161 Rev. 0 WOLF CREEK 14.2.12.3.5.3 Test Method

a. Before critical operation, loop elbow differential

pressure readings are taken with all reactor coolant

pumps running, and RCS flow rate is calculated.

b. During initial power operation, calorimetric data are

taken from Procedure S-07SC03, "Thermal Power

Measurement and Statepoint Data Collection," and RCS

flow rate is calculated.

14.2.12.3.5.4 Acceptance Criteria

RCS flow rate by loop elbow differential pressure measurement is greater than

or equal to 90 percent of the thermal design value and by calculation from calorimetric data is greater than or equal to the thermal design value.

14.2.12.3.6 Reactor Coolant System Flow Coastdown Test (SU7-BB04)

14.2.12.3.6.1 Objectives

a. To measure the rate at which reactor coolant flow

changes, subsequent to simultaneously tripping all

reactor coolant pumps.

b. To determine that the reactor coolant system low-flow

delay time is less than or equal to the total low-flow

delay time assumed in the safety analysis for loss of

flow.

14.2.12.3.6.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The reactor core is installed, and the plant is at

normal operating temperature and pressure with all

reactor coolant pumps running.

14.2.12.3.6.3 Test Method

Flow coastdown stabilization and loss of coolant delay-time data are recorded

while tripping reactor coolant pumps.

14.2-162 Rev. 0 WOLF CREEK 14.2.12.3.6.4 Acceptance Criteria

a. The rate of change of reactor coolant flow is within

design specifications.

b. The reactor coolant system low-flow delay time is less

than or equal to the total low-flow delay time assumed

in the safety analysis for loss of flow.

14.2.12.3.7 Pressurizer Continuous Spray Flow Verification

(S-07BB05)

14.2.12.3.7.1 Objectives

To establish a setting for the pressurizer continuous spray flow valves to obtain an optimum continuous spray flow.

14.2.12.3.7.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits

are operational.

c. The reactor core is installed with the plant in the hot

shutdown condition at normal operating temperature and

pressure with all reactor coolant pumps running.

d. The reactor coolant system is borated to the value required for fuel loading.
e. This test shall be performed prior to initial

criticality.

f. The preliminary setting of the continuous spray flow

valves has been completed during hot functional testing.

14.2.12.3.7.3 Test Method

Continuous spray flow valves are adjusted to establish the optimum continuous

spray flow, and the valve throttle positions are recorded.

14.2.12.3.7.4 Acceptance Criteria

The continuous spray flow valves are throttled to establish the optimum

continuous spray flow to keep the spray line warm and minimize normal steady-

state pressurizer heater loads.

14.2-163 Rev. 0 WOLF CREEK 14.2.12.3.8 RTD/TC Cross Calibration (S-07BB06)

14.2.12.3.8.1 Objectives

a. To provide a functional checkout of the reactor coolant system resistance temperature detectors (RTDs) and

incore thermocouples and to generate isothermal cross-

calibration data for subsequent correction factors to

indicated temperatures.

NOTE This portion of the test need be performed only if the

data collected in S-03BB16, RTD/TC Cross Calibration,

during hot functional testing, so warrants.

b. To provide a functional checkout of the core subcooling

monitor system including the detecting thermocouples.

14.2.12.3.8.2 Prerequisites

a. Required component testing and instrument calibration

are complete.

b. Required electrical power supplies and control circuits are operational.
c. Plant heatup, following core loading, is in progress,

and all reactor coolant pumps are operating.

14.2.12.3.8.3 Test Method

a. At various temperature plateaus RTD and incore

thermocouple data are recorded. Isothermal

cross-calibration correction factors for individual

thermocouples and the installation corrections for

individual RTDs are determined.

b. At normal operating temperature, the thermocouple core

subcooling monitors' operational and programmable functions are verified, including associated alarms, displays, and printouts.

14.2.12.3.8.4 Acceptance Criteria

a. Individual RTD readings are within the design

specifications.

b. The installation corrections of the RTDs are within

design specifications.

14.2-164 Rev. 0 WOLF CREEK

c. The thermocouple core subcooling monitor alarms, displays, and printouts function in accordance with

design specifications.

14.2.12.3.9 Core Loading Instrumentation and Neutron Source Requirements (S-07SC01)

14.2.12.3.9.1 Objectives

To verify proper alignment, calibration, and neutron response of the temporary

core loading instrumentation prior to start of fuel- loading; to check the

neutron response of the nuclear instrumentation system (NIS) source range

channels prior to start of fuel-loading; and to check the neutron response of

the temporary and NIS 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. To verify the signal to noise ratio is greater than 2.

14.2.12.3.9.2 Prerequisites

a. Hot functional testing is completed.
b. The nuclear instrumentation system is installed and

calibrated.

14.2.12.3.9.3 Test Method

a. A portable neutron source (1-5 curie), plus preshipment

equipment checkout data, is used to verify proper

alignment, calibration, and neutron response of the

temporary core-loading instrumentation.

b. A portable neutron source (1-5 curie) is used to check

the neutron response of the NIS source range detectors.

c. A portable neutron source (1-5 curie) or movement of a

source-bearing fuel element to produce the desired

change in neutron level to verify the neutron response

of the temporary and NIS 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.

d. Perform a statistical evaluation of 10 observations for

each channel, to verify operability of the equipment.

14.2.12.3.9.4 Acceptance Criteria

Neutron instrumentation is operational, calibrated, and indicates a

positive/negative change in count rate as the neutron level is increased and/or

decreased. The signal to noise ratio is greater than 2.

14.2-165 Rev. 0 WOLF CREEK 14.2.12.3.10 Thermal Power Measurement and Statepoint Data Collection (S-07SC03)

14.2.12.3.10.1 Objectives

To measure core thermal power and obtain data for instrumentation calibration.

14.2.12.3.10.2 Prerequisites

a. Calorimetric instrumentation is installed.
b. This test is performed at 30-percent, 50-percent, 75-

percent, 90-percent, and 100-percent power.

14.2.12.3.10.3 Test Method Collect data and calculate thermal power. Obtain statepoint data, compute the

average for each parameter measured, convert to the appropriate units, and

summarize the data for each RCS loop.

14.2.12.3.10.4 Acceptance Criteria

This test is for the collection of data.

14.2.12.3.11 Nuclear Instrumentation System Test (SU7-SE01)

14.2.12.3.11.1 Objectives

The purpose of this test is to verify that the nuclear instrumentation system

performs the required indications and control functions through the source, intermediate, and power ranges of operation prior to core loading.

14.2.12.3.11.2 Prerequisites

a. The nuclear instrumentation system is installed,

calibrated, aligned, and operational for a period of at

least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b. The plant is at ambient temperature and pressure.

14.2.12.3.11.3 Test Method

a. The source and intermediate range channels are subjected

to various test signals to verify that the appropriate

indicators alarm, illuminate, or actuate, and the source

range local and remote speakers function.

14.2-166 Rev. 0 WOLF CREEK

b. The power range channels are subjected to various test signals to observe proper meter reading and function of

the comparator and rate circuitry.

c. The high voltage circuitry of the source and intermediate range channels is tested.

14.2.12.3.11.4 Acceptance Criteria

The control and indication functions and the reactor trip set points of the

nuclear instrumentation system source, intermediate, and power range channels

have been verified.

14.2.12.3.12 Operational Alignment of Nuclear Instrumentation

(S-07SE02) 14.2.12.3.12.1 Objectives

To 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 prior to initial criticality to at

or near full reactor power.

14.2.12.3.12.2 Prerequisites

a. The nuclear instrumentation system has been aligned.
b. This test is conducted prior to criticality, during

power escalation, and at or near full power.

14.2.12.3.12.3 Test Method

a. All functions are calibrated, tested, and verified,

utilizing permanently installed controls and adjustment

mechanisms.

b. Operational modes of the source range, intermediate

range, and power range channels are set for their proper

functions, as per the test instructions.

14.2.12.3.12.4 Acceptance Criteria

The overlap between the source, intermediate, and power range channels must be

at least 1-1/2 decades, and the power range channels are capable of being

adjusted to agree with the results of plant calorimetric calculations.

14.2-167 Rev. 0 WOLF CREEK 14.2.12.3.13 Axial Flux Difference Instrumentation Calibration (S-07SE03)

14.2.12.3.13.1 Objectives

To derive calibration factors for overpower, overtemperature, and

T setpoints, based on incore flux data, calorimetric data, and excore nuclear

instrumentation detector currents.

14.2.12.3.13.2 Prerequisites

a. The axial flux difference instrumentation system has

been aligned.

b. Data has been obtained from flux maps taken at 30-percent and 50-percent power.

14.2.12.3.13.3 Test Method

Collect data, as required by test instruction, at 50-percent and 75-percent power, perform FI calculations to calibration factors, and extrapolate results for use at the 100-percent power plateau.

14.2.12.3.13.4 Acceptance Criteria

Calibration factors agree with Technical Specifications.

14.2.12.3.14 Control Rod Drive Mechanism Operational Test (S-

07SF01)

14.2.12.3.14.1 Objectives

To demonstrate the proper operation of the rod drive mechanisms under both cold

and hot plant conditions and to provide verification of proper slave cycler

timing.

14.2.12.3.14.2 Prerequisites

a. The control rod drive mechanisms are installed.
b. The rod drive motor-generator sets are installed and

power is available.

c. For the control rod drive mechanism timing test, the

core is installed, rod position indication is installed,

and the control rod driving mechanism cooling fans are

operational.

d. Nuclear instrumentation channels operable and operating.

14.2-168 Rev. 0 WOLF CREEK

e. A fast speed oscillograph (Visicorder or equivalent) to monitor test parameters is available.

14.2.12.3.14.3 Test Method

a. With the reactor core installed and reactor in the cold

shutdown condition, confirm that the slave cycler

devices supply operating signals to the proper CRDM

stepping magnet coils.

b. Verify proper operation of all CRDMs under both cold and

hot shutdown conditions. CRDM magnet coil currents and

audio noise signals are recorded.

14.2.12.3.14.4 Acceptance Criteria The control rod drive mechanisms conform to the requirements for proper

mechanism operation and timing as described in the magnetic control rod drive

mechanism instruction manual.

14.2.12.3.15 Rod Control System (S-07SF02)

14.2.12.3.15.1 Objectives

To demonstrate and document that the rod control system performs the required

control and indication functions just prior to initial criticality. To

demonstrate operation of the rod inhibit functions.

14.2.12.3.15.2 Prerequisites

a. The reactor coolant system is at normal operating pressure and temperature.
b. The rod control system is installed and aligned.
c. The source range nuclear instruments are operable.
d. The rods are capable of withdrawal.
e. The rod position indication system is operable.

14.2.12.3.15.3 Test Method

a. With the reactor at no load operating temperature and

pressure, and just prior to initial criticality, the

control is checked for each applicable position of the

bank selector switch for proper operation.

14.2-169 Rev. 0 WOLF CREEK

b. Status lights, alarms, and indicators are verified.

14.2.12.3.15.4 Acceptance Criteria

The control and indication functions in accordance with the rod position indication system and rod control system manuals. Rod motion is inhibited upon

application of an inhibit function.

14.2.12.3.16 Rod Drop Time Measurement (SU7-SF03)

14.2.12.3.16.1 Objectives

To determine the rod drop time of each rod cluster control assembly under no-

flow and full-flow conditions, with the reactor in the cold shutdown condition

and at normal operating temperature and pressure.

14.2.12.3.16.2 Prerequisites

a. Initial core loading is completed.
b. Rod control system is installed and tested.
c. Individual rod position indication is installed and

checked.

14.2.12.3.16.3 Test Method

Withdraw each rod cluster control assembly, interrupt the electrical power to

the associated rod drive mechanism, and measure and record the rod drop time.

This test is performed with the reactor at cold and hot conditions and at no-flow and full- flow.

14.2.12.3.16.4 Acceptance Criteria

The rod drop times are acceptable in accordance with plant technical

specifications.

14.2.12.3.17 Rod Position Indication System (SU7-SF04)

14.2.12.3.17.1 Objectives

To verify that the rod position indication system satisfactorily performs

required indication functions for each individual rod and that each rod

operates satisfactorily over its entire range of travel.

14.2-170 Rev. 0 WOLF CREEK 14.2.12.3.17.2 Prerequisites

a. Plant system conditions are established as follows:
1. Test performed at T avg <200°F, nominal RCS pressure for T avg noted 2. Test results verified at T avg nominally 557°F, RCS pressure nominally 2235 psig and at least one reactor coolant pump in service.

14.2.12.3.17.3 Test Method

a. All shutdown rod banks are fully withdrawn by bank

stopping at 18,210 and 228 steps to record the rod

position, the Digital Rod Position Indication display

(DRPI), and the group step position indication.

b. All control rod banks are fully withdrawn by bank in 24

step increments while recording rod position as

indicated by the plant control room DRPI readout, and

the group step position indication.

c. In addition, the pulse-to-analog converter chassis bank

position digital readout is recorded for all control rod

banks.

14.2.12.3.17.4 Acceptance Criteria

The rod position indication system performs the required indication functions,

and each rod operates over its entire range of travel within the limits of the

rod position indication instruction manual and the plant precautions,

limitations,setpoints manual, and WCGS Technical Specifications.

14.2.12.3.18 Automatic Reactor Control System (S-07SF05)

14.2.12.3.18.1 Objectives

To demonstrate the capability of the reactor control system to respond properly

to input signals and to transmit proper control signals to other plant control

systems and components.

14.2.12.3.18.2 Prerequisites

a. The reactor is at approximately 30-percent power.

14.2-171 Rev. 0 WOLF CREEK

b. Pressurizer level and pressure, steam dump, steam generator level, and main feed pump speed control

systems are in automatic.

14.2.12.3.18.3 Test Method

T average will be successively varied from the T ref set point to verify the transient recovery capabilities of the auto reactor control system.

14.2.12.3.18.4 Acceptance Criteria

a. No manual intervention should be required to bring the

plant conditions to equilibrium values following

initiation of a 6 F temperature transient.

b. T avg should return to within +

1.5 F of T ref following initiation of a 6 F temperature transient.

c. Rod motion is inhibited by application of the

appropriate inhibit inputs.

14.2.12.3.19 Incore Flux Mapping (S-07SR01, S-07SR02)

14.2.12.3.19.1 Objectives

To obtain core power and temperature profiles for evaluating core performance.

14.2.12.3.19.2 Prerequisites

a. The incore monitoring system has been functionally

tested.

b. This test is performed at low power, 30-, 50-, 75-, 90-,

and 100-percent power.

c. The reactor is stabilized prior to taking a map.

14.2.12.3.19.3 Test Method

The movable detectors are inserted into the core, data is obtained, and

thermocouples are monitored while at a stable power. The obtained data is

retained for evaluation.

14.2.12.3.19.4 Acceptance Criteria

Flux and temperature data is obtained at the various power levels.

14.2-172 Rev. 0 WOLF CREEK 14.2.12.3.20 Incore Instrumentation Test (S-07SR03, S-07SR04)

14.2.12.3.20.1 Objectives

To set up and demonstrate operation of the incore instrumentation system.

14.2.12.3.20.2 Prerequisites

a. The incore instrumentation system is installed.
b. Proper rotation and limit switch operation has been

verified.

c. Testing is performed at cold shutdown and hot standby.

14.2.12.3.20.3 Test Method

At cold shutdown a dummy cable is inserted into each thimble, and proper

rotation and limit switch operation is verified. At hot standby the detectors

are inserted into the thimbles to demonstrate performance in all operational

modes.

14.2.12.3.20.4 Acceptance Criteria

The incore instrumentation system is capable of taking a flux map.

14.2.12.3.21 Operational Alignment of Process Temperature

Instrumentation (S-07SF06)

14.2.12.3.21.1 Objectives To align T and Tavg process instrumentation under isothermal conditions, prior to criticality and at power.

14.2.12.3.21.2 Prerequisites

a. This alignment is performed prior to initial criticality

and again at 75-percent power. Alignment is checked at

100-percent power.

b. All reactor coolant pumps shall be operating.

14.2.12.3.21.3 Test Method

a. Align T and Tavg per test instructions under isothermal conditions prior to criticality and at approximately 75

14.2-173 Rev. 0 WOLF CREEK percent power. Extrapolate the 75-percent power data to determine T and Tavg values for the 100-percent power plateau.

b. At or near full power, check the alignment of the T and T avg channels for agreement with the results of thermal power measurement. Realign any channels, as necessary, to meet test specifications.

14.2.12.3.21.4 Acceptance Criteria

The 100 percent power indications for T and Tavg channels must be within the maximum design values as specified in vendor design documents.

14.2.12.3.22 Startup Adjustments of Reactor Control System (S-07SF07)

14.2.12.3.22.1 Objectives

To obtain the optimum plant efficiency.

14.2.12.3.22.2 Prerequisites

a. The reactor coolant system is at normal operating

pressure and temperature.

b. Plant instrumentation shall have been aligned according

to Operational Alignment of Process Temperature

Instrumentation.

c. The turbine control system shall have been aligned.

14.2.12.3.22.3 Test Method

a. Obtain system temperature and steam pressure data at

steady-state conditions for zero power and at hold

points during power escalations.

b. Evaluation of these data will provide the basis for

adjustments to the reactor control system.

14.2.12.3.22.4 Acceptance Criteria

The Tavg controller must be capable of maintaining full load steam pressure

within turbine pressure limitations specified in the vendor's technical manual.

14.2-174 Rev. 0 WOLF CREEK 14.2.12.3.23 RCCA or Bank Worth Measurement at Zero Power (S-07SF08)

14.2.12.3.23.1 Objectives

To determine the differential and integral reactivity worth of a rod cluster

control bank (RCC) or an individual rod cluster control assembly (RCCA).

14.2.12.3.23.2 Prerequisites

a. The reactor is critical with the neutron flux level

within the range established for zero power physics

testing.

b. The reactor coolant system is at normal operating pressure and temperature.

14.2.12.3.23.3 Test Method

RCC and RCCA worth are validated by constant addition and/or dilution of boron

in the reactor coolant system, causing rod movement to compensate for the boron

addition and/or dilution. This rod movement will cause step changes in

reactivity which are used to compute the worths.

14.2.12.3.23.4 Acceptance Criteria

The integral reactivity worth of the RCC or RCCA over its entire range of

travel agrees with acceptance criteria given in the Nuclear Design Report

within tolerance values specified in vendor design documents.

14.2.12.3.24 RCCA or Bank Worth Measurement at Power (SU7-SF09)

14.2.12.3.24.1 Objectives

a. To measure RCCA worth for a rod ejected from the HFP rod

insertion limit position.

b. To determine in-core response resulting from a dropped

rod with all other control rods near fully withdrawn.

14.2-175 Rev. 0 WOLF CREEK 14.2.12.3.24.2 Prerequisites

Testing will be performed at 30-percent power with the reactor stable.

  • 14.2.12.3.24.3 Test Method
a. Ejected rod - Compute the change in reactivity

associated with the change in RCCA position.

b. Dropped rod - Determine the quadrant power tilt ratio

and hot channel factors by use of the in-core flux

mapping system.

14.2.12.3.24.4 Acceptance Criteria

a. Ejected rod - The rod worth of the ejected rod is within tolerance values specified in vendor design documents.
b. Dropped rod - The peaking factors are within the limits

specified in vendor design documents.

14.2.12.3.25 Reactor Systems Sampling for Core Load (S-07SJ01)

14.2.12.3.25.1 Objectives

To verify uniform boron concentration, prior to core load, in the reactor

coolant system and directly connected auxiliary systems.

14.2.12.3.25.2 Prerequisites

a. Boric acid tanks, pumps, and transfer lines are all filled with 4 percent boric acid solution.
b. Reactor coolant system is filled with reactor grade

water which has been borated to a concentration as

specified in the technical specifications.

14.2.12.3.25.3 Test Method

a. Filling and circulating the reactor coolant system with

borated water should be accomplished, utilizing normal

flow paths as much as possible.

_______________________

  • This test was performed at 50 percent power at Callaway.

Callaway has the same core and Nuclear Instrumentation System

as Wolf Creek. Wolf Creek Core parameters measured prior to

the pseudo rod drop test were compared with the corresponding

results for Callaway to verify that the plant response was the

same. This exemption was approved in a July 3, 1985 letter

from the NRC.

14.2-176 Rev. 0 WOLF CREEK

b. Collect and analyze four samples taken at equidistant depths in the reactor vessel simultaneously with one

sample from the operating residual heat removal loop to

check uniform boron concentration.

14.2.12.3.25.4 Acceptance Criteria

Boron concentration of the samples obtained from the designated sample points

must be within a 30-ppm range of values.

14.2.12.3.26 Initial Core Loading (SU7-0001)

14.2.12.3.26.1 Objectives

a. To load fuel in a controlled manner.
b. To measure boron concentration.

14.2.12.3.26.2 Prerequisites

a. Sufficient preoperational testing has been completed to

ensure the necessary equipment and attendant

instrumentation is functional.

b. Required technical specification surveillance is

completed and the necessary systems are operable.

14.2.12.3.26.3 Test Method

Instruction includes a core-loading sequence which specifies the loading in a step-by-step fashion with the appropriate data collection records.

14.2.12.3.26.4 Acceptance Criteria

A permanent record of the final as-loaded core configuration has been made, and

the configuration is consistent with the fuel assembly core loading plan.

Boron concentration is as specified in the Technical Specifications.

14.2.12.3.27 Inverse Count Rate Ratio Monitoring For Core Loading

(S-070002)

14.2.12.3.27.1 Objectives

a. To obtain nuclear monitoring data during initial core

loading.

b. To prevent criticality during core loading.

14.2-177 Rev. 0 WOLF CREEK 14.2.12.3.27.2 Prerequisites

a. Temporary and plant source range nuclear instrumentation

has been operational for a minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to achieve

stable operation.

b. Plant is prepared for initial core loading.

14.2.12.3.27.3 Test Method

Data from the nuclear monitoring channels is used to assess the safety with

which core loading operations may be conducted. Inverse count rate ratio is

plotted and evaluated to prevent any unexpected deviation from subcriticality.

The core is monitored and maintained in a subcritical configuration throughout

the core loading.

14.2.12.3.27.4 Acceptance Criteria

The core is loaded without achieving criticality.

14.2.12.3.28 Inverse Count Rate Ratio Monitoring for Approach to

Initial Criticality (S-070003)

14.2.12.3.28.1 Objectives

a. To obtain nuclear monitoring data during initial

criticality.

b. To anticipate and determine criticality.

14.2.12.3.28.2 Prerequisites

a. Both source range and intermediate range nuclear

channels alarm, trip functions, and indicating devices

have been checked out and calibrated.

b. Both source range and intermediate range nuclear

channels have been energized a minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to

insure stable operation.

14.2.12.3.28.3 Test Method

a. Obtain base line count rates prior to rod withdrawal and

boron dilution. After each increment of rod withdrawal,

and periodically during boron dilution, count rates are

obtained, and inverse count rate ratio is evaluated.

b. Core reactivity is monitored during the approach to

criticality.

14.2-178 Rev. 0 WOLF CREEK 14.2.12.3.28.4 Acceptance Criteria

To determine criticality.

14.2.12.3.29 Initial Criticality (S-070004)

14.2.12.3.29.1 Objectives

To achieve initial criticality in a controlled manner.

14.2.12.3.29.2 Prerequisites

a. Initial core loading is completed.
b. Required technical specification surveillance is completed and the necessary systems operable.
c. Sufficient post-core loading precritical testing has

been completed to ensure the necessary equipment and

attendant instrumentation is functional.

14.2.12.3.29.3 Test Method

a. At preselected points during rod withdrawal and/or boron

dilution, data is taken and inverse count rate plots

made to enable extrapolation to be carried out to the

expected critical point.

b. Initial criticality is achieved by boron dilution or, if

desired, by withdrawing control rods.

14.2.12.3.29.4 Acceptance Criteria

The reactor is critical with the flux level established at approximately 1 x 10-8 amps on the intermediate range nuclear channels.

14.2.12.3.30 Determination of Core Power Range for Physics

Testing (S-070005)

14.2.12.3.30.1 Objectives

To determine the reactor power level at which effects from fuel heating is

detectable and to establish the range of neutron flux in which zero power

reactivity measurements are to be performed.

14.2.12.3.30.2 Prerequisites

a. The reactor is critical and stable in the intermediate

range.

14.2-179 Rev. 0 WOLF CREEK

b. Control rods are sufficiently deep in the core to allow positive reactivity insertion by rod withdrawal.
c. Reactor coolant temperature is established at a value

that minimizes the moderator temperature coefficient reactivity feedback.

14.2.12.3.30.3 Test Method

a. Withdraw control rod bank and allow the neutron flux

level to increase until nuclear heating effects are

indicated by the reactivity computer.

b. Record the reactivity computer picoammeter flux level

and, if possible, the corresponding IR channel currents at which nuclear heating occurs, to obtain zero power testing range.

14.2.12.3.30.4 Acceptance Criteria

The power level at which zero power testing is conducted is determined.

14.2.12.3.31 Boron Endpoint Determination (S-070006)

14.2.12.3.31.1 Objectives

To determine the critical reactor coolant system boron concentration

appropriate to an endpoint configuration (RCC configuration).

14.2.12.3.31.2 Prerequisites

a. The reactor is critical within the range for zero power

testing and stable.

b. The reactor coolant is at normal operating pressure and

temperature.

c. Rods are at the approximate end point configuration.

14.2.12.3.31.3 Test Method

Boron endpoints are measured by determining the boron concentration of the

reactor coolant system with the rods close to or at the desired configuration.

If not, the rods are then quickly moved to the desired configuration with no

boron adjustment. The change in reactivity is measured, and this reactivity is

converted to an equal amount of boron to yield the endpoint at that particular

rod configuration.

14.2-180 Rev. 1 WOLF CREEK 14.2.12.3.31.4 Acceptance Criteria

The results of the boron endpoint calculations meet the requirements of the

Nuclear Design Report within tolerance values specified in vendor design

documents.

14.2.12.3.32 Isothermal Temperature Coefficient Measurement

(S-070007)

14.2.12.3.32.1 Objectives

To determine isothermal temperature coefficient, then derive the moderator

temperature coefficient from the isothermal data.

14.2.12.3.32.2 Prerequisites

a. The reactor is critical within the range for zero power

testing and stable.

b. The reactor coolant is at normal operating pressure and

temperature.

c. Control rods are at the approximate end point

configuration.

14.2.12.3.32.3 Test Method

The isothermal temperature coefficient is determined by heating/cooling the

reactor coolant system at a constant rate and plotting temperature versus

reactivity. The moderator temperature coefficient may be derived from isothermal data, if desired.

14.2.12.3.32.4 Acceptance Criteria

The average of the measured values of the isothermal and, if desired, the

derived moderator temperature coefficient agrees with acceptance criteria given

in the Nuclear Design Report within tolerance values specified in vendor design

documents.

14.2.12.3.33 Power Coefficient Determination (S-070008)

14.2.12.3.33.1 Objectives

To verify the power coefficient of reactivity.

14.2.12.3.33.2 Prerequisites

a. Reactor power level, reactor coolant temperature and

pressures, and RCCA and RCC bank configuration are as

follows:

14.2-181 Rev. 1 WOLF CREEK

1. RCS pressure - nominal 2235 psig
2. RCCA, RCC bank configuration - nominally all rods

out, D at bite position

3. Reactor power level - nominally 30, 50, 75, and 90

percent RTP

4. T avg - consistent with the nominal value corresponding to the T avg program at the identified nominal power levels.
b. All subsystems which affect overall plant transient

response should be in automatic mode of operation with

the exception of the rod control system and automatic makeup. The CVCS demineralizer shall be bypassed.

14.2.12.3.33.3 Test Method

a. As generator electrical load is changed, the primary side

is permitted to freely respond without any control rod

motion.

b. The power coefficient verification factor is calculated

by measuring the change in RCS temperature and the

corresponding change in core power.

14.2.12.3.33.4 Acceptance Criteria

The average value of the measured verification factor agrees with that obtained

from design predictions of the isothermal temperature coefficient and doppler

power coefficient. This agreement is within limits given in the test

instructions.

14.2.12.3.34 Load Swing Tests (S-070009)

14.2.12.3.34.1 Objectives

To verify proper nuclear plant transient response, including automatic control

system performance, when load changes are introduced at the turbine generator.

14.2.12.3.34.2 Prerequisites

Step load changes are initiated from steady state conditions at approximately

30-, 75-, and 100-percent power.

14.2-182 Rev. 1 WOLF CREEK 14.2.12.3.34.3 Test Method

a. Manually reduce the turbine generator output as rapidly

as possible to achieve an approximate 10-percent load

decrease/increase.

b. Plant variables are recorded, along with values observed

on the normal plant instrumentation, during the load

transient for those parameters required.

14.2.12.3.34.4 Acceptance Criteria

The following acceptance criteria are to be used to determine successful test

completion. Failure to meet these criteria does not constitute a need for

stopping the test program, but correction of any deficiences should be accomplished, as required, consistent with the current plant schedule.

a. Reactor and turbine must not trip.
b. Safety injection is not initiated.
c. Neither steam generator atmospheric relief valves nor safety valves shall lift.
d. Neither pressurizer relief valves nor safety valves shall

lift.

e. No manual intervention shall be required to bring plant conditions to steady state.
f. Nuclear power overshoot (undershoot) must be less than 3

percent for load increase (decrease).

14.2.12.3.35 Large Load Reduction Test (S-070010)

14.2.12.3.35.1 Objectives

To demonstrate satisfactory plant transient response to various specified load changes, to monitor the reactor control systems during these transients, and, if necessary, optimize the reactor control system setpoints.

14.2.12.3.35.2 Prerequisites

Step load reduction changes of 50 percent are initiated from steady state

conditions at approximately 75- and 100-percent power.

14.2-183 Rev. 13 WOLF CREEK 14.2.12.3.35.3 Test Method

a. Manually reduce the turbine generator output to achieve

an approximate 50-percent load reduction.

b. Monitor plant response during the transient and record

plant variables, as required.

c. If necessary, adjust the reactor control system setpoints

until optimal response is obtained.

14.2.12.3.35.4 Acceptance Criteria

The following acceptance criteria are to be used to determine successful test

completion. Failure to meet these criteria does not constitute a need for stopping the test program, but correction of any deficiencies should be accomplished, as required, consistent with the current plant schedule.

a. Reactor and turbine must not trip.
b. Safety injection is not initiated.
c. Steam generator safety valves shall not lift.
d. Pressurizer safety valves shall not lift.
e. No manual intervention shall be required to bring plant

conditions to steady state.

14.2.12.3.36 Plant Trip From 100 Percent Power (S-070011) 14.2.12.3.36.1 Objectives

To verify the ability of the plant automatic control systems to sustain a trip

from 100 percent and to bring the plant to stable conditions following the

transient, to determine the overall response time of the hot leg resistance

temperature detectors, and to evaluate the data resulting from the trip to

determine if changes in the control system setpoints are warranted to improve

transient response based on actual plant operations.

14.2.12.3.36.2 Prerequisites

a. The rod control system, steam generator level,

pressurizer pressure and level, and the steam dump system

are in the automatic control mode.

b. The plant is operating at normal steady state full power.
c. Diesel generators in standby idling condition.

14.2-184 Rev. 1 WOLF CREEK 14.2.12.3.36.3 Test Method

a. Initiate a plant trip by opening the main generator

output breaker, monitor plant response, and record plant

variables, as required.

b. If necessary, adjust the control system setpoints to

obtain optimal response.

14.2.12.3.36.4 Acceptance Criteria

The system parameters must stay within the limitations specified in the

vendor's design transient analysis document.

14.2.12.3.37 Rods Drop and Plant Trip (S-070012) 14.2.12.3.37.1 Objectives

To demonstrate that the negative rate trip circuit will trip the reactor and to

monitor plant response.

14.2.12.3.37.2 Prerequisites

a. The rod control system, steam generator level,

pressurizer pressure and level, and the feedwater pump

speed control are in the automatic control mode. Steam

dump control system is in the Tavg mode.

b. The plant is operating at a steady state power of 30 to

50 percent.

c. The rod group and the selected rods to be dropped have

been identified.

14.2.12.3.37.3 Test Method

a. Drop two RCCAs from a common group which, because of

their worth and location, are the most difficult to

detect by the nuclear instrumentation system (NIS).

b. Monitor systems behavior and plant response to trip from

an intermediate power level prior to the plant trip test

from full power.

14.2.12.3.37.4 Acceptance Criteria

The following acceptance criteria are to be used to determine successful test

completion:

14.2-185 Rev. 1 WOLF CREEK

a. The reactor shall have tripped as a result of the negative rate trip.
b. All RCCAs shall release and bottom on receipt of a trip

signal.

c. The pressurizer safety valves shall not lift.
d. Steam generator safety valves shall not lift.
e. Safety injection is not initiated.

14.2.12.3.38 Shutdown and Maintenance of Hot Standby External to

the Control Room (S-070014)

14.2.12.3.38.1 Objectives

To demonstrate, using a plant procedure, that the plant can be taken from >

10 percent power to hot standby conditions, and verify that the plant can be maintained in hot standby for at least 30 minutes with a minimum shift crew,

using controls and instrumentation external to the control room.

14.2.12.3.38.2 Prerequisites

a. Required component testing and instrument calibration are

complete.

b. Required electrical power supplies and control circuits

are operational.

c. The plant is at normal operating conditions at >

10 percent power.

d. The authority and responsibility of the control room

observers has been established and is specified in this procedure.

14.2.12.3.38.3 Test Method

a. The plant is taken from >

10 percent power to hot standby conditions, using a plant procedure, minimum shift crew, and controls and instrumentation external to the control

room.

b. Hot standby conditions are maintained for at least 30

minutes.

14.2-186 Rev. 1 WOLF CREEK

c. All actions performed by the control room observers is documented within this procedure for use in evaluating

their impact on the test results.

14.2.12.3.38.4 Acceptance Criteria

The plant can be taken from >

10 percent power to hot standby conditions which are maintained for >

30 minutes, using a plant procedure, minimum shift crew, and controls and instrumentation external to the control room.

14.2.12.3.39 Power Ascension Thermal Expansion and Dynamic Test (S-070015)

14.2.12.3.39.1 Objectives

a. To demonstrate during specified power ascension

transients that the systems' monitored points respond in

accordance with design.

b. To demonstrate during the heatup to full power

temperature that the systems' piping can expand without obstruction and that the expansion is in accordance with design. Also, during the subsequent cooldown to ambient

temperature, the piping returns to its cold position in

accordance with system design.

14.2.12.3.39.2 Prerequisites

a. Reference points for measurement of the systems are

established.

b. Power ascension testing is in progress.
c. All subject systems are available for the specified

dynamic operations.

d. Required instrument calibration is complete.
e. A preservice inspection of the associated piping snubbers

has been completed within 6 months.

14.2.12.3.39.3 Test Method

a. Record cold baseline data.
b. Obtain measurement data at various specified temperature

plateaus.

14.2-187 Rev. 1 WOLF CREEK

c. The systems are aligned for the specified dynamic operation.
d. The specified dynamic event of pump operation, valve

operation, etc., is initiated, and the system is monitored for response.

e. On completion of cooldown to ambient temperature, obtain

measurement data.

14.2.12.3.39.4 Acceptance Criteria

a. There shall be no evidence of blocking of the thermal

expansion of any piping or components, other than by

design.

b. The total stresses shall not exceed applicable code

limits.

c. Spring hanger movement must remain within the hot and

cold set points, snubber swing clearance remains

satisfactory., and snubbers must not become fully

retracted or expanded.

d. Piping and components must return to their baseline

position on cooldown in accordance with system design.

e. The measured thermal movement shall be within 25 percent

of the analytical value or +

0.25 inch, whichever is greater.

14.2.12.3.40 Biological Shield Testing (S-070016)

14.2.12.3.40.1 Objectives

a. To measure and record the neutron and gamma ray radiation

levels in accessible areas of the plant where radiation

levels above background are anticipated.

b. To determine locations if any, where shielding is

deficient.

c. To ensure that plant personnel are not subjected to overexposure from radiation as a result of inadequate shielding.

14.2.12.3.40.2 Prerequisites

a. Required instrument calibration is complete.

14.2-188 Rev. 1

WOLF CREEK

b. Appropriate reactor power levels are attained.

14.2.12.3.40.3 Test Method

Neutron and gamma ray surveys are conducted in each of the following reactor power level ranges.

Test  % Reactor Power Range Preoperational Shield Tests <

0 Low Power Tests 0-5

Intermediate Power Tests 5-50

High Power Tests 50-100

14.2.12.3.40.4 Acceptance Criteria

Neutron and gamma ray radiation surveys in all accessible areas of the plant

where radiation levels above background are anticipated reveal no shielding

deficiencies; or identify and implement appropriate administrative controls in

accordance with 10 CFR 20 for the areas determined to be radiation areas.

14.2.12.3.41 Loss of Heater Drain Pump Test (S-070017)*

14.2.12.3.41.1 Objectives To verify proper nuclear plant response to a loss of heater drain pump

accident.

14.2.12.3.41.2 Prerequisites

The plant is operating at steady state conditions at 90-percent power.

14.2.12.3.41.3 Test Method

The heater drain pumps are tripped and plant variables are recorded, along with

values observed on the normal plant instrumentation, during the transient for

those parameters required.

_______________________

  • This test was performed at Callaway only, with the consent of

the NRC, as Callaway and Wolf Creek have identical Heater Drain

Systems.

14.2-189 Rev. 1 WOLF CREEK 14.2.12.3.41.4 Acceptance Criteria

The following acceptance criteria are to be used to determine successful test

completion. Failure to meet these criteria does not constitute a need for

stopping the test program, but correction of any deficiencies should be accomplished as required, consistent with the current plant schedule.

a. Reactor and turbine must not trip.
b. Safety injection is not initiated.
c. Neither steam generator atmospheric relief valves nor safety valves shall lift.
d. Neither pressurizer relief valves nor safety valves shall

lift.

e. No manual intervention shall be required to bring plant conditions to steady state.

14.2.12.3.42 Calibration of Steam and Feedwater Flow

Instrumentation at Power Test (S-070018)

14.2.12.3.42.1 Objectives

a. To calibrate the steam flow transmitters against feed-

water flow.

b. To perform a cross-check verification of all signals indicating feedwater and steam flow.

14.2.12.3.42.2 Prerequisites

a. Test equipment, including transmitters, has been

calibrated for expected ranges of plant conditions.

b. The plant shall be at steady state conditions for each

power level at which testing is performed.

14.2.12.3.42.3 Test Method

At 30 and 50 percent power, perform Step a if the steam flow/ feedwater flow

mismatch alarm actuates. At 75 and 100 percent power, perform Steps a and b.

a. Verify calibration of the steam flow by comparing steam

flow signal to referenced feedwater flow.

14.2-190 Rev. 13 WOLF CREEK

b. Compare, using plots, the steam and feedwater flow values to determine if recalibration is necessary prior to the

next power escalation.

14.2.12.3.42.4 Acceptance Criteria

a. Steam flow/feedwater flow mismatch alarm does not actuate

at 30, 50, 75, and 100 percent power.

b. Steam flow indication should be within +

4 percent of feedwater flow panel indicator at 75 and 100 percent power.

c. The test feedwater flow instrument versus plant feed-water flow instrument and plant steam flow instrument

curves should be within +

2.5 percent and +

3.0 percent of their respective ideal curves at 75 and 100 percent power.

14.2.12.3.43 Natural Circulation Test (S-090024)*

14.2.12.3.43.1 Objectives

To demonstrate the length of time required to stabilize natural circulation; to

demonstrate core flow distribution during natural circulation using incore

thermocouples.

14.2.12.3.43.2 Prerequisites

a. Required low power physics testing has been completed.
b. Required instrumentation is installed and calibration

complete.

c. The plant is operating at steady state conditions at 3

percent power.

14.2.12.3.43.3 Test Method

All reactor coolant pumps are simultaneously tripped while at 3 percent rated

power. The transients are monitored and establishment of natural circulation

verified.

  • Due to similar plant design for Callaway and Wolf Creek, the

NRC allowed WCGS to use Callaway Natural Circulation test data

and pertinent results.

14.2-191 Rev. 1 WOLF CREEK 14.2.12.3.43.4 Acceptance Criteria Natural circulation has been demonstrated. The measured core T as a function of core power under natural circulation conditions is no greater than the

limiting reactor coolant system T based on design requirements.

14.2-192 Rev. 1

WOLF CREEK TABLE 14.2-1 SAFETY-RELATED PREOPERATIONAL TEST PROCEDURES Test Abstract Test Number Title USAR Section S-03AB01 Steam Dump System Preoperational Test 14.2.12.1.1

SU3-AB02 Main Steam Safety Valve Test 14.2.12.1.2

S-03AB03 Main Steam Line Isolation Valve Test 14.2.12.1.3 S-03AB04 Main Steam System Preoperational Test 14.2.12.1.4 S-03AE01 Main Feedwater System Preoperational

Test 14.2.12.1.5 S-03AE02 Steam Generator Level Control Test 14.2.12.1.6 S-03AL01 Auxiliary Feedwater Motor-Driven Pump

and Valve Preoperational Test 14.2.12.1.7 SU3-AL02 Auxiliary Feedwater Turbine-Driven Pump and Valve Preoperational Test 14.2.12.1.8

SU3-AL03 Auxiliary Feedwater Motor-Driven Pump Endurance Test 14.2.12.1.9 S-03AL04 Auxiliary Feedwater System Water

Hammer Test 14.2.12.1.10 SU3-AL05 Auxiliary Feedwater Turbine-Driven Pump Endurance Test 14.2.12.1.11

S-03BB01 Reactor Coolant Pump Initial Operation 14.2.12.1.12 SU3-BB02 PRT Cold Preoperational Test 14.2.12.1.13 SU3-BB03 RTD Bypass Flow Measurement 14.2.12.1.14

S-03BB04 Pressurizer Pressure Control Test 14.2.12.1.15 S-03BB05 Reactor Coolant System Hot Preoperational Test 14.2.12.1.16

S-03BB06 Thermal Expansion 14.2.12.1.17 d-03BB07 Pressurizer Level Control Test 14.2.12.1.18 SU3-BB08 Pressurizer Heater and Spray Capability

Test 14.2.12.1.19 SU3-BB09 Reactor Coolant System Flow Measurement Test 14.2.12.1.20

SU3-BB10 Reactor Coolant System Flow Coastdown Test 14.2.12.1.21 S-03BB11 Reactor Coolant System Hydrostatic Test 14.2.12.1.22

SU3-BB12 Pressurizer Continuous Spray Flow Verification Test 14.2.12.1.23 S-03BB13 Pressurizer Relief Valve and PRT Hot

Preoperational Test 14.2.12.1.24 S-03BB14 Reactor Coolant Loop Vibration Surveillance Test 14.2.12.1.25

SU3-BB15A Leak Detection System Preoperational Test 14.2.12.1.26 SU3-BB15B Leak Detection System Preoperational

Test 14.2.12.1.27 S-03BB16 RTD/TC Cross Calibration 14.2.12.1.28 Rev. 0 WOLF CREEK TABLE 14.2-1 (Sheet 2)

Test Number Title USAR Section S-03BG01 Chemical and Volume Control System Major Component Test 14.2.12.1.29 SU3-BG02 Seal Injection Preoperational Test 14.2.12.1.30 SU3-BG03 Charging System Preoperational Test 14.2.12.1.31 SU3-BG04 Boron Thermal Regeneration System Preoperational Test 14.2.12.1.32

SU3-BG05 Boric Acid Blending System Preopera-tional Test 14.2.12.1.33 S-03BG06 Chemical and Volume Control System

Hot Preoperational Test 14.2.12.1.34 SU3-EC01 Fuel Pool Cooling and Cleanup System Preoperational Test 14.2.12.1.35

S-03EC02 Spent Fuel Pool Leak Test 14.2.12.1.36 SU3-EF01 Essential Service Water System Pre-operational Test 14.2.12.1.37

SU3-EF02 Essential Service Water Pump Preopera-tional Test 14.2.12.1.37 S-03EG01 Component Cooling Water System Pre-

operational Test 14.2.12.1.38 SU3-EJ01 Residual Heat Removal System Cold Pre-operational Test 14.2.12.1.39

SU3-EJ02 Residual Heat Removal System Hot Preoperational Test 14.2.12.1.40 SU3-EM01 Safety Injection System Cold Pre-

operational Test 14.2.12.1.41 SU3-EM02 Safety Injection Flow Verification Test 14.2.12.1.42 SU3-EM03 Safety Injection Check Valve Test 14.2.12.1.43 SU3-EM04 Boron Injection Tank and Recirculation Pump Test 14.2.12.1.44 S-03EN01 Containment Spray System Nozzle Air Test 14.2.12.1.45 SU3-EN02 Containment Spray System Preoperational Test 14.2.12.1.46

S-03EP01 Accumulator Testing 14.2.12.1.47 SU3-FC01 Auxiliary Feedwater Pump Turbine Preoperational Test 14.2.12.1.48

SU3-GD01 Essential Service Water Pumphouse HVAC Preoperational Test 14.2.12.1.49 SU3-GF01 Miscellaneous Building HVAC System

SU3-GF02 Preoperational Tests SU3-GF03 14.2.12.1.50 S-03GG01 Fuel Building HVAC System Preoperational

Test 14.2.12.1.51 SU3-GK01 Control Building HVAC System Preopera-tional Test 14.2.12.1.52

SU3-GL01 Auxiliary Building HVAC System Pre-operational Test 14.2.12.1.53 S-03GM01 Diesel Generator Building HVAC Pre-

operational Test 14.2.12.1.54 Rev. 3 WOLF CREEK TABLE 14.2-1 (Sheet 3)

Test Number Title USAR Section SU3-GN01 Containment Cooling System Preoperational Test 14.2.12.1.55 S-03GN02 CRDM Cooling Preoperational Test 14.2.12.1.56 SU3-GP01 Integrated Containment Leak Rate Test 14.2.12.1.57 SU3-GP02 Reactor Containment Structural Integ-

rity Acceptance Test 14.2.12.1.58 S-03GS01 Post-Accident Hydrogen Removal System Preoperational Test 14.2.12.1.59

S-03GT01 Containment Purge System HVAC Pre-operational Test 14.2.12.1.60 S-03HA01 Gaseous Radwaste System Preoperational

Test 14.2.12.1.61 S-03JE01 Emergency Fuel Oil System Preoperational Test 14.2.12.1.62

SU3-KE01 Spent Fuel Pool Crane Preoperational Test 14.2.12.1.63 SU3-KE02 New Fuel Elevator Preoperational Test 14.2.12.1.64

SU3-KE03 Fuel Handling and Storage Preoperational Test 14.2.12.1.65 SU3-KE04 Fuel Transfer System Preoperational

Test 14.2.12.1.66 SU3-KE05 Refueling Machine and RCC Change Fixture Preoperational Test 14.2.12.1.67

S-03KE06 Refueling Machine Indexing Test 14.2.12.1.68 SU3-KE07 Fuel Handling System Integrated Preoperational Test 14.2.12.1.69

S-03KJ01 Diesel Generator Mechanical Preopera-tional Test 14.2.12.1.70 S-03NB01 4160-V (Class IE) System Preoperational

Test 14.2.12.1.71 S-03NE01 Diesel Generator Electrical Preopera-tional Test 14.2.12.1.72

SU3-NF01 Integrated Control Logic Test 14.2.12.1.73 S-03NF02 LOCA Sequencer Preoperational Test 14.2.12.1.74 S-03NF03 Shutdown Sequencer Preoperational Test 14.2.12.1.75

S-03NG01 480-V (Class IE) System Preoperational Test 14.2.12.1.76 SU3-NG02 480-V Class IE System (ESW) Preopera-

tional Test 14.2.12.1.77 S-03NK01 125-V (Class IE) DC System Preopera-tional Test 14.2.12.1.78

S-03NN01 Instrument AC System (Class IE) Pre-operational Test 14.2.12.1.79 SU3-SA01 Engineered Safeguards (NSSS) Preopera-

tional Test 14.2.12.1.80 Rev. 0 WOLF CREEK TABLE 14.2-1 (Sheet 4)

Test Number Title USAR Section SU3-SA02 Engineered Safeguards (BOP) Pre-operational Test 14.2.12.1.81 SU3-SA03 Engineered Safeguards Verification Test 14.2.12.1.82 S-03SB01 Reactor Protection System Logic Test 14.2.12.1.83 S-03SJ01 Primary Sampling System Preoperational Test 14.2.12.1.84

S-03SP01 Process Radiation Monitoring System Preoperational Test 14.2.12.1.85 SU3-0004 Power conversion and ECCS Systems

Thermal Expansion Test 14.2.12.1.86 S-030005 Power Conversion and ECCS Systems Dynamic Test 14.2.12.1.87

SU3-0006 HEPA Filter Test 14.2.12.1.88 S-030008 Cooldown from Hot Standby External to the Control Room 14.2.12.1.89

S-030009 Compressed Gas Accumulator Testing 14.2.12.1.90 Rev. 0 WOLF CREEK TABLE 14.2-2 NONSAFETY-RELATED PREOPERATIONAL TESTS Test Number Title USAR Section S-04AC02 Turbine Trip Test 14.2.12.2.1 S-04AC03 Turbine System Cold Test 14.2.12.2.2 S-04AD01 Condensate System Preoperational Test 14.2.12.2.3 S-04AF01 Secondary Vent and Drain System Pre-operational Test 14.2.12.2.4 S-04AQ01 Condensate and Feedwater Chemical Feed System Preoperational Test 14.2.12.2.5 S-04BL01 Reactor Makeup Water System Preopera-tional Test 14.2.12.2.6 S-04CG01 Condenser Air Removal System Pre-operational Test 14.2.12.2.7

SU4-DA01 Circulating Water System Preoperational Test 14.2.12.2.8 S-04EA01 Service Water System Preoperational Test 14.2.12.2.9 S-04EB01 Closed Cooling Water System Preopera-tional Test 14.2.12.2.10 SU4-FP03 Fire Protection System Preoperational Test 14.2.12.2.11 S-04GH01 Radwaste Building HVAC System Pre-operational Test 14.2.12.2.12 SU8-GP01 Local Containment Leak Rate Test 14.2.12.2.13 S-04HB01 Liquid Radwaste System Preoperational Test 14.2.12.2.14

SU4-HB02 Waste Evaporator Preoperational Test 14.2.12.2.15 S-04HC01 Solid Waste System Preoperational Test 14.2.12.2.16 S-04HC02 Solid Waste Filter Handling System Preoperational Test 14.2.12.2.17 SU4-HC03 Resin Transfer Preoperational Test 14.2.12.2.18 SU4-KC01A Fire Protection System (Water) Pre-

SU4-KC01B operational Test 14.2.12.2.19 S-04KC02 Fire Protection System (Halon) Pre-operational Test 14.2.12.2.20 S-04KC03 Fire Protection System Detection and Alarm Preoperational Test 14.2.12.2.21 S-04LE01 Oily Waste System Preoperational Test 14.2.12.2.22

SU4-LF01 Floor and Equipment Drain System Pre-operational Test 14.2.12.2.23 S-04PA01 13.8-kV System Preoperational Test 14.2.12.2.24

S-04PB01 4,160-V (Non-Class IE) System Pre-operational Test 14.2.12.2.25 S-04PG01 480-Volt (Non-Class IE) System Pre-

operational Test 14.2.12.2.26 Rev. 0 WOLF CREEK TABLE 14.2-2 (Sheet 2)

Test Number Title USAR Section S-04PJ01 250-V DC System Preoperational Test 14.2.12.2.27 S-04PK01 125-V (Non-Class IE) DC System Pre-

S-04PK02 operational Test 14.2.12.2.28 S-04PN01 Instrument AC (Non-Class IE) System Pre-operational Test 14.2.12.2.29 S-04QD01 Emergency Lighting System Preopera-tional Test 14.2.12.2.30 S-04QF01 Public Address System Preoperational Test 14.2.12.2.31 S-04QJ01 Heat Tracing Freeze Protection System Preoperational Test 14.2.12.2.32 S-04RM01 Secondary Sampling System Preoperational Test 14.2.12.2.33 S-04SD01 Area Radiation Monitoring Preoperational Test 14.2.12.2.34 S-04SG01 Seismic Monitoring Instrumentation System Preoperational Test 14.2.12.2.35 SU4-SQ02 Loose Parts Monitoring System Test 14.2.12.2.36 SU8-0007 Plant Performance Test 14.2.12.2.37 S-090023 Electrical Distribution System Voltage

Verification Test 14.2.12.2.38 Rev. 0 WOLF CREEK TABLE 14.2-3 INITIAL STARTUP TEST Test Number Title USAR Section S-07AB01 Automatic Steam Generator Level Control 14.2.12.3.1 SU7-AB02 Dynamic Automatic Steam Dump Control 14.2.12.3.2 S-07BB01 RTD Bypass Flow Measurement 14.2.12.3.3 S-07BB02 Pressurizer Heater and Spray Capability Test 14.2.12.3.4 S-07BB03 Reactor Coolant System Flow Measurement 14.2.12.3.5 SU7-BB04 Reactor Coolant System Flow Coastdown Test 14.2.12.3.6 S-07BB05 Pressurizer Contiuous Spray Flow Verification 14.2.12.3.7 S-07BB06 RTD/TC Cross Calibration 14.2.12.3.8

S-07SC01 Core Loading Instrumentation and Neutron Source Requirements 14.2.12.3.9 S-07SC03 Thermal Power Measurement and Statepoint Data Collection 14.2.12.3.10 SU7-SE01 Nuclear Instrumentation System Test 14.2.12.3.11 S-07SE02 Operational Alignment of Nuclear Instru-mentation 14.2.12.3.12 S-07SE03 Axial Flux Difference Instrumentation Calibration 14.2.12.3.13 S-07SF01 Control Rod Drive Mechanism Operational Test 14.2.12.3.14 S-07SF02 Rod Control System 14.2.12.3.15

SU7-SF03 Rod Drop Time Measurement 14.2.12.3.16 SU7-SF04 Rod Position Indication System 14.2.12.3.17 S-07SF05 Automatic Reactor Control System 14.2.12.3.18 S-07SR01/ Incore Flux Mapping S-07SR02 14.2.12.3.19 S-07SR03/ Incore Instrumentation Test

S-07SR04 14.2.12.3.20 S-07SF06 Operational Alignment of Process Temperature Instrumentation 14.2.12.3.21 S-07SF07 Startup Adjustments of Reactor Control System 14.2.12.3.22 S-07SF08 RCCA or Bank Worth Measurement at

Zero Power 14.2.12.3.23 SU7-SF09 RCCA or Bank Worth Measurement at Power 14.2.12.3.24

S-07SJ01 Reactor Systems Sampling for Core Load 14.2.12.3.25 SU7-0001 Initial Core Loading 14.2.12.3.26

S-070002 Inverse Count Rate Ratio Monitoring for Core Loading 14.2.12.3.27 Rev. 0 WOLF CREEK TABLE 14.2-3 (Sheet 2)

Test Number Title USAR Section S-070003 Inverse Count Rate Ratio Monitoring for Approach to Initial Criticality 14.2.12.3.28

S-070004 Initial Criticality 14.2.12.3.29 S-070005 Determination of Core Power Range for Physics Testing 14.2.12.3.30 S-070006 Boron Endpoint Determination 14.2.12.3.31 S-070007 Isothermal Temperature Coefficient Measurement 14.2.12.3.32 S-070008 Power Coefficient Determination 14.2.12.3.33 S-070009 Load Swing Tests 14.2.12.3.34 S-070010 Large Load Reduction Test 14.2.12.3.35 S-070011 Plant Trip from 100 Percent Power 14.2.12.3.36 S-070012 Rods Drop and Plant Trip 14.2.12.3.37 S-070014 Shutdown and Maintenance of Hot Standby External to the Control Room 14.2.12.3.38 S-070015 Power Ascension Thermal Expansion and Dynamic Test 14.2.12.3.39 S-070016 Biological Shield Testing 14.2.12.3.40 S-070017 Loss of Heater Drain Pump Test 14.2.12.3.41 S-070018 Calibration of Steam and Feedwater

Flow Instrumentation at Power Test 14.2.12.3.42 S-090024 Natural Circulation Test 14.2.12.3.43 Rev. 0

Retrieved from "https://kanterella.com/w/index.php?title=ML17151B013&oldid=752260"