ML20247H403
| ML20247H403 | |
| Person / Time | |
|---|---|
| Site: | 05200002, 05000470 |
| Issue date: | 03/30/1989 |
| From: | ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | |
| Shared Package | |
| ML20247G537 | List:
|
| References | |
| NUDOCS 8904040452 | |
| Download: ML20247H403 (156) | |
Text
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EFFECTIVE PAGE LISTING CHAPTER 14 Table of contents
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14.2-28 8904040452 gjgg$j70 Amendment E DR ADOCK PDR December 30, 1988
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TABLE OF CONTENTS 1
CHAPTER 14 Section Egbiect Pace No.
14.0 INITIAL TEST PROGRAM 14.1-1 14.1 SPECIFIC INFORMATION TO BE INCLUDED 14.1-1 IN PSAR 14.2 SPECIFIC INFORMATION TO BE INCLUDED 14.2-1 IN FSAR 14.2.1
SUMMARY
OF TEST PROGRAM AND 14.2-1 E
OBJECTIVES.
14.2.1.1 Summary of the Startuo Test 14.2-1 i
Procram 14.2.1.1.1 Prerequisite Testing 14.2-1
[ ~s Phase I - Preoperational Testing 14.2-2 14.2.1.1.2
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14.2.1.1.3 Phase II - Fuel Loading and 14.2-2
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Post-core Hot Functional Testing 14.2.1.1.4 Phase III - Initial Criticality 14.2-3 and Low Power Physics Testing 14.2.1.1.5 Phase IV - Power Ascension Testing 14.2-3 14.2.2 ORGANIZATION AND STAFFING 14.2-3 l
14.2.2.1 Manacement Organization 14.2-3 14.2.2.2 Systems Encineer 14.2-4 14.2.2.3 Startuo Enaineer 14.2-5 14.2.2.4 NPM Vendor 14.2-6 14.2.2.5 Architect Encineer (A/E) 14.2-6 14.2.2.6 Other Technical Specialties 14.2-6 14.2.2.7 Test Workino Groun 14.2-6 14.2.2.8 Plant Review Board 14.2-7 14.2.2.9 NPM Vendor Site Sta'rtuo 14.2-7
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Organization Amendment E i
December 30, 1988
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TABLE OF CONTENTS (Cont'd)
CEAPTER 14 Section Hybiect Pace No.
14.2.2.10 A/E Site Startuo Organization 14.2-7 E
14.2.2.11 Qualification 14.2-8 14.2.2.12 Utilization of the Plant Staff 14.2-8 14.2.3 TEST PROCEDURES 14.2-8 14.2.3.1 Prerequisite Test Procedure 14.2-9 PreparatiGD 14.2.3.2 Test Procedure Preparation 14.2-9 14.2.3.3 Snecial Test Procedures 14.2-10 14.2.4 CONDUCT OF TEST PROGRAM (PHASES I 14.2-10 THROUGH IV) 14.2.4.1 Sian-Off Provisions 14.2-11 14.2.4.2 Maintenance / Modification 14.2-11 Procedures 14.2.4.3 Test Performance 14.2-11 14.2.5 REVIEW, EVALUATION, AND APPROVAL OF 14.2-12 PHASES I THROUGH IV TEST RESULTS 14.2.6 TEST RECORDS 14.2-13 l
14.2.7 CONFORMANCE OF TEST PROGRAMS 14.2-13 WITH REGULATORY GUIDES STANDARDS 14.2.7.1 Reculatory Guide 1.68. Initial 14.2-13 Test Procrams for Water-Cooled Reactor Power Plants 14.2.7.1.1 Reference Appendix A, Section 2.6 14.2-14 14.2.7.1.2 Reference Appendix A, Appendix C, 14.2-14 Section 3 14.2.7.1.3 Reference Appendix C, Section 4 14.2-14 14.2.7.1.4 Reference Appendix A, Section 5.a 14.2-15 Amendment E ii December 30, 1988
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TABLE OF CONTENTS (Cont'd)
CHAPTER 14 I
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Section Subiect Face No.
14.2.7.1.5 Reference Appendix A, Section 5.1 14.2-15 14.2.7.1.6 Reference Appendix A, Section m.m 14.2-15 E
14.2.7.1.7 Reference Appendix A, Section k.k 14.2-15 l
14.2.7.2 Reculatory Guide 1.79.
14.2-15 Preocerational Testina of Emercency Core Coolina Systems for Pressurized Water Reactors 14.2.7.3 Reculatory Guide 1.68.2.
14.2-16 Initial Startuo Test Procram E
to Demonstrate Remote Shutdown Capability for Water Cooled Nuclear Power Plants j
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7-- g 14.2.8 UTILIZATION OF REACTOR OPERATING 14.2-16 AND TESTING EXPERIENCE IN DEVELOPMENT
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OF INITIAL TEST PROGRAM 14.2.9 TRIAL USE OF PLANT OPERATING AND 14.2-16 EMERGENCY PROCEDURES 4.2.10 INITIAL FUEL LOADING AND INITIAL 14.2-16 CRITICALITY 14.2.10.1 Initial Fuel Loadina 14.2-16 l
l 14.2.10.1.1 Safety Loading Criteria 14.2-18 E
14.2.10.1.2 Fuel Loading Pr7cedure 14.2-19 14.2.10.2 Initial Criticality 14.2-19 14.2.10.2.1 Safe Criticality Criteria 14.2-20 14.2.11 TEST PROGRAM SCHEDULE 14.2-20 14.2.11.1 Testina Secuence 14.2-21 14.2.12 INDIVIDUAL TEST DESCRIPTIONS 14.2-21 l
14.2.12.1 Preonerational Tests 14.2-21 p-~)
14.2.12.1.1 Reactor Coolant Pump Motor 14.2-21 Initial Operation l
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TABLE OF CONTENTS (Cont'd)
CHAPTER 14 Section gyhject Pace No.
14.2.12.1.2 Reactor Coolant System Test 14.2-22 14.2.12.1.3 Pressurizer Safety Valve Test 14.2-23 14.2.12.1.4 Pressurizer Pressure and 14.2-24 Level Control System 14.2.12.1.5 CVCS Letdown Subsystem Test 14.2-26 14.2.12.1.6 CVCS Purification Subsystem Test 14.2-27 14.2.12.1.7 Volume Control Tank Subsystem Test 14.2-28 14.2.12.1.8 CVCS Charging Subsystem Test 14.2-30 14.2.12.1.9 Chemical Addition Subsystem Test 14.2-31 14.2.12.1.10 Reactor Drain Tank Subsystem Test 14.2-32 14.2.12.1.11 Equipment Drain Tank Subsystem 14.2-34 Test 14.2.12.1.12 Boric Acid Batching Tank 14.2-35 Subsystem Test 14.2.12.1.13 Concentrated Boric Acid Subsystem 14.2-36 Test 14.2.12.1.14 Reactor Makeup Subsystem Test 14.2-37 14.2.12.1.15 Holdup Subsystem Test 14.2-39 14.2.12.1.16 Boric Acid Concentrator 14.2-40 Subsystem Test 14.2.12.1.17 Gas Stripper Subsystem Test 14.2-41 14.2.12.1.18 Boronometer Subsystem Test 14.2-42 14.2.12.1.19 Letdown Process Radiation 14.2-43 Monitor Subsystem Test lE 14.2.12.1.20 Gas Stripper Effluent 14.2-44 Radiation Monitor Subsystem Test 14.2.12.1.21 Shutdown Cooling Subsystem Test 14.2-45 14.2.12.1.22 Safety Injection Subsystem Test 14.2-46 14.2.12.1.23 Safety Injection Tank Subsystem 14.2-48 E
Test 14.2.12.1.24 Megawatt Demand Setter (MDS) 14.2-49 Subsystem Test i
14.2.12.1.25 Engineered Safety Features-14.2-50 j
Component Control System Test E
j 14.2.12.1.26 Plant Protection System (PPS) 14.2-52 1
Test 14.2.12.1.27 Ex-core Nuclear Instrumentation 14.2-54 l
System Test l
14.2.12.1.28 Fixed In-core Nuclear Signal 14.2-55 lE Channel Test l
14.2.12.1.29 Control Element Drive Mechanism 14.2-56 Control System (CEDMCS) Test 1
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TABLE OF CONTENTS (Cont'd)
CHAPTER 14 l
Section Egbiect Pace No.
l 14.2.12.1.30 Reactor Regulating System (RRS) 14.2-57 Test 14.2.12.1.31 Steam Bypass Control System 14.2-58 (SBCS) Test 14.2.12.1.32 Feedwater Control System (FWCS) 14.2-59 Test i
14.2.12.1.33 Core Operating Limit Supervisory 14.2-60 System (COLSS) Test 14.2.12.1.34 Reactor Power Cutback System 14.2-61 l
(RPCS) Test 14.2.12.1.35 Fuel' Equipment '.'est 14.2-62 14.2.12.1.36 Emergency Feedwater System 14.2-64 E
14.2.12.1.37 Reactor Coolant System Hydrostatic 14.2-65 Test 14.2.12.1.38 CEDM Cooling System 14.2-66 c
14.2.12.1.39 Safety Depressurization Subsystem 14.2-67 I
Test
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14.2.12.1.40 Containment Spray System 14.2-69 14.2.12.1.41 Integrated Engineered Safety 14.2-70 i
Features / Loss of Power Test l
14.2.12.1.42 In-containment Refueling Water 14.2-71 Storage Tank Subsystem 14.2.12.1.43 Internals Vibration Monitoring 14.2-72 System 14.2.12.1.44 Loose Part Monitoring System 14.2-73 14.2.12.1.45 Acoustic Leak Monitoring System 14.2-74 14.2.12.1.46 Data Processing System, and 14.2-76 Discrete Indication and Alarm System 14.2.12.1.47 Critical Function Monitoring (CFM) 14.2-77 14.2.12.1.48
' Pre-core Hot Functional Test 14.2-78 Controlling Document 14.2.12.1.49 Pre-core Instrument Correlation 14.2-79 14.2.12.1.50 Remote Shutdown Panel 14.2-80 14.2.12.1.51 Alternate Protection System 14.2-81 14.2.12.1.52 Pre-core Test Data Record 14.2-82 14.2.12.1.53 Pre-core Reactor Coolant 14.2-83 System Expansion Measurements 14.2.12.1.54 Pre-core Reactor Coolant and 14.2-84 Secondary Water Chemistry Data 14.2.12.1.55 Pre-core Pressurizer Performance 14.2-85 f-(
)
14.2.12.1.56 Pre-core Control Element 14.2-87 l
\\d Drive Mechanism Performance Amendment E j
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TABLE OF CONTENTS (Cont'd)
CHAPTER 14 Dection g32Aject Pace No.
14.2.12.1.57 Pre-core Reactor Coolant System 14.2-88 Flow Measurements 14.2.12.1.58 Pre-core Reactor Coolant System 14.2-89 Heat Loss 14.2.12.1.59 Pre-core Reactor Coolant 14.2-91 System Leak Rate Measurement 14.2.12.1.60 Pre-core Chemical and volume 14.2-91 Control System Integrated Test 14.2.12.1.61 Pre-core Safety Injection 14.2-93 Check Valve Test i
14.2.12.1.62 Pre-core Boration/ Dilution 14.3-94 Measurements 14.2.12.1.63 Downcomer Feedwater System 14.2-95 Water Hammer Test 14.2.12.2 Post-core Hot Functional Tests 14.2-96 14.2.12.2.1 Post-core Hot Functional Test 14.2-96 Controlling Document E
14.2.12.2.2 Loose Parts Monitoring System 14.2-97 14.2.12.2.3 Post-core Reactor Coolant 14.2-98 System Flow Measurements 14.2.12.2.4 Post-core Control Element 14.2-99 Drive Mechanism Performance 14.2.12.2.5 Post-core Reactor and Secondary 14.2-101 Water Chemistry Data 14.2.12.2.6 Post-core Pressurizer Spray 14.2-102 Valve and Control Adjustments j
14.2.12.2.7 Post-core Reactor Coolant 14.2-103 j
System Leak Rate Measurement 14.2.12.2.8 Post-core In-core Instrumentation 14.2-104 l
Test l
14.2.12.2.9 Post-core Instrument Correlation 14.2-104 l
14.2.12.2.10 Acoustic Leak Monitoring System 14.2-105 E 14.2.12.3 Low Power Physics Tests 14.2-106 14.2.12.3.1 Low Power Biological Shield 14.2-106
- 14. 2-107 l E Survey Test i
14.2.12.3.2 Isothermal Tempera ~ture Coefficient j
Test j
14.2.12.3.3 Shutdown and Regulating CEA 14.2-108 Group Worth Test i
1 Amendment E vi December 30, 1988 I
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V TABLE OF CONTENTS (Cont'd)
CHAPTER 14 Section Subject Pace No.
14.2.12.3.4 Differential Boron Worth Test 14.2-109 14.2.12.3.5 Critical Boron Concentration Test 14.2-110 E
{
14.2.12.4 Power Ascension Tests 14.2-111 14.2.12.4.1 Variable Tavg (Isothermal 14.2-111 Temperature Coefficient and Power Coefficient) Test q
14.2.12.4.2 Unit Load Transient Test 14.2-112 j
14.2.12.4.3 Control Systems Checkout Test 14.2-113 1
14.2.12.4.4 Reactor Coolant and Secondary 14.2-114 Chemistry and Radiochemistry Test 14.2.12.4.5 Turbine Trip Test 14.2-115 14.2.12.4.6 Unit Load Rejection Test 14.2-116 14.2.12.4.7 Shutdown from Outside the 14.2-117 Control Room Test j
r 14.2.12.4.8 Loss of Offsite Power Test 14.2-118 i
\\s 14.2.12.4.9 Biological Shield Survey Test 14.2-120lE 14.2-119 14.2.12.4.10 Steady-State Core Performance Test 14.2.12.4.11 Intercomparison of PPS, Core 14.2-121 Protection Calculator (CPC), DPS E
and DIAS Inputs 14.2.12.4.12 Verification of CPC Power 14.2-122 l
Distribution Related Constants i
Test 14.2.12.4.13 Main and Emergency Feedwater 14.2-124 Systems Test 14.2.12.4.14 CPC Verification 14.2-125 14.2.12.4.15 Steam Bypass Valve Capacity Test 14.2-126 1
14.2.12.4.16 In-core Detector Test 14.2-127 14.2.12.4.17 COLSS Verification 14.2-128
- 14. 2-13 0 l E 14.2.12.4.18 Baseline NSSS Integrity Monitoring 14.2-129 14.2.12.4.19 Natural Circulation Test 14.2.12.4.20 Reactor Power Cutback System 14.2-131 (RPCS) Tests E
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Amendment E vii December 30, 1988
CESSAR nutriem:u O
LIST OF TABLES CHAPTER 14 TAhle D_ubiect E
14.2-1 Preoperational Tests 14.2-2 Hot Functional Tests 14.2-3 Low Power Physics Tests 14.2-4 Power Ascension Tests 14.2-5 Power Ascension Tests 14.2-6 Physics (Steady-State) Test Acceptance Criteria Tolerances e
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Amendment E vili December 30, 1988 i
CESSAR Unincuia 14.0 IMIIJAL TEST PROGRAM 14.1 SPECIFIC INFORMATION TO BE INCLUDED IN PSAR E
This section is not applicable to this - Safety Analysis Report.
Sco Section 14.2 for a description of the initial test program.
r Amendment E 14.1-1 December 30, 1988
CESSARn % mn fO 14.2 SPECIFIC INFORMATION TO BE INCLUDED IN FSAR 14.2.1
SUMMARY
OF TEST PROGRAM AND OBJECTIVES 14.2.1.1 Summary of the StartuD Test Procram E
l l
The Startup Tot.t Program includes testing activities commencing with the completion of construction and installation and ending with the completion of the power ascension testing.
This test
]
program demonstrates that components and systems operate in accordance with design requirements and meet the requirements of 10 CFR 50, Appendix B,
Criterion XI.
The Startup Test Program results confirm that performance levels meet the operational l
safety requirements and verify the adequacy of component and system design and system operability over their operating ranges.
l It also aids in the establishment of baseline performance data I
and cerves to verify that normal operating and emergency procedures accomplish their intended purposes.
The Startup Test Program consists of Prerequisite Testing plus the following four phases:
A.
Phase I:
Preoperational Testing
[
B.
Phase II:
Fuel Loading and Post Core Hot Functional Testing
(
C.
Phase III:
Initial Criticality and Low Power Physics Testing D.
Phase IV:
Power Ascension Testing Specific Administrative Controls established for use during the Startup Program are addressed in the site-specific FSAR.
14.2.1.1.1 Prerequisite Testing Prerequisite Testing consists of tests and inspections required to assure construction is complete and that systems are ready for Phase I Testing.
Prerequisite testing verifies that construction activities associated with structures, components, and systems have been satisfactorily completed.
Prerequisite testing consists of preliminary tests and inspections which include, but are not limited to, initial instrument calibration, flushing, cleaning, circuit integrity and separation checks, hydrostatic pressure
- tests, and functional tests of components.
Delineation of specific prerequisite test requirements will be established in accordance with the site-specific administrative procedures.
J Amendment E 14.2-1 December 30, 1988
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E 14.2.1.1.2 Phase I - Preoperationti Testing Phase I - Preoperational Testing is performed to demonstrate that structures, systems, and components operate in accordance with design operating modes throughout the full design operating range.
Where required, simulated signals or inputs are used to demonstrate the full range of the systems that are used during normal operation.
Systems that are not used during normal plant operation, but must be in a state of readiness to perform safety functions, are checked under various modes and test conditions prior to fuel load.
Wheneve'r practical, these tests are performed under the conditions expected when the systems would be required to function.
When these conditions cannot be attained or appropriately simulated at the time of the test, the system is tested to the extent practical under the given conditions, with additional testing completed at a
time when appropriate conditions can be attained.
Preoperational Testing ensures that systems and equipment perform in accordance with the Safety Analysis Report.
Analysis of test results is made to verify that systems and components are performing satisfactorily, and if not, to provide a basis for recommended corrective action.
Upon completion of the specific preoperational testing, a series of integrated system
- tests, typically termed Pre-core Hot Functional
- Testing, are performed to verify proper systems operation prior to fuel Loading.
A listing of preoperational tests is provided in Table 14.2-1 and individual test descriptions are presented in Section 14.2.12.1.
A listing of pre-core Hot Functional tests is also provided in Table 14.2-1, 14.2.1.1.3 Phase II - Fuel Loading and Post-Core Hot Functional Testing Initial fuel loading starts after completion of the Preopera-tional Testing.
This phase of the initial test program provides a systematic process for safely accomplishing and verifying the initial fuel loadings.
Fuel loading is discussed in more detail in Section 14.2.9.1.
The Post-Core Hot Functional tests are performed following the completion of Initial Fuel Loading operations and prior to Initial Criticality.
The objectives of these tests are to provide additional assurances that plant systems necessary for Amendment E 14.2-2 December 30, 1988
CESSAR nainemou O
normal plant operation function as expected and to obtain performance data on core related systems and components.
Normal plant operating procedures, in so far as practical, are used to bring the plant from COLD SHUTDOWN conditions through HOT SHUTDOWN to Hot, Zero Power (HZP) conditions.
Testing normally proceeds directly to Initial criticality and the beginning of Low Power Physics Testing.
A list of Post-Core Hot Functional tests is provided in Table 14.2-2 and a description of each test is provided in Section 14.2.12.2.
14.2.1.1.4 Phase III - Initial Criticality and Low Power Physics Testing The Initial Criticality phase of the startup test program assures that criticality is achieved in a safe and controlled manner.
A description of the procedures followed during the approach to Initial Criticality is included in Section 14.2.9.2.
Following Initial Criticality, a series of Low Power Physics Tests is performed to verify selected core design parameters.
These tests serve to substantiate the Safety Analysis and Technical Specification,s.
They also demonstrate that core characteristics are within expected limits and provide data for O
characteristics bench-marking the design methodology used for predicting core later in life.
A list of the Low Power Physics Tests is provided in Table 14.2-3 and a description of each test is provided in Section 14.2.12.3.
14.2.1.1.5 Phase IV - Power Ascension Testing A series of Power Ascension Tests is conducted to bring the reactor to full power.
Testing is performed at plc.teaus of approximately 20, 50, 80, and 100% power and is intended to demonstrate that the facility operates in accordance with its design during steady state conditions
- and, to the extent practicable, during anticipated transients.
A list of the Power Asce'.sion Tests is provided in Table 14.2-4 and a description of each test is provided in Section 14.2.12.4.
14.2.2 ORGANIZATION AND STAFFING 14.2.2.1 Manacement Organization The site operator is responsible for appointing a senior level l
manager to a position of overall responsibility for defining the responsibilities, requirements, and interfaces necessary to safely and efficiently design, construct, start up, oper te, maintain and modify the nuclear power plant.
This person is 9
managers,as determined by the applicant.
assisted in the performance of these duties by other senior ictcl l
hondment E 14.2-3 December 30, 1988 j
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CESSAR 88Gncua O
Responsibilities associated with startup test programs include E
the preparation of test procedures, performance of applicable initial tests, and the preparation of approp?tiate test related documentation.
Test procedures are prepared by the cognizant Startup or Operations Departments (as applicable) with assistance from C-E, the architect engineer, and other vendors, as required.
These procedures are subject to review and comment by th'e appropriate project organizations.
The organizations assigned responsibility for conducting the tests are responsible for establishing specific requirements for scheduling and accomplishing testing, as well as for providing the necessary direction and coordination of groups having respon-sibility for specific activities in the startup test program.
The site operator is responsible for specifying a
startup organization for conducting the four phased test programs for the plant and for the technical and functional aspecce of the Startup program including the conduct of the Prerequisite and Phases I through IV programs.
These include the following responsibili-ties:
A.
Approval of Startup Administrative Control Procedures.
B.
Review and recommend approval of requests for modifications or changes required during the test program.
C.
Approval of p.
equisite and Phases I
through IV test procedures.
D.
Maintain lir ison with the project vendors through onsite representa? tes kteping them informed of status, problems, and support requirements.
The site operator's startup organization consists of System Engineers who have assigned responsibility for specific systems and Startup Engineers who have responsibility for testing evolntions and/or specific test.
14.fl.2.2 Systems Encrineer A.
Assigned responsibility for a specific system or subsystem.
B.
Provide technical guidance and assistance in the preparation of test procedures.
C.
Determine the testing requirements,
- sequence, and test method on assigned systems.
Recommend plant scheduling changes as necessary to support the testing effort.
I Amendnent E 14.2-4 December 30, 1988
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D.
Review test procedures, test procedure modifications, and test data in accordance with the site-specific administrative procedures.
E.
Recommend changes in plant design and or/ construction to facilitate testing, operation, and maintenance.
F.
Assist in the preparation of special reports concerning startup activities when required.
j G.
Review system discrepancies and deficiencies and the status of their resolution and correctio, for assigned systems.
14.2.2.3 Startup Encineer A.
Assures that assigned test procedures are written, reviewed, and approved in accordance with the site-specific administrative procedures.
B.
Assures all prerequisites for assigned tests are completed prior to the performance of the test.
O C.
Conducts assigned tests using and insuring compliance with approved test procedures.
D.
Keeps the Startup organization informed of the status of the preparation and performance of assigned tests.
E.
Suspends testing if the test cannot safely be conducted as written until the problem is resolved.
F.
Signs off individual steps in test procedures and ensures that required data are recorded.
G.
Assures that required startup materials, instruments, and consumables are available to support scheduled startup l
activities.
H.
Conducts pre-test and pre-shift startup briefings.
I.
Provides overall direction for all testing activities on each shift, as assip ed.
The site-specific startup organization will be augmented by contractor and vendor support personnel, as necessary.
These personnel may be integrated into the applicant's startup organization and function in any position designated by the site operator.
V Amendment E 14.2-5 December 30, 1988
CESSAR8Ebmu E
14.2.2.4 NPM Vendor C-E will provide onsite technical assistance during the installation, startup, testing, and initial operations of the NPM.
Through this effort, C-E aids and assures itself that the NPM is built, started, tested, and operated in conformance with design intent.
C-E onsite personnel provide technical assistance and act as technical liaison with the design headquarters to j
resolve problems within the NPM scope.
C-E provides a member of i
the Test Working Group.
C-E will review and comment on test 4
procedures involving the NPM scope of supply.
14.2.2.5 Architect Encrineer ( A/E)
The A/E will provide a representative to serve as a member of the Test Working Group and staff augmentation addressed in Section 14.2.2.3.
If the A/E is the Constructor, the A/E will coordinate the construction schedules with Test Program requirements and provide manpower support as needed to meet the schedule, to correct deficiencies, or to make repairs.
14.2.2.6 9ther Technical Specialties In addition to the staff described in Section 14.2.2.3, the t
utility will augment the Startup Staff from other contractors and vendors as deemed necessary.
14.2.2.7 Test Workina Group
)
The function of the Test Working Group (TWG) is to advise on the technical adequacy of the testing pro ~ ram.
The TWG functions include coordinating organizational
- r., possibility in areas of test procedure and test results
- leviews, evaluations, and approval recommendations.
The TWG is headed by a chairman appointed by the applicant and consists of the following minimum membership:
A.
Startup Representative B.
C-E Project Representative C.
Architect Engineer Project Representative D.
Engineering Department Representative E.
Operating Department Representative O
Amendment E 14.2-6 December 30, 1988
CESSAR En&b.
Ov The TWG members are chosen to provide expertise in specific' E
phases of testing.
As such, the composition of the TWG can be changed to obtain required expertise as the test program progresses.
14.2.2.8 Plant Review Board The Plant Review Board provides high level review and approval of the test program.
The membership of this group is specified by the applicant.
This group reviews the results of startup tests l
performed in accordance with procedures requiring their review.
Before fuel
- load, reviews and approves carryover of all i
prerequisite and Phase I tests to Phases II through IV.
The justification for their deferral includes a proposed schedule for their performance.
14.2.2.9 NPH Vendor Site Startup Organization C-E site startup test group will c 1sist of the Site Manager and an appropriate staff of startup consultants.
The startup group may be supplemented during the startup by others temporarily assigned to the site as needed.
C-E vendor representatives provide technical advice and consultation on matters concerning the design, operation, and testing of the NPM.
To achieve this objective, the startup site personnel will:
A.
Provide advice and consultation during the conduct of the entire test program.
B.
Provide assistance during the evaluation of test results.
C.
Resolve problems and inconsistencies utilizing internal engineering expertise and sub-vendor engineering personnel.
D.
Arrange for onsite representation as required.
E.
Provide a
representative to the appropriate site administrative groups or committees which review and approve all test procedures and changes thereto.
14.2.2.10 A/E Bite Startup OrcanizatioJ1 The A/E project organization provides technical advice and consultation on matters relating to the design, construction, operation, and testing of systems and equipment.
j Amendment E 14.2-7 December 30, 1988 i
l 1
]
e
o 1
CESSARn h mu 1
l 9l Accordingly, the A/E project organization is responsible for the following:
A.
Providing a
representative to the appropriate site administrative groups or committees which review and approve all test procedures and changes thereto.
B.
Reviewing test procedures pertaining to its scope of supply systems (e.g., balance of plant systems).
C.
Evaluating balance of plant test results.
D.
Coordinating resolution of problem areas by providing technical support and liaison with the Startup Organization and the A/E construction and design groups.
E.
Providing startup assistance as requested.
14.2.2.11 Qualifications The recommendations of Regulatory Guide 1.58 will be followed to insure that the qualification requirements, indoctrination, and training of persor.nel who perform inspections, examinations, and testing are accomplished and maintained.
14.2.2.12 Utilization of the Plant Staff The plant operating, maintenance, and engineering personnel are utilized to the extent practicable during the Startup Test Program.
The plant staff operates permanently installed and powered equipment for Phases I through IV and subsequent system tests.
Service personnel such as instrument, chemistry,
- computer, radiation protection, and maintenance personnel are used extensively to perform tests and inspections applicable to their field of specialization.
14.2.3 TEST PROCEDURES The site operator has the responsibility for assuring the preparation and designating the approval process for prerequisite and Phases I through IV test procedures.
Detailed procedure guidelines and procedures provided by the appropriate design organization are utilized to develop various system test procedures.
Thus, test procedures are based on requirements of system designers and applicable Regulatory G. ides.
O Amendment E 14.2-8 December 30, 1988
CESSAR 8HWicari:n
/%
E 14.2.3.1 Prerequisite Test Procedure-Preparation Test procedures will be prepared by the site operator using pertinent reference material provided by the appropriate design and/or vendor organizations.
Prerequisite test procedures contain (as a minimum) the following major topic areas:
A.
Purpcse/ Objective B.
References C.
Definitions and Abbreviations D..
Precautions and Limitations E.
Prerequisites (Initial Conditions)
F.
Instructions (Including Acceptance Criteria)
G.
Restoration i
Prerequisite test procedures are reviewed as specified in I
administrative procedures.
At the completion of these reviews, j
any required changes are incorporated into each test procedure by j
the originating organization.
14.2.3.2 Test Procedure Preparation l
l Detailed test procedures for Phases I through IV tests are prepared by the site operator.
Each test procedure is prepared using pertinent reference material provided by the appropriate design and vendor organizations, the
- FSAR, the Technical Specifications, and the applicable regulatory guides.
A test procedure is prepared for each specific system test to be performed during the four phases of the test program.
Each system test procedure contains-(as a minimum) the following major i
topic areas:
A.
Test Objectives B.
Acceptance Criteria l
C.
References D.
Prerequisites O
Amendment E 14.2-9 December 30, 1988
CESSAR EL"icariau
'O E.
System Initial Conditions F.
Environmental Conditions G.
Special Precautions H.
Detailed Procedure (Including Data Collection)
I.
Restoration J.
Documentation of Test Results Test procedures are reviewed as specified by the site-specific administrative control procedures.
At the completion of these reviews, any required changes are incorporated into each test
{
procedure by the originating organization.
14.2.3.3 Special Test Procedures Special test procedures may become necessary during the Phases I through IV test program for investigative purposes.
The preparation, review, and approval of these special procedures are governed by site-specific administrative control procedures.
Special test procedures that deal with nuclear safety are processed under the same controls as normal startup test procedures.
14.2.4 CONDUCT OF TEST PROGRAM (PHASES I THROUGH IV)
When a Phases I
through IV system test procedure has been i
released for performance, a Startup Engineer will be assigned responsibility for:
A.
Ensuring that prerequisites are satisfactorily met or i
allowable exceptions are noted in accordance with administrative procedures.
B.
Verifying that the testing is performed as required by the procedure.
The test is then performed by operating personnel or others in accordance with the approved test procedure.
The Operations Shift Supervisor is responsible for the safe operation of the plant during testing and may stop any system test in progress and place the plant in a safe condition.
Required data resulting from the test is compiled within the test procedure in specified data blanks, on specially prepared data
- sheets, or as otherwise specified by administrative control Amendment E 14.2-10 December 30, 1988-
)
)
J
CESSARnaibmu o
E procedures.
Personnel completing data forms or checklists will sign and date the forms.
Upon test completion, the test data is compared with the test acceptance criteria, and any discrepancies noted are resolved in accordance with applicable administrative procedures.
Once a procedure has been approved, procedure changes will be made in accordance with the provisions of the administrative procedures.
C-E will shall participate in the approval process of the NPM related procedures and shall review any proposed changes to approved NPM test procedures.
14.2.4.1 Sian-Off Provisions Each approved test procedure shall contain sign-off provision ~
for prerequisites and for all procedural steps.
The person responsible for the conduct of the test is responsible for l
signing and dating each data form in the spaces provided as the data is entered.
14.2.4.2 Maintenance / Modification Procedures Work authorization documents, controlled in accordance with the site operator procedures, are used to initiate maintenance and implement modifications on systems that are jurisdictionally turned over from the construction organization.
The work authorization document assigns an organization responsibility for the completion of the activity and specifies any retest requirements.
Upon completion of the activity, a copy of the signed-off form is returned to the responsible testing organization to ensure retest requirements are met.
Results of retests due to maintenance will be reviewed by the responsible Startup Engineer.
Results of retests due to modifications will be reviewed and approved in the same manner as those from the original tests.
14.2.4.3 Test Performance For Prerequisite and Phases I through IV testing, a Test Director will be designated.
The official copy of the test procedure shall be available in the test area during the performance of a preoperational or startup test.
The person conducting the test is charged with responsibility for performing the test in accordance with the approved test procedure.
If, during the performance of the test, it is determined that the test cannot be conducted as written, it is the responsibility of the person h
conducting the test to resolve the problem in accordance with
(,/
approved administrative control procedures.
Amendmant E 14.2-11 December 30, 1988
CESSAREna m O
E 14.2.5 REVIEW, EVALUATION, AND APPROVAL OF PHASES I THROUGH IV TEST RESULTS Individual test results will be reviewed and approved as provided in the site-specific administrative procedures.
Completed procedures and test reports will be reviewed for acceptance.
The specific acceptance criteria for determining the success dr I
failure of the test will be included as part of the procedure and will be used during the review.
j i
The responsible Startup Engineer will present the completed test i
procedure and test report with remarks and recommendations to the i
responsible reviewer.
Following this
- review, the complete,d procedure and test report will be submitted to the Test Working Group or the Plant Review Board for final review, evaluation, and approval recommendation.
If the as-built configuration of a system is not capable of demonstrating its ability to meet the acceptance criteria, an engineering evaluation will be performed.
Test results for each phase of the test program will be reviewed and verified as complete (as required) and satisfactory before testing in the next phase is started.
Preoperational testing on a system will not normally be started until all applicable prerequisite tests have been completed, reviewed, and approved.
Prior to initial fuel loading and the commencement of initial criticality, a
comprehensive review of required completed preoperational procedures will be conducted by the Test Working Group.
This review will provide assurance that required plant systems and structures will be capable of supporting the initial fuel loading and subsequent startup testing.
It is intended that Phase I testing be completed prior to i
ccmmencing initial fuel loading.
If prerequisite and Phase I
~
testing is incomplete at this time, provisions for carrying over testing will be planned and approved in accordance with the j
site-specific administrative procedures.
The startup testing phases (Phases II, III, and IV) of the test program are subdivided into the following categories:
A.
Initial fuel load.
B.
Post-core hot functional testing.
C.
Initial criticality.
D.
Low power physics testing E.
Power ascension testing.
It ends with the completion of testing at 100% power.
Amendment E 14.2-12 December 30, 1988
CESSAR n!WICATICN O
I Each subdivision is a prerequisite which must be completed, E
reviewed, and approved before tests in the next category are started.
Power ascension tests will be scheduled and conducted at pre-determined power levels.
i The plateaus for the power ascension testing are indicated in I
Table 14.2.5.
Results from each test conducted at a given plateau will be evaluated prior to proceeding to the next level.
For those tests which result in a plant transient for which a realis lc plant transient performance analysis has been o
performed, the test results will be compared to the results of the realistic transient analysis rather than the results of the transient analysis based on accident analysis assumptions.
f l
Following completion of testing at 100% of rated power, final l
test results will be reviewed, evaluated, and approved.
i 14.2.6 TEST RECORDB j
l A single copy of each test procedure is designated as the I
official copy to be used for testing.
The official copy and information specifically called for in the test procedure, such f-as completed data sheets, instrumentation calibration data and chart recordings, are retained for the life of the plant in accordance with Regulatory Guides for record retention.
14.2.7 CONFORMANCE OF TEST PROGRAMS WITH REGULATORY GUIDES The Startup Test Program is consistent with the recommendations I
of the following Regulatory Guides associated with startup (with l
exceptions as noted and revisions as specified in Section 1.8):
Regulator / Guides:
1.9, 1.18, 1.20, 1.30, 1.37, 1.41, 1.52, 1.68, 1.68.2, 1.68.3, 1.79, 1.108, 1.116, 1..l18, and 1.140.
1 14.2.7.1 Regulatory Guide 1.68, Initial Test Programs for Water-Cooled Reactor Power Plants The following exceptions and/or clarifications address only significant differences between the proposed test program and the applicable regulatory position.
Minor terminology differences, testing not applicable to the plant design, and testing that is part of required surveillance tests will not be addressed.
Reference is made to the applicable portion of Regulatory Guide
.I 1.68.
O l
Amendment E 14.2-13 December 30, 1988 i
__ a
CESSAREnL a 0
14.2.7.1.1 Reference Appendix A, Section 2.b I
This section suggests that rod drop times be measured for all I
control element assemblies (CEAs) at hot and cold full-flow and no-flow conditions.
The CEA drop-time testing is consistent with the recommendations of the regulatory guide; however, tests which do not provide meaningful data will be deleted.
As outlined in Test Summary (Section 14.2.12.2.4), the CEA drop-time testing will consist of:
lE A.
One drop of each CEA at hot, full-flow conditions.
B.
Those CEAs falling outside the two-sigma limit for similar CEAs will be dropped three additional times.
C.
Hot no-flow scram insertion rod drops will not be performed.
C-E has demonstrated that rod drop times under full-flow conditions are more limiting than the drop times under conditions of no-flow.
D.
The CEA drop time test at low temperature plateau waslE eliminated since the hot, full-flow conditions are more bounding and since criticality is not allowed below 500*F except for a short period of time during low power physics testing (if required).
E.
Cold no-flow drops will not be performed as the Technical Specifications do not normally permit criticality under these conditions.
14.2.7.1.2 Reference Appendix A, Appendix C, Section 3 1/2lE This section requires that a neutron count rate of at least count per second should be registered on the startup channels fully lE before the startup begins.
The design criterion calls for a neutron count rate of 1/2 count per second with all CEAs withdrawn and a multiplication of 0.98.
Therefore, prior to the initiation of the initial approach to criticality, the startup persecond;lE channels may see significantly less than 1/2 count but prior to exceeding a multiplication of 0.98, the desired neutron count rate of 1/2 count per second will have been achieved.
14.2.7.1.3 Reference Appendix 0, Section 4 E
The standard test plateau power levels of 20, 50, 80, and 100 percent are used instead of the recommended power levels of 25, 50, 75, and 100 percent.
Amendment E 14.2-14 December 30, 1988
CESSAR nEncarisu J
V E
14.2.7.1.4 Reference Appendix A, Section 5.a Power reactivity coefficients will be measured at 50 and 100%
power levels.
This is consistent with requirements for non-first-of-a-kind plants.
14.2.7.1.5 Reference Appendix A, Section 5.1 Since the Plant Protection System (CPCs and CEACs) detects the l
CEA positions by means of two independent sets of reed switches 1'
and uses this.information in determining margin to trip, it is not necessary to rely on in-core or ex-core nuclear l
l instrumentation to detect control element ' misalignment / drop.
Thus, this testing will not be performed.
E 14.2.7.1.6 Reference Appendix A, Section m.m This section requires that the dynamic response of the plant to automatic closure of all Main Steam Isolation Valves (MSIVs) ' be demonstrated from full power.
Performance of this test could l
result in the opening of primary and secondary safety valves.
Instead, the dynamic response of the plant can be obtained during the performance of the turbine trip test when the turbine stop (q) valves are closed.
The _ turbine trip test from full power will v'
result in essentially similar dynamic plant' response and should ensure that primary and secondary safety valves do not lift open during the performance of the test.
For these reasons, the plant response to automatic closure of all MSIVs from. full power will not be demonstrated.
14.2.7.1.7 Reference Appendix A, Section k.k This section requires that the dynamic response of the plant to the most severe reduction in feedwater temperature be demonstrated from 50 to 90% power.
The reduction in feedwater temperature results in only minor changes to RCS temperatures and pressure and reactor power.
In addition, the performance of this test will result in unnecessary thermal cycling of the steam generator economizer valves.
The performance of load rejection test and turbine trip test from full power provides sufficient information to verify design adequacy.
Thus, the plant response l
to reduction in feedwater temperatures will not be demonstrated.
14.2.7.2 Regulatory Guide 1.79, Preoperational Testing of Emergency Core Coolinq Systems for Pressurized Water Reactors The intent of Section C.1.c(2),
Isolation Valve
- Test, is
[
satisfied by opening the valves under maximum differential
(_,'}
pressure (RCS at ambient pressure) using normal electrical power Amendment E 14.2-15 December 30, 1988
CESSAR 8Enhes e
only.
Conditions at the valve motor are independent of the power source for this test.
The breaker response and the response of the valves to the " confirmatory open" signal is verified during
)
the Integrated Safety Injection Actuation System Test.
14.2.7.3 Regulatory Guide 1.68.2, Initial E
Startup Test Program to Demonstrate Remote Shutdown Capability for Water Cooled Nuclear Power Plants Shutdown outside the control room will be demonstrated to Hot Standby condition, Plant cooldown to entry into Shutdown Cooling conditions will be demonstrated during Hot Functional testing.
14.2.8 UTILIZATION OF REACTOR OPERATING AND TESIING EXPERIENCE IN DEVELOPMENT OF INITIAL TEST PROGRAM C-E maintains an ongoing effort which continually provides feedback to its startup organization during the development of, and throughout, the Initial Test Program.
This information reflects both C-E operating and test experience and industry wide experience concerning Pressurized Water Reactors.
Unit Operations reviews reactor operating and testing experiences E
at other facilities similar in design and capacity to the unit starting up.
This review is accomplished by circulating Licensee Event Reports (LERs) or summaries of LERs and NRC I&E Bulletins, circulars, and Information Notices to Startup and Operation personnel so that pertinent information can be utilized in the startup program.
14.2.9 TRIAL USE OF PLANT OPERATING AND EMERGENCY PROCEDURES i
The schedule for the development of the plant operating and emergency procedures should allow sufficient time for trial uselE of these procedures during the Initial Test Program.
14.2.10 INITIAL FUEL LOADING AND INITIAL CRITICALITY 14.2.10.1 Initial Fuel Loading overall direction, coordination, and control of the initial fuel loading evolution will be the responsibility of the site operator.
C-E will provide technical assistance during the E
initial fuel loading evolution.
The fuel.1oading evolution will be controlled by use of approved plant procedures which will be used to establish plant Amendment E 14.2-16 December 30, 1988 9
P r
l CESSAR inWICATICN O
V conditions, control
- access, establish
- security, control maintenance activitics, and provide instructions pertaining to the use of fuel handling equipment.
The overall process of initial fuel loading will be directed from the main control room.
The evolution itself will be supervised by a licensed Senior Reactor Operator.
In the unlikely event that mechanical damage to a fuel assembly is sustained during fuel loading operations, an alternate core loading scheme, whose characteristics closely approximate those of the initially prescribed core configuration, will be determined and approved prior to implementation.
The fuel assemblies will be installed in the reactor vessel in water containing dissolved boric acid in a quantity calculated to maintain a core effective multiplication constant at less than, E
or equal to, the Technical Specification value.
It is not anticipated that the refueling cavity will be completely filled.
However, the water level in the reactor vessel will be maintained above the installed fuel assemblies at all times.
The Shutdown Cooling System will be in service to provide coolant circulation to ensure adequate mixing and a means of controlling s) water temperature.
The IRWST will be in service and will contain E
borated water at a volume and concentration conforming to the Technical Specifications.
Applicable administrative controls will be used to prevent unauthorized alteration of system lineups or change to the boron concentration in the Reactor Coolant System.
Minimum instrumentation for fuel loading will consist of two temporary source range channels installed in the reactor vessel or one temporary channel and one permanently installed ex-core nuclear channel in the event that one of the temporary channels becomes inoperative.
Both temporary-and permanent channels will be response checked with a
neutron source.
The temporary channels will display neutron-count rate on a count rate meter installed in the containment and will be monitored by personnel conducting the fuel loading operation.
The permanent channel will display neutron count rate on a meter and strip chart recorder located in the main control room and will be monitored by licensed operators.
In addition, at least one temporary channel and one permanent channel will be equipped with audible rate indicators in two locations, temporary in the containment and permanent, or temporary, in the main control room.
E Continuous area radiation monitoring will be provided during fuel handling and fuel loading operations.
Permanently installed O
radiation monitors display radiation levels in the main control room and will be monitored by licensed operators.
Amendment E 14.2-17 December 30, 1988
h CESSARnaL a O
Fuel assemblies, together with inserted components, will be placed in the reactor vessel, one at a time, according to a previously established and approved sequence which was developed to provide reliable core monitoring with minimum possibility of core mechanical damage.
The initial fuel loading procedure will include detailed instructions which will prescribe successive i
movements of each fuel assembly from its initial position in the storage racks to is final position in the core.
The procedures will establish a system and a requirement for verification of each fuel assembly movement prior to proceeding with the next assembly.
Multiple checks will be made for fuel assembly and inserted component serial numbers to guard against possible inadvertent exchanges or substitutions.
At least two fuel assemblies containing neutron sources will be placed into the core at appropriate specified points in the initial fuel loading procedure to ensure a neutron population large enough for adequate monitoring of the core.
As each fuel assembly is loaded, at least two separate inverse count rate plots will be maintained to ensure that the extrapolated inverse count rate ratio behaves as would be expected.
In addition, nuclear instrumentation will be monitored to ensure that the "just loaded" fuel assembly does not excessively increase the count rate.
The results of each loading step will be reviewed and evaluated before the next prescribed step is started.
14.2.10.1.1 Safe Loading Criteria Criteria for the safe loading of fuel require that loading operations stop immediately if:
A.
The neutron count rate from either temporary suelear channel unexpectedly doubles during any single loading
- step, excluding anticipated change due to detector and/or source movement or spatial effects (i.e.,.
fuel assembly coupling source with a detector), or B.
The neutron count rate on any individual nuclear channel increased by a factor of five during any single loading step, excluding anticipated changes due to detector and/or source movement or spatial effects (i.e, fuel assembly coupling source with a detector).
A fuel assembly shall not be ungrappled from the refueling E
machine until stable count rates have been obtained.
In the event that an unexplained increase in count rate is observed on any nuclear channel, the last fuel assembly loaded shall be withdrawn.
The procedure and loading operation will be reviewed and evaluated before proceeding to ensure the safe loading of fuel.
4 Amendment E 14.2-18 December 30, 1988
CESSAR 8anr"lCATION 1
f~)
14.2.10.1.2 Fuel Loading Procedure E
An approved detailed test procedure will be followed during the initial fuel loading to ensure that the evolution will be com-pleted in a safe and controlled manner.
This procedure will specify applicable precautions and limitations, prerequisites, initial conditions, and the necessary procedural steps.
14.2.10.2 Initial Criticality overall direction, coordination, and control of the initial criticality evolution will be the responsibility of the site operator.
It is,
- however, intended that qualified plant E
personnel will execute the procedure.
C-E will provide technical assistance during the initial criticality evolution.
A predicted boron concentration for criticality will be deter-mined for the precritical CEA configuration specified in the procedure.
This configuration will require all CEA groups to be fully withdrawn with the exception of the last regulating group, which will remain far enough into the core to provide effective control when criticality is achieved.
This position will be specified in the procedure.
The Reactor Coolant System (RCS) b)
boron concentration will then be reduced to achieve criticality,
(
at which time the regulating group will be used to control the chain reaction.
Core response during CEA group withdrawal and RCS boric acid concentration reduction will be monitored in the main control j
room by observing the change in neutron count rate as indicated j
by the permanent wide-range nuclear instrumentation.
i Neutron count rate will be plotted as a function of CEA group j
position and RCS boron concentration _ dur.inct the approach to j
criticality.
Primary safety relunce is based on inverse count I
rate ratio monitoring as an. indication of the nearness and rate of approach to criticality during CEA group withdrawal and during j
the dilution of the reactor coolant boric acid concentration.
The approach to criticality will be controlled and specific holding points will be specified in the procedure.
The results of the inverse count rate monitoring and the indications on installed instrumentation will be reviewed and evaluated before proceeding to the next prescribed hold point.
l OO I
Amendment E
)
14.2-19 December 30, 1988 1
l
1 CESSAR HEncarian O
l 14.2.10.2.1 Bafe Criticality Criteria Criteria for ensuring a
safe and controlled approach to criticality require:
A.
That high flux trip setpoints be reduced to a
value E
consistent with the Technical Specification limits.
B.
That a sustained startup rate of one decade per minute not be exceeded.
C.
That CEA withdrawal or boron dilution be suspended if unexplainable changes in neutron count rates are observed.
D.
That CEA withdrawal or boron dilution be suspended if the extrapolated inverse count rate ratio predicts criticality outside the tolerance specified in the procedure.
E.
That the Technical Specifications are met.
F.
That criticality be anticipated at any time positive reactivity is added by CEA withdrawal or boron dilution.
G.
That a minimum of one decade of overlap be observed between the startup and log safety channels of the ex-core nuclear instruments.
14.2.11 TEST PROGRAM SCHEDULE E
The schedule for plant startup shall allow sufficient time to systematically perform the required testing in each phase.
No specific time periods for each phase are required.
The scheduling of individual tests or test sequences is made to I
ensura that syste.mc 'And components that are required to prevent or mitigate the consequences of postulated accidents are tested prior to fuel loading.
Tests that require a substantial core power level for proper performance are performed at the lowest power level commensurate with obtaining acceptable test data.
Phase I
test procedures are scheduled to be approved and available for review by the NRC inspectors at least 60 days prior to their scheduled performance date.
Phases II through Phase IV Startup Test Program administrative control procedures, the majority of the individual test procedures, and the following milestone controlling procedures: Fuel Loading, Post Core HFT, Initial Criticality, Low Power Physics Test and Power Ascension, are scheduled to be approved and available for review at least 60 0 Amendment E 14.2-20 December 30, 1988 I
CESSAR Mi&"icari2u 7(d E
days prior to fuel load.
The remaining individual test procedures will be scheduled for approval and available for review by the NRC inspectors at least 60 days prior to their intended performance date.
14.2.11.1 Testina Secuence The site operator shall specify the testing sequence to insure that the plant's safety is not wholly dependent any time during the testing on untested systems.
14.2.12 INDIVIDUAL TEST DESCRIPTIONS 1
14.2.12.1 Preoperational Tests 14.2.12.1.1 Reactor Coolant Pump Motor Initial Operation 1.0 OBTECTIVE 1.1 To verify the proper operation of each RCP motor.
1.2 To collect base data for each RCP motor.
I 2.0 PREREQUISITES 2.1 RCP motor instrumentation has been calibrated.
l 2., 2 Each RCP motor and its respective pump are uncoupled.
l 2.3 Support systems required for operation of each RCP motor are operational.
l 3.0 TEST METHOD 3.1 Start CCW flow to the RCP motor and observe indicating lights and alarms.
3.2 Using a torque wrench and phase rotation meter rotate RCP motor and verify proper wiring of motor leads and l
torque required to rotate the motor.
3.3 Jog RCP motor and verify proper rotatiors.
3.4 Start RCP motor and verify proper operation.
Record motor operating data.
3.5 Determine oil level setpoints of oil reservoirs by draining oil from motor reservoirs and subsequently g
refilling.
Amendment E 14.2-21 December 30, 1988
~
L CESSARn!L mu 9
3.6 Simulate oil lift pumps and CCW system starting interlocks preventing RCP motor operation and observe effects.
4.0 DATA REQUIRED I
4.1 Motor operating data.
4.2 Torque needed to rotate the RCP motors.
4.3 Setpoints at which indications, alarms, and interlocks occur.
5.0 ACCEPTANCE CRITERIA 5.1 The RCP motors, support systems, alarms, indications, and interlocks perform as described in Section 5.4.1.
14.2.12.1.2 Reactor Coolant System Test 1.0 OBJECTIVE 1.1 To perform the initial venting of the RCPs and RCS.
1.2 To perform the initial operation of the RCPs.
1.3 To verify RCP performance.
J 1.4 To verify alarm setpoints.
1.5 To verify the operation of the RCS sample isolation valves.
2.0 PREREQUISITES 2.1 Construction activities on the
2.2 RCP and RCS instrumentation has been calibrated.
2.3 Component cooling water is available.
2.4 RCP motor initial operation preoperational test has been completed.
2.5 Support systems required for operation of the RCPs and RCS sample isolation valves are operational.
O 14.2-22
CESSAR !!!Luou
(%
(
)
v.
3.0 TEST METHOD 3.1 Simulate temperature, pressure, and flow signals from each RCP and verify alarm setpoints.
3.2 Simulate temperature signals from each RCS RTD that has an alarm function and verify alarm setpoints.
i 3.3 Perform initial venting of
- RCPs, pressurizer, and l
reactor vessel.
3.4 Perform initial run of RCPs.
Vent the RCS after each run is complete.
3.5 Perform RCS sample valves performance testing.
l 4.0 DATA REOUIRED 4.1 Setpoints at which alarms occur.
4.2 RCP performance data, 4.3 RCS sample valves position indications.
(my) 5.0 ACCEPTANCE CRITERIA i
5.1 RCS and RCP performance and alarms are as described in Sections 5.4.1 and 5.4.3.
E 14.2.12.1.3 Pressurizer Safety Valve Test 1.0 OBJECTIVE To verify the popping pressure of the pressurizer safety valves.
2.0 PREREQUISITES 2.1 Construction activities on the pressurizer have been completed and all associated instrumentation has been checked and calibrated.
2.2 Reactor coolant system is at
- hot, zero power temperature and pressure.
2.3 Support systems required for the testing of the pressurizer safety valves are operational.
[Q 2.4 Lifting device with associated support equipment and calibration data is available.
Amendment E 14.2-23 December 30, 1988 1
CESSAR 8!?f,"lCATICN 0\\
l 3.O TEST METHOD 3.1 Using the lifting device, increase the lifting force on the safety valve until the safety valve starts to simmer.
j 1
3.2 Determine popping pressure from the lifting device correlation data.
3.3 Adjust valve popping set pressure if necessary and retest.
4.0 DATA REOUIRED 4.1 Pressurizer pressure and temperature.
4.2 Pressure applied to the lifting device to lift the safety valve off its seat.
5.0 A.CCEPTANCE CRITERIA 5.1 Safety valves perform as described in Section 5.4.13.
14.2.12.1.4 Pressurizer Pressure and Level Control System 1.0 OBJECTIVE 1.1 To verify the proper operation of the pressurizer i
pressur a and level control system.
l 2.0 PREREQUISITES 3
2.1 Construction activities on the pressurizer pressure and level control system have been completed.
2.2 Pressurizer pressure and level control system l
instrumentation has been calibrated.
I 2-3 Support systems requ. ed for operation of components in the pressurizer pressure and level control system are operational.
3.0 TEST METHOD 3.1 Close and open Mckup heater breakers from the main control room.
voserve breaker operation and indicating light response.
3.2 Simulate a decreasing pressurizer pressure and verify proper outputs to the heater control circuits.
Verify alarm setpoints.
14.2-24
CESSAR n!Wncamu O
3.3 Simulate an increasing pressurizer pressure and verify proper outputs to the heater and spray valves control valve circuits.
Verify alarm setpoints.
3.4 Simulate a low level error in the pressurizer and verify proper outputs to the charging pump control valve circuit.
Verify alarm setpoints.
E 3.5 Simulate a high level error 'in the pressurizer and verify proper outputs to the pressurizer backup heater and the letdown valve control circuits.
Verify alarm setpoints.
3.6 Simulate signals to pressurizer pressure and level controllers and verify proper outputs.
3.7 Simulate a low-low pressurizer level and verify proper system outputs.
3.8 Simulate a low pressurizer level and verify proper output signals to the letdown valve control circuits.
j y
4.0 DATA REOUIRED 4.1 Simulated pressurizer
- level, pressure
- signals, and outputs to pressurizer heaters control circuits.
4.2 Simulated pressurizer pressure signals and outputs to spray valve control circuits.
4.3 Simulated pressurizer level signals and outputs to charging pump control valve.;ircuits.
E 4.4 Simulated pressurizer hvel to letdown valve control circuits.
4.5 Setpoints at which alarm, indications, and interlocks occur.
5.0 ACCEPTANCE CRITERIA 5.1 Pressurizer pressure and level control system performs as described in Section 7.7.1.
t Amendment E 14.2-25 December 30, 1988
CESSAREHL mu 9
14.2.12.1.5 CVCS Letdown Subsystem Test i
1.O OBJECTIVE 1.1 To verify the proper operation of the chemical and volume control system letdown subsystem during normal and emergency operation.
2.0 PREREQUISITES 2.1 Construction activities on the letdown subsystem have been completed.
2.2 Letdown subsystem instrumentation has been calibrated.
2.3 Support systems required for the operation of the letdown subsystem control valves are operational.
3.0 TEST METHOD 3.1 Operate control valves from all appropriate control positions, observe valve operation and position indications and, where required, measure opening and closing times.
3.2 Simulate failed conditions and observe valve response.
3.3 Simulate SIAS/CIAS signals and observe isolation valve response.
3.4 Simulate letdown temperature and observe the response of control valves.
Observe alarm and interlock operation.
3.5 Measure Delta P across letdown flow orifice and verify E
design flow rates.
4.0 DATA REQUIRED 4.1 Valve opening and closing time where required.
j 4.2 Valve position indication.
4.3 Response of control valves to failed conditions.
4.4 Response of isolation valves to SIAS/CIAS.
4.5
Response
of control valves to
' simulated letdown temperature.
Amendment E 14.2-26 December 30, 1988
CESSAR EnWicaries
(
E 4.6 Delta P across letdown flow orifice.
4.7 Setpoints at which alarms,. indications, and interlocks l
occur.
5.0 ACCEPTANCE CRITERIA 5.1 The CVCS letdown subsystem performs as described in Section 9.3.4.
14.2.12.1.6 CVCS Purification Subsystem Test.
1.O OBJECTIVE 1.1 To verify flowpaths between the reactor makeup water system, the purification and deborating ion exchangers and the Solid Waste Management System.
1.2 To verify flowpaths between the purification and deborating ion exchanger and Gaseous Waste Managenent System.
I 2.0 PREREQUISITES 2.1 Construction activities on the Chemical and Volume l
Control System purification subsystem have been completed.
2.2 CVCS purification subsystem instrumentation has been calibrated.
j 2.3 Test instrumentation has been calibrated.
2.4 Support systems required for operation of the CVCS purification subsystem are complete and operational.
3.0 LEST METHOD 3.1 Lineup the purification system ion exchangers to complete a flowpath from the reactor makeup water (RMW) system through each purification system ion exchanger to the Solid Waste Management system.
Start an RMW pump and sequentially, so that only one ion exchanger is in use at a time, valve-in each ion exchanger.
Verify flow by observing RMW flow indicators and changes in RMW and spent resin tank levels.
Select all possible flow paths to the solid waste management
,< 3 system.
Amendment E 14.2-27 December 30, 1988
CESSAREnLbmu O
3.2 Individually connect each purification ion exchanger and the deborating ion exchanger to the plant air system and connect a pressure gage to the ion exchanger vent.
Adjust the plant air supply to 15-20 psig.
Start air flow to the ion exchangers and individually open each ion exchanger vent valve and valve the ion exchanger to the gaseous waste management system.
Observe the ion exchanger vent pressure, gas supply pressure, and flow rate.
4.0 DATA REOUIRED 4.1 RMW flow rate 4.2 RMW and spent resin tank levels 4.3 Air supply pressure and flow rate 4.4 Ion exchanger test pressure 5.0 ACCEPTANCE CRITERIA 5.1 Verification of flowpaths between the RMW system, the purification and deborating ion exchangers, and the Solid Waste Management System will have been demonstrated upon successful completion of Test Method 3.1.
5.2 Verification of flowpaths between the purification and deborating ion exchangers and the Gaseous Waste Management system will have been demonstrated upon successful completion of Test Method 3.2.
14.2.12.1.7 Volume Control Tank Subsystem Test 1.0 OBJECTIVE 1.1 To verify proper operation of the volume control tank subsystem.
2.0 PREREQUISITES i
i 2.1 Construction activities on the volume control tank subsystem have been completed.
2.2 Volume control tank subsystem instrumentation has been calibrated, 2.3 Reactor makeup water is available to the VCT.
14.2-28 J
CESSAR in&"icarieu nV 2.4 Support systems required for operation of the volume control tank are complete and operational.
3.0 TEST METHOD 3.1 Operate control valves from all appropriate control positions.
Observe valve operation and position indication and, where required, measure opening and closing times.
3.2 Simulate failed conditions and observe valve response.
3.3 Partially fill the VCT with RMW and pressurize the VCT l
using the nitrogen pressurization system.
Observe alarm operation.
1 3.4 Vent the VCT and repressurize using the hydrogen I
pressurization system.
(The hydrogen system will be temporarily connected to a nitrogen supply.)
j I
3.5 Drain and refill the VCT with RMW.
Observe level
)
alarms and interlocks.
f'h I,
3.6 Simulate VCT temperature and observe alarms.
4.0 DATE REOUIRED 4.1 Valve opening and closing times, where required.
4.2 Valve position indication.
l 4.3 Response of valves to simulated failed conditions.
4.4 VCT pressurization data.
4.5 VCT level program data.
l 4.6 Values of parameters at which alarms and interlocks l
occur.
5.O ACCEPTANCE CRITERI_4 5.1 The volume control tank subsystem performs as described in Section 9.3.4.
O 14.2-29
CESSAR!annc-0 14.2.12.1.8 CVCS Charging Subsystem Test 1.0 OBJECTIVE 1.1 To verify the proper performance of the chemical and volume control system charging subsystem.
2.0 PREREQUISITES 2.1 Construction activities on the reactor coolant charging subsystem have been completed.
2.2 CVCS charging subsystem is operational to supply E
charging pump suction.
2.3 The volume control tank subsystem is operational to supply charging pump suction.
2.4 The reactor vessel is ready to receive water from the charging headers.
2.5 The pressurizer is ready to receive water from the auxiliary spray line.
1 2.6 Reactor coolant pumps are operational.
2.7 Support systems required for operation of the reactor coolant charging subsystem are operational.
3.0 TEST METHOD 3.1 Operate control valves from all appropriate control positions.
Observe valve operation and position I
indication and, where required, measure opening and closing times.
j 3.2 Simulate failed conditions and observe valve response.
3.3 Manually start each charging pump seal lube pump and observe the operation of the seal and lube oil system.
3.4 Manually start each charging pump.
Observe charging pump operation including charging pump alarms and interlocks.
3.5 Simulate pressurizer level error signals and observe charging pump control valve response.
E O
Amendment E 14.2-30 December 30, 1988
CESSAR nai"icariou 3.6 With a charging pump running, open the seal injection lines, and observe flow.
3.7 With b charging pump running, open the auxiliary spray valve, and observe flow.
4.0 DATA REOUIRED 4.1 Valve opening and closing times, where required.
4.2 Valve position indication.
4.3 Response of valves to simulated failed conditions.
4.4 Charging
- pump, seal, and oil lubrication system performance.
4.5 Charging pump running data.
4.6 Response of charging pumps to sir.ulated pressurizer level error signa]s.
4.7 Setpoints at which alarms and interlocks occur.
4.8 Seal injection flow rates.
4.9 Auxiliary spray slo'? rates.
5.0 ACCEPTANCE CRITERIA 5.1 The chemical and volume control system charging subsystem performs as described in Section 9.3.4.
14.2.12.1.9 Chemical Addition Subsystem Test 1.0 OBJECTIVE 1.1 To demonstrate that the chemical addition subsystem can inject water into the charging pump discharge line.
1.2 To varify a flowpath from the chemical addition tank to the Miscellaneous Liquid Waste Management System.
2.0 PREREQUISITES 2.1 Support systems required for operation of the chemical addition subsystem are complete and operational.
14.2-31
1 CESSARU hreu 1
Oi 1
2.2 The chemical addition tank has been filled from the 1
makeup system with a pre-determined amount of RMW.
2.3 Charging subsystem is in operation.
i l
2.4 Associated instrumentation has been calibrated.
]
3.0 TEST METHOD j
a 3.1 With a charging pump in operation, start the chemical l
addition pump and observe the chemical addition tank l
level.
j 3.2 Drain the chemical addition tank to the Miscellaneous Liquid Waste Management System and observe the chemical E
addition tank level.
4.0 DATA REOUIRED 4.1 Chemical addition tank levels.
5.0 ACCEPTANCE CRITERIA 5.1 Chemical additicn to charging pump suction is demonstrated whan Test Method 3.1 is completed with a i
decreasing chem:.. cal addition tank level.
5.2 A flowpath to the Miscellaneous Liquid Waste Management System is demonstrated when Test Method 3.2 is completed with a decreasing chemical addition tank level.
14.2.12.1.10 Reactor Drain Tank Subsystem Test 1.0 OBJECTIVE l
1.1 To verify the proper performance of the reactor drain I
tank subsystem.
2.0 PREREQUISITES 2.1 Construction activities on the reactor drain tank subsystem have been completed.
2.2 Reactor drain tank subsystem instrumentation has been calibrated.
2.3 Equipment drain tank subsystem is ready to accept water from the reactor drain tank.
Amendment E 14.2-32 December 30, 1988
CESSAR E!Ninema r
(
2.4 Plant nitrogen system is operational.
i 2.5 Support systems required for operation of the reactor l
drain tank subsystem are operational.
l 3.0 TEST METHOD 3.1 Operate control valves from all appropriate control positions, observe valve operation and position-indication and, where required, measure opening and closing times.
3.2 Simulate failed conditions and observe valve response.
3.3 Simulate a CIAS and observe isolation valve response.
3.4 Fill the reactor drain tank from any convenient source and observe level and pressure indications and alarms.
3.5 Using the N system, pressurize the RDT and observe indications $nd alarms.
3.6 Line up the reactor drain tank (RDT) to the equipment drain tank and drain the RDT using each RDT pump, s_
observe level and pressure indicators,
- alarms, and interlocks.
3.7 Simulate RDT temperature and observe indicators and alarms.
4.0 DATA REOUIRED 4.1 Valve opening and closing times, where required.
4.2 Valve position indications.
4.3 Response of valves to simulated failed conditions.
4.4 Valve response to simulated CIAS.
4.5 RDT level, pressure, and temperature.
4.6 Setpoints of alarms and interlocks.
5.0 ACCEPTANCE CRITERIA 5.1 The reactor drain tank subsystem performs as described in Section 9.3.4.
\\
14.2-33
CESSARHML -
0 14.2.12.1.11 Equipment Drain Tank Subsystem Test 1.O OBJECTIVE l
1.1 To verify the proper performance of the equipment drain l
tank subsystem.
I 2.0 PREREQUISITES
}
2.1 Construction activities on the equipment drain tank subsystem have been completed.
2.2 Equipment drain tank subsystem instrumentation has been calibrated.
2.3 Holdup tank subsystem is operational.
2.4 Reactor drain tank subsystem is operational.
l 2.5 Reactor makeup subsystem is operational.
3.0 TEST METHOD 3.1 operate control valves from all appropriate control j
positions and observe valve operation and position indication.
3.2 Simulate fail conditions and observe valve response.
3.3 Fill the EDT from the reactor makeup water subsystem and observe indications, alarms, and interlocks.
i 3.4 Drain the EDT using a reactor drain tank pump and j
observe indications, alarms, and interlocks.
3.5 Simulate high equipment drain tank temperature and observe indications and alarms.
3.6 Simulate high equipment drain tank pressure and observe indications and alarms.
4.0 DATA REOUIRED 4.1 Valve position indications, i
4.2 Response of valves to simulated failed conditions.
4.3 Equipment drain tank level, pressure, and temperature.
O 14.2-34 1
~
l i
CESSAR neificari:n I
i t
4.4 Setpoints at which alarms and interlocks occur.
5.0 N EPTANCE CRITERIA 5.1 The equipment drain tank subsystem performs as described in Section 9.3.4.
j 14.2.12.1.12 Boric Acid Batching Tank Subsystem Test I
1.O OBJECTIVE 1.1 To verify proper operation of the boric acid batching tank subsystem.
2.0 PREREQUISITES 2.1 Construction activities on the boric acid batching tank subsystem have been completed.
2.2 Tha in-containment refueling water storage tank l
subsyt=. tem is operational.
E 1
2.3 Support systems required for operation of the boric
(
acid batching tank are complete and operational.
\\
2.4 The Boric Acid Storage Tank Subsystem is operational.
E 3.0 TEST METHOD 3.1 Fill the boric acid batching tank with water from the RMW system.
Energize heaters and measure the length of time required to heat the tank.
Observe heater control setpoints.
3.2 Line up the boric acid batching tank to the Boric Acid Storage Tank.
Start a boric acid makeup pump and E
l observe the batching tank level.
3.3 Refill the boric acid batching tank, dissolve boric acid crystals, and start the batch tank mixer.
Take samples as the tank is drained to the equipment drain tank and determine the boric acid concentration.
4.0 DATA REOUIRED 4.1 Batching tank heater performance data.
4.2 Heatup rate.
O l
l Amendment E 14.2-35 December 30, 1988 l
CESSAR EnWricari:n O
4.3 Boric acid concentration.
]
5.0 ACCEPTANCE CRITERIA 5.1 The boric acid batching tank subsystem performs as described in Section 9.3.4.
14.2.12.1.13 Concentrated Boric Acid Subsystem Te.9 1.0 OBJECTIVE 1.1 To verify the proper performance of the concentrated boric acid subsystem.
2.0 PREREQUISITES 2.1 Construction activities of the concentrated boric acid and Boric Acid Storage Tank (BAST) subsystems have been E
completed.
2.2 Concentrated boric acid subsystem instrumentation has been calibrated.
2.3 The reactor coolant charging subsystem is complete and operational.
2.4 The VCT subsystem is complete and operational.
2.5 The boric acid batching tank subsystem is complete and operational.
2.6 Support systems required for operation of the concentrated boric acid and BAST systems are complete E
and operational.
3.0 TEST METHOD 3.1 Oparate control valves from all appropriate control positions, observe valve operation and position indication and, when required, measure opening and closing times.
3.2 Simulate failed conditions and observe valve response.
3.3 Fill the BAST with RMW from the boric acid batching E
tank subsystem and observe level alarm setpoints.
3.4 operate each BAMU pump and observe pump performance.
O Amendment E 14.2-36 December 30, 1988
CESSAREnnnc-10 3.5 Operate BAMU pumps utilizing all interconnections between BAMU pumps and BAST.
E 3.6 Line up the BAMU to charging pump suction and verify ability of the BAMU pumps to supply adequate flow to the charging pumps.
charging pump suction and verify l 3.7 Line up the BAST to that adequate flow is delivered to the charging pumps.
E 3.8 Simulate high and low BAST levels and observe indications and alarms.
3.9 Simulate high and low BAST temperature and observe indications and alarms.
3.10 Line up the BAMU pumps'to the VCT and verify that the makeup system is capable of supplying BAMU ttnd RMW to the VCT and charging pump suction at the selected rates and quantities in all modes of operation.
Observe alarms and interlocks.
(
4.0 DATA REOUIRED 8
4.1 Valve opening and closing times where required.
)
4.2 Valve position indication.
)
4.3 Response of valves to simulated failed conditions.
4.4 BAMU pump performance data.
4.5 Makeup system performance data.
4.6 Setpoints at which alarms, automatic actuations, and interlocks occur.
5.0 ACCEPTANCE CRITERIA 5.1 The concentrated boric acid subsystem performs as described in Section 9.3.4.
14.2.12.1.14 Reactor Makeup Subsystem Test 1.0 OBJECTIVE 1.1 To verify the performance of the reactor makeup subsystem.
N.
Amendment E 14.2-37 December 30, 1988
~
l CESSAR El.%ncuen O
2.0 PREREQUISITES 2.1 Construction activities on the reactor makeup subsystem have been completed.
2.2 Reactor makeup subsystem instrumentation has been calibrated.
2.3 Plant makeup system is operational.
2.4 Support systems required for the operation of the reactor makeup subsystem are complete and operational.
3.0 TEST METHOD 3.1 Operate control valves from all appropriate control positions and observe valve operation and position i
indication.
3.2 Simulate failed conditions and observe valve response.
3.3 Fill the reactor makeup water tank and observe level indications and alarms.
3.4 Simulate reactor makeup water tank temperature and observe indications and alarms.
3.5 Drain the reactor makeup water tank using each RMW r
pump.
Observe tank level and pump discharge pressure, indications, and alarms.
3.6 Simulate RMW filter differential pressure and observe j
indications and alarms.
4 4.0 DATA REOUIRED 4.1 Valve position indication.
4.2 Valve response to simulated fail conditions.
4.3 RMWT level, pressure, and temperature.
4.4 RMW pump discharge pressure.
4.5 RMWT filter differential pressure.
4.6 Setpoints of alarms and interlocks.
O 14.2-38
CESSAR8Ennema rw 5.0 ApQp yrANCE CRITERIA 5.1 The reactor makeup subsystem-performs as described in Section 9.3.4.
1 14.2.12.1.15 Holdup subsystem Test 1.O OBJECTIVE 1.1 To verify proper operation of the holdup subsystem.
l 2.0 PREREQUISITES 4
2.1 Construction activities on the hold subsystem have been completed.
2.2 Holdup subsystem instrumentation has been calibrated.
2.3 Boric acid concentrator is ready to receive water from the holdup tank.
2.4 Support systems required for operation of the holdup p
subsystem are complete and operational.
]
'b 3.0 TEST METHOD 1
3.1 Fill the holdup tank and observe level indications and alarms.
j 3.2 Simulate holdup tank temperature and observe indications and alarms.
3.3 Using each holdup pump, drain the holdup tank to the boric acid concentrator.
Observe holdup tank level indications,
- alarms, interlocks, and holdup pump discharge pressure.
i 3.4 Refill and isolate the holdup tank.
Open the holdup tank recirculation valves and start each holdup pump.
Observe tank level.
Line up the holdup pumps to the reactor drain tank filter and observe holdup tank level.
4.0 DATA REOUIRED 4.1 Holdup tank level and temperature.
i 4.2 Holdup pump pressure.
i 14.2-39
CESSAR En9, caries O
4.3 Setpoints of alarms and interlocks.
j 5.0 ACCEPTANCE CRITERIA 5.1 The holdup subsystem performs as described in Section 9.3.4.
14.2.12.1.16 Boric Acid Concentrator Subsystem Test 1.0 OBJECTIVE 1.1 To verify the performance of the boric acid concentrator subsystem.
2.0 PREREQUISITES 2.1 Construction activities have been completed on the boric acid concentrator subsystem.
2.2 Support systems required for operation of the boric acid concentrator are complete and operational.
2.3 Boric acid concentrator subsystem instrumentation has been calibrated.
3.0 TEST METHOD 3.1 Operate control valves from all appropriate control positions and observe valve operation and position indication.
3.2 Simulate failed conditions and observe valve response.
3.3 Simulate interlock signals from interfacing equipment and observe boric acid concentrator subsystem response observe alarms.
3.4 Line up the boric acid concentrator subsystem to 1
interfacing systems and, using appropriate operating modes and indications, establish flow paths to these systems.
4.0 DATA REOUIRED 4.1 Valve position indication.
4.2 Response of valves to simulated failed conditions.
O 14.2-40
CESSAR EnMnenia e
N_
4.3 Boric acid condensate subsystem response to simulated interlocks.
4.4 Setpoints at which alarms interlock and automatic actuations occur.
4.5 Flow indications.
5.0 ACCEPTANCE CRITERIA 5.1 The boric acid concentrator subsystem performs as described in Section 9.3.4.
14.2.12.1.17 Gas Stripper Subsystem Test 1.O OBJECTIVE 1.1 To verify proper operation of the gas stripper subsystem.
2.0 PREREQUISITES 2.1 Construction activities have been completed on the gas (O) stripper subsystem.
v 2.2 Gas stripper subsystem instrumentation has been calibrated.
2.3 Support systems required for operation of the gas stripper subsystem are operational.
3.0 TEST METHOD
)
3.1 Operate control valves from all appropriate control positions and observe. valve operation and position indications.
3.2 Simulate failed conditions and observe valve response.
3.3 Simulate interlock signals from interfacing equipment and observe gas stripper subsystem response.
3.4 Line up the gas stripper subsystem to interfacing systems and, using appropriate operating modes and indications, establish flow paths to'these systems.
3.5 Observe alarms.
bG 14.2-41
CESSAREne mu O
4.0 DATA REOUIRED 4.1 Valve position indication.
]
4.2 Valve response to simulated failed conditions.
4.3 Setpoints at which alarms, automatic actuations, and interlocks occur.
4.4 Flow indications.
5.0 ACCEPTANCE CRITERIA 5.1 The gas stripper subsystem performs as described in Section 9.3.4.
14.2.12.1.18 Boronometer Subsystem Test 1.0 OBJECTIVE 1.1 To demonstrate proper operation of the boronometer electronics system.
2.0 PREREQUISITES l
2.1 The boronometer has been calibrated and is operational.
2.2 Support systems required for boronometer subsystem operation are complete and operational.
3.0 TEST METHOD j
3.1 Utilizing the built-in test features observe boronometer indications, outputs to interface equipment, and alarm operation.
4.0 DATA REOUIRED 4.1 Pulse rates and boronometer output.
4.2 Alarm se'. points and actuation levels.
5.0 ACCEPTANCE CRITERIA 5.1 The boronometer subsystem performs as described in Section 9.3.4.
O 14.2-42
CESSAR Ennficarieu f.V 14.2.12.1.19 Letdown Process Radiation Monitor Subsystem Test 1.O OBJECTIVE 1.1 To demonstrate proper operation of the letdown process radiation monitor subsystem.
l 2.0 PREREQUISITES 2.1 The process radiation monitor has been installed, all interconnections have been completed, and - the sample chamber has been filled with reactor makeup water.
2.2 The process radiation monitor has been calibrated.
2.3 A check source is available.
2.4 Support systems required for operation of the process radiation monitor subsystem are complete and operational, p
3.0 TEST METHOD 3.1 Utilizing the built-in test features, obs.orve process monitor indications, outputs to interface equipment, and a) arm operation.
3.2 Utilizing the check source, verify calibration of the process monitor.
4.0 DATA REOUIRED 4.1 Check source data.
4.2 Process monitor operating data.
4.3 Process monitor response to the check source.
J l
4.4 Value of parameters required to actuate alarms.
5.O ACCEPTANCE CRITERIA 5.1 The letdown process radiation monitor subsystem performs as described in Subsection 9.3.4.
i O
14.2-43
CESSAR 8!ahiu Ol 1
14.2.12.1.20 Gas Stripper Effluent Radiation Monitor E
subsystem Test 1.0 OBJECTIVE 1.1 To demonstrate proper operation of the gas stripper ef fluent radiation mor.
or subsystem.
E 2.0 PREkEOUISITES beenlE 2.1 The gas stripper effluent radiation monitor has installed, all interconnections have been completed, and the sample chamber has been filled with reactor makeup water.
)
2.2 The gas stripper radiation monitor has been calibrated.
2.3 Support systems required for operation of the gas stripper effluent radiation monitor subsystem are E
complete and operational.
2.4 A check source is available.
3.0 TEST METHOD 3.1 Utilizing the built-in test features, observe process l
radiation monitor indications, outputs to interface equipment, and alarm operation.
3.2 Utilizing a check source, verify calibration of the process monitor.
4.0 DATA REOUIRED 4.1 Process monitor operating data.
4.2 Process monitor response to the check source.
4.3 Value of parameters required to actuate alarms.
5.O ACCEPTANCE CJ3JJ'FJLQ 5.1 The gas stripper effluent radiation monitor performs as E
described in Section 9.3.4.
i O
Amendment E 14.2-44 December 30, 3988
~
CESSAR En@icarisu b\\
Q 14.2.12.1.21 Shutdown Cooling Subsystem Test 1.0 OBJECTIVE 1.1 To demonstrate proper operation of Shutdown Cooling Subsystem and the Shutdown Cooling pumps.
E l
2.0 PREREQUISITES l
2.1 Construction activities on the system., to be tested are l
complete.
I i
2.2 Plant systems required to support testing a)e operable and temporary systems are installed and operable.
2.3 Permanently installed instrumentation is operable and calibrated.
2.4 Test instrumentation is available and calibrated.
2.5 All lines in the Shutdown Cooling Subsystem have been filled and vented.
3.0 TEST METHOD C
3.1 Verify proper operation of each shutdown cooling pump with minimum flow established.
3.2 Verify pump performance including head and flow characteristics for all design flow paths.
3.3 Perform a full flow test of the shutdown cooling system.
3.4
- Verify, if possible, proper operation, failure mode, stroking speed, and position indication of control valves.
3.5 Verify the proper operation of the protective devices,
- controls, interlocks, and alarms using actual or simulated signals.
4.0 DATA REOUIRED 4.1 Valve position indications.
4.2 Pump head versus flow characteristics.
4.3 Valve opening and closing times, where required.
~
l Amendment E 14.2-45 December 30, 1988 l
1
CESSAR n!Oicarien O
5.0 ACCEPTANCE CRITERIA 5.1 The Shutdown Cooling System performs as described in Section 5.4.7.
14.2.12.1.22 Safety Injection Subsystem Test E
1.O OBJECTIVE 1.1 To functionally test the operation and performance of the components within the Safety Injectioh (SI) subsystem including valve and pump performances.
1.2 To verify proper SI response to a SIAS signal using normal, alternate, and emergency power sources.
1.3 To verify the flow paths through the Direct Vessel Injection (DVI) Nozzles and the Hot Leg Residual Heat Removal piping.
1.4 To demonstrate the capability to perform full flow test of the Safety Injection System.
1.5 To verify the SI sampling system functions as designed.
2.0 PREREQUISITES 2.1 Construction activities have been completed on the Safety Injection System.
2.2 Support systems and instrumentation required for operation of the SI subsystem are essentially complete and operational.
2.3 The In-containment Refueling Water Storage Tank (IRWST) is filled with sufficient primary makeup water to conduct testing on the SI subsystem.
2.4 The reactor vessel head and internals have been removed.
2.5 Test instrumentation to be used for pump performance has been installed and calibrated.
2.6 SI subsystem instrumentation has been checked and calibrated.
O Amendment E 14.2-46 December 30, 1988
CESSAR nairlCATIDN l
f%
'i
\\
E 3.0 TEST METHOD l
3.1 Operate control valves' from all appropriate control locations and observe valve operation and position i
indication.
Where
- required, measure opening and closing times.
3.2 Simulate failed conditions and observe valve response.
l 3.3 Operate SI from alternate electrical power sources and determine pump and valve responses including response l
times, when required.
3.4 Start each SI pump using a SIAS signal and collect initial pump operating data.
For this portion of the test, the SI pumps will be aligned to discharge to the depressurized RCS with appropriate discharge valves throttled and calibrated instrumentation installed to verify that SI pump flow and discharge pressure conform to the pump manufacturer's head-flow curve.
This test i
shall be performed using
- normal, alternate, and emergency power.
Suction will be taken from the IRWST I
under maximum flow conditions in the combined suction (G
i header.
Measured suction head shall conform to the l
manufacturer's NPSH requirements when corrected for IRWST minimum level attainable during a
SIAS and l
maximum IRWST fluid temperature.
l 3.5 Run each SI pump to demonstrate the ability to perform full flow test capability.
3.6 Collect fluid samples from each of the system sampling points.
4.0 DATA REOUIRED l
4.1 Valve position indication.
l 4.2 Valve opening and closing times, where required.
l 4.3 Responses of values to simulated failed conditions.
4.4 SI pump initial operational data including pump head versus flow, pump suction pressure and pumped fluid temperature, chemistry, and debris content.
4.5 Response of SI subsystem to SIAS when powered by normally alternate and emergency power sources.
Amendment E 14.2-47 December 30, 1988
C E S S A R En Wicaritu 4.6 SI flow rates.
5.0 ACCEPTANCE CRITERIA 1
5.1 The SI subsystem performs as described in Section 6.3 to provide adequate flow (manufacturer's curves) under i
minimum actual suction head to maintain RCS inventory j
and/or cool the core for the RCS breaks and transients j
in the scope of the Safety Analysis (Chapter.; f ang1 1
15).
i 5.2 SI subsystem response times are less than those specified in Section 6.3.
5.3 Water samples from the SI system can be obtained.
5.4 Full flow testing of the SI system can be performed.
j 14.2.12.1.23 Safety Injection Tank subsystem Test 1.0 OBJECTIVE l
1 1.1 To demonstrate the proper operation of the safety injection tank subsystem.
)
2.0 PREREQUISITES l
2.1 Construction activities on the safety injection tank
[
subsystem have been completed.
l 2.2 Support systems required for the operation of the safety injection tank subsystem are complete and operational.
2.3 Adequate supply of makeup water from the IRWST is E
available.
2.4 The reactor vessel head and internals have been removed.
2.5 The reactor vessel is filled above the RV injection E
nozzles.
2.6 Safety injection tank subsystem instrumentation has
{
been checked and calibrated.
1 Ol Amendment E 14.2-48 December 30, 1988
CESSAR n!?!?icarian
(~'S x_s' 3.0 TEST METHOD j
3.1 Operate control valves ' from all appropriate control locations and-observe valve operation and position indication.
Where required, measure valve opening and closing times.
3.2 Simulate failed conditions and observe valve response.
j 3.3 Simulate a SIAS signal and observe valve interlock and alarm operation.
l 3.4 Fill the safety injection tanks. from the IRWST and E
observe level indication and alarm operation.
3.5 Pressurize the safety injection. tanks and observe pressure indication and alarm operation.
3.6 Simulate a SIAS to each safety injection tank and measure the time required for the safety injection tanks to discharge their contents to the RCS.
I l
4.0 DATA REOUIRED A/
4.1 Valve position indications.
s 4.2 Valve opening and closing times, where required.
4.3 Response of valves to simulated failed conditions.
4.4 System response to SIAS.
4.5 Setpoints at which alarms and interlocks occur.
4.6 Times required for safety injection tanks to discharge their contents to the RCS.
5.0 ACCEPTANCE CRITERIA 5.1 The safety injection tank subsystem performs as described in Section 6.3.2.
14.2.12.1.24 Megawatt Demand Setter (MDB) Subsystem Test 1.0 OBJECTIVE 1.1 To verify the proper installation and operation of the MDS.
V Amendment E 14.2-49 December 30, 1988
CESSAR 8!Lbra e
2.0 PREREQUISITES 2.1 Construction activities are essentially complete and the applicable systems and components are ready for 4
testing.
)
2.2 Applicable operating manuals are available.
2.3 Test equipment and instrumentation is available and calibrated.
2.4 Plant systems required to support testing are operable to the extent necessary to perform the testing or suitable simulations are used.
3.0 TEST METHOD 3.1 Verify input data and control paths from systems associated with the MDS.
3.2 Simulate inputs and verify system responses and demand settings.
3.3 Verify the proper functioning of the four operational j
modes of the MDS.
4.0 DATA REOUIRED 4.1 Input signals from associated systems.
4.2 MDS demand outputs in response to inputs.
5.0 ACCEPTANCE CRITERIA 5.1 The MDS functionally operates as described in Section 7.7.1.1.3.
14.2.12.1.25 Engineered Safety Features - Component Control System (EBF-CCS) Test 1.O OBJECTIVE 1.1 To demonstrate the proper operation of the Engineered Safety Features - Component Control System.
2.0 PREREQUISITES 2.1 Construction activities on the ESFAS have been completed.
Amendment E 14.2-50 December 30, 1988
CESSAR nnincuim O
2.2 ESFAS instrumentation has been calibrated.
2.3 External test instrumentation is available and calibrated.
1 2.4 Support systems required for operation of the ESFAS are operational.
i 3.0 TEST METHOD j
3.1 Energize power supplies and observe output voltages.
3.2 Simulate ground faults and observe operation of the ground. fault detectors.
3.3 Individually deenergize each group relay and monitor contact operation.
3.4 Test manual trips and monitor relay operation.
3.5 Decnergize all combinations of the two-out-of-four trip logic for each of the actuation systems (SIAS, CIAS,.
j CSAG, CCAS, MSIS, EFAS) and observe actuation of the E
l appropriate trip circuit and associated alarms.
1 3.6 Simulate inputs to the appropriate circuits and observe trip initiations.
3.7 Exercise the manual control functions to the Safety E
Depressurization and Shutdown Cooling System to verify proper operations.
3.8 Exercise automatic and manual test functions to verify control functions of ESF-CCS.
4.0 DATA REOUIRED 4.1 Power supply voltages.
4.2 Resistance for ground fault detector operation.
4.3 Group relay contact status.
4.4 Response to manual trips.
4.5 Response to two-out-of-four logic trips.
4.6 Trip setpoints.
Amendment E 14.2--51 December 30, 1988
CESSAR 8!MICAT10N O
l 4.7 Automatic and manual test function outputs and E
displays.
5.0 ACCEPTANCE CRITERIA 5.1 The engineered safety feature auxiliary relay cabinet; performs as descrit ed in Section 7.3.1.
14.2.12.1.26 Plant Protection System (PPS) Test 1.0 OBJECTIVE 1.1 To demonstrate the proper operation of the plant protection system.
1.2 Determine the Reactor Protection System and the Engineering Safety Features Actuation System Response Times.
2.0 PREREQUISITES 2.1 Construction activities on the trip circuit breaker and plant protection system and ESF-CCS have been E
]
completed.
2.2 PPS system instrumentation has been calibrated.
2.3 External test instrumentation is available and calibrated.
2.4 Support systems required for operation of the trip circuit breakers, ESF-CCS and plant protection system E
l are operational.
3.0 TEST METHOQ 3.1 Energize power supplies and verify output voltage.
3.2 Simulate ground faults and observe operation of the ground fault detectors.
3.3 Using simulated reactor trip signals, trip each reactor trip circuit breaker with the breaker in the test position.
Observe circuit breaker operation.
3.4 Repeat Step 3.3 with the reactor trip circuit breakers in the operate position.
O' Amendment E 14.2-52 December 30, 1988
CESSAR EEWicari:n 3.5 Exercise the bistable comparators using internal and E
external test circuitry and observe the setpoints and operation of the appropriate ESF circuit.
3.6 Check the operation of trip channel hypass features including, where applicable, observation of the setpoints at which the trip bypasses are cancelled automatically.
3.7 Test manual trips and observe relay operation.
3.8 Check that Low Pressurizer Pressure and Low Steam l
Generator Pressure trip setpoints track the process variable at the prescribed rate and can be manually reset to the proper margin below the process variable.
3.9 Utilizing the installed testing
- devices, Local E
Coincidence Logic. (LCL),
observe test functions and verify proper operation.
I a
3.10 Using manually initiated semi-automatic test functions l
to trip the reactor trip circuit breakers and'ESF-CCS interfaces, observe interlock,
- alarm, and interface p}
(J operation.
3.11 Verify proper operation of the core protection and control assembly calculator subsystems by input / output and internal function tests.
3.12 Inject signals into appropriate sensors or sensor i
terminals and measure the elapsed time to achieve tripping of the Reactor Trip circuit breakers or actuation of the actuation relays.
Trip or Actuation paths may be tested in several segments.
1 1
4.0 DATA REOUIRED 4.1 Power supply voltages.
4.2 Resistance for ground fault detector operation.
l 4.3 Circuit breaker and indicator operation.
4.4 Point of actuation of bistable comparators.
4.5 Reset margin and rate of setpoint change of variable setpoints.
')
4.6 Maximum and minimum values of variable setpoints.
%./
Amendment E 14.2-53 December 30, 1988
CESSAR 8!L"icari:n l
O 4.7 RPS and ESF trip and actuation txth response times.
l 4.8 Local Coincidence Logic operation E
5.0 ACCEPTANCE CRITERIA 5.1 The Plant Protection System performs as described in Sections 7.2 and 7.3.
E 5.2 The total response time of each RPS and EFAS trip or Actuation path is verified to be conservative with
{
respect to the times used in the safety analysis.
14.2.12.1.27 Ex-core Nuclear Instrumentation System Test 1.0 OBJECTIVE 1.1 To verify the proper functional performance of the ex-core nuclear instrumentation system.
1.2 Verify the proper performance of audio and visual indicators.
2.0 PREREQUISITES 2.1 Construction activities on the ex-core nuclear l
instrumentation system have been completed.
I 2.2 Ex-core nuclear instrumentation system instrumentation has been calibrated.
2.3 External test equipment has been calibrated and is operational.
2.4 Support systems required for operation of the ex-core nuclear instrumentation system are operational.
3.0 TEST METHOD 3.1 Utilizing appropriate test instrumentation, simulate E
and vary input signals to the startup, safety and control channels of the ex-core nuclear instrumentation system.
3.2 Monitor and record all output signals as a function of variable inputs provided by test instrumentation.
3.3 Record the performance of audio and visual indicators in response to changing input signals.
Amendment E 14.2-54 December 30, 1988
CESSAR EMMncma n
-\\ g 4.0 DATA REOUIRED 4.1 Values of input and output signals for correlation purposes, as required.
4.2 Values of all output signals triggering audio and visual alarms.
5.O ACCEPTANCE CRITERI.g 5.1 The ex-core nuclee.r instrumentation system performs as described in Sections 7.2.1 and 7.7.1.
14.2.12.1.28 Fixed In-cole Nuclear Signal Channel Test 1.0 OBJECTIVE 1.1 To measure cable insulation resistance.
1.2 To verify proper amplifier operation.
2.0 PREREQUISITES
}
2.1 Construction activities on the In-core Nuclear i
As/
Instrumentation System are complete (Detectors do not need to be installed).
2.2 Fixed in-core nuclear signal channel instrumentation has been calibrated.
l 2.3 External test equipment has been checked and calibrated.
l 2.4 Support systems required for operation of the In-core Nuclear Instrumentation System are operational.
3.0 TEST METHOD i
3.1 Measure and record cabling insulation resistance.
3.2 Using external test instrumentation, simulate in-core detector signals into the signal conditioning circuits.
E 3.3 Using internal test circuits, test each amplifier for proper operation in accordance with manufacturer's l
instruction manual.
i 3.4 Vary the simulated inputs to the amplifier-and record
[
its outputs to the plant computer.
1 l
Amendment E 14.2-55 December 30, 1988
1 l
r CESSAR E!'4ince l
O 4.0 DATA REOUIRED 4.1 Cabling insulation resistance readings.
4.2 Status and performance of the internal test circuits.
4.3 Values of simulated input and derived output signal's for correlation purposes.
5.0 ACCEPTANCE CRITERIA 5.1 The fixed in-core nuclear signal channel cables and instrumentation perform as described in Section 7.7.1.
E
\\
I 14.2.12.1.29 Control Element Drive Mechanism Control System (CEDMCB) Test 1.O OBJECTIVE 1.1 To demonstrate proper input signals and proper sequencing of input signals to control element drive mechanism (CEDM) coils.
1.2 To demonstrate proper operation of the control element drive mechanism control system (CEDMCS) in all modes.
1.3 To verify proper operation of the CEDMCS interlocks and alarms.
2.0 PREREQUISITES 2.1 Construction activities on the CEDMCS have been completed.
2.2 Cable continuity tests have been completed.
2.3 Special test instrumentation has been calibrated and is operational.
2.4 Special test equipment is operational.
2.5 Support systems required for operation of the CEDMCS are operational.
3.0 TEST METHOD l
3.1 Using special test instrumentation, observe the sequence in which withdraw and insert signals are passed to the appropriate CEDM coil.
Observe operation of the digital CEA position indicators.
Amendment E 14.2-56 December 30, 1988 l
1 CESSAR EniirlCAT12N i
I i
3.2 Operate the CEDMCS in all modes.
Simulate input I
signals and observe operation of interlocks and alarms.
l 4.0 DATA REQUIRED 4.1 CEDM coil current traces.
4.2 CEDMCS totalizer indications.
4.3 CEDMCS operating data.
4.4 Interlock and alarm actuation points.
1 5.0 ACCEPTANCE CRITERIA l
1 5.1-The control element drive mechanism control system performs as described in Section 7.7.1.
14.2.12.1.30 Reactor Regulating System (RRS) Test 1.0 OBJECTIVE l
1.1 To demonstrate the proper operation of the reactor
- O-regulating system.
2.0 PREREQUISITES i
2.1 Construction activities on the RRS have been completed.
2.2 RRS instrumentation has been calibrated.
2.3 External test equipment has been calibrated and is operational.
2.4 Support systems required for operation of the RRS are i
operational.
2.5 Cabling has been completed between the RRS and interface equipment.
3.0 TEST METHOD 3.1 Utilizing actual or simulated interface inputs to the RRS, observe receipt of these signals at the RRS.
3.2 Utilizing installed and external test instrumentation, vary all input signals to the system and observe output responses at the RRS and at interfacing equipment, k
14.2-57
CESSARH5ince O
I 4.0 DATA REOUIRED 4.1 Input signal values.
4.2 Status of interfacing control board equipment.
l 4.3 RRS output response.
4.4 Status of outputs received at interfacing equipment.
5.0 ACCEPTANCE CRITERIA 5.1 The reactor regulating system performs as described in Section 7.7.1.
14.2.12.1.31 Steam Bypass Control System (SDCS) Test 1.O OBJECTIVE 1.1 To demonstrate the proper operation of the steam bypass control system.
2.0 PREREQUISITES i
2.1 Construction activities on the steam bypass control system (SBCS) and interfacing equipment have been completed.
2.2 Steam bypass control system instrumentation has been calibrated.
2.3 External test equipment has been calibrated and is operational.
2.4 Support systems required for operation of the steam bypass control system are operational.
3.0 TEST METHOD l
3.1 Utilizing actual or simulated interface inputs to the SBCS, observe receipt of these signals at the SBCS.
3.2 Utilizing installed and external test equipment, vary system inputs and observe output responses at the SBCS and at interfacing equipment.
O 14.2-58
CESSAR Eniiriemu O
1 3.3 Verify proper response of the steam bypass valves and position indicators.
NOTES:
1.
Dynamic operation of the steam bypass valves will be demonstrated' during hot i
functional testing.
2.
Capacity testing of the steam bypass valves will be demonstrated during power ascension testing.
4.0 DATA REOUIRED 4.1 Input signal values.
4.2 Status of interfacing control board equipment.
l 4.3 SBCS output response.
4.4 Status of outputs received at interfacing equipment.
5.0 ACCEPTANCE CRITERIA 5.1 The steam bypass control system performs as described in Sections 7.7.1 and 10.4.4.
,(
14.2.12.1.32 Feedwater Control System (FWCS) Test 1.0 OBJECTIVE 1.1 To demonstrate the proper operation of the feedwater control system.
2.0 PREREQUISITES 2.1 Construction activities on the FWC5
.id interfacing equipment have been completed.
2.2 FWCS instrumentation has been calibrated.
2.3 External test equipment has been calibrated and is operational.
2.4 Support systems required for the operation of the FWCS are operational.
2.5 Cab 1fng har been completed between the FWCS and interfa,ing e pipment.
OV 14.2-59
CESSAR Einnemu 9
3.0 TEST METHOD 3.1 Utilizing actual or simulated interface inputs to the FWCS, observe receipt of these signals at the FWCS.
3.2 Utilizing installed and external test instrumentation, vary all input signals to the system and observe output responses at the FWCS and at interfacing equipment.
4.0 DATA REOUIRED 4.1 Input signal values.
4.2 Status of interfacing control board equipment.
4.3 FWCS output response.
4.4 Status of output received at interfacing equipment.
5.0 ACCEPTANCE CRITERIA 5.1 The feedwater control system performs as described in Sections 7.7.1 and 10.4.7.
14.2.12.1.33 Core Operating Limit Supervisory System (COLSS) Test 1.O OBJECTIVE 1.1 To verify proper operation of the core operating limit supervisory system (COLSS).
2.0 PREREQUISITES 2.1 The on-line computer system is functioning to support this testing.
2.2 COLSS has been implemented into the on-line computer system.
2.3 Test cases have been generated and adopted to interface with the on-line computer test prograr.
2.4 Results of the test case runs performed on the COLSS FORTRAN code are availabic.
O\\
i 14.2-60 l
CESSAR EMMnCAMN i
l q
q 3.0 TEST METHOD 3.1 Using the test program contained in the on-line computer system, simulate the COLSS inputs for each test case.
4.0 DATA REOUIRED 4.1 Record values of all simulated
- inputs, appropriate l
l intermediate values and outputs.
The on-line test
)
program automatically performs this task.
5.0 ACCEPTANCE CRITER_TA 1
5.1 The core operating limit supervisory system performs as l
described in Section 7.7.1.
j
-l 14.2.12.1.34 Reactor Power Cutback System (RPCS) Test 1.0 OBJECTIVE 1.1 To demonstrate proper operation of the reactor power cutback system.
O 2.0
'1 PREREQUISITES 2.1 Construction activities on the RPCS have been completed.
l 2.2 RPCS instrumentation has been calibrated.
2.3 External test equipment has been checked and calibrated.
2.4 Support systems required for the operation of the RPCS are operational.
3.0 TEST METHOD 3.1 Utilizing actual or simulated interface inputs to the RPCS, observe receipt of these signals at the RPCS.
3.2 Utilizing installed and external instrumentation, vary all input signals to the system and observe output responses at the RPCb and at interfacing equipment.
0 1V l
14.2-61
CESSAR HEbnw e
4.0 DATA REOUIRED 4.1 Input signal values.
4.2 Status of interfacing control board equipment.
4.3 RPCS output response.
4.4 Status of outputs received at interfacing equipment.
5.0 ACCEPTANCE CRITERIA 5.1 The reactor power cutback system performs as described in Section 7.7.1.
14.2.12.1.35 Fuel Equipment Test 1.0 OBJECTIVE 1.1 To verify the proper operation of the Fuel Handling equipment.
2.0 PREREQUISITES 2.1 Construction activities on the systems to be tested are complete.
2.2 Permanently installed instrumentation is operable and calibrated.
2.3 Plant systems required to support testing are operable or temporary systems are installed and operable.
2.4 Test instrumentation is available and calibrated.
2.5 The reactor vessel head and upper guide structure are removed.
2.6 The core support barrel is installed and aligned.
2.7 Dummy fuel assemblies, dummy CEAs, and test weights are available.
3.0 TEST METHOD j
l 3.1 Verify the proper operation of the new fuel elevator I
and the full load interlock disabling the elevator raise feature.
O I
Amendment E 14.2-62 December 30, 1988
i
.CESSAR Ennncm8,.
E
.i 3.2 Verify the proper operation of the spent. fuel handling bridge, checking bridge, trolley, hoist speeds, load
-limits, interlocks, and limit. switches.
3.3 Using the X-Y coordinates and the spent--fuel handling machine, trial fit each of the spent fuel storage rack positions.-
3.4 Verify the transfer system using both consoles and upenders to prove proper operation.
1 3.5 Verify the proper
~ operation of :the dual masted j
refueling-machine. checking
- bridge, trolley, hoist speeds, limit switches, interlocks, and load limits.
3.6 Index the reactor core positions using the X-Y coordinates with the refueling machine.
1 3.7 Using a dummy fuel assembly, trial fit the storage racks and record coordinates.
3.8 Prove operability of the dry sipping equipment, checking console resistance temperature: detector (RTD) responses, and complete pneumatic and blowdown cycle.*
3.9 Verify the following:
~
3.9.1 Using tne full sequence of focusing, camera tilt. and camera rotation, verify the proper operation of the underwater TV camera system.
3.9.2 Utilizing the complete Fuel Handling equipment, transfer a dummy fuel assembly from.the new fuel elevator through a total fuel loading cycle in the reactor core and a total spent fuel cycle.from the core to the spent fuel storage area both in automatic and
= manual modes of operation.
3.9.3 Demonstrate the capabilities of the speci~al-fuel handling tools through proper operation with dummy fuel assembly and dummy control element assembly.
l i
- This portion of the test need not be performed prior to initial i
fuel load but may be performed prior to initial use of dry sipping equipment.
Amendment E l
14.2-63 December 30, 1988
CESSARina mu 4.0 DATA REOUIRED 1
4.1 Applicable indexing coordinates.
4.2 Monitoring instrumentation responses.
5.0 ACCEPTANCE CRITERIA l
J 5.1 The Fuel Handling and Storage System performs as described in Section 9.1.
14.2.12.1.36 Emergency Feedwater System 1.0 OFk7ECTIVE 1.1 To demonstrate the ability of the Emergency Feedwater System to supply feedwater to the steam generators for design emergency conditions.
2.0 PREREQUISITES 2.1 Construction activities on the systems to be tested are complete.
2.2 Permanently installed instrumentation is operable and calibrated.
2.3 Test instrumentation is available and calibrated.
I 2.4 Plant systems required to support testing are operable, or temporary systems are installed and operable.
3.0 TEST METHOD 3.1 Verify all control logic.
3.2 Verify head and flow characteristics of motor driven emergency feedwater pumps.
3.3 Verify the starting time and head and flow characteristics of the turbine-driven emergency feedwater pump at the full design range of steam pressures.
3.4 During the course of the startup program, demonstrate five consecutive cold quick starts for the steam driven emergency feedwater pump.
O Amendment E 14.2-64 December 30, 1988
CESSAR !afiric 12.
/~'s e
U 3.5 Verify all design flow paths and verify flow downstream of Venturi meets design requirement.
3.6 Verify proper operation in response to signals from the Plant Protection System.
3.7 Verify, if appropriate, proper operation, failure mode, stroking
- speed, and position indication of control valves.
3.8 Verify proper operation of protective
- devices, controls, interlocks, instrumentation and alarms using actual or simulated inputs.
3.9 Demonstrate proper pump performance during an endurance test.
4.0 DATA REOUIRED 4.1 Valve position indications.
4.2 Valve opening and closing times, wnere required.
[ 'T 4.3 Pump head versus flow curves.
k/
m 4.4 Flow rates downstream of Venturi.
4.5 Response of Emergency Feedwater Pumps to ESFAS signals.
4.6 Pump start times.
5.0 ACCEPTANCE CRITERIA 5.1 The Emergency Feedwater System performs as described in Section 10.4.9.
14.2.12.1.37 Reactor Coolant System Hydrostatic Test 1.0 OBJECTIVE 1.1 To verify the integrity of the Reactor Coolant System (RCS) pressure boundary and associated Safety Class I ciping.
2.0 PREREQUISITES 2.1 The RCS is
- filled, vented, and at the required temperature.
[D
( ).
2.2 The reactor coolant pumps are operable.
Amendment E 14.2-65 December 30, 1988
1 l
CESSAR n%nce O
E 2.3 Test pump is available.
I I
2.4 Primary safety valves are gagged or lamoved.
2.5 Permanently installed instrumentation necessary for testing is operable and calibrated.
2.6 Test instrumentation is available and calibrated.
3.0 TEST METHOD 3.1 Operate reactor coolant pumps to sweep gass' from the steam generator tubes.
3.2 Vent the RCS and all control element drive mechanism housings.
3.3 Operate the reactor coolant pumps to increase the RCS temperature to that required for pressurization of RCS to test pressure.
3.4 Perform the test in accordance with the ASME code.
4.0 DATA REOUIRED 4.1 RCS temperature, pressure.
5.0 ACCEPTANCE CRITERIA 5.1 The RCS hydrostatic test meets the requirements of ASME Boiler and Pressure Vessel Code,Section III.
14.2.12.1.38 CEDM Cooling System 1.0 OBJECTIVE 1.1 To verify the proper operation of the Control Element Drive Mechanism (CEDM) Cooling System.
2.0 OBJECTIVE 2.1 Construction activities on the systems to be tested are complete.
2.2 Permanently installed instrumentation is operable and calibrated.
2.3 Test instrumentation is available and calibrated.
O Amendment E l
14.2-66 December 30, 1988
CESSAR 8HViricarien n
O E
2.4 Plant systems required to support testing are operable, or temporary systems are installed and operable.
3.0 TEST METHOD 3.1 Verify all control logic.
3.2 Operate the system in the normal mode and verify system air flow and balance.
3.3 Verify the proper operation of interlocks and alarms.
3.4 During hot functional testing, verify that the system l
maintains design temperature under actual heat load I
conditions.
l 4.0 DATA REOUIRED 4.1 Air flow rates.
l 4.2 RCS temperatures and pressures.
4.3 Setpoints at which interlocks and alarms occur.
/
5.0 ACCEPTANCE CRITERIA 5.1 The CEDM Cooling System performs as described in Section 9.4.5.7.
14.2.12.1.39 Bafety Depressurization Subsystem Test 1.0 OBJECTIVE l
1.1 To verify.the proper operation of the Reactor Coolant l
Gas Venting. System.
l 1.2 To verify the proper operation of the Rapid i
Depressurization System.
2.0 PREREQUISITES i
2.1 Construction activities on the system to be tested are essentially complete.
l l
2.2 Plant systems required to support testing are operable, or temporary systems are installed and operable.
2.3 Permanently installed instrumentation is operable and
[T calibrated.
\\
/
v' Amendment E 14.2-67 December 30, 1988
CESSARn!L mu l
E 3.0 TEST METHOD 3.1 Verify that flow paths can be established through the Reactor Coolant Gas Venting System from the pressurizer to the Reactor Drain Tank.
3.2 Verify that flow paths can be established through the Reactor Coolant Gas Venting System from the reactor vessel to the Reactor Drain Tank.
3.3 Verify that total flow from the reactor vessel through the Reactor Coolant Gas Venting System meets design depressurization rates.
3.4 Verify that flow paths can be established through the Rapid Depressurization System from the pressurizer to the IRWST.
3.5 Verify that the total flow through the rapid depressurization syste.
meets design depressurization rates.
4.0 DATA REOUIRED 4.1 Valve position indications.
4.2 RCS temperature and pressures.
4.3 Flow rates through rapid depressurization system, and Reactor Coolant Gas Venting System.
4.4 Reactor Drain Tank temperature, pressure, level.
4.5 IRWST temperature, pressure, level.
5.0 ACCEPTANCE CRITERIA 5.1 The Reactor Coolant Gas Venting System allows venting of the pressurizer and reactor vessel through designed flow paths.
52 The total flow from the ramator vessel through the Reactor Coolant Gas Venting System meets the design depressurization rates.
l
\\
O i
Amendment E 14.2-68 December 30, 1988
CESSAR En@ication E
5.3 The rapid depressurization system allows depressurization through designed flow paths.
5.4 Total flow through rapid depressurization system meets the design depressurization rates.
14.2.12.1.40 Containment Spray System 1.0 Q&7ECTIVE 1.1 To verify the proper operation of the Containment Spray System and the containment spray pumps.
2.0 PREREQUISITES 2.1 Construction activities on the systems to be tested are complete.
2.2 Plant systems required to support testing are operable E,,
and temporary systems are installed and operable.
2.3 Permanently installed instrumentation is operable and calibrated.
.4 Test instrumentation is available and calibrated.
3.0 TEST METHOD 3.1 Verify proper operation of each containment spray pump with minimum flow established.
3.2 Verify pump performance including head and flow characteristics for all design flow paths.
3.3 Verify, if applicable, proper operation, failure node, stroking speed, and position indication of control valves.
3.4 Verify by using service air that the containment spray header and nozzles are free of obstructions.
3.5 Verify the automatic operation of all components in response to a containment spray actuation signal.
Amendment E 14.2-69 December 30, 1988
~
l CESSAREHL mu Y
4.0 DATA REOUIRED l
4.1 Valve position indications.
4 4.2 Pump head versus flow characteristics.
i 4.3 Valve opening and closing time, where required.
l 1
4.4 Setpoints at which interlocks and alarms occur.
l 1
5.0 ACCEPTANCE CRITERIA 5.1 The Containment Spray System and containment spray pumps perform as described in Section 6.5.
14.2.12.1.41 Integrated Engineered Safety Feat"res/ Loss of Power Test 1.0 OBJECTIVE
]
1.1 To verify the full operational sequence of the engineered safety features (ESF).
1.2 To demonstrate electrical redundancy, independence, and lo&d group assignment.
1.3 To demonstrate proper plant response to partial and full losses of offsite power.
2.0 PREREQUISITES 1
2.1 Individual system preoperational tests are complete.
2.2 Containment spray isolation valves are tagged shut.
2.3 Permanently installed instrumentation is operable and l
calibrated.
2.4 Test instrumentation is available and calibrated.
3.0 TEST METHOD J
1 3.1 Perform partial and full losses of offsite power.
1 Verify the proper response of ESF systems, alternate power
- sources, uninterruptible power
- supplies, and 1
instrumentation and control systems.
I O\\
l Amendment E i
14.2-70 December 30, 1988 l
CESSAR an&"icuian o
E 3.2 Under loss-of-power conditions, verify operability of systems / components from energized buses and absence of voltage on deenergized buses.
Include ESF systems, appropriate HVAC systems, decay heat removal systems, and systems required under post-accident conditions.
3.3 Demonstrate the proper diesel generator response to loss of power including bus energization, load sequencing, and load carrying capability.
Verify that full load is within diesel generator design capability.
3.4 Demonstrate proper response to actual or simulated engineered safety features actuation signals (ESFAS).
4.0 DATA REQUIRED 4.1 Response to ESFAS signals.
4.2 Diesel start times, load sequence times.
5.0 ACCEPTANCE CRITERIA 5.1 The ESFs respond as described in Chapter 6 and in g
Sections 7.3, 8.3, 9.3, 9.5, and 10.4.
i i
V 5.2 Electrical redundancy, independence, and load group assignments are as designed.
5.1 Plant response to partial and full losses of offsite power is as designed.
5.4 The diesel generators re-energize loads as designed and full load is within design capability.
14.2.12.1.42 In-containment Refueling Wdter Storage Tank-Subsystem 1.O OBJECTIVE 1.1 To demonstrate the proper operation of the IRWST subsystem.
2.0 PREREQUISITES 2.1 Construction activities on the systems to be tested are complete.
2.2 Plant systems required to support ~ testing are operable
[j.-)
or temporary systems are installed and operable.
\\
Amendment E 14.2-71 December 30, 1988
CESSAREHFine-
' O 2.3 Permanently installed instrumentation is operable and calibrated.
I 2.4 Test instrumentation is available and calibrated.
3.0 TEST METHOD 3.1 Operate control valves from all appropriate control positions.
Observe valve operation, position indication and, where required, measure opening and closing times.
3.2 Simulate failed conditions and observe valve response.
3.3 Fill the IRWST with reactor makeup water and record volume versus indicated level.
Observe level alarms.
3.4 Simulate IRWST temperature and observe alarms.
3.5 Verify design flow path from IRWST to the reactor cavity.
4.0 DATA REOUIRED 4.1 Valve position indications.
4.2 Valve opening and closing time, where required.
4.3 Response of valves to simulated failed conditions.
4.4 Setpoint at which alarms occur.
5.0 ACCEPTANCE CRITERIA 5.1 The IRWST subsystem performs as described in Section 6.3.
14.2.12.1.43 Internals Vibration Monitoring System l
1.O OBJECTIVE 1.1 To verify the proper operation of the Internals Vibration Monitoring System (IVMS) of the NSSS Integrity Monitoring System (NSSS IMS).
2.0 PREREOUISITEE 2.1 Construction activities on the NSSS IMS applicable to the IVMS are completed.
Amendment E 14.2-72 December 30, 1988
CESSAR EnnflCATICN
[v E
2.2
- Sensors, cables, and signal conditioning electronics are installed and operable.
2.3 Data analysis software programs are installed. and operable.
2.4 Power cabinets are operable to support testing requirements.
2.5 Required test equipment is operable.
3.0 TEST METHOD 3.1 Verify the ability to detect and record reactor core internal motion by applying simulated signals to the core internal motion channels.
3.2 Verify all alarming function, as applicable.
3.3 Verify that data analysis software programs receive appropriate data and perform specified analysis functions.
j 4.0 DATA REOUIRED
\\
.y 4.1 Data analysis results and evaluations.
5, 0 ACCEPTANCE CRITERIA 5.1 The IVMS performs as described in Section 7.7.1.6.1.
14.2.12.1.44 Loose Parts Monitoring System 1.0 OBJECTIVE 1.1 To verify the proper operation of the Loose Parts Monitoring System (LPMS) of the NSSS Integrity Monitoring System (NSSS IMS).
1.2 To adjust the loose parts alarm setpoints for power operation.
2.0 PREREQUISITES 2.1 Construction activities on the NSSS IMS applicable to l
the LPMS are completed.
I 2.2
- Sensors, cables, and signal conditioning electronics g
are installed and operable.
(V}
Amendment E 14.2-73 December 30, 1988
CESSAREnnnemu l
2.3 Power cabinets, test circuits, and amplifiers are ready to support testing.
l 2.4 Required test equipment is operational.
1 3.0 TEST METHOD i
1 3.1 Verify the calibration and alarm setpoint of the loos
]
parts monitoring channels with a mechanical impulse
]
type device.
3.2 Verify all alarm functions.
3.3 Establish baseline monitoring data for a
- cold, subcritical plant.
3.4 Establish the alarm level for loose parts channels in a cold, subcritical plant.
This alarm level will apply to the preoperational test phase, to startup, and to power operations.
4.0 DATA REOUIRED 4.1 Baseline vibration data.
4.2 Alarm levels applicable to detectable loose parts.
5.0 ACCEPTANCE CRITERIA 5.1 The LPMS perforr.s as described in Section 7.7.1.6.3.
]
5.2 The loose parts alarm setpoints have been adjusted for power operetion.
14.2.12.1.45 Acoustic Leak Monitoring System
]
1.0 OBJECTIVE 1.1 To verify proper operation of the Acoustic Leak Monitoring System (ALMS) of the NSSS Integrity Monitoring System (NSSS IMS).
1.2 To adjust the alarm setpoints under operational conditions.
1.3 To verify automated calibration features.
O Amendment E 14.2-74 December 30, 1988
n.
I CESSAR EnnnCATl*N j
E 2.0 PREREQUISITES 2.1 Construction activities on the NSSS IMS applicable.to the ALMS.
2.2
- Sensors, cables, and signal conditioning electronics are installed and operable, 2.3 Power cabinets, test circuits, and amplifiers are ready i
i to support testing.
2.4 Required test equipment is operable.
2.5 Data
- analysis, storage, and trending software is operable.
3.0 TEST METHOD 3.1 Verify the calibration and alarm setpoints using simulated signals to the acoustic monitoring channels.
3.2 Verify all alarm functions.
3.3 Establish baseline monitoring data under operating
'V conditions for a cold, subcritical plant.
3.4 Verify the automated electronics calibration functions, j
4.0 DATA REOUIRED l
4.1 Baseline acoustic data.
l 4.2 Alarm levels applicable to detection of coolant leaks.
l 5.0 ACCEPTANCE CRITERIA j
l 5.1 The ALMS performs as described in Section 7.7.1.6.2.
5.2 The alarm setpoints have been established.
1 I
\\
Amendment E 14.2-75 December 30, 1988
CESSAR Mairicari2n h
14.2.12.1.46 Data Processing System, and Discrete Indication and Alarm System 1.0 OBJECTIVE 1.1 To verify that the Data Processing System (DPS), as incorporated in the Advanced control
- complex, i's installed
- properly, responds correctly to external inputs and provides proper outputs to the distributed display, control, and permanent recording equipment.
1.2 To verify proper operation of the Discrete Indication and Alarm System (DIAS).
2.0 PREREQUISITES 2.1 Construction activities on the systems to be tested are complete.
2.2 Applicable operating manuals are available.
2.3 Required software is installed and operable.
2.4 External test equipment and instrumentation is available and calibrated.
2.5 Plant systems required to support testing are operable to the extent necessary to perform the testing or suitable simulation of these system are used.
3.0 TEST METHOD 3.1 Verify power sources to all related equipment.
3.2 Validate that external inputs are received and processed correctly by the appropriate system devices.
l 3.3 Verify that alarms and indication displays respond correctly to actual or simulated inputs.
3.4 Verify the operability of required software application programs.
3.5 Verify the correct operation of data output devices and displays at applicable work stations and terminals.
3.6 Evaluate processing system loading under actual or simulated operating conditions.
O Amendment E 14.2-76 December 30, 1988
i CESSAR Enn"icari:n O
4.0 DATA REOUIRED
{
i 4.1 Computer generated summaries of external input. data, data processing, analysis functions, displayed information, and permanent data records.
?
5.0 ACCEPTANCE CRITERIA i
5.- 1 The DPS and DIAS associated with the Advanced Control Complex performs as described in Section 7.7.1.3.
j i
14.2.12.1.47 Critical Function Monitoring (CFM) 1.0 OBJECTIVE 1.1 To verify the proper installation and operation of the CFM which operates as an application program of the Data Processing System (DPS).
1.2 To verify the proper performance of the Safety Parameter Displays (SPD) as incorporated into the CFM.
l 1.3 To verify the proper performance of the Inadequate Core
/n)
Cooling Monitoring (ICCM) displays as incorporated into 3
C/
the CFM.
l l
2.0 PREREQUISITES 2.1 Construction activities are essentially complete and the applicable systems and components are ready for testing.
l l
2.2 Applicable operating manuals are available.
2.3 Required software is installed and operable.
2.4 External test equipment and instrumentation is available and calibrated.
2.5 Plant systems required to support testing are operable to the extent necessary to perform the testing or suitable simulation of these systems are used.
3.0 TEST METHOD 3.1 Verify primary and backup power systems to system components.
O
(
Amendment E 14.2-77 December 30, 1988
k)!!h!h/klISERT IC A TION I
I E
3.2 Validate that required external inputs are received and i
processed correctly by the applicable system devices.
1 3.3 Verify that alarms and indication devices respond correctly to actual or simulated inputs.
3.4 Verify the correct operation of data output devices and displays at applicable terminal points.
4.0 DATA REOUIRED l
i 4.1 Data
- displays, alarm indications, and hardcopy printouts.
5.0 ACCEPTANCE CRITERIA 5.1 The CFM with it subfunctions of the SPDS and the ICCMS functions as described in Sections 7.5 and 7.7.1.10.
14.2.12.1.48 Pre-core Hot Functional Test Controlling i
Document 1.0 OBJECTIVE j
To demonstrate the proper integrated operation of plant systems when in simulated or actual operating configurations.
This shall include a demonstration that reactor coolant temperature and pressure can be lowered to permit operation of the shutdcwn cooling system and the shutdown cooling system can be used to achieve cold shutdown at a cool down rate not exceeding i
Technical Specification limits and a demonstration of I
the operation of the steam bypass valves.
1 l
2.0 PREREQUISITES 2.1 All construction activities on the systems to be tested are completed.
I 2.2 All permanently installed instrumentation on systems to be tested have been properly calibrated and are operational.
2.3 All necessary test instrumentation is available and properly calibrated.
2.4 Hydrostatic testing has been completed.
O Amendment E 14.2-78 December 30, 1988
CESSAR 8anneuieu (V
2.5 Steam generators are in set layup in accordance with the NSSS Chemistry manual.
2.6 Reactor internals, as appropriate for pre-core hot functional testing, have been installed.
3.0 TEST METHOD 3.1 Specify plant conditions and coordinate the execution of the related pre-core hot functional test appendices.
1 4.0 DATA REOUIRED l
4.1 As specified by the individual pre-core hot functional test appendices.
5.0 ACCEPTANCE CRITERIA 5.1 Integrated operation of the RCS, secondary, and related auxiliary systems perform in accordance with design criteria.
5.2 RCS temperature and pressure can be lowered to permit operation of the shutdown cooling system.
5.3 The shutdown cooling system is used to achieve cold shutdown at a
cool down rate note in excess of Technical Specification limits.
5.4 The steam bypass valves can be operated to control RCS I
temperature.
5.5 As specified by the individual pre-core hot functional test procedures.
14.2.12.1.49 Pre-core Instrument Correlation 1.0 OBJECTIVE 1.1 To demonstrate that the inputs and appropriate outputs between the
- PPS, Process Instrumentation, Discrete Indication and Alarm System and Data Processing System E
are in agreement.
1.2 To verify narrow range temperature an pressure instrumentation accuracy and operation by comparing similar channels of instrumentation.
a Amendment E i
14.2-79 December 30, 1988 I
i l
CESSAR Eininema O
2.0 EEEREOUISITES 2.1 Instrumentation has been calibrated and is. operational.
3.0 TEST METHOD 3.1 Record wide range process instrumentation DIAS and Data Processing System readings as directed by the Pre-core E
Hot Functional Test.
3.2 Record narrow range process instrumentation DIAS and Data Processing System readings as directed by the Pre-core Hot Functional Test.
4.0 DATA REOUIRED 4.1 Control room panel instrument reading.
4.2 DIAS and DPS readings.
E 5.0 ACCEPTANCE CRITERIA 5.1 All narrow range instrument readings shall agree within the accuracy of the instrumentation.
5.2 All wide range instrument readings shall agree within the accuracy of the instrumentation.
14.2.12.1.50 Remote Shutdown Panel 1.0 OBJECTIVE 1.1 To verify proper operation of the Remote Shutdown Instrumentation.
1.2 To determine that the plant can be cooled down from the remote shutdown panel.
I 2.0 PREREQUISITES 2.1 All construction activities on the remote shutdown panel have been completed.
2.2 All remote shutdown panel instrumentation has been calibrated.
2.3 The communication systems between the control room and remote shutdown panel location has been demonstrated to be operational.
Amendment E 14.2-80 December 30, 1988
CESSAR 8HMeum G
V E
3.0 TEST METHOD 3.1 Using simulated signals, verify proper operation of remote shutdown panel instrumentation.
3.2 During preoperational Post Core Hot Functional tests, perform a controlled cooldown from the remote shutdown panel.
4.0 DATA REOUIRED 4.1 RCS temperatures, pressures.
1 5.0 ACCEPTANCE CRITERIA 5.1 The ability to cooldown using Remote Shutdown Instrumentation has been demonstrated.
14.2.12.1.51 Alternate Protection System 1.0 OBJECTIVE 1.1 To demonstrate the proper operation of the Alternate Protection System (APS).
2.0 PREREQUISITES l
2.1 Construction activities on the trip circuit breaker and the alternate protection system have been calibrated.
2.2 APS instrumentation has been calibrated.
2.3 External test instrumentation is available and calibrated.
2.4 Support systems required for operation of trip circuit breaker and APS are operational.
3.0 TEST METHODS 3.1 Energize power supplies and verify output voltage.
3.2 Simulate ground faults and observe operation of the ground fault detectors.
3.3 Using simulated signals, trip each reactor trip circuit breaker with the breaker in the test position.
Observe circuit breaker operation.
D\\
l l
L Amendment E l
14.2-81 December 30, 1988
CESSAR Eanneuiu
'Ill>
3.4 Repeat Step 3.3 with circuit breaker in operate
]
position.
3.5 Simulate input signals and observe trip initiations.
4.0 DATA REOUIRED 4.1 Power supply voltages.
4.2 Resistance for ground fault detector operation.
4.3 Trip setpoints.
5.0 ACCEPTANCE CRITERIA 5.1 The APS performs as described in Section 7.7.1.1.11.
14.2.12.1.52 Pre-core Test Data Record 1.0 OBJECTIVE 1.1 To monitor instrumentation during integrated plant operation.
1.2 To verify, by cross checking channels, the satisfactory tracking of process instrumentation.
1.3 To provide a permanent record of plant pre-core loading parameter indication.
2.0 EEEREOUISITES 2.1 Instrumentation has been calibrated and is operational.
3.0 TEST METHOD 3.1 Record control room instrumentation steady state readings as directed by the pre-core hot functional test controlling document.
4.0 DATA REOUIRED 4.1 Plant conditions at time when instrument readings are recorded.
4.2 Instrument readings.
j l
O Amendment E 14.2-82 December 30, 1988 i
CESSAR En#1CATICN O
v 5.0 ACCEPTANCE CRITERIA 5.1 All.like instrumentation readings shall agree within the accuracy limits of the instrumentation.
14.2.12.1.53 Prs-core Reactor Coolant System Expansion Measurements l
1.O OBJECTIVE 1.1 To demonstrate that the RCS components are free to expand thermally as designed during initial plant heatup and return to their baseline cold. position after the initial cooldown to ambient temperatures.
2.0 PREREQUISITES 2.1 All construction activities have been completed on the RCS components.
2.2 Initial ambient dimensions have been set on the steam I
generator and RC pump hydraulic snubbers, upper and I
lower steam generator and reactor vessels keys, and RC l
pump columns.
E V
2.3 Initial ambient dimensions for the steam generator, reactor vessel, and reactor coolant pump supports have i
been recorded.
I 3.0 TEST METHOD 1
3.1 Clearances at hydraulic snubber
- joints, keys, and E
I column clevisis shall be checked at 50"F. increments l
during heatup and recorded at 100*F increments.
3.2 At stabilized conditions, record all steam generator, reactor vessel, and reactor coolant pump clearances.
E l
4.0 DATA REOUIRED I
4.1 Plant conditions.
4.2 Clearances at the steam generator sliding base keys, hydraulic snubber
- joints, upper
- keys, and piston setting at hydraulic snubbers.
E 4.3 Clearance between the reactor vessel upper and lower supports and expansion plates.
i Amendment E 14.2-83 December 30, 1988 a-
l l
CESSAR EHL"lCATI';N Oi 4.4 Reactor vessel support temperature.
4.5 Clearances at the reactor coolant pump snubbers, column joints, and piston setting for the hydraulic snubbers.
E
]
4.6 Clearances at all test points after cooldown.
5.0 ACCEPTANCE CRITERIA 5.1 Unrestricted expansion for selected points on components.
5.2 Verification that components return to their baseline ambient position.
5.3 Verification that proper gaps exist for selected points on components.
14.2.12.1.54 Pre-core Reactor Coolant and Secondary Water Chemistry Data 1.0 OBJECTIVE 1.1 To demonstrate that proper water chemistry for the RCS and steam generator can be maintained.
1 2.0 PREREQUISITES 2.1 Primary and secondary sampling systems are operable.
2.2 Chemicals to support hot functional testing are available.
2.3 The primary and secondary chemical addition systems are operable.
2.4 Purification ion exchangers are charged with resin.
3.0 TEST METHOD 3.1 Minimum sampling frequency for the steam generator and RCS will be specified by the chemistry manual.
The sampling frequency will be modified as required to ensure the proper RCS and steam generator water chemistry.
O Amendment E 14.2-84 December 30, 1988
v 1
( IE5iSL Alft !!!!nne n:o l
OU 3.2 Perform RCS and steam generator' sampling and chemistry analysis after every significant change in plant conditions (i.e.,
- heatup, cooldown, chemical additions).
4.0 DATA REOUIRED i
I 4.1 Plant conditions.
4.2 Steam generator chemistry analysis.
4.3 RCS chemistry analysis.
5.0 ACCEPTANCE CRITERIA 5.1 RCS and steam generator water chemistry can be l
maintained as described in Sections 9.3.4 and 10.3.4, l
14.2.12.1.55 Pre-core Pressurizer Performance 1
1.0 OBJECTIVE 1.1 Demonstrate that the pressurizer pressure and level control systems function properly.
1.2 Demonstrate proper operation of the' auxiliary spray valves and pressurizer heaters.
1.3 Demonstrate proper operation of the letdown flow l
control valves and charging pumps.
l l
2.0 PREREQUISITES 1
2.1 Pressurizer pressure and level control system instrumentation has been calibrated.
2.2 Support systems required for the operation of the pressurizer pressure and level control systems are operational.
2.3 Test equipment is available and calibrated.
3.0 TEST METHOD 3.1 Simulate a decreasing pressurizer pressure and observe heater response and alarm and interlock setpoints.
14.2-85
1 CESSAR Eanneui:n l
l O
3.2 Simulate an increasing pressurizer pressure and observe heater and spray valve response and alarm and interlock setpoints.
3.3 Simulate a low level error jn the pressurizer and observe proper charging pump response and alarm and interlock setpoints.
3.4 Simulate a high level error in the pressurizer and observe proper charging pump response and alarm and interlock setpoints.
3.5 Simulate a low pressurizer level and observe operation of the letdown control valves.
3.6 Simulate a low-low pressurizer level and observe heater response and alarm and interlock setpoints.
4.0 DATA REQUIRED 4.1 Response of pressurizer heaters to simulated pressure and level signals.
4.2
Response
of spray valves to simulated pressurizer pressure.
4.3 Response of charging pumps to simulated pressurizer level.
l 4.4 Recponse of letdown control valves to simulated pressurizer level.
4.5 Response of letdown control valves to simulated low i
pressurizer level.
4.6 Values of parameters at which alarms and interlocks occur.
5.0 ACCEPTANCE CRITERIA 5.1 The pressurizer performs as described in Sections 7.7.1 and 5.4.10.
O 14.2-86 l
CESSAR EL"icarien
,c b
14.2.12.1.56 Pre-core Control Element Drive Mechanism Performance 1.0 OBJECTIVE 1.1 To determine the effectiveness of the CEDM cooling system by measurement of coil resistance at several temperature plateaus during RCS heatup.
1.2 To determine the operating temperature of the upper gripper coils.
1.3 To verify proper operation and sequencing of the CEDM armatures.
2.0 PREREQUISITES 2.1 CEDM coil stacks are assembled and associated cabling is conn 2cted.
2.2 Cabling between the reactor bulkhead and the CEDM control System is disconnected.
2.3 CEDM
" cold" coil resistance has been measured and b
recorded.
2.4 Individual CEDM cable resistance has been measured and recorded.
2.5 CEDM cooling system is operational.
l 2.6 Test equipment is available and calibrated.
2.7 Support systems required for operation of the CEDM are i
operational.
i 3.0 TEST METHOD i
3.1 At the specified RCS temperature and pressure, measure and record the loop resistance for each of the CEDM coils.
3.2 Balance CEDM cooling system as required to maintain the coil temperatures within the specified limits.
3.3 Connect cabling between the reactor bulkhead and the CEDMCS cabinets and energize the CEDM.
Measure and record the DC voltage'across the upper gripper coil and
's across the shunt on the CEDMCS Power Switch Assembly
[Q Pcnol.
14-2-87 l
1 ke!!hhkhkbbr$kiCATl2N i
1 I
O 3.4 Operate the CEDM and observe count totalizer operation.
i 4.0 DATA REOUIRED 4.1 CEDM " cold" coil resistance.
4.2 CEDM cable resistance.
4.3 RCS temperature and pressure.
4.4 CEDM coil loop resistance at specified RCS temperature and pressure.
4.5 DC voltage across the upper gripper coil at the specified RCS temperature and pressure.
4.6 DC voltage across the shunt.
4.7 CEDM count totalizer readings.
5.0 MLQ.EPTANCE CRITERIA 5.1 The control element drive mechanism performs as described in Section 7.7.1.
14.2.12.1.57 Pre-core Reactor Coolant System Flow Measurements 1.0 OBJECTIVE 1.1 To determine the pre-core RCS flow rate.
1.2 To establish baseline RCS pressure drops.
2.0 PREREQUISITES 2.1 All permanently installed instrumentation has been properly calibrated and is operational.
2.2 All test instrumentation has been checked and calibrated.
2.3 RCS operating at nominal hot, zero power conditions.
2.4 Desired reactor coolant pumps operating.
2.5 COLSS, CPCs, and Data Process:ng System in operation.
E O
Amendment E 14.2-88 December 30, 1988 i
-~
CESSAR Eanncmou 3.0 TEST METHOD 3.1 RCS flow, pressure drops, and the data necessary to calculated RCS flows for four reactor coolant pump operations will be obtained.
4.0 TEST DATA 4.1 Data Processing System.
E 4.2 RCP differential pressure.
4.3 RCS temperature and pressure.
4.4 RCP speed.
4.5 Reactor vessel differential pressure.
4.6 Pump configurations.
5.0 ACCEPTANCE CRITERIA 5.1 The RCS flow exceeds the value necessary to insure that post core flow is in excess of that used for analysis E
in Chapter 15 but less than the flow which could cause core uplift.
14.2.12.1.58 Pre ~ core Reactor Coolant System Heat Loss 1.O Olk7ECTIVE 1.1 Measure RCS heat loss under hot, zero power conditions.
1.2 Measure pressurizer heat loss under hot, zaro power conditions.
2.0 PREREQUISITES 2.1 Test instrumentation is available and calibrated.
2.2 Constr"ction activities on the RCS and associated syster, are completed.
2.3 All permanently installtid instrumentation on the system to be tested is available and calibrated.
3.0 TEST METHOD 3.1 Determine the RCS heat loss using the steam-down method.
Amendment E 14.2-89 December 30, 1988
CESSAR sanricari:n l
l 9
3.1.1 Stabilize the steam generator levels with the RCS at hot, zero power conditions.
.s 3.1.2 Secure steam generator feedwater and blowdown.
3.1.3 Measure both the pressurizer heater power required to maintain RCS temperature and pressure and RCP power.
3.1.4 Perfocm a heat balance calculation to determine heat loss.
3.2 Determine the pressurizer heat loss, with* and without E
continuous spray flow, by measuring the pressurizer heater power required to maintain the RCS at hot, zero power conditions, and then performing a heat balance calculation.
4.0 DATA REOUIRED 4.1 RCS temperatures.
4.2 Pressurizer pressure and level.
4.3 Steam generator pressures and levels.
4.4 Pressurizer heater power.
4.5 RCP power.
5.0 ACCEPTANCE CRITERIA 5.1 The measured heat loss is less than, or equal to, the anticipated heat loss or an engineering evaluation finds the results acceptable.
Pressurizer heat loss with continuous spray flow to be determine during post core hot functional test after spray E
valve adjustments have been performed per Section 14.2.12.3.6.
O Amendment E 10.2-90 December 30, 1988 1
CESSAR Eanncamn c
14.2.12.1.59 Pre-core Reactor Coolant System Leak Rate Measurement 1.0 OBJECTIVE 1.1 To measure the reactor coolant leakage at hot, zero power conditions.
2.0 PREREQUISITES 2.1 Hydrostatic testing of the RCS and associated systems has been completed.
2.2 The RCS and the CVCS are operating as a closed system.
2.3 The RCS is at hot, zero power conditions.
3.0 TEST METHOD 3.1 Measure r.WJ record the changes in water inventory. of the RCS and CVCS for a specified interval of time.
4.0 TEST DATA rs
(_,
4.1 Pressurizer pressure, level, and temperature.
l 4.2 Volume control tank level, temperature, and pressure.
4.3 Reactor drain tank level, temperature, and pressure.
4.4 RCS temperature and pressure.
4.5 Safety injection tank level and pressure.
4.6 Time interval.
5.0 ACCEPTANCE CRITERIA 5.1 Identified and unidentis ad leakage shall be within the limits described in the echnical specification.
14.2.12.1.60 Pre-core Chemical and Volume Control System Integrated Test l
1.0 OBJECTIVE 1.1 To verify proper operation of the letdown subsystem and q
i l
ion exchangers.
I
\\~-)
14.2-91
CESSAR EE'Jnem 1
O i
2.0 PREREQUISITES j
i 2.1 The CVCS is in operation.
l 2.2 Selected ion exchanger has been filled with special l
anion resin.
2.3 Ion exchangers not to be used have been bypassed.
l l
2.4 Associated instrumentation has been checked and calibrated.
l 3.0 TEST METHOD 3.1 Taking manual control of the letdown control valve controller, position the letdown flow control valve to obtain various letdown flow rates between 0% and 100%
flow, inclusive.
3.2 Measure and record the pressure drops across the ion exchanger, filter, and strainer.
4.0 DATA REOUIRED 4,1 Letdown control valve controller settings.
4.2 Letdown temperature, pressure, and flow ratas.
4.3 Charging temperature and flow rates.
4.4 Ion exchanger,
- filter, and strainer differential pressure.
4.5 Volume control tank pressure and level.
4.6 Pressurizer level.
4.7 RCS temperature and pressure.
5.0 ACCEPTANCE CRITERIA i
)
5.1 The chemical and volume control system performs as described in Section 9.3.4.
1 O1 14.2-92
CESSAREnnnc-
\\
O 14.2.12.1.61 Pre-core Safety Injection Check Valve Test 1.O OBJECTIVE 1.1 To verify that the safety injection tank discharge l
check valve will pass flow with the RCS at hot, zero power conditions.
l 1.2 To verify that the safety injection loop check valves will pass flow with the RCS at
- hot, zero power conditions.
1 2.0 PREREQUISITES,
l 2.1 RCS at hot, zero power conditions.
2.2 Safety injection tanks are filled and pressurized to their normal operating conditions.
2.3 CVCS is in operation.
3.0 TEST METHOD
)
3.1 Verify flow through the safety injection loop check
(,/
valves by lining up the CVCS charging pumps to
)
discharge into the safety injection discharge header.
)
3.2 Verify flow through each safety injection tank i
discharge check valva by flowing back to the IRWST.
E 4.0 TEST DATA
)
1 4.1 Safety injection tank level and pressure.
4.2 Safety injection discharge header pressure.
4.3 CVCS charging pump flow.
5.0 ACCEPTANCE CRITERIA 5.1 Verification that the loop check valves and safety injection tank discharge check valves will pass flow with the RCS at hot, zero power conditions.
OV Amendment E 14.2-93 December 30, 1988 l
CESSARn % mu O
14.2.12.1.62 Pre-core Boration/ Dilution Measurements 1.0 QBJECTIVE 1.1 To demonstrate the ability of the CVCS to control the t
boron concentration of the reactor coolant system by the feed and bleed method.
1.2 To demonstrate the ability of the CVCS to supply concentrated boric acid to the reactor coolant system.
2.0 PREREQUISITES 2.1 BAST is filled with borated water.
E 2.2 The boron addition system is operational.
2.3 The boronometer is operational.
2.4 RCS and CVCS boron concentration is zero (0) ppm.
3.0 TEST METHOD 3.1 Line up the Boric Acid Makeup (BAMU) pumps to take suction from the BAST and discharge to the charging pump suction and to the RCS, and observe operation of E
the boron addition system.
3.2 Perform boration and dilution operation of the Reactor l
Coolant System (RCS) by operating the boric acid makeup control system in its various modes of operation.
3.3 Sample the RCS during boration and dilution operations and observe operation of the boronometer.
4.0 DATA REOUIRED 4.1 RCS temperature and pressure.
4.2 Makeup controller flow readings and setpoints.
4.3 Chemical analysis of boron concentration.
4.4 VCT level.
4.5 Boronometer readings.
4.6 Charging flow rates.
O Amendment E 14.2-94 December 30, 1988
CESSARM.h mu
)
v 4.7 Letdown flow rate.
5.0 ACCEPTANCE CRITERIA 5.1 The boration subsystem performs as described in Section 9.3.4.
14.2.12.1.63 Downcomer Feedwater System Water Hammer Test 1.0 OBJECTIVE 1.1 To demonstrate the absence of any significant water hammer during steam generator water level recovery following the exposure of the downcomer feedwater sparger to a steam environment.
2.0 PREREQUISITES 1
I 2.1 Construction activities on the Emergency Feedwater system (EFWS) and those sections of the Main Feedwater i
System (MFWS) that are affected have been completed.
2.2 Feedwater Control Systems (FWCS) instrumentation and g
other appropriate permanently installed instrumentation i
i
(
has been calibrated.
l 2.3 Main Steam System is available.
2.4 Appropriate AC and DC power sources are available.
2.5 RCS operating at nominal hot, zero power conditions (hot standby).
3.0 TEST METHOD 3.1 Lower the steam generator water level below the feedwater sparger but within the Narrow Range (NR) level indication band for a period of 30 minutes (n E
feedwater will be introduced into the generator through the sparger during this period).
3.3 Station personnel as appropriate
- to monitor for noise l
or vibration.
3.4 Initiate emergency feedwater flow to restore steam generator level in a manner that simulates automatic l
EFW actuation.
Personnel safety will limit proximity to Feedwater System.
Amendment E 14.2-95 December 30, 1988 1
CESSAR Eink",cm:n O
4.O ACCEPTANCE CRITERIA 4.1 Visual inspection indicates that the integrity of feedwater piping, supports, and sparger* have not been violated.
14.2.12.2 Post-core Hot Functional Tests 14.2.12.2.1 Post-core Hot Functional Test Controlling Document 1.O OBJECTIVE 1.1 To demonstrate the proper integrated operation of plant
- primary, secondary, and auxiliary systems with fuel loaded in the core.
2.0 PREREQUISITES 2.1 All pre-core hot functional testing has been completed as required.
2.2 Fuel loading has been completed.
2.3 All permanently installed instrumentation on systems to be tested is available and calibrated in accordance with technical specifications and test procedures.
2.4 All necessary test instrumentation is available and calibrated in accordance with technical specifications and test procedures.
2.5 All cabling between the CEDMs and the CEDM control system is connected.
i 2.6 Steam generators are la wet layup in accordance witn the NSSS chemistry manual.
2.7 RCS has been borated to the proper concentration.
- Visually inspect during next regular SG inspection following testing.
O 14.2-96
CESSAR Ennr"icariou 9
3.0 TEST METHOD 3.1 Specific plant conditions and coordinate the execution of the related post-core hot functional test appendices.
4.0 DATA REOUIRED 4.1 As specified by the individual post-core hot functional test appendices.
5.0 ACCEPTANCE CRITERIA 5.1 Integrated operation of the primary, secondary, and related auxiliary systems is in accordance with the system descriptions.
E 14.2.12.2.2 Loose Parts Monitoring System i
1.0 OBJECTIVES 1.1 To obtain baseline data on the Loose Parts Monitoring System (LPMS).
1.2 To adjust LPMS alarm setpoints as necessary.
2.0 PREREQUISITES 2.1 Preoperational tests on LPMS have been completed.
2.2 All LPMS instrumentation has been calibrated and are operable.
3.0 TEST METHOD 3.1 Collect baseline data using the LPMS during plant heatup and at normal operating conditions.
3.2 Analyze baseline data and, if necessary, adjust alarm setpoints.
4.0 DATA REOUIRED 4.1 Baseline data using LPMS.
4.2 LPMS alarm setpoints.
4.3 RCS temperature and pressure.
O Amendment E 14.2-97 December 30, 1988
i CESSARMnincm O
5.0 ACCEPTANCE CRITERM E
5.1 LPMS performs as described in Section 7.7.1.6.3.
l 5.2 The LPMS alarm setpointu have been adjusted as necessary.
14.2.12.2.3 Post-core Reactor Coolant System Flow Measurements 1.0 OBJECTIVE 1.1 To determine the post-core RCS flow rate and flow coastdown characteristics.
1.2 To establish reference post-core RCS pressure drops.
1.3 To make adjustments to the flow related constants of the CPCs as required.
1.4 To collect data on the operation of the flow related portions of the COLSS and the CPCs for steady-state and transient conditions.
2.0 PREREQUISITES 2.1 Construction activities completed.
2.2 All permanently installed instrumentation is properly calibrated and operational.
2.3 All test instrumentation is available and properly calibrated.
2.4 RCS operating at nominal hot, zero power conditions.
2.5 Required reactor coolant pumps are operational.
2.6 COLSS and CPCs are in operation.
3.O TEST METfQD 3.1 RCS flow is measured for all operationally allowed j
reactor coolent pump comninationc and the necessary j
data to calculate RCS flow is collected.
]
O I
Amendment E 14.2-98 December 30, 1988
CESSARn h mu O
3.2 RCS flow coastdown measurements are pat?ormed by tripping the allowable reacter coolant pump (s) for collection of coastdown data.
3.3 CPCs and COLSS flow related data is varified by comparison with measured flows.
4.0 DATA REOUIRED l
4.1 COLSS and CPCs flow related data.
4.2 Reactor coolant pump differential pressure and speed.
4.3 Reactor vessel differential pressure.
4.4 RCS temperature and pressure.
4.5 Pump configuration.
4.6 Coastdown time.
5.0 ACCEPTANCE CRITERIA
)
51 Measured RCS flow exceeds the flow rates used in the
(/
safety analysis in Chapter 15.
l 5.2 Measured RCS flow coastdown is conservative with respect to the coastdown used in the safety analysis.
5.3 CPC and COLSS flow constants are adjusted to be conservative with respect to the measured flows and for those portions of the coastdowns which occur prior to CPC initiation of a trip.
14.2.12.2.4 Post-core Control Element Drive Mechanism Performance 1.0 OBJECTIVE 1.1 To demonstrate the proper operation of the CEDMs and CEAs under Hot Shutdown and hot, zero power conditions.
1.2 To verify proper operation of the CEA position indicating system and alarms.
1.3 To measure CEA drop times.
(
14.2-99 l
l
CESSAR EBOicari3.
O' 2.0 PREREQUISITES 2.1 The CEDMCS pre-core performance test has been completed.
2.2 All test instrumentation is available and calibrated.
2.3 Plant Monitoring rystem is operational.
2.4 The CEDM cooling system is operational.
2.5 CEDM coil resistance has been measured.
3.0 TEST METHOD 3.1 Perform the following at Hot Shutdown conditions:
3.1.1 Withdraw and insert each CEA to verify proper operation of CEDM.
3.2 Perform the following at hot, zero power conditions:
I 3.2.1 Withdraw and insert each CEA to verify proper operation
[
of CEDM.
3.2.2 Measure and record drop time for each CEA.
3.2.3 Perform three measurements of drop time ' for each of I
those CEAs falling outside the two-sigma limit for similar CEAs.
3.3 Perform the following at any time:
3.3.1 Withdraw and insert each CEA while recording position indications and alarms.
4.0 DATA REOUIRED 4.1 CEA drop time.
4.2 RCS temperature and pressure to be taken during measurement and recording of drop time for each CEA.
4.3 CEA position and alarm indications.
5.0 ACCEPTANCE CRITERIA 5.1 The CEDM/CEAs and their associated position indications operate as described in Section 7.7.1.
O 14.2-100
CESSAR 82Mncuc,,
O b
5.2 CEA drop times are in agreement with the Technical Specifications.
5.3 CEA insertion and withdrawal times meet design E
requirements.
14.2.12.2.5 Post-core Reactor and Secondary Water Chemistry Data 1.0
,QLkTECTIVE 1.1 To maintain the proper water chemistry for the RCS and steam generators during post-core hot functional l
testing.
2.0 PREREQUISITES 2.1 Primary and secondary sampling systems are operable.
2.2 Chemicals to support hot functional testing are i
i available.
l 2.3 The primary and secondary chemical addition system are
(
1 2.4 Purification ion exchangers are charged with resin.
3.0 UST METHOD i
1 3.1 Minimum sampling frequency for the steam generator and l
l RCS will be as specified by the chemistry manual.
The sampling frequency will be modified as required to ensure the proper RCS and steam generator water chemistry.
3.2 Perform RCS and steam generator sampling and chemistry analysis after every significant change in plant conditions (i.e.,
- heatup, cooldown, chemical additions).
4.0 DATA REOUIRED 4.1 Plant conditions.
4.2 Steam generator chemistry analysis.
4.3 RCS chemistry analysis.
A
- j 1
Amendment E 14.2-101 December 30, 1988 l
l L_____-----
CESSAR n!nnCATl!N O'
5.0 ACCEPTANCE CRITERIA 5.1 RCS and steam generator water chemistry can be maintained as described in Sections 9.3.4 and 10.3.4.
5.2 Baseline data for the steam generators and RCS is established.
14.2.12.2.6 Post-core Pressurizer Spray Valve and Control Adjustments 1.0 OBJECTIVE 1.1 To establish the proper settings of continuous spray valves.
1.2 To measure the rate at which pressurizer pressure can be reduced using pressurizer spray.
2.0 PREREQUISITES 2.1 The RCS is being operated at nominal hot, zero power conditions.
2.2 All permanently installed instrumentation is available and calibrated.
2.3 Test instrumentation is available and calibrated.
3.0 TEST METHOD 3.1 Adjust continuous spray valves to obtain specified Delta T between the RCS temperature and pressurizer spray line temperature.
3.2 Using various combinations of pressurizer spray valves, measure and record the rate at which the pressurizer pressure can be reduced.
4.0 DATA REOUIRED 4.1 RCS temperature and pressure.
4.2 Spray line temperature.
4.3 Continuous spray valve settings.
l 4.4 Spray valve combinations.
14.2-102 L _ ___________ ___ _ ____
l I
l CESSAR8ah mu O
V 5.O ACCEPTANCE CRITERIA 5.1 The pressurizer performs as described in Sections 7.7.1 and 5.4.10.
14.2.1242.7 Post-core Reactor Coolant System Leak Rate Measurement 1.0 OBJECTIVE 1.1 To measure the post-core load RCS leakage at hot, zero power conditions.
2.0 PREREQUISITES 2.1 Hydrostatic testing of the RCS and associated systems has been completed.
1 2.2 The RCS and the CVCS are operating as a closed system.
2.3 The RCS is at hot, zero power conditions.
2.4 All permanently mounted instrumentation is properly
,O) calibrated.
v 3.O TEST METHOD 3.1 Measure and record the changes in water inventory of the RCS and CVCS for a specified interval of time.
4.0 DATA REOUIRED 4.1 Pressurizer pressure, level, and temperature.
4.2 Volume control tank level, temperature, and pressure.
4.3 Reactor drain tank level, temperature, and pressure.
4.4 RCS temperature and pressure.
4.5 Safety injection tank level and pressure.
4.6 Time interval.
5.0 ACCEPTANCE CRITERIA 5.1 Ident1.fied and unidentified leakage shall be within the limits described in the Technical Specifications.
A J (V
14.2-103 1
CESSAR Ene"ic 12.
9 1.2.12.2.8 Post-core In-core Instrumentation Test 1.0 OBJECTIVE f
1.1 To measure the leakage resistance of the fixed in-core detectors.
]
2.0 PREREQUISITES 2.1 All permanently installed instrumentation is properly calibrated.
2.2 Installation and preoperational checkout of the in-core j
instrumentation is completed.
{
l 2.3 In-core instrumentation to the Data Processing System E
(DPS) has been installed.
I 2.4 The DPS is operational.
2.5 Special test equipment is available and calibrated.
3.0 TEST METHOD 3.1 Measure and record the leakage resistance of each in-core detector at the nominal
- hot, zero power conditions.
E 4.0 DATA REOUIRED 4.1 RCS temperature and pressure.
4.2 Leakage resistance measurements.
4.3 Plant Monitoring System readout.
4.4 Movable in-core detector selection and guide tube path selection.
5.O ACCEPTANCE CRITERIA i
5.1 Leakage resistance of the in-core detectors is as E
described in manufacturer's recommendations.
14.2.12.2.9 Post-core Instrument Correlation 1.O OBJECTIVE 1.1 To demonstrate the proper operation of the PPS, CPC, DPS and DIAS.
E Amendment E 14.2.1.04 December 30, 1988
CESSAR !!Minem:n O
2.0 PREREQUISITES 2.1 Core Protection Calculators (CPCs) are in operation.
2.2 DPS, DIAS and COLSS are in operation.
2.3 Permanently installed control room instrumentation for the CPCs, COLSS, PPS, DPS and DIAS systems have been calibrated and is in operation.
3.0 TEST METHOD 3.1 When specified, obtain PPS, CPC, DPS and DIAS readouts.
3.2 Obtain control room instrument readings.
4.0 DATA REOUIRED 4.1 DPS and DIAS readout.
l 4.2 PPS and-CPC data.
4.3 Control room instrument readings.
O 5.0 I
ACCEPTANCE CRITERIA 5.1 The
- DPS, DIAS,
14.Z.12.2.10 Acoustic Leak Monitoring System l
1.0 OBJECTIVES 1.1 To obtain baseline data on the Acoustic Leak Monitoring System (ALMS).
1.2 To adjust ALMS alarm setpoints as necessary.
2.0 PREREQUISITES 2.1 Preoperational tests on ALMS have been completed.
l 2.2 All ALMS instrumentation have been calibrated are operable.
C\\
O l
Amendment E 14.2-105 December 30, 1988
m CESSARE!ah m.
j 4
E 3.0 TEST METHOD 3.1 Collect baseline data using the ALMS during plant l
heatup and at normal operation conditions.
J 4.0 DATA REOUIRED l
4.1 Baseline data using ALMS.
4.2 ALMS alarm setpoints.
4.3 RCS temperature and pressure.
5.0 ACCEPTANCE CRITERIA 5.1 ALMS performs as described in Section 7.7.1.6.2.
5.2 The ALMS alarm setpoints have been adjusted as necessary.
14.2.12.3 Low Power Physics Tests 14.2.12.3.1 Low Power Biological Shield Survey Test 1.0 OBJECTIVE 1.1 To measure radiation in accessible locations of the plant outside of the biological shield.
i 1.2 To obtain baseline levels for comparison with future i
measurements of level buildup with operation.
2.0 PREREQUISITES 2.1 Radiation survey instruments calibrated.
2.2 Background
radiation levels measured in designated locations prior to initial critical
'v.
3.0 TEST METHOD 3.1 Measure gamma and neutron dose rates during low power
(<5% RTP) operation.
E 4.0 DATA REOUIRED 4.1 Power level.
Amendment E 14.2-106 December 30, 1988
___v i
l)lb!hbhfklI0kR i
ICATICN
(^\\
4.2 Gamma and neutron dose rates at each specified location.
5.0 ACCEPTANCE CRITERIA E
5.1 Baseline neutron and Gamma surveys have been completed.
14.2.12.3.2 Isothermal Temperature Coefficient Test 1.0 OBJECTIVE 1.1 To measure the isothermal temperature coefficients (ITCs) for various RCS temperatures, pressures, and CEA configurations.*
1.2 To determine the moderator temperature coefficient j
(MTC) from the measured ITC.
l 2.0 PREREQUISITES 2.1 The reactor is critical with a
stable boron concentration and the desired CEA configuration and RCS temperature and pressure.
1 (s,/
2.2 The reactivity computer is operable.
3.0 TEST METHOD 3.1 Changes in RCS temperature are introduced and the 5
resultant changes in reactivity measured.
3.2 Reactivity and power swings are limited by compensation with CEA motion when necessary.
4.0 DATA REOUIRED 4.1 Conditions of the measurement.
4.1.1 Pressurizer pressure.
4.1.2 CEA configuration.
4.1.3 Boron concentration.
l
- For unit, this test will be performed only at 565'F, 2250 psia.
E Amendment E 14.2-107 December 30, 1988
m 1
CESSAR 8t'Am2 4.2 Time dependent information.
4.2.1 Reactivity.
E 4.2.2 CEA position.
4.2.3 Temperature.
5.0 ACCEPTANCE CRITERIA 5.1 The measured ITCs agree with the predicted values within the acceptance criteria specified in Table E
14.2-6.
5.2 The moderator temperature coefficients (MTC) derived from the measured ITC are in compliance with the Technical Specifications.
14.2.12.3.3 Shutdown and Regulating CEA Group Worth Test 1.0 QBJECTIVE 1.1 To determine regulating and shutdown CEA group worths necessary to demonstrate adequate shutdown margin.
E 1.2 To demonstrate that the shutdown margin is adequate.
2.0 PREREQUISITES 2.1 The reactor is critical.
2.2 The reactivity computer is operating.
3.0 TEST METHOD 3.1 Measurement of regulating and shutdown CEA groups.
3.1.1 The CEA group worths will be measured by dilution /boration of the RCS or by using the CEA Exchange Method.
I 3.1.2 Worths may be determined by CEA drop and/or by use of alternate CEA configurations.
4.0 DATA REOUIRED 4.1 Conditions of the measurement.
4.1.1 RCS temperature.
s j
Ameradment E 14.2-108 December 30, 1988 i
1
CESSAR En#lCATl3N
'O w.)
4.1.2 Pressurizer pressure.
4.1.3 CEA configuration.
4.1.4 Boron concentration.
4.2 Time dependent information.
4.2.1 Reactivity variation.
E 4.2.2 CEA positions.
5.0 ACCEPTANCE CRITERIA 5.1 The measured CEA group worths agree with predictions within the acceptance criteria specified in Table E
14.2-6.
5.2 Evaluation of the measurements verifies shutdown margin.
E 14.2.12.3.4 Differential Boron Worth Test 1.0 OBJECTIVE 1.1 To measure the differential boron reactivity worth for various CEA configurations.
2.0 PREREQUISITES 2.1 CEA group worth tests are completed.
2.2 Critical configuration boron concentration tests are completed.
3.0 TEST METHOD 3.1 The differential boron worths are determined from the measured boron concentrations associated with state points measured during the CEA group worth tests.
4.0 DATA REOUIRED 4.1 Conditions of the measurement at state points.
4.1.1 RCS temperature.
4.1.2 Pressurizer pressure.
E
%./
Amendment E 14.2-109 December 30, 1988
i l
l CESSAR Ennncari:n 0
1 4.1.3 CEA configuration.
4.1.4 Boron concentration 4.2 Integral reactivity changes between state points.
l
)
l 5.0 ACCEPTANCE CRITERIA I
5.1 The measured boron worths agree with the predicted values within the acceptance criteria specified in Table 14.2-6.
E I
14.2.12.3.5 Critical Boron Concentration Test 1.0 OBJECTIVE 1.1 To measure critical boron concentrations for various CEA configurations at appropriate temperatures and associated pressures.
2.0 PREREQUISITES 2.1 The reactor is critical at the test conditions.
1 3.0 TEST METHOD 3.1 The reactor is critical with the desired CEA configuration (arrived at as endpoints for selected plateaus in the CEA group worth tests).
E 3.2 Coolant samples are taken and chemically analyzed for boron content until it is established that an equilibrium state has been achieved.
)
1 4.0 DATA REOUIRED 4.1 Critical conditions.
4.1.1 Boron concentration.
4.1.2 CEA positions.
4.1.3 RCS temperature.
4.1.4 Pressurizer pressure.
E O
Amendment E 14.2-110 December 30, 1988
CESSAR ?!'O'ic4Ii2u A
l
(\\ss-)
I 5.0 ACCEPTANCE CRITERIA 5.1 The measured critical boron concentrations agree with the predictions within the acceptance criteria specified in Table 14.2-6.
E 14.2.12.4 Power Ascension Tests 14.2.12.4.1 Variable Tavg (Isothermal Temperature Coefficient and Power Coefficient) Test 1.0 OBJECTIVE 1.1 To measure the Isothermal Temperature Coefficient and Power Coefficient of reactivity,at selected power levels.
2.0 PREREQUISITES 2.1 The reactor is at the desired power level with equilibrium Xe and boron concentration and the desired CEA configuration.
[V) 3.0 TEST METHOD 3.1 The ITC is measured by changing the core average temperature and using CEA movement to maintain the power essentially constant and/or by balancing temperature against power changes.
3.2 The Power Coefficient is measured by changing the core power using CEA movement to maintain the core average temperature essentially constant.
4.0 DATA REOUIRED Conditions of the measurement.
4.1.1 Power.
4.1.2 CEA configuration.
4.1.3 Boron concentration.
4.1.4 Core Burnup.
4.2 Time dependent data.
4.2.1 Power level.
v Amendment E 14.2-111 December 30, 1988
CESSAR Eanncmon O
4.2.2 RCS temperature.
4.2.3 CEA positions.
5.0 ACCEPTANCE CRITERIA 5.1 Measured values agree with predictions within the acceptance criteria specified in Table 14.2-6 and E
conform with the Technical Specifications.
14.2.12.4.2 Unit Load Transient Test
_\\
1.0 OBJECTIVE 1.1 To demonstrate that load changes can be made at the desired rates.
2.0 PREREQUISITES 2.1 The reactor is operating at the desired power level.
2.2 The RRS, FWCS, SBCS, RPCS, and the pressurizer level and pressure control systems are in automatic operation.
1 3.0 TEST METHOD 3.1 Load increases and decreases (steps and ramps) in accordance with the C-E Fuel Preconditioning Guidelines I
and as allowed by the RRS will be performed at power levels in the 75% to 95% range and in the 25% to 50%
power range.
4.0 DATA REOUIRED 4.1 Time dependent data.
4.1.1 Pressurizer level and pressure.
4.1.2 RCS temperatures.
4.1.3 CEA position.
4.2.4 Power level and demand.
4.1.5 Steam generator levels and pressures.
4.1.6 Feedwater and steam flow.
4.1.7 Feedwater temperature.
Amendment E
^
14.2-112 December 30, 1988
CESSAR nutric,Iion O
5.0 ACCEPTANCE CRITERIA 5.1 The step and ramp transients demonstrate that the plant performs load changes allowed by C-E's Fuel Preconditioning Guidelines and data has been taken that will demonstrate the plant's ability to meet unit load swing design transients.
5.2 That no audible noise or significant vibration is observed in the economizer er in the rest of the Feedwater and Emergency Feedwater systems due to water hammer.*
E 14.2.12.4.3 Control Systems Checkout Test 1.0 OBJECTIVE 1.1 To demonstrate that the automatic control systems operate satisfactorily during steady-state and transient conditions.
1 2.0 PREREQUISITES 2.1 The reactor is operating at the desired conditions.
2.2 The RRS, FWCS, SBCS, RPCS, and the pressurizer level and pressure controls are in auto.latic operation.
E 2.3 The Megawatt Demand Setter (MDS) is operational.
3.0 TEST METHOD 3.1 The performance of the control systems including the MDS during steady-state and transient conditions will be monitored to desc7 strate that the systems are operating satisfactols.
e 4.0 DATA REOUIRED 4.1 Time dependent data.
4.1.1 Pressurizer level and pressure.
- Acceptance criteria can be satisfied by performing system E
walkdown when conditions permit entry to containments.
O l
Amendment E 14.2-113 December 30, 1988
CESSAR ESErlCATION l
O 1
4.1.2 RCS temperatures.
l l
4.1.3 CEA position.
4.1.4 Power level and demand.
4.1.5 Steam generator levels and pressures.
4.1.6 Feedwater and steam flow.
4.1.7 Feedwater temperature.
5.0 ACCEPTANCE CRITERIA 5.1 The control systems maintain the reactor power, RCS
)
temperature, pressurizer pressure and level, and steam generator levels and pressures within their control bands during steady-state operation and are capable of returning these parameters to within their control bands in response to transient operation.
14.2.12.4.4 Raactor Coolant and Secondary Chemistry and Radiochemistry Test 1.O OBJECTIVE 1.1 To conduct chemistry tests at various power levels with the intent of gathering corrosion data and determining activity buildup.
1.2 To verify proper operation of the process radiation monitor.
1.3 To verify the adequacy of sampling and analysis procedures.
2.0 PREREQUISITES 2.1 The reactor is stable at the desired power level.
2.2 Sampling systems for the RCS and CVCS are operable.
{
3.0 TEST METHOD 3.1 Samples will be collected from the RCS and secondary system at various power levels and analyzed in the laboratory suing applicable sampling and analysis procedures.
O 14.2-114
)
CESSAR !!!'iflCATION r
O 3.2 Samples will be collected at the procer,s radiation monitor at various power
- levels, analy;ad in the laboratory, and compared with the process radiation monitor to verify proper operation.
4.0 DATA REOUIREQ 4.1 Conditions of the measurement.
4.1.1 Power.
4.1.2 RCS temperature.
1 4.1.3 Boron concentration.
4.1.4 Core average burnup.
4.2 Samples for measurement of gross activities and/or isotopic activities.
5.0 ACCEPTANCE CRITERIA 5.1 Measured activity levels are within their limits.
O 5.2 The process radiation monitors agree with the laboratory analyses within measurement uncertainties.
5.3 Procedures for sample collection and analysis are verified.
14.2.12.4.5 Turbine Trip Test 1.O OBJECTIVE 1.1 To demonstrate that the plant responds and is controlled as designed following a 100% turbine trip without RPCS in service.
2.0 PREREQUISITES 2.1 The reactor is operating above 95% power.
2.2 The SBCS, FWCS, RRS, and pressurizer pressure and level control systems are in automatic operation.
2.3 The RPCS is in Auto Actuai:e Out of Service.
O 14.2-115
CESSAREEncun O
3.0 TEST METHOD 3.1 The turbine is tripped.
3.2 The plant behavior is monitored to assure that the RRS, SBCS, FWCS, and pressurizer pressure and level control systems maintain the NSSS within operating limits.
4.0 DATA REOUIRED 4.1 Plant condition prior to trip.
4.2 The following acceptance criteria parameters are monitored prior to and throughout the transient.
4.2.1 Pressurizer pressure and level.
4.2.2 RCS hot leg temperatures.
4.2.3 SG pressures.
4.2.4 CEA drop times.
4.3 Additional key plant parameters will be monitored for base line data.
5.0 ACCEPTANCE CRITERIA 5.1 The test will be evaluated against single valued acceptance limits.
E 14.2.12.4.6 Unit Load Rejection Test 1.0 OBJECTIVE 1.1 To demonstrate that the plant responds and is controlled as designed following a 100% load rejection with RPCS in service.
2.0 PREREQUISITES 2.1 The reactor is operating above 95% power.
2.2 The SBCS,
- CEDMCS, RPCS, and pressurizer pressure and level control are in automatic operation.
j O'
Amendment E 14.2-116 December 30, 1988
i CESSAR Eniinemu 3.0 TEST METHOD 3.1 A breaker (s) is tripped so as to subject the turbine to the maximum credible overspeed condition.
3.2 The plant behavior is monitored to assure that the RRS, CEDMCS, SBCS, RPCS, FWCS, and pressurizer pressure and level control systems maintain the monitored parameters.
4.0 DATA REOUIRED 4.1 Plant condition prior to load rejection.
4.2 The following acceptance criteria parameters are monitored prior to and throughout the transient.
4.2.1 Pressurizer pressure and level.
4.2.2 RCS hot leg temperatures.
4.2.3 SG pressures.
! )
4.3 Additional key plant parameters will be monitored for baseline data.
5.0 ACCEPTANCE CRITERIA 5.1 The test will be evaluated against single valued acceptance limies.
E 14.2.12.4.7 Shutdown from Outside the Control Room Test 1.0 OBJECTIVE 1.1 To demonstrate that the plant can be maintained in Hot Standby from outside the control room following a
2.0 PREREOUIEITES 2.1 The reactor is operating at 2 10% of rated power.
2.2 The capability to cool down the plant from the remote shutdown panel has been demonstrated during pre-or post-core hot functional tests.
O Amendment E 14.2-117 December 30, 1988
CESSAR HiWICATl*N l
e 2.3 The remote shutdown panel instrumentation is operating properly.
2.4 The communication systems between the control room and remote shutdown location has been demonstrated to be operational.
j 2.5 The remote shutdown instrumentation controls and systems have been preoperationally tested.
3.0 TEST METHOD 3.1 The operating crew evacuates the control L som (standby crew remains in the control room).
3.2 The reactor is tripped from outside the control room.
3.3 The reactor is brought to Hot Standby by the operating crew from outside the control room and is maintained in this condition for at least 30 minutes.
4.0 DATA REOUIRED 4.1 Time dependent data.
4.1.1 Pressurizer pressure and level.
4.1.2 RCS temperatures.
4.1.3 Steam generator pressure and level.
4.1.4 CEA drop times.
E 5.0 ACCEPTANCE CRITERIA 5.1 The ability to achieve and control the reactor at Hot Standby from outside the control room is demonstrated.
14.2.12.4.8 Loss of Offsite Power Test 1.0 OBJECTIVE E
1.1 To verify that the reactor can be shut down and maintained in Hot Standby in the event of loss of offsite power.
2.0 PREREQUISITES 2.1 Reactor operating at 2 10% rated power.
Amendment E 14.2-118 December 30, 1988
ll CESSAR !!5Lmu E
3.0 TEST METHOD 3.1 The plant is tripped in a manner to produce a loss of generator and offsite power.
l 3.2 The plant is maintained in Hot Standby for at least 30 minutes before restoring power.
I 4.0 DATA REOUIRED 4.1 Time dependent data.
4.1.1 Steam generator pressure and levels.
4.1.2 Pressurizer pressure and level.
i 4.1.3 RCS temperatures.
f i
4.1.4 Boron concentration.
4.1.5 CEA drop times.
f 5.0 ACCEPTANCE CRITERIA 5.1 The reactor is shut down and maintained in Hot Standby on emergency power for at least 30 minutes during a simulated loss of offsite power.
14.2.12.4.9 Biological Shield Survey Test 1.0 OBJECTIVE 1.1 To measure the radiation levels in accessible locations
)
of the plant outside of the biological shield.
l 1.2 To determine occupancy times for these areas during i
j power operation.
2.0 PREREQUISITES 2.1 Radiation survey instruments have been calibrated.
l 2.2 Results of the radiation surveys performed at zero power conditions are available.
3.0 TEST METHOD l
l 3.1 Measure gamma and neutron dose rates at 50 and 100%
power levels.
/O 1
1 Amendment E l
14.2-119 December 30, 1988 l
l
CESSARSnacau 9
4.0 DATA REOUIRED 4.1 Power level.
4.2 Gamma dose rates in the accessible locations.
4.3 Neutron dose rates in the accessible locations.
AC,EPTANCE CRITERIA 5.0 Q
5.1 Accessible areas and occupancy times during power operation have been defined.
E 14.2.12.4.10 Steady-State Core Performance Test 1.0 OBJECTIVE 1.1 To determine core power distributions using in-core instrumentation.
1.2 To demonstrate that the core has been assembled as E
designed.
2.0 PREREQUISITES 2.1 The reactor is operating at the desired power level and CEA configuration with equilibrium Xe.
2.2 The in-core instrumentation system is in operation.
3.0 TEST METHOD 3.1 Selected DPS outputs and CPC outputs are recorded.
E 3.2 The core power distribution is obtained using the in-core detectors.
4.0 DATA REOUIRED 4.1 Conditions of the test.
4.1.1 Reactor power.
4.1.2 CEA positions.
4.1.3 Boron concentration.
l t
O Amendment E 14.2-120 December 30, 1988 l
3
CESSAR EMUncma 4.1.4 Core average burnup.
4.1.5 Selected plant computer outputs and CPC cutputs.
4.1.6 In-core detector maps.
5.0 ACCEPTANCE CRITERIA 5.1 Agreement between the predicted and measured power distributions and core peaking factors are within the acceptance criteria specific in Table 14.2-6.
5.2 The measured power of each assembly in a syremetric group is within 10% of the average powers of the group.
5.3 Quadrant ti.1t is less than 10%.
14.2.12.4.11 Intercomparison of PPS, Core Protection Calculator (CPC), DPS and DIAS Inputs 1.0 OBJECTIVE
[
1.1 To verify that process variable inputs / outputs of the
2.0 PREREQUISITES 2.1 The plant is operating at the desired conditions.
2.2 All CPCs, CEACs, DPS and the DIAS are operable.
3.0 TEST METHOD 3.1 Process variable inputs / outputs of the PPS, the CPCs, the DIAS, the DPS, and console instruments are read as near simultaneously as practical.
4.0 DATA REOUIRED 4.1 Conditions of the measurement.
4.1.1 Power.
O
\\
Amendment E 14.2-121 December 30, 1988
CESSAR ENGnce 4.1.2 Boron concentration.
f 4.1.3 RCS temperatures.
4.1.4 Pressurizer pressure and level.
4.1.5 Steam generator pressures and levels.
4.1.6 RCP speeds and differential pressures.
5.0 ACCEPTANCE CRITERIA 5.1 The process variable inputs / outputs from the PPS, the CPCs, ths DPS, the DIAS, and the console instruments are within the uncertainties assumed for them in the E
14.2.12.4.12 Ve6fication of CPC Power Distributi m Related Constants Test 1.O OIkTECTIVE 1.1 To verify the planar radial
- peaking, temperature annealing, and CEA shadowing factors, and the shape annealing matrix and boundary point power correlation constants, and to verify the algorithms used in the CPCs to relate ex-core signals to in-core power distribution.
2.0 PREREQUISITES 2.1 The reactor is at the desired poder level and CEA configuration with equilibrium Xe.
2.2 The in-core detector system is in operation.
2.3 The safety channels have been properly calibrated.
3.0 TEST METHOD 3.1 Planar radial peaking factors are verified for varicus CEA configurations by comparison of the CPC values with values measured with the in-core detector system.
j 3.2 The CEA uhadowing factors are verified by comparing ex-core detector responses for various CEA configurations with the unrodded ex-core responses.
Amendment E 14.2-122 December 30, 1988
CESSAR EMUicarieu 3.3 The shape annealing factors are measured by comparing in-core power distributions and ex-core detector responses during a free Xe oscillation.
3.4 The temperature shadowing factors are verified by comparing core power and ex-core detector responses for various RCS temperatures.
l 4.0 DATA REOUIRED 4.1 Conditions of the measurement.
4.1.1 Power 4.1.2 Burnup i
l 4.2 Time dependent data.
4.2.1 In-core and ex-core detector readings.
li 4.2.2 CEA position.
4.2.3 RCS temperatures.
5.0 ACCEPTANCE CRITERIA 5.1 Measured radial peaking factors determined from in-core flux maps are no higher than the corresponding values used in the CPCs.
5.2 The CEA shadowing factors and temperature shadowing factors used in the CPCs agree within the acceptance criteria specified in the CPC test requirements.*
5.3 The shape annealing matrix have been measured and the boundary point power correlation constants used in the CPCs are within the limits specified by the test requirements.*
- References to be provided in the FSAR.
OU 14.2-123
CESSAR nnnncarian O
14.2.12.4.13 Main and Emergency Feedwater Systems Test 4
1.0 OBJECTIVE 1.1 To demonstrate that the operation of the main feedwater and emergency feedwater systems during Hot Standby, Startup, and other normal operations, transients, and t
plant trips is satisfactory.
A list of transients which require monitoring of the MFW and EFW system performances is provided below:
E Evolutio.D MEE EEE MFW Downcomer to Economizer Transfer X
Unit Load Transient Test X
Control Systems Checkout Test X
Turbine Trip Test X
Unit Load Rejection Test X
Shutdown From Outside Control Room X
X Loss of Offsite Power Test X
X RPCS Test X
2.0 PRER_3UISITES 2.1 The SBCS,
- RPCS, CEDMCS, and pressurizer pressure and level controls are operable in either manual or automatic modes.
3.0 TEST METHOD 3.1 Performance of the feedwater systems will be monitored during normal operation, transients, and trips.
Specifically, the downcomer to economizer transfer will be monitored for noise or vibration due to water hammer.
l 4.0 DATA REOUIRED 4.1.1 Reactor power.
4.1.2 RCS temperatures.
4.1.3 Pressurizer pressure.
4.1.4 Steam generator levels and pressures.
4.1.5 Steam and feedwater flows.
I O
Amendment E 14.2-124 December 30, 1988
CESSARiMan.
E 4.1.6 Feedwater temperature and pressure.
4.1.7 CEA position.
5.0 ACCEPTANCE CRITERIA 5.1 The main and emergency feedwater systems perform as designated by the system description.
5.2 No effects due to water hammer are detected.
Check for water hammer noise utilizing appropriately placed personnel or check for water hammer vibration utilizing suitable instrumentation.*
E 14.2.12.4.14 CPC Verification 1.0 OBJECTIVE 1.1 To verify DNBR and Local Power Density (LPD) i calculations of the CPCs.
2.0 PREREQUISITES O) 2.1 The reactor is at the desired power level and CEA
(,,
configuration with equilibrium Xe.
2.2 The CPCs are operational.
2.3 The in-core detector system is operational.
3.0 TEST METHOD 3.1 Specified values are recorded from the CPCs.
3.2 The values for LPD and DNBR obtained from the CPCs are compared with the values calculated for the same conditions using the CPC FORTRAN Simulator.
4.0 DATA REOUIRED 4.1 Reactor power.
4.2 CEA positions.
- Acceptance Criteria can be satisfied by performing system E
walkdown when conditions permit entry to containment.
Amendment E 14.2-125 December 30, 1988
CESSAR n!nnceu O
4.3 Boron concentration.
J 4.4 Specified CPC inputs, outputs, and constants.
5.0 ACCEPTANCE CRITERIA 5.1 The values of DNBR and LPD calculated by the CPCs are consistent with the values calculated by the CPC FORTRAN code.
14.2.12.4.15 Steam Bypass Valve Capacity Test 1.O OBJECTIVE 1.1 To demonstrate that the maximum steam flow capacity of each atmospheric steam dump valve upstream of the main steam isolation valves is less than that assumed for the safety analysis.
1.2 To measure the capacity of each steam bypass valve individually to determine that the capacity of each steam bypass valve is less than the value used in the safety analysis.
2.0 PREREQUISITES i
2.1 The reactor power is > 15% full power.
2.2 Control systems are in automatic where applicable.
i 2.3 The operation of the atmospheric steam dump, turbine
- bypass, and shutdown cooling system have been demonstrated as part of the Hot Functional testing.
3.0 TEST METHOD 3.1 The individual steam flows through each of the atmospheric dump valves upstream of the MSIVs are measured.
3.2 The capacity of each steam bypass valve is measured.
4.0 DATA REOUIRED 4.1 Reactor power.
4.2 RCS temperatures.
1 4
i 14.2-126
'CESSAR !!nama Q
4.3 Pressurizer pressure.
4.4 Steam generatcr levels and pressure.
D 4.5 Steam dump and bypass valve positions.
4.6 Feedwater flow rates and feedwater temperatures.
5.0 b0'CEPTANCE CRITERIA 5.1 The capacities of the individual steam dump valves are less thma the values uued in the safety analysis but greater than the values required for a safe cooldown.
5.2 Tlie capacity of - each steam bypass valve has been measured and the capacity of each steam bypass valve is less than the value used in the safety analysis.
14.2.12.4.16 In-core Detector Test 1.0 OBJECTIVE f-w 1.1 To verify conversion of the fixed in-core detector
.l t
signals to voltages for input to the DPS.
E j
2.0 PREREQUISITES 2.1 The reactor is at the specified power level and conditions.
E 3.0 TEST METHOD 3.1 Amplifier output signals are measured.
3.2 Group symmetric instrument signals are measured.
3.3 Background detector signals are recorded.
4.0 DATA REOUIRED 4.1 Reactor power.
4.2 CEA position.
4.3 Boron concentration.
Amendment E 14.2-127 December 30, 1988
CESSAR E!Mi"lCATl3N O
4.4 In-core detector system data.
5.O A_CCEPTANCE CRITEPlA 5.1 The DPS input signals for group symmetric instruments E
are within the measurement and power distribution uncertainties.
5.2 Backgicund detector signals are within tolerances specified by C-E.
14.2.12.4.17 COL 88 Verification l
1.0 OBJECTIVE 1.1 To verify COLSS Secondary Calorimetric, DNBR and Local 1
Power Density (LPC) calculation.
4 2.0 PREREQUISITES 1.1 The reactor is at the desired power level and CEA configuration with equilibrium Xe.
2.2 The COLSS is operational.
2.3 The in-core detector system is operational.
3.0 TEST METHO_Q 1
3.1 Specified values are recorded from the COLSS.
I 3.2 The values for secondary calorimetric power, LPD and DNBR obtained from the COLSS are compared with E
independently calculated values using the COLSS algorithms.
4.0 DATA REOUIRED 4.1 Reactor power.
l 4.2 CEA positions.
j
]
4.3 Boron concentration.
4.4 Specified COLSS inputs, outputs, and constants.
4.5 In-core detectcr maps.
Ol Amendment E 14.2-128 December 30, 1988
CESSAR !!!nncm2 E
5.0 ACCEPTANCE CRITERIA 5.1 The values of COLSS secondary calorimetric power, DNBR and LPD obtained fros the COLSS agree with the independently calculated values within the uncertainties in computer processing contained in the COLSS uncertainty analysis.
14.2.12.4.18 Baseline N888 Integrity Monitoring 1.0 OBJECTIVE 1.1 To obtain baseline Internals Vibration Monitoring System (IVMS) data at various power plateaus.
1.2 To obtain baseline Acoustic Leak Monitoring system (ALMS) data at various power plateaus.
1.3 To obtain baseline Loose Parts Monitoring system (LPMS) data at various reactor coolant pump configurations
- and power plateaus.
1.4 To verify existing, or establish new alarm setpoints as required for the NSSS Integrity Monitoring System.
s 2.0 EBI:REOUISITES I
2.1 Plant is stable at the applicable power level (0, 20, 50, 80, and 100 percent).
2.2 IVMS, AMS, LPMS are operational as applicable.
3.0 TEST METHOD 3.1 Collect baseline data at the applicable power levels.
3.2 Collect baseline data with various reactor coolant pump combinations.
4.0 DATA REOUIRED 4.1 Reactor power level, temperature, pressure.
4.2 Baseline data for ALMS, IVMS, LPMS.
- Performed at Post-Core Hot Functional tests.
/S N u) l Amendment E 14.2-129 December 30, 1988
CESSARnM%ma 1
9 5.O ACCEPTANCE CRITERIA 5.1 Baseline data have been collected for various reactor coolant pump combinations.
5.2 Baseline data has been collected at.
20, 50, 80, and 100 percent power.
5.3 Alarm setpoints have been evaluated for adequacy.
I 14.2.12.4.19 Natural circulation Test 1.0 OBJECTIVE 1.1 To evaluate natural circulation flow conditions.
t 2.0 PREREQUISITES 2.1 The power history prior to test is such that the loop E
AT (T -T ) under natural circulation condition is not expecbed to drop below 10'F during the performance of C
this test.
3.0 TEST.t1ETHOD 3.1 The reactor coolant pumps are tripped.
3.2 The plant is tripped.
3.3 The natural circulation power to flow ratio is determined.
3.4 Initiate a
cooldown under natural circulation conditions.
4.0 D2TA REOUIRED 4.1 Previous power history.
4.2 RCS temperatures.
4.1 Core exit thermocouple readings.
j 4.4 Steam generator levels and pressures.
L 4.5 Pressurizer pressure and level.
4.6 HJTC indications.
1 Amendment E 14.2-130 December 30, 1988
)
CESSAR 88&icarieu l
/^\\
N 5.0 ACCEPTANCE CRITERIA 5.1 The natural circulation power to flow ratio is less than 1.0.
14.2.12.4.20 Reactor. Power Cutback System (RPCS) Tests E
1.0 OBJECTIVE 1.1 To evaluate system response to a loss of one of two operating feedwater pumps.
1.2 To evaluate system response to a FLCEA drop at power.
2.0 PREREQUISITES 2.1 Plant is operating at > 50% RTP.
l 2.2 RRS, RWCS, SBCS, RPCS, pressurizer level control and pressurizer pressure controls are in automatic.
l 2.3 CEACs are operating (not in INOP).
3.0 TEST METHOD 3.1 Loss of Main Feedwater Pump.
l l
3.1.1 One of the two operating feedwater pumps is tripped.
l 1
i 3.2 CEA Drop.
l One CEA is dropped from the full-out position.
3.2.1 1
4.0 DATA REOUIRED 4.1 Time dependent data.
4.1.1 Pressurizer level and pressure.
4.1.2 RCS temperatures.
l 4.1.3 CEA positions.
1 4.1.4 Power level.
l 4.1.5 Steam generator levels and pressures.
4.1.6 Feedwater and steam flows.
(%
(,)
4.1.7 Feedwater temperatures.
Amendment E 14.2-131 December 30, 1988
1 CESSAR Ennneuion E
5.0 ACCEPTANCE CRITERIA 5.1 The control systems stabilize the plant to normal 1
operating control bands.
5.2 No safety actuation limits are exceeded, i
i G:
I I
l O
Amendment E 14.2-132 December 30, 1988 o
CESSAR !EOicarian O
TABLE 14.2-1 (Sheet 1 of 4)
PREOPERATIONAL TESTS Section Title 14.2.12.1.1 Reactor Coolant Pump Motor Initial Operation 14.2.12.1.2 Reactor Coolant System Test 14.2.12.1.3 Pressurizer Safety Valve Test 14.2.12.1.4 Pressurizer Pressure and Level Control System 14.2.12.1.5 CVCS Letdown Subsystem Test 14.2.12.1.6 CVCS Purification Subsystem Test 14.2.12.1.7 Volume Control Tank Subsystem Test i
14.2.12.1.8 CVCS Charging Subsystem Test 1
14.2.12.1.9 Chemical Addition Subsystem Test l
14.2.12.1.10 Reactor Drain Tank Subsystem Test 14.2.12.1.11 Equipment Drain Tank Subsystem Test 14.2.12.1.12 Boric Acid Batching Tank Subsystem Test 14.2.12.1.13 Concentrated Boric Acid Subsystem Test 14.2.12.1.14 Reactor Makeup Subsystem Test 14.2.12.1.15 Holdup Subsystem Test l
14.2.12.1.16 Boric Acid Concentrator Subsystem Test 14.2.12.1.17 Gas Stripper Subsystem Test 14.2.12.1.18 Boronometer Subsystem Test 14.2.12.1.19 Letdown Process Radiation Monitor Test j
f E
l 14.2.12.1.20 Gas Stripper Effluent Radiation Monitor Test Amendment E December 30, 1988 l
CESSAR H5incari:n O
TABLE 14.2-1 (Cont'd)
(Sheet 2 of 4)
PREOPERATIONAL TEST 8 Bection Title 14.2.12.1.21 Shutdown Cooling Subsystem Test 14.2.12.1.22 Safety Injection Subsystem Test 14.2.12.1.23 Safety Injection Tank Subsystem Test 14.2.12.1.24 Megawatt Demar.d Setter Subsystem Test E
14.2.12.1.25 Engineered Safety Features - Component Control System 14.2.12.1.26 Plant Protection System Test i
14.2.12.1.27 Ex-core Nuclear Instrumentation System Test 14.2.12.1.28 Fixed In-core Nuclear Signal Channel Test E
14.2.12.1.29 Control Element Drive Mechanism Control System Test 14.1.12.1.30 Reactor Regulating System Test 14.2.12.1.31 Steam Dypass Control System Test i
14.2.12.1.32 Feedwater Control system Test 14.2.12.1.33 Core Operating Limit Supervisory System Test 14.2.12.1.34 Reactor Power Cutback System Test 14.2.12.1.35 Refueling Equipment Test E
14.2.12.1.36 Emergency Feedwater System 14.2.12.1.37 Reactor Coolant System Hydrostatic Test 14.2.12.1.38 CEDM Cooling System 14.2.12.1.39 Safety Depressurization Subsystem Test 14.2.12.1.40 Containment Spray System Amendment E December 30, 1988
CESSARHMau.
O v
TABLE 14.2-1 (Cont'd)
(Sheet 3 of 4)
PREOPERATIONAL TESTS Section Title 14.2.12.1.41 Integrated Engineered Safety Features / Loss of E
Power Test 14.2.12.1.42 In-containment Refueling Water Storage Tank Subsystem 14.2.12.2.43 Internals Vibrations Monitoring System 14.2.12.2.44 Loose Parts Monitoring System 14.2.12.1.45 Acoustic Leak Monitoring System 14.2.12.1.46 Data Processing System and Data Indication and Alarm System
)
14.2.12.1.47 Critical Function Monitoring (CFM) 14.2.12.1.48 Pre-core Hot Functional Test Controlling Document 14.2.12.1.49 Pre-core Instrument Correlation 14.2.12.1.50 Remote Shutdown Panel 14.2.12.1.51 Alternate Protection System 14.2.12.1.52 Pre-core Test Data Record l
14.2.12.1.53 Pre-core Reactor Coolant System Expansion Measurements 14.2.12.1.54 Pre-core Reactor Coolant and Secondary Water Chemistry Data 1
14.2.12.1.55 Pre-Core Pressurizer Performance 14.2.12.1.56 Pre-Core Control Element Drive Mechanism Performance t
14.2.12.1.57 k
Pre-core Reactor Coolant System Flow Measurements Amendment E December 30, 1988
kw!
h h k ! bb ICATION O
TABLE 14.2-1 (Cont'd)
(Sheet 4 of 4)
PREOPERATIONAL TESTS Section Title 14.2.12.1.58 Pre-core Reactor Coolant System Heat Loss E
14.2.12.1.59 Pre-core Reactor Coolant System Leak Rate Measurement 14.2.12.1.60 Pre-core Chemical Volume Control System Integrated Test 14.2.12.1.61 Pre-core Safety Injection Check Valve Test 14.2.12.1.62 Pre-core Boration/ Dilution Measurements 14.2.12.1.63 Downcomer Feedwater System Water hammer Test O
a O
Amendment E December 30, 1988
CESSAR n.%"icari:n f
s TABLE 14.2-2 i
HOT FUNCTIONAL TESTS section Title 14.2.12.2.1 Post-core Hot Functional Test Controlling l
Document E
14.2 12.2.2 Loose Parts Monitoring System 14.2.12.2.3 Reactor Coolant System Flow Measurements 14.2.12.2.4 Post-core Control Element Drive Mechanism Performance 14.2.12.2.5 Post-core Reactor Coolant and Secondary Water Chemistry Data.
14.2.12.2.6 Post-core Pressurizer Spray Valve and Control Adjustments 14.2.12.2.7 Post-core Reactor Coolant System Leak Rate
[
Measurement 14.2.12.2.8 Post-core In-core Instrumentation 14.2.12.2.9 Post-core Instrument Correlation 14.2.12.2.10 Post-core Acoustic Leak Monitor System Test l
l 1
j i
l l
1 l
l Amendment E I
December 30, 1988
1 CESSAR ESincamu l
O TABLE 14.2-3 LOW POWER PHYSICS TESTS Section Title 14.2.12.3.1 Low Power Biological Shield Survey Test E
14.2.13.3.2 Isothermal Temperature Coefficient Test l
14.2.12.3.3 Shutdown and Regulating CEA Group Worth Test 14.2.12.3.4 Differential Boron Worth Test 14.2.12.3.5 Critical Boron Concentration Test E
)
Amendment E December 30, 1988
CESSAREBEnc-O TABLE 14.2-4 POWER ASCENSION TESTS Section Title 14.2.12.4.1 Variable Tavg (Isothermal Temperature Coefficient & Power Coefficient) Test 14.2.12.4.2 Unit Load Transient Test 14.2.12.4.3 Control Systems Checkout Test i
14.2.12.4.4 RCS and Secondary Chemistry and Radiochemistry Test 14.2.12.4.5 Turbine Trip Test 14.2.12.4.6 Unit Load Rejection Test I
14.2.12.4.7 Shutdown From Outside the Control Room Test 14.2.12.4.8 Loss of Offsite Power Test 14.2.12.4.9 Biological Shield Survey Test E
14.2.12.4.10 Steady-State Core Performance Test 14.2.12.4.11 Intercomparison of PPS, CPCs, DPS and DIAS Inputs E
14.2.12.4.12 Verification of CPC Power Distribution l
Related Constants 14.2.12.4.13 Main and Emergency Feedwater System Test 14.2.12.4.14 CPC Verification 14.2.12.4.15 Steam Bypass Valve Test 14.2.12.4.16 In-core Detector Test 14.2.12.4.17 COLSS Verification 14.2.12.4.18 Baseline NSSS Integrity Monitoring E
14.2.12.4.19 Natural Circulation
(~~')
1 (f
14.2.12.4.20 RPCS Testing E
I Amendment E I
December 30, 1988 i
CESSAR 8lni"lCAT10N TABLE 14.2-5 (Sheet 1 of 2)
POWER ASCENSION TESTS Test Title Plateau Variable Tavg (Isothermal Temperature 50, 100%*
E Coefficient & Power Coefficient) Test Unit Load Transient Test 50, 100%
Control Systems Checkout Test 50, 80%
RCS and Secondary Chemistry and Radiochemistry Test 20, 50, 80, 100%
Turbine Trip Test 100%
Unit Load Rejection Test 100%
Shutdown from outside the control Room Test 2 10%
Loss of Offsite Power Test 2 10%
Diological Shield Survey Test 50, 100%
Steady-State Core Performance Test 20, 50, 80, 100%
Intercomparison of PPS, CPC, DPS and DIAS Inputs 20, 50, 80, 100%
Verification of CPC Power Distribution Related Constants 20, 50%
Main and Emergency Feedwater 2 10%
CPC Verification 20, 50, 80, 100%
Steam Dump and Byphas Valve Capacity Test 2 15%
Amendment E December 30, 1988
CESSAR 8HMcui:n TABLE 14.2-5 (8heet 2 of 2) t POWER A8CENSION TESTE Test Title Plateau E
In-core Detector Test 20, 50, 80, 100%
COLSS Verification 20, 50, 80, 100%
Baseline NSSS Integrity 20, 50, 80, 100%
Monitoring Reactor Power Cutbach System
> 50%
Natural Circulation Test
> 80%
O The temperature and power coefficient: measurements are done as close as possible to 100% at a level where CEA motion is practical accounting for margin considerations.
O Amendment E December 30, 1988
CESSAR EinLmu O) l s_
TABLE 14.2-6 PHYSICS (8TEADY-STATE) TEST ACCEPTANCE CRITERIA TOLERANCES l
Parameter Tolerance LPPT E
CEA Group Worths i 10% or.05% Ap whichever is greater Total Worth (Net Shutdown) 10%
i
_4 l
Temperature Coefficient
.3 x 10 Ap/*F Critical Boron Concentration 50 ppm Boron Worth 15 ppm /%Ap PAPT Power Distribution (Radial and Axial)
- RMS $ 3%*
Peaking Factors (Fxy, FR, Fzl, Fq) i 7.5%
Temperature Coefficient
.3 x 10_4 Ap/*F 4
Power Coefficient
.2 x 10 Ap/% Power
,fg b
at 50% power and above N
PRED MEAS where N = total number RMS
=
1 of fuel assemblies in
-core or number of axial planes, as appropriate.
If CEA Exchange methods are used, the acceptance criteria provided in CEN 319 are applicab]3.
O(V t
Amendment E December 30, 1988
mu&I 6 STANDARD DESIGN
\\;7/
/
x x
/'
CESSAR Bli'!!ncano.
O Volume 11 commsusnon)suams
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