ML17212A054

Final Safety Analysis Report, Rev. 35, Chapter 13, Initial Tests and Operation

ML17212A054
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Site:	Millstone
Issue date:	06/29/2017
From:	Dominion Nuclear Connecticut
To:	Office of Nuclear Reactor Regulation
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Millstone Power Station Unit 2 Safety Analysis Report Chapter 13 MPS2 UFSAR 13-i Rev. 35 CHAPTER 13-INITIAL TE STS AND OPERATION Table of ContentsSection Title Page

13.1DESCRIPTION

OF THE STARTUP TEST PROGRAM................................13.1-113.1.1Scope.........................................................................................................13.1-113.1.2Objectives.................................................................................................13.1-113.2STARTUP TEST PROGRAM ORGANIZATION AND RESPONSIBILITIES13.2-113.2.1Plant Organiza tion....................................................................................13.2-1 13.2.2Startup Test Group....................................................................................13.2-113.2.2.1Organization..............................................................................................13.2-1 13.2.2.2 Duties and Responsibilities.......................................................................13.2-1 13.2.2.3 Qualifications............................................................................................13.2-5 13.3 ADMINISTRATIVE CONDUCT OF THE STARTUP TEST PROGRAM....13.3-1 13.3.1Test Procedures - Discussion....................................................................13.3-113.3.2Test Procedure Preparation.......................................................................13.3-1 13.3.3Test Procedure Execution and Changes Thereto......................................13.3-2 13.3.4Evaluating Test Procedure Data...............................................................13.3-213.3.5Test Result Documentation.......................................................................13.3-3 13.4MILLSTONE STARTUP GROUP TRAINING PROGRAM..........................13.4-113.5INITIAL INSPECTION AND COMPONENT TESTING PHASE..................13.5-1 13.6PREOPERATIONAL AND ACCEPTANCE TEST PROGRAM....................

13.6-113.6.1Description of Preoperational and Acceptance Test Program..................13.6-1 13.6.2 Index of Preoperational Tests and General Testing Sequence.................13.6-1 13.6.3 Index of Acceptance Tests and General Testing Sequence......................13.6-3 13.7HOT FUNCTIONAL TEST PROGRAM.........................................................13.7-1 13.7.1Description of Hot Functional Test Program............................................13.7-1 13.7.2 Reactor Coolant System Hot Functional Test (Pre-Core) Description.....13.7-1 13.7.3 Reactor Coolant System Hot Functional Test (Post-Core) - Description.13.7-3 13.8INITIAL FUEL LOADING...............................................................................

13.8-1 MPS2 UFSAR Table of Contents (Continued)

Section Title Page 13-ii Rev. 3513.8.1The purposes of the Initial Fuel Loading procedure are:..........................13.8-113.8.2Initial conditions which will be established prior to the initial fuel loading are:

13.8-113.8.3Precautions which shall be observed during the initial fuel loading are:.13.8-2 13.8.4 The fuel loading procedures shall include the following considerations:13.8-313.8.5..................................................................................................................

13.8-413.9INITIAL CRITICALITY...................................................................................13.9-113.10LOW POWER PHYSICS TESTING..............................................................13.10-113.11POWER ASCENSION TESTING..................................................................13.11-1 13.12PIPING OPERATIONAL TESTING..............................................................13.12-113.13ACTIVE VALVES OPERATIONAL TESTING...........................................13.13-1 13.A PREOPERATIONAL TEST DESCRIPTIONS...............................................13.A-1 13.A.1SYSTEM: 125 VOLT DC SYSTEM.......................................................13.A-113.A.1.1Objective..................................................................................................13.A-113.A.1.2Prerequisites.............................................................................................13.A-113.A.1.3Method.....................................................................................................13.A-113.A.1.4Acceptance Criteria..................................................................................13.A-1 13.A.2SYSTEM: RESERVE STATION SERVICE TRANSFORMER...........13.A-213.A.2.1Objective..................................................................................................13.A-213.A.2.2Prerequisites.............................................................................................13.A-2 13.A.2.3Method.....................................................................................................13.A-213.A.2.4Acceptance Criteria..................................................................................13.A-213.A.3SYSTEM: PRIMARY WATER TREATMENT SYSTEM....................13.A-2 13.A.3.1Objective..................................................................................................13.A-213.A.3.2Prerequisites.............................................................................................13.A-213.A.3.3Method.....................................................................................................13.A-3 13.A.3.4Acceptance Criteria..................................................................................13.A-313.A.4SYSTEM: 4,160 VOLT ELECTRICAL SYSTEM.................................13.A-313.A.4.1Objective..................................................................................................13.A-313.A.4.2Prerequisites.............................................................................................13.A-313.A.4.3Method.....................................................................................................13.A-4 13.A.4.4Acceptance Criteria..................................................................................13.A-413.A.5SYSTEM: 480-VOLT ELECTRICAL LOAD CENTERS.....................13.A-4 13.A.5.1Objective..................................................................................................

13.A-4 MPS2 UFSAR Table of Contents (Continued)

Section Title Page 13-iii Rev. 3513.A.5.2Prerequisites.............................................................................................13.A-413.A.5.3Method.....................................................................................................13.A-413.A.5.4Acceptance Criteria..................................................................................13.A-4 13.A.6SYSTEM: SERVICE WATER SYSTEM...............................................13.A-5 13.A.6.1Objectives................................................................................................13.A-513.A.6.2Prerequisites.............................................................................................13.A-5 13.A.6.3Method.....................................................................................................13.A-513.A.6.4Acceptance Criteria..................................................................................13.A-513.A.7SYSTEM: CLEAN LIQUID RADWASTE SYSTEM...........................13.A-5 13.A.7.1Objective..................................................................................................13.A-513.A.7.2Prerequisites.............................................................................................13.A-5 13.A.7.3Method.....................................................................................................13.A-5 13.A.7.4Acceptance Criteria..................................................................................13.A-613.A.8SYSTEM: AERATED LIQUID RADWASTE SYSTEM......................13.A-613.A.8.1Objective..................................................................................................13.A-6 13.A.8.2Prerequisites.............................................................................................13.A-613.A.8.3Method.....................................................................................................13.A-613.A.8.4Acceptance Criteria..................................................................................13.A-7 13.A.9SYSTEM: 480-VOLT MOTOR CONTROL CENTERS.......................13.A-713.A.9.1Objective..................................................................................................13.A-713.A.9.2Prerequisites.............................................................................................13.A-7 13.A.9.3Method.....................................................................................................13.A-713.A.9.4Acceptance Criteria..................................................................................13.A-713.A.10SYSTEM: TURBINE BUILDING CLOSED COOLING WATER SYSTEM..

13.A-713.A.10.1Objective..................................................................................................13.A-713.A.10.2Prerequisites.............................................................................................13.A-8 13.A.10.3Method.....................................................................................................13.A-813.A.10.4Acceptance Criteria..................................................................................13.A-813.A.11SYSTEM: FIRE PROTECTION SYSTEM............................................13.A-8

13.A.11.1Objective..................................................................................................13.A-813.A.11.2Prerequisites.............................................................................................13.A-8 13.A.11.3Test Method.............................................................................................13.A-9 13.A.11.4Acceptance Criteria..................................................................................13.A-913.A.12SYSTEM: RECOVERED BORIC ACID SYSTEM...............................13.A-9 13.A.13SYSTEM: INSTRUMENT AIR SYSTEM.............................................13.A-913.A.13.1Objectives................................................................................................13.A-913.A.13.2Prerequisites.............................................................................................13.A-9 13.A.13.3Method.....................................................................................................13.A-913.A.13.4Acceptance Criteria................................................................................13.A-1013.A.14SYSTEM: PRIMARY WATER STORAGE SYSTEM........................

13.A-10 MPS2 UFSAR Table of Contents (Continued)

Section Title Page 13-iv Rev. 3513.A.14.1Objective................................................................................................13.A-1013.A.14.2Prerequisites...........................................................................................13.A-1013.A.14.3Method...................................................................................................13.A-10 13.A.14.4Acceptance Criteria................................................................................13.A-1013.A.15SYSTEM: 120-VOLT INSTRUMENT AC SYSTEM.........................13.A-11 13.A.15.1Objective................................................................................................13.A-1113.A.15.2Prerequisites...........................................................................................13.A-1113.A.15.3Method...................................................................................................13.A-1113.A.15.4Acceptance Criteria................................................................................13.A-11 13.A.16SYSTEM: 120-VOLT VITAL AC SYSTEM.......................................13.A-11 13.A.16.1Objective................................................................................................13.A-1113.A.16.2Prerequisites...........................................................................................13.A-11 13.A.16.3Method...................................................................................................13.A-1113.A.16.4Acceptance Criteria................................................................................13.A-1213.A.17SYSTEM: GASEOUS RADWASTE SYSTEM...................................13.A-12 13.A.17.1Objectives..............................................................................................13.A-1213.A.17.2Prerequisites...........................................................................................13.A-12 13.A.17.3Method...................................................................................................13.A-12 13.A.17.4Acceptance Criteria................................................................................13.A-1213.A.18SYSTEM: CONDENSATE STORAGE SYSTEM...............................13.A-1313.A.18.1Objective................................................................................................13.A-13 13.A.18.2Prerequisites...........................................................................................13.A-1313.A.18.3Method...................................................................................................13.A-1313.A.18.4Acceptance Criteria................................................................................13.A-13 13.A.19SYSTEM: AUXILIARY AND EMERGENCY FEEDWATER SYSTEM........

13.A-1313.A.19.1Objective................................................................................................13.A-1313.A.19.2Prerequisites...........................................................................................13.A-1313.A.19.3Method...................................................................................................13.A-1413.A.19.4Acceptance Criteria................................................................................13.A-14 13.A.20SYSTEM: STEAM GENERATOR FEEDWATER SYSTEM.............13.A-1413.A.20.1Objective................................................................................................13.A-1413.A.20.2Prerequisites...........................................................................................13.A-14 13.A.20.3Method...................................................................................................13.A-1513.A.20.4Acceptance Criteria................................................................................13.A-1513.A.21SYSTEM: CONDENSATE SYSTEM..................................................13.A-15 13.A.21.1Objective................................................................................................13.A-1513.A.21.2Prerequisites...........................................................................................13.A-15 13.A.21.3Method...................................................................................................13.A-1513.A.21.4Acceptance Criteria................................................................................13.A-1513.A.22SYSTEM: FEEDWATER HEATER DRAINS AND VENTS.............

13.A-16 MPS2 UFSAR Table of Contents (Continued)

Section Title Page 13-v Rev. 3513.A.22.1Objective................................................................................................13.A-1613.A.22.2Prerequisites...........................................................................................13.A-1613.A.22.3Method...................................................................................................13.A-16 13.A.22.4Acceptance Criteria................................................................................13.A-1613.A.23SYSTEM: MAIN STEAM....................................................................13.A-1613.A.23.1Objective................................................................................................13.A-16 13.A.23.2Prerequisites...........................................................................................13.A-1713.A.23.3Method...................................................................................................13.A-1713.A.23.4Acceptance Criteria................................................................................13.A-17 13.A.24SYSTEM: SAMPLING SYSTEM........................................................13.A-1713.A.24.1Objectives..............................................................................................13.A-1713.A.24.2Prerequisites...........................................................................................13.A-18 13.A.24.3Method...................................................................................................13.A-1813.A.24.4Acceptance Criteria................................................................................13.A-1813.A.25SYSTEM: SPENT FUEL COOLING AND PURIFICATION.............13.A-18 13.A.25.1Objective................................................................................................13.A-1813.A.25.2Prerequisites...........................................................................................13.A-18 13.A.25.3Method...................................................................................................13.A-19 13.A.25.4Acceptance Criteria................................................................................13.A-1913.A.26SYSTEM: REACTOR BUILDING CLOSED COOLING WATER SYSTEM.

13.A-1913.A.26.1Objective................................................................................................13.A-1913.A.26.2Prerequisites...........................................................................................13.A-1913.A.26.3Method...................................................................................................13.A-20 13.A.26.4Acceptance Criteria................................................................................13.A-2013.A.27FUEL HANDLING SYSTEM PREOPE RATIONAL TEST - DESCRIPTION 13.A-2013.A.27.1Purpose...................................................................................................13.A-20 13.A.27.2General Prerequisites.............................................................................13.A-20 13.A.27.3Test Method...........................................................................................13.A-2113.A.27.4Acceptance Criteria................................................................................13.A-2113.A.28SAFETY INJECTION SYSTEM PREO PERATIONAL Test - DESCRIPTION 13.A-2113.A.28.1Purpose...................................................................................................13.A-21 13.A.28.2General Prerequisites.............................................................................13.A-21 13.A.28.3Test Method...........................................................................................13.A-2213.A.28.4Acceptance Criteria................................................................................13.A-22 13.A.29SYSTEM: DIESEL FUEL OIL TRANSFER SYSTEM.......................13.A-22 13.A.29.1Objective................................................................................................13.A-2213.A.29.2Prerequisites...........................................................................................13.A-2213.A.29.3Method...................................................................................................

13.A-22 MPS2 UFSAR Table of Contents (Continued)

Section Title Page 13-vi Rev. 3513.A.29.4Acceptance Criteria................................................................................13.A-2213.A.30SYSTEM: DIESEL GENERATORS....................................................13.A-2313.A.30.1Objective................................................................................................13.A-23 13.A.30.2Prerequisites...........................................................................................13.A-2313.A.30.3Method...................................................................................................13.A-2313.A.30.4Acceptance Criteria................................................................................13.A-23 13.A.31SYSTEM: CONTAINMENT SPRAY SYSTEM..................................13.A-24 13.A.31.1Objective................................................................................................13.A-2413.A.31.2Prerequisites...........................................................................................13.A-2413.A.31.3Method...................................................................................................13.A-2413.A.31.4Acceptance Criteria................................................................................13.A-2413.A.32SYSTEM: SHUTDOWN COOLING SYSTEM...................................13.A-24 13.A.32.1 Test Objectives......................................................................................13.A-24 13.A.32.2Prerequisites...........................................................................................13.A-2413.A.32.3Method...................................................................................................13.A-25 13.A.32.4Acceptance Criteria................................................................................13.A-2513.A.33SYSTEM: ENGINEERED SAFEGUARDS ACTUATION SYSTEM13.A-2513.A.33.1Objectives..............................................................................................13.A-2513.A.33.2Prerequisites...........................................................................................13.A-2513.A.33.3Method...................................................................................................13.A-2513.A.33.4Acceptance Criteria................................................................................13.A-26 13.A.34REACTOR COOLANT SYSTEM PREOPERATIONAL TEST - DESCRIP

-TION......................................................................................................13.A-2613.A.34.1Test Objective........................................................................................13.A-26 13.A.34.2 General Prerequisites.............................................................................13.A-26 13.A.34.3Test Method...........................................................................................13.A-2713.A.34.4Acceptance Criteria................................................................................13.A-27 13.A.35REACTOR REGULATING SYSTEM PREOPERATIONAL TEST - DE

-SCRIPTION...........................................................................................13.A-2713.A.35.1Purpose...................................................................................................13.A-27 13.A.35.2General Prerequisites.............................................................................13.A-27 13.A.35.3Test Method...........................................................................................13.A-2813.A.35.4Acceptance Criteria................................................................................13.A-2813.A.36REACTOR PROTECTIVE SYS TEM PREOPERATIONAL TEST - DE

-SCRIPTION...........................................................................................13.A-2813.A.36.1Purpose...................................................................................................13.A-2813.A.36.2General Prerequisites.............................................................................13.A-28 13.A.36.3Test Method...........................................................................................13.A-2913.A.36.4Acceptance Criteria................................................................................13.A-2913.A.37CHEMICAL AND VOLUME CONT ROL SYSTEM PREOPERATIONAL TEST -DESCRIPTION..........................................................................13.A-29 MPS2 UFSAR Table of Contents (Continued)

Section Title Page 13-vii Rev. 3513.A.37.1Test Objective........................................................................................13.A-2913.A.37.2General Prerequisites.............................................................................13.A-2913.A.37.3Test Method...........................................................................................13.A-30 13.A.37.4Acceptance Criteria................................................................................13.A-3013.A.38NUCLEAR INSTRUMENTATION SYSTEM PREOPERATIONAL TEST -DESCRIPTION.....................................................................................13.A-3013.A.38.1Purpose...................................................................................................13.A-30 13.A.38.2General Prerequisites.............................................................................13.A-30 13.A.38.3General Test Methods............................................................................13.A-3113.A.38.4Acceptance Criteria................................................................................13.A-3113.A.39IN-CORE INSTRUMENTATION PREOPERATIONAL TEST - DESCRIP

-TION......................................................................................................13.A-3113.A.39.1Purpose...................................................................................................13.A-31 13.A.39.2General Prerequisites.............................................................................13.A-31 13.A.39.3Test Method...........................................................................................13.A-3113.A.39.4Acceptance Criteria................................................................................13.A-3213.A.40SYSTEM: PROCESS RADIATION MONITORING SYSTEMS.......13.A-32 13.A.40.1Objective................................................................................................13.A-3213.A.40.2Prerequisites...........................................................................................13.A-32 13.A.40.3Method...................................................................................................13.A-3213.A.40.4Acceptance Criteria................................................................................13.A-32 13.A.41SYSTEM: AREA RADIATION MONITORING SYSTEM................13.A-32 13.A.41.1Objective................................................................................................13.A-3213.A.41.2Prerequisites...........................................................................................13.A-33 13.A.41.3Method...................................................................................................13.A-3313.A.41.4Acceptance Criteria................................................................................13.A-3313.A.42BORONOMETER AND PROCESS RADIATION MONITOR PREOPERA

-TIONAL TEST - DESCRIPTION.........................................................13.A-3313.A.42.1Purpose...................................................................................................13.A-33 13.A.42.2General Prerequisites.............................................................................13.A-33

13.A.42.3Test Methods..........................................................................................13.A-3313.A.42.4Acceptance Criteria................................................................................13.A-34 13.A.43SYSTEM: MAIN AND NORMAL STATION SERVICE TRANSFORMERS 13.A-3413.A.43.1Test Objectives......................................................................................13.A-34 13.A.43.2Prerequisites...........................................................................................13.A-3413.A.43.3Method...................................................................................................13.A-34 13.A.43.4Acceptance Criteria................................................................................13.A-35 13.A.44SYSTEM: ENCLOSURE BUILDI NG FILTRATION AND HYDROGEN RE

-MOVAL SYSTEM................................................................................13.A-3513.A.44.1Objective................................................................................................

13.A-35 MPS2 UFSAR Table of Contents (Continued)

Section Title Page 13-viii Rev. 3513.A.44.2Prerequisites...........................................................................................13.A-3513.A.44.3Method...................................................................................................13.A-3513.A.44.4Acceptance Criteria................................................................................13.A-35 13.A.45CEDS SIMULATOR BOX OPERATION - DESCRIPTION..............13.A-3613.A.45.1Purpose...................................................................................................13.A-3613.A.45.2General Prerequisites.............................................................................13.A-36

13.A.45.3Test Methods..........................................................................................13.A-3613.A.45.4Acceptance Criteria................................................................................13.A-36 13.A.46SYSTEM: SOLID RADWASTE SYSTEMS........................................13.A-37 13.A.46.1 Test Objectives......................................................................................13.A-37 13.A.46.2Prerequisites...........................................................................................13.A-3713.A.46.3Method...................................................................................................13.A-37 13.A.46.4Acceptance Criteria................................................................................13.A-3713.A.47SYSTEM: CONTAINMENT BUIL DING INTEGRATED LEAK RATE TEST 13.A-3713.A.47.1Objective................................................................................................13.A-37 13.A.47.2Prerequisites...........................................................................................13.A-3713.A.47.3Method...................................................................................................13.A-38 13.A.47.4Acceptance Criteria................................................................................13.A-3813.A.48SYSTEM: CONTAINMENT BUIL DING STRUCTURAL INTEGRITY TEST......................................................................................................13.A-3813.A.48.1Objective................................................................................................13.A-38 13.A.48.2Prerequisites...........................................................................................13.A-3813.A.48.3Method...................................................................................................13.A-38 13.A.48.4Acceptance Criteria................................................................................13.A-3813.A.49SYSTEM: CONTAINMENT PENETRATION VENTILATION SYSTEM.....

13.A-3813.A.49.1Objective................................................................................................13.A-3813.A.49.2Prerequisites...........................................................................................13.A-3813.A.49.3Method...................................................................................................13.A-39 13.A.49.4Acceptance Criteria................................................................................13.A-3913.A.50SYSTEM: CONTAINMENT PURGE SYSTEM.................................13.A-39 13.A.50.1Objectives..............................................................................................13.A-3913.A.50.2Prerequisites...........................................................................................13.A-3913.A.50.3Method...................................................................................................13.A-3913.A.50.4Acceptance Criteria................................................................................13.A-3913.A.51SYSTEM: CONTROL ELEMENT DRIVE ASSEMBLY VENTILATION......

13.A-3913.A.51.1Objective................................................................................................13.A-3913.A.51.2Prerequisites...........................................................................................13.A-3913.A.51.3Method...................................................................................................

13.A-40 MPS2 UFSAR Table of Contents (Continued)

Section Title Page 13-ix Rev. 3513.A.51.4Acceptance Criteria................................................................................13.A-4013.A.52SYSTEM: CONTAINMENT AIR RECIRCULATION SYSTEM......13.A-4013.A.52.1Objectives..............................................................................................13.A-40 13.A.52.2Prerequisites...........................................................................................13.A-4013.A.52.3Method...................................................................................................13.A-4013.A.52.4Acceptance Criteria................................................................................13.A-40 13.A.53SYSTEM: CONTROL ROOM AIR CONDITIONING SYSTEM.......13.A-40 13.A.53.1Objectives..............................................................................................13.A-4013.A.53.2Prerequisites...........................................................................................13.A-40 13.A.53.3Method...................................................................................................13.A-4113.A.53.4Acceptance Criteria................................................................................13.A-4113.A.54SYSTEM: NON-RADIOACTIVE VENTILATION SYSTEM............13.A-41

13.A.54.1Objective................................................................................................13.A-4113.A.54.2Prerequisites...........................................................................................13.A-41 13.A.54.3Method...................................................................................................13.A-41 13.A.54.4Acceptance Criteria................................................................................13.A-4113.A.55SYSTEM: DIESEL GENERATOR VENTILATION SYSTEM..........13.A-4113.A.55.1Objective................................................................................................13.A-41 13.A.55.2Prerequisites...........................................................................................13.A-4113.A.55.3Method...................................................................................................13.A-4213.A.55.4Acceptance Criteria................................................................................13.A-42 13.A.56SYSTEM: MAIN EXHAUST SYSTEM..............................................13.A-42 13.A.56.1Objectives..............................................................................................13.A-4213.A.56.2Prerequisites...........................................................................................13.A-42 13.A.56.3Method...................................................................................................13.A-4213.A.56.4Acceptance Criteria................................................................................13.A-4213.A.57SYSTEM: FUEL HANDLING AREA VENTILATION SYSTEM.....13.A-42 13.A.57.1Objective................................................................................................13.A-4213.A.57.2Prerequisites...........................................................................................13.A-42 13.A.57.3Method...................................................................................................13.A-43 13.A.57.4Acceptance Criteria................................................................................13.A-4313.A.58SYSTEM: RADWASTE VENTILATION SYSTEM...........................13.A-4313.A.58.1Objective................................................................................................13.A-43 13.A.58.2Prerequisites...........................................................................................13.A-4313.A.58.3Method...................................................................................................13.A-4313.A.58.4Acceptance Criteria................................................................................13.A-4313.A.59SYSTEM: PRIMARY CHEMICAL ADDITION SYSTEM................13.A-43 13.A.59.1Objective................................................................................................13.A-4313.A.59.2Prerequisites...........................................................................................13.A-43 13.A.59.3Method...................................................................................................13.A-4413.A.59.4Acceptance Criteria................................................................................

13.A-44 MPS2 UFSAR Table of Contents (Continued)

Section Title Page 13-x Rev. 3513.A.60SYSTEM: POST-INCIDENT RECIRCULATION SYSTEM..............13.A-4413.A.60.1Objective................................................................................................13.A-4413.A.60.2Prerequisites...........................................................................................13.A-44 13.A.60.3Method...................................................................................................13.A-4413.A.60.4Acceptance Criteria................................................................................13.A-4413.A.61REACTOR COMPONENTS HANDLING SYSTEM..........................13.A-44 13.A.61.1Purpose...................................................................................................13.A-4413.A.61.2General Prerequisites.............................................................................13.A-44 13.A.61.3Test Method...........................................................................................13.A-4513.A.61.4Acceptance Criteria................................................................................

13.A-45 MPS2 UFSAR 13-xi Rev. 35 CHAPTER 13-INITIAL TE STS AND OPERATION List of Tables Number Title13.12-1Seismic Category I-ASME Section III Classes 1 and 2 Piping Systems MPS2 UFSARNOTE: REFER TO THE CONTROLLED PLANT DRAWING FOR THE LATEST REVISION.

13-xii Rev. 35CHAPTER 13 - INITIAL TESTS AND OPERATION List of Figures Number Title13.2-1Millstone Nuclear Power Station Organization Diagram During Initial Startup13.2-2Startup Group Organization MPS2 UFSAR13.1-1Rev. 35CHAPTER 13 - INITIAL TESTS AND OPERATION

13.1 DESCRIPTION

OF THE STARTUP TEST PROGRAM 13.1.1 SCOPEThe Millstone Unit 2 Startup Test Program consisted of all testing activities commencing at the completion of the construction phase and ending with the completio n and acceptance of all test data. The Startup Test Program was di vided into the following test phases.Phase I:Initial Inspection and Component TestingPhase II:Preoperational and Acceptance Testing Phase III:Pre-Core Hot Functional TestingPhase IV:Initial Fuel Loading Phase V:Post-Core Hot Functional TestingPhase VI:Reactor Initial Criticality Phase VII:Low Power Physics TestingPhase VIII:Power Ascension Testing Each of the above testing phases will be discussed in detail in succeeding sections. The Initial Inspection and Component Te sting phase bega n as the various syst em construction was completed. This phase was fo llowed by the preoperational, acceptance and pre-core hot functional test phases. After fuel load, the fi nal 4 phases of testing were completed by May 1976.

13.1.2 OBJECTIVESThe Startup Test Program demonstrated that components and systems operate and function in accordance with the FSAR and syst em descriptions. The test results confirme d that the plant can be safely operated and that perf ormance levels can be maintained in accordance with the safety requirements established by the Fi nal Safety Analysis Report. Th e program result s established baseline performance data, and served as verification that normal plant operating and plant emer gency procedures accomplish the pur poses for which they were prepared.

MPS2 UFSAR13.2-1Rev. 35 13.2 STARTUP TEST PROGRAM ORGANIZATION AND RESPONSIBILITIES 13.2.1 PLANT ORGANIZATION The Millstone Point Company was responsible for supe rvising, directing, and ensuring that all phases of plant testing are accomplished in accordance with established criteria. The Plant Superintendent had the responsibility for ensuri ng that all phases of th e Startup Test Program were properly accomplished and accepted. The Startup Group and Plant Staf f was responsible to the Plant Superintendent for pl anning and accomplishment of the Startup Test Program. The organization of the Plant Staff including Millstone Startup personnel is shown in Figure 13.2-1. A detailed description of the Startup Gr oup is provided in the following section.

13.2.2 STARTUP TEST GROUP 13.2.2.1 OrganizationThe Startup Group was organized as shown on Figure 13.2-2. The Joint Test Group, composed of the Assistant Plant Superintendent, Combustion Engineering Site Manager , and the Bechtel Supervising Startup Engineer, ad ministratively controlled the conduct of the Startup Test Program. The plant operating staff conducted all testing operati ons under the direction of the Millstone Startup E ngineers. The Millstone Lead Startup Engineer coordinated the entire Startup Test Program, working with the Joint Test Group and directing th e activities of the Millstone Startup Engineers.

During the equipment checkout a nd preoperational tests phases of the Startup Test Program, Millstone Startup E ngineers were on shift only if required for the performa nce of a particular pre-operational/acceptance test. The Millstone Startup Engineer normally acted as the Test Supervisor. Bechtel Startup Engineer s were on shift during this time if a need for their particular expertise exists as determined by the Lead Startup Engineer. Combustion Engineering Startup Engineers were on site whenever CE supplied equipment was being tested. This includes a commitment for full shift coverage if necessary.

During hot functional testi ng, initial fuel loading, initial criticality, low power physics testing and power ascension testing, Millstone Startup Engineers norma lly provided full shift coverage directing the test program. Duri ng long periods of norma l operation using fully tested systems, the JTG elected to temporarily suspend full coverage by Millstone Startup Engineers. Bechtel Startup Engineers were assigned to full shift coverage as necessary by the Millstone Lead Startup Engineer.

Combustion Engineering provided full coverage as requested by the Lead Startup Engineer during periods of changing core reactiv ity or testing NSSS components.

13.2.2.2 Duties and Responsibilitiesa.Joint Test Group MPS2 UFSAR13.2-2Rev. 351.Coordinate the Startup Test Program including formulat ing, reviewing and approving the schedule of startup testing events.2.Shall meet as required to ensure the safety and proper sequencing of evolutions of the Startup Test Program.3.Shall ensure that the Startup Test Pr ogram is conducted in accordance with approved procedures and the Millstone Startup Manual.

4.Shall ensure that each organization's engineering requirements are satisfied.

5.Shall approve and release for execu tion and authorize changes to startup test procedures except for Phase I.6.Shall review and approve the results of tests (Phase II and subsequent) performed under the Startup Test Program.7.Shall recommend the disposition of deficiencies.8.Shall direct the return of systems or portions thereof to Bechtel Construction for correct ion of deficiencies.9.Shall recommend modifications to sy stem design, equipment, or operating procedures to the Plant Superinte ndent, based on the evaluation of the Startup Test Program.10.Shall recommend acceptance of the satisfactorily tested systems by the Plant Superintendent.b.Assistant Plant Superintendent1.Shall serve as Chairman of the Joint Test Group, or may designate a member of the Plant Staff to act as Chairman in his absence.2.Shall be responsible to the Plant Superintendent for the execution of the Startup Program in accordance with the Startup Manual.c.Combustion Engineering Startup Test Or ganizationThe C-E Startup Test Group shall consist of a Site Manager, a Chief Test Engineer, and three Startup Engineers. In addition, design engineers will be temporarily assigned to the site to supplement the C-E Startup Group.

The group shall provide technical advice a nd consultation on all matters relating to the design, operation, and testing of C-E supplied systems and equipment.

MPS2 UFSAR13.2-3Rev. 35Accordingly, the C-E Startup personnel will:1.Monitor the conduct of preoperationa l, hot functional, fuel loading, criticality, low power physics testing and power testing of C-E supplied equipment.

2.Shall provide site evaluation of test results.3.Shall coordinate resolution of problem areas acting as a liaison between the site and home office design groups. 4.Will arrange for onsite ve ndor representation as required. 5.The C-E Site Manager or his authori zed representative shall be a member of the Joint Test Group and as such shall review and approve all startup Test procedures and changes thereto. 6.Minimum qualifications for this group are included in Section 13.2.2.3. d.Bechtel Startup Test OrganizationThe Bechtel Startup Test Gr oup shall consist of a Supervising Startup Engineer and three Startup Engineers (i.e., Mechan ical, Electrical, and Instrumentation and Control).

The group shall provide tec hnical advice and consultatio n on matters relating to the design, operations, and testin g of systems and equipment. Accordingly, the Bechtel Startup personnel will: 1.Monitor the conduct of preoperational, hot functional and power testing of systems and equipment. 2.Shall provide site evaluation of test results. 3.Shall coordinate resolutions of problem area acting as a liaison between the site and home office design groups. 4.Will arrange for onsite ve ndor representation as required. 5.The Lead Supervising Startup Engineer or his authorized representative shall be a member of the Joint Test Group and as such shall review and approve all startup test proc edures and changes thereto. 6.Minimum qualifications for this group are included in Section 13.2.2.3.

MPS2 UFSAR13.2-4Rev. 35e.Millstone Lead Startup Engineer1.Shall attend meetings of the Joint Test Group and may , if so designated, act as Chairman of the JTG in the absence of the Assistant Plant Superintendent. 2.Shall be responsible to the JTG for implementation of the Startup Test program. 3.Shall coordinate the preparation and review of all procedures required for the Startup Test Program. 4.Shall, as directed by the JTG, coordinate the transfer of systems, or portions thereof, from Bechtel Construction to Millstone Point Company for testing. 5.Shall coordinate, as appropriate, th e flushing and hydrostatic testing of systems. 6.Shall coordinate the testing func tions of Millstone Maintenance, Instrument, and Operations Departments. 7.Shall ensure timely completion of test prerequisites and notification to the JTG of system readiness to test. 8.Shall ensure that sufficient pers onnel and equipment are available to execute each test of the Startup Test Program. 9.Shall submit test results to the JTG for evaluation. 10.Shall coordinate resolution of design, construction, or testing deficiencies. 11.Shall, when directed by the JTG, s upervise the transfer of systems or portion thereof to Bechtel Construction for further work or correction or deficienci es. 12.Shall approve for use Phase I Test Procedures. f.Millstone Startup Engineers1.Shall assist the Lead Startup Engin eer in the performance of his duties. 2.Shall prepare test procedures.

3.Shall supervise the performance of te st, ensuring that the tests are properly conducted in accordance with the te st procedure, applicable operating procedures, and the Startup Manual.

MPS2 UFSAR13.2-5Rev. 35 13.2.2.3 Qualifications Minimum qualifications of the key personnel comprising the Millstone Startup Group are as follows: a.Millstone Lead Startup Engineer1.At least two years of formal college level academic trai ning or equivalent. 2.At least six years of power plant-rela ted work experience including not less than two years directly involved in the operation, engineering, and/or maintenance disciplines. 3.At least three years of training or e xperience with nuclear power plants or equivalent. 4.Senior Operator's License. b.Millstone Startup Engineers1.At least two years of formal college level academic trai ning or equivalent. 2.At least six years of pow er plant related work experience in cluding not less than two years directly involved in the operation, engineering, and/or maintenance disciplines. 3.At least two years of training or experience, with nuclear power plants or equivalent. 4.Senior Operator's License or equivalent knowledge and background. c.Combustion Engineering Site Manager1.B.S. Engineering Nuclear Power Training (Military, ORSORT or equivalent). 2.Ten years' nuclear reactor operations, testing and training. 3.SRO or equivalent on power reactor (military, commercial, or test reactor). d.Combustion Engineering Chief Test Engineer1.M.S. or B.S. Nuclear Engineer ing with equivalent experience. 2.Ten years' reactor analysis, de sign, operation and testing. Previous experience in installation and startup testing, power and research reactor.

MPS2 UFSAR13.2-6Rev. 353.SRO or equivalent on power reactor (military, commercial or test reactor). e.Combustion Engineering Startup Engineer1.B.S. Engineering Nuclear Power Training (Military, ORSORT or equivalent). 2.Five years' nuclear reactor operation testing or training. 3.SRO or equivalent on power reactor (military, commercial or test reactor). f.Bechtel Supervising Startup Engineer1.Will have previously held a similar capacity of Supervising Startup Engineer on another nuclear plant, or been a group leader (Electrical, Mechanical, I&C) on a nother nuclear plant.

2.Will be familiar with AEC require ments for the pre-operational test program, including documentation, quality control and quality assurance. 3.Will be capable of planning and c oordinating the entire plant startup program.g.Bechtel Startup Engineers1.Will have held a similar position of Startup Engineer on another nuclear plant.2.Will be familiar with AEC requireme nts for pre-operational test program, including documentation, quality c ontrol and quality assurance. 3.Will be capable of planning and coor dinating the startup activities within his discipline (Electrical , Mechanical, and I&C).

MPS2 UFSAR 13.2-7 Rev. 35FIGURE 13.2-1 MILLSTONE NUCLEAR POWER STATION ORGANIZATION DIAGRAM DURING INITIAL STARTUP CODE: RO - R E A CTO R O P E RA TO R SR O - S ENIO R R E A CTO R O P E RA TO R SR O SR O ASST. ENG. Q A/QC (1)

ASST. PLNT. S U P E R. UNIT 1 O R G ANIZ ATION (AS UNIT 2) (1)CHE M. & H.P. S U P E R VI S O R (1) H.P. TECH S. (4)HE ALTH P HY SICI S T (1)CHE M I S T UNIT 1 (1) CHE M. TECH S.(3)CHE M I S T UNIT 2 (1) CHE M. TECH S.(3)ASS I S T ANT ENGINEE R (1) MACHINI S T (3) S TOCK MA N (3) S TO REKEE P E R (1) BLDG S E R V. (5) CLE R K (5)O FFICE MA N A GE R (1) M ECH S. (8) ELECT. (2)MAINTEN ANCE F O R E MA N (1)SR O O P E RATION S S U P E R VI S O R (1) P L ANT EQUI P. O P E RA TO RS (10)R O CONT ROL O P E RA TO RS (5)R O S U P E R VI SING CONT ROL O PS. (5)SR O S HI F T S U P E R VI S O R (5) MA I NTE N ANCE S U P E R VI S O R (1) ASS I S T ANT ENGINEE R (3)R E A CTO R ENG. TECHNICI A N (1)ASS I S T ANT ENGINEE R (1)R E A CTO R ENGINEE R (1)IN ST. & CONT. TECHNICI A N (4)IN ST. & CONT.

S U P E R VI S O R (1)S T AR T U P ENGINEE RS (5)LE A D S T AR T U P ENGINEE R (1)S E RVICE G R OU P S U P E R VI S O R (1)ASST. P L ANT S U P E R. UNIT 2 (1) P L ANT S U P T. (1)

MPS2 UFSAR 13.2-8Rev. 35FIGURE 13.2-2 STARTUP GROUP ORGANIZATION JOINT TEST GROUP LEAD START UP ENGINEER START UP ENGRS. REACTOR ENGINEER ENGRS. INSTR. SUPV. TECHS. CHEM. & H.P.

SUPV. TECHS. FRMN. MAINT. SUPV. INDICATES ADVICE AND CONSULTATION INDICATES NORMAL PLANT OPERATIONS AUTHORITY C.E. CHIEF TEST ENGINEER OPERATIONS SUPERVISOR BECHTEL S/U ENGRS.

C.E. S/U ENGRS.

SHIFT SUPERVISORS SENIOR CONTROL OPERATORS REACTOR OPERATORS ASSISTANT PLANT SUPT. C.E. SITE MANAGER BECHTEL SUPERVISING S/U ENGINEER

MPS2 UFSAR13.3-1Rev. 35 13.3 ADMINISTRATIVE CONDUCT OF THE STARTUP TEST PROGRAM 13.3.1 TEST PROCEDURES - DISCUSSIONTest procedures were prepared by the plant staff using test guideli nes provided by Bechtel or C-E. These tests were reviewed by NUSC O, Bechtel and C-E. Additionally, other members of the plant staff were assigned to review test procedures. With the exception of Phase I test procedures, all procedures were reviewed and approved by the JTG. The test s were performed by Millstone personnel, under the direction of a Millstone Startup Engineer. Al l procedures were adhered to with deviations permitted only th rough administrative contracts.Test data was recorded and evaluated. Test deficiencies were resolv ed and the test accepted before the test was considered complete by the JT G (for Phase II and subsequent tests).

All tests and associated documents will be retained for the life of the plant.

13.3.2 TEST PROCEDURE PREPARATION Detailed test procedures were prepared by the plant staff using test guide lines provided by Bechtel or Combustion Engineering, for each specific te st performed during the various phases of the Startup Test Program. Each test procedure contained th e following major sections:Test Objective Acceptance Criteria References

Prerequisites Initial Conditions Special Precautions Procedure StepsSystem Restoration Upon completion of preparation of a test procedure, the pr ocedure was processed through a review circuit. The Millstone Lead Startup Engineer coordinated the review of all procedures.

As appropriate for a particular procedure, the document was re viewed by some or all of the following:

Combustion Engineering MPS2 UFSAR13.3-2Rev. 35Bechtel Startup GroupNortheast Utilities Service Company Millstone Instrument DepartmentMillstone Chemistry/Heal th Physics DepartmentMillstone Reactor E ngineering Department Upon completion of these reviews, any necessary changes were incorporated by the originator. Te st procedures for Phase I of the Startup Test Program were approved for use by the Millstone Lead Startup Engineer. All other test procedur es were forwarded to the JTG for approval.

13.3.3 TEST PROCEDURE EXECUTION AND CHANGES THERETO Once the test procedure had been approved, the Millstone Lead Startup Engineer coordinated the completion of prerequisites. When all test prerequisites were comple te and any allowable exceptions noted, the test was returned to the Millstone Lead Startup Engineer who discussed any prerequisite exceptions with the JTG and arranged for the test to be scheduled.When authorized for performance, each test was performed in conformance with the test procedure and authorized changes. All test data was recorded on data bla nks within the procedure or on specially prepared data sh eets. When the test was completed, the Millstone St artup Engineer reviewed the test data agains t the stated acceptance criteria and resolved discrepancies in accordance with the Startup Manual.

At all times the shift supervis or was responsible for the safe and proper operation of plant equipment and systems and for th e safety of plant personnel.

In the fulfillment of this responsibility he took whatever action was necessary including but not limited to stopping any test and placing plant equi pment in a safe condition.

Once a procedure had been approve d, all procedure changes were made using the Test Procedure Change Form. This form provided a means for making on-the-spot changes providing the change did not alter the intent of the pr ocedure or endanger plant personnel or equipment. In the case of a Phase I test procedure only, th e shift supervisor and test S upervisor provided joint change authorization. Changes for all other phases were jointly authorized by the Shift Supervisor and the Millstone Startup Engineer. Concurrence of the C-E Startup Engineer and/or Bechtel Startup Engineer as appropriate was obtained prior to ma king the change. The cha nge was then confirmed by the JTG by the end of one work ing week. JTG approva l was not required for changes to Phase I test procedures.

13.3.4 EVALUATING TEST PROCEDURE DATA All tests were evaluated by a minimum of one individual not a member of the department performing the test. This would normally be done by NUSCO, Bechtel, or C-E. Additionally, MPS2 UFSAR13.3-3Rev. 35other members of the Millstone Plant Staff were also requested to evaluate the completed test.

This evaluation included determining that all deficiencies had been identified. The evaluation of all test procedures was coordinated by the Millstone Lead Startup Engineer.

Once the test had been evaluated, test deficiencies resolved, a nd no additional re testing required, the Millstone Lead Startup Engineer signed for test acc eptance on all Phase I tests.

For all other tests, the JTG re viewed the test results and, wh en satisfied, signed for test acceptance.

13.3.5 TEST RESULT DOCUMENTATION As a test procedure was being pe rformed, test data was recorded on data blanks within the body of the procedure or on provided data sheets. Included were the exp ected or desire d value of the parameters.

The execution copy of all test procedures, reco rds, startup forms, recorder tracings, and photographs are the sole property of the Millstone Point Company and will be retained for the life of the pl ant.

MPS2 UFSAR13.4-1Rev. 35 13.4 MILLSTONE STARTUP GROUP TRAINING PROGRAM An intensive training pr ogram was conducted to pr epare the Millstone Unit 2 Startup Engineers, Staff Supervisors, Supervising C ontrol Operators, Reactor Operat ors, Plant Equipment Operators and certain members of the Millstone Plant Staff fo r their responsibilities in conducting the Unit 2 Startup Test Program. The details of the training program are given in Chapter 12.

MPS2 UFSAR13.5-1Rev. 35 13.5 INITIAL INSPECTION AND COMPONENT TESTING PHASEDuring this phase of the Startup Test Program, each system compon ent was individually tested for conformance with acceptance criteria. Typical items to be perf ormed during this phase by the maintenance or instrumentati on departments were phase ro tation checks, megger checks, alignment checks, etc. These checks were performed in accordance with prepared test procedures. Additionally, the Operations Department direct ed the performance of flushes and hydrostatic tests. These operations were performed in accordance with prepared test procedures and served as some of the prerequisites for the preoperational/acceptance test phase of the Startup Test Program.

MPS2 UFSAR13.6-1Rev. 35 13.6 PREOPERATIONAL AND ACCEPTANCE TEST PROGRAM 13.

6.1 DESCRIPTION

OF PREOPERATIONAL AND ACCEPTANCE TEST PROGRAM The comprehensive preoperational a nd acceptance testing phase were performed to ensure that all equipment and systems were capabl e of performan ce in accordance with their acceptance criteria, and to establish initial base line performance data for th e equipment and systems. The preoperational and acceptance test phase in general included adjust ments, calibrations, determination of pump head characteristics and overall system capability under ambient conditions. The tests involved actual operations of the systems and equipmen t where possible. All tests were performed in accorda nce with written procedure. Ad ministrative control of the preoperational test procedures is described in Section 13.3 of this chapter. Testing operations were conducted under the direction of the personnel described in

Section 13.2.2.

13.6.2 INDEX OF PREOPERATIONAL TESTS AND GENERAL TESTING SEQUENCE Listed below , in an appropr iate sequence of performance, are the systems which were preoperationally tested.

Communications System 125 V olt DC SystemReserve Station Service Transformer Primary Water Treatment System 4,160 Volt Electrical System 480 Volt Load Centers Service Water System

Clean Liquid Radwaste System

Aerated Liquid Radwaste System 480 Volt Motor Control Centers Turbine Building Closed Cooling Water System

Fire Protection System

Recovered Boric Acid SystemInstrument Air SystemPrimary Water Storage System 120 Volt Nonvital Instrument AC System 120 Volt Vital Instrument System MPS2 UFSAR13.6-2Rev. 35 Gaseous Radwaste SystemCondensate Storage and Transfer System Auxiliary and Emergency Feedwater System Steam Generator Feedwater System

Condensate System Feedwater Heater Drain and Vents Main Steam (Bypass and Steam Dump Valves)

Sampling System

Spent Fuel Cooling and Purification Reactor Building Closed Cooling Water System

Fuel Handling Systems

Safety Injection Systems (High-Pressure, Low-Pressure, and Safety Injection Tanks)

Diesel Fuel Oil System Diesel Generators

Containment Spray System

Shutdown Cooling System

Engineered Safeguards Actuation System Reactor Coolant System

Reactor Regulating System

Reactor Protection System Chemical Volume Control and Purification System Nuclear Instrumentation Systems In-Core Instrumentation System

Process Radiation Monitoring Systems Area Radiation Monitoring Systems

Boronometer and Process Radiation Monitor Main and Normal Station Service Transformer Enclosure Building Filtration SystemControl Element Assemblies - CEDS BOX SIMULATOR

Solid Radwaste

Containment Building Integrated Leak Te st MPS2 UFSAR13.6-3Rev. 35Containment Building Structural Integrity Test Containment Penetration Cooling System Containment and Enclosure Building Purge System

Control Element Drive Mechanism Cooling System

Containment Air Recirculation System

Control Room Air Conditioning System Nonradioactive Ventilation System Diesel Generator Ventilation System

Main Exhaust System

Fuel Handling Area Ventilation System Radwaste Ventilation System Primary Chemical Addition System

Access Control Area Air Conditioning System

Engineered Safety Features Room (Air Recirculation and Cooling) Ventilation SystemVital Electrical Switchgear (Emergency Cooling) Ventilation System Containment Post-Incid ent Hydrogen Control Preoperational test descripti ons are given in Appendix 13.A.

13.6.3 INDEX OF ACCEPTANCE TESTS AND GENERAL TESTING SEQUENCEListed below, in an approximate sequence of performance, are the systems which were acceptance tested: Domestic Water System 345 kV Switchyard Plant Computer Screen Wash System

Chlorine System Auxiliary Boiler Fuel Oil System Plant Heating and Condensate Recovery System Condenser Air Removal System Water Box Primary System

Condenser Air Removal Exhaust System MPS2 UFSAR13.6-4Rev. 35Intake Structure Ventilation System Cathodic Protection System Main Circulating Water System Station Air System Extraction Steam System

Secondary Chemical Addition System 6,900 Volt Electrical System Auxiliary Steam Reboiler and Deaerating Feedwater SystemReheat Steam and Moisture Separator System Warehouse Ventilation System Containment Auxiliary Circulation System Turbine Building Heating and Ventilation System Turbine Seal Oil System Turbine Lube Oil System Exciter Air Cooler System Main Turbine and Controls

Hydrogen System

Nitrogen System

Generator Hydrogen Cooler System

Carbon Dioxide and Hydrogen System

Main Generator Turbine Gland Seal and Drain System Stator Liquid Cooling System Station Lighting and Grounding MPS2 UFSAR13.7-1Rev. 35 13.7 HOT FUNCTIONAL TEST PROGRAM 13.

7.1 DESCRIPTION

OF HOT FUNCTIONAL TEST PROGRAM The integrated pre-core hot functional test phase of the Start up Test Program was performed on major plant systems prior to ini tial fuel loading with the reac tor coolant system at operating temperature and pressure. The pre-core hot functi onal test heated the pr imary plant from ambient to normal operating temperature and pressure, st opping at specific temp erature plateaus and performing specified evaluations (i.e., pressurizer bubble, coolan t flow and vibration checks, primary plant chemistry analysis, bypass and dump valve operation, etc.).

The post-core hot functional test phase was conducted upon the completion of the initial core loading operations. This test es sentially consisted of CEDM coupling, CEA position checks, CEA drop tests and loss of flow and flow coast down tests.

13.7.2 REACTOR COOLANT SYSTEM HOT FUNCTIONAL TEST (PRE-CORE)

DESCRIPTION

a.Test Objective1.To demonstrate the proper perfor mance of the NSSS under normal operating conditions of temp erature, pressure, and fl ow prior to performing the initial core loading.2.To provide chemical pa ssivity of the RCS piping prior to reactor operation.b.General Prerequisites1.All pre-operational test procedures have been completed and discrepancies corrected or waived.2.The reactor vessel internals have been installed with the exception of the fuel.3.Temporary instrumentation to meas ure reactor coolant pump and reactor vessel differential pressures during flow testing is installed and has been calibrated.4.Prestartup system checkoff lists have been completed.5.The RCS, SIS, CVCS, RBCCWS, and al l other associated systems have been lined up for normal operation in accordance with the applicable P&IDs.6.A suitable source for heat rejection from the RCS is available.

MPS2 UFSAR13.7-2Rev. 357.All systems including the RCS, the SIS, and the CVCS have been filled with demineralized water in accor dance with the water chemistry specifications for cold shutdown with the exception that the boron concentration is zero ppm.c.Test Methods1.Using normal operating procedures bring the RCS to a temperature of 260°F and a pressure of 415 psia with a bubble in the pressurizer, normal zero-power pressurizer level, and two reactor coolant pumps operating.2.With the RCS at 260

°F and 415 psia, perform a te st data record, measure RCS flow under various pump combina tions, perform a calibration check of the process instrume ntation, measure the RC S component expansion, and measure the CEDM temperatures.

3.Perform RCS heatup and pressurizat ion using the same pressure and temperature steps that will be used during the Post-Core Hot Functional Tests and Low Power Physics Testing. The steps will involve heatup from 260°F, 415 psia to 360

°F, 415 psia; pressurization from 415 psia to 1100 psia to 2250 psia, 460

°F, and heatup from 460

°F to 532°F, 2250 psia.4.During the heatup and pressurization th e heatup rate will be determined, the pressurizer heatup rate will be me asured, calibration checks will be conducted on temperature detectors, CEDM temperatures will be monitored, RCS components expansion will be measured, test data records will be completed, and pressure det ector calibrations will be checked.5.At 532°F, 2250 psia test data records wi ll be taken, reactor coolant flow measurements will be performed, reactor coolant heat loss measurements will be made, CEDM temperatures will be monitored, RCS component expansion will be measured, proce ss instrumentation will have their calibrations checked.6.The reactor will be c ooled down in accordance with normal plant operating procedures to 260

°F, 415 psia.7.The RCS will be cooled down in accordance with normal operating procedures to approximately 130

°F and all systems will be prepared for initial fuel load ing.d.Acceptance Criteria The NSSS performs in accordance with th e FSAR description, the various system descriptions, appropriate vendor manuals, and Technical Specifications.

MPS2 UFSAR13.7-3Rev. 35 13.7.3 REACTOR COOLANT SYSTEM HOT FUNCTIONAL TEST (POST-CORE) -

DESCRIPTION a.Test Objective1.To demonstrate operation of the NSSS with fuel prior to performing the initial criticality.2.T o measure the RCS heatup rates, heat losses, and system flows. 3.To demonstrate the proper functi oning of the CEDMs and the CEAs. b.General Prerequisites1.Initial core loadi ng has been completed.2.Reactor vessel internals and head have been installed with all appropriate wiring connections made.3.Prestartup system checkoff lists have been completed.4.All systems are ready for normal operation.c.Test Methods1.Using standard operating proced ures, heatup the plant to 260

°F, 415 psia with a bubble in the pressurizer, norma l zero-power pressu rizer level, and two or three reactor coolant pumps operating.2.With the RCS at 260

°F, 415 psia conduct a test data record, and perform the cold CEA performance test. Cold rod drop times will be performed once on each CEA with no reactor coolant pumps operating.3.Increase RCS temperatur e and pressure using the same steps as used in NH-RC-2. During these heatups and pressurizations, remeasure the RCS heatup rate and the pressurizer heatup rate.4.With the RCS at 532

°F, 2250 psia, conduct a test data record, measure the RCS flows under various two-, three- and four-pump combinations, perform flow coast down measuremen ts, determine the RCS heat loss, perform the hot CEA performance test, and conduct boron dilution and boration tests. The performance test s include determining CEA drop times once on each CEA with full RCS flow plus additional measurement of the fastest and slowest CEA's ten times each at full flow.5.Prepare for performing initial criticality.

MPS2 UFSAR13.7-4Rev. 35d.Acceptance Criteria The RCS flows, the CEA performance, the RCS heat losses, etc., are in agreement with the FSAR description, the appropriate system descriptions, the appropriate vendor manuals, and the Technical Specifications.

MPS2 UFSAR13.8-1Rev. 35 13.8 INITIAL FUEL LOADINGThe Millstone Startup Group directed the initial fuel loading operat ions with the responsibility for the operation resting with the Pl ant Superintendent. The Combus tion Engineering Site Manager and Chief Test Engineer or thei r representatives provided technical advice as required during the fuel loading operations.

13.8.1 THE PURPOSES OF THE INITIA L FUEL LOADING PROCEDURE ARE:a.To provide a safe, organized method of accomplishing the initial fuel loading for the Millstone Unit 2 reactors. General procedures and supplemental detailed procedures will be provide d to perform the following:

1.Loading of 217 fuel assemblies.2.Insertion of 81 CEA's.3.Insertion of neutron source assemblies.b.To provide a fuel loading sequence whic h will result in early coupling of the loaded portion of the core and the reactor plant out-of-core nuclear instrumentation system.

Fuel loading shall be performed in acc ordance with written procedure. After completion of each step of the procedur e, approval must be obtained from the Millstone Startup Engineer before the next procedural step will be initiated.

Administrative control of the fuel loadi ng procedures shall be as described in Section 13.3 of this chapter.

13.8.2 INITIAL CONDITIONS WHICH WILL BE ESTABLISHED PRIOR TO THE INITIAL FUEL LOADING ARE:

a.Pre-core loading briefing for opera ting and supervisory personnel has been conducted.b.The reactor protective system calibrati on tests, preoperati onal tests, and hot functional tests have been satisfactorily completed as far as possible with all known discrepancies documented and corr ected or waived for the purpose of proceeding with the initial core loading;c.The reactor vessel head and upper guide structure are removed. The reactor coolant system is filled to a specified level with refueling concentration borated water. Valve check lists are completed to minimize the possibilit y of an inadvertent change in boron concentration. Representati ve samples of system coolant will be withdrawn periodically and analyzed fo r boron concentration during the loading

operation; MPS2 UFSAR13.8-2Rev. 35d.Temporary neutron detectors will be inst alled in the core and final calibration and alignment completed. Readouts will be available in the loading area. A communications link will be established between the c ontrol room, the refueling pool area, and the spent fuel pool area; e. A start-up neutron source will be installed in the core with the first fuel assembly and verification of the neut ron level monitoring instru mentation made. Equipment will be provided to conduct inverse count rate monitoring of the core during loading; f.A tag board will be provide d in the control room for identifying the lo cation of all movable core components. These includ e sources, neutron detectors, fuel assemblies and control element assemblies; g.The reactor coolant system , chemical and volume cont rol system, and auxiliary systems are lined up for fueling operati ons in accordance with plant operating procedures; andh.Continuous area radiation monitoring in the spent fuel pool handling and refueling pool areas is maintained.

13.8.3 PRECAUTIONS WHICH SHALL BE OBSERVED DURING THE INITIAL FUEL LOADING ARE: a.Continuous monitoring of the temporar y neutron instrumentation will be conducted and operations halte d if any unusual increase in count rate is observed, or if the addition of two consecutive fuel assemblies causes the inverse count rate plot to vary significantly from the expected behavior. b.A fueling monitor will be assigned to the refu eling pool area to observe and verify all fuel handling operations. His sole responsibility will be the verification of serial numbers and core locations of fuel asse mblies and CEA's. He shall not perform any other task during the fue ling operation. He wi ll verify the fuel assembly serial number prior to its removal from the reacto r side transfer machine. Core location and assembly serial number orientation will be verified and recorded once the bundle is placed in the core. CEA serial numbers will be verified upon insertion into the proper fuel assembly and thei r installed location will be recorded; c.Reactor coolant boron concentration shall be maintained at 1770

+/- 50 ppm. Boron concentration of the reactor coolant in the reactor vessel will be verified periodically throughout the fuel loading pr ocess, and the results reviewed by the Millstone Startup Engineer. Water level in the reactor coolant system will be monitored and recorded periodically.

MPS2 UFSAR13.8-3Rev. 35d.Whenever makeup water is added to the reactor coolant system the refueling water boron concentration must be verified at the refueling concentration of 1770

+/- 50 ppm boron;e.Water level in the reactor vessel during loading will be maintained at a specified distance from the reactor vessel flange. If any unexplained increase or decrease in water level occurs the fueling operation wi ll be stopped until the cause for the change in water level has been determin ed and the boron concentration verified;f.Extreme care will be taken throughout th e fuel loading operation to maintain accurate records of fuel assembly and CEA locations; g.An overall fuel and CEA location map, in cluding the exact status of each fuel assembly and CEA, will be maintaine d in the refueling pool area and the control room. A step-by-step record of the fueli ng procedure will be maintained in each area;h.The fueling sequence will be strictly followed; andi.Core loading operations will be stopped if communications are lost between the control room and the refueling pool area.

13.8.4 THE FUEL LOADING PROCEDURES SH ALL INCLUDE THE FOLLOWING CONSIDERATIONS:

a.The refueling machine will be operate d in accordance with plant operating procedures;b.A record of the time and date as a given step is completed will be written on the appropriate procedure sheet;c.As each step is completed the Shift Supervisor must initial for the step. His signature must appear at the bottom of each page of this procedure. The Shift Supervisor must be informed prior to the performance of each step of the procedure and at the completion of each step;d.Count rate of each wide ra nge channel and temporary channel will be recorded on an appropriate data sheet; e.1/m (Inverse count rate multiplication) values will be calculated, plotted, and evaluated after each loading step;f.The count rate of the tem porary neutron detect ors must be norma lized after each move of the detector. Each detector move must be documented on the plotting sheet to account for possible di scontinuities of the plot; MPS2 UFSAR13.8-4Rev. 35g.When fuel loading has been complete d, a thorough visual inspection will be conducted, recording serial numbers on a core map, and noting any obvious misalignment of the fuel assemblies; andh.The upper guide structure, in strumentation and reactor vess el head will be installed in accordance with applicable procedures.

13.8.5 The plant reactor engineer has the responsibility and authority, as delegated by the Plant Superintendent, necessary to assure the safe and efficient conduct of the core loading operation and the safeguarding and accountabilit y of Special Nuclear Material. In this regard, he has the authority to initiate alterations to the fuel loading procedure, and stop fuel loading operations when deemed necessary in the interest of safeguarding personnel, the plant and SNM. Approved written procedur es will be strictly adhered to. As a minimum, these procedures will contain th e following: criteria for minimum operable instrumentation; scope of co mmunications between the contro l room and the fuel handling areas; a containment evacuation plan and its a ssociated safety meas ures; actions to be followed in the event of fuel damage; sequencing instructions for core loading, including positioning, orienting and seating of fuel and components; inde pendent verification of fuel and component locations; documentation instru ctions for SNM accountability; methods for the gathering, reduction and evaluation of st atistical count-rate data; and criteria for stopping the fuel loading evolution.

MPS2 UFSAR13.9-1Rev. 35 13.9 INITIAL CRITICALITY The purpose of the Initial Approach to Criticality Procedure was to provide a safe and controlled method of achieving initial reactor criticality.

The initial approach was performed by primary coolant boron dilution with contro l rods in the nearly fully wit hdrawn position at a temperature and pressure specified in the procedure.Administrative control of the initial criticality procedure is described in Section 13.3 of this chapter. After completion of each step of the procedure, approval was obtained from the Millstone Startup Engineer before the next procedural step was initiated. Initial criticality approach was conducted under the direction of the organization described in Section 13.2 of this chapter.

Initial conditions which will be established prio r to the initial approach to criticality are: a.Preoperational and hot functional te sting will have been completed;b.Reactor coolant system boron concentrat ion is at the refueling concentration;c.Reactor coolant system is maintained at specified temperature and pressure;d.Pressurizer and steam generators are maintained at specified water levels; e.Reactor protective system calib ration tests have been performed;f.Reactor coolant pumps are in the stat us specified in the procedure; andg.Containment integrity established in ac cordance with the containment integrity check procedures.

Precaution which must be observed during the initial approach to criticality are:

a.Operating personnel will be vigilant in seeking out and evaluating unexpected behavior of the reactor plant thr oughout the approach to criticality;b.Criticality will be anticipated whenever CEAs are being withdrawn or whenever boron dilution operations are being performed;c.The maximum startup rate will not be exceeded;d.Any changes in plant operating conditions that may produce a sudden change in primary loop water temperature or boron concentration will be avoided if possible;e.The initial approach to cr iticality will be guided by plot s of the inverse count rate multiplication versus time and versus bor on concentration (chemical analysis) and of boron concentration (chemical analysis and boronometer) versus dilution time will be maintained.

MPS2 UFSAR13.9-2Rev. 35f.Reactor coolant system boron concentrat ion will be determined periodically.

Results of boron analysis will be recorded in the control room and compared with the boronometer reading.

The procedure for the initial approach to critic ality will include the following considerations:

a.Reactor coolant system will be sampled to establish initial boron concentration and general reactor coolant system chemistry;b.Periodic sampling of the reactor coolant system for boron will be initiated and results recorded in the control room;c.A boronometer check will be made periodically for proper operation;d.Actuation of the low steam generator pressure and the thermal margin/low-pressure trip will be bypassed;e.Withdrawal of each group of CEAs by th e increment specified will be performed. Test personnel shall maintain plots of the inverse count rate multiplication versus CEA group sequence position for th e wide-range instrumentation; f.Reactor coolant system boron concentratio n will be decreased by dilution. Plots of the inverse count rate multiplication versus time, versus actual boron concentration, and versus calculated bor on concentration will be maintained.

Dilution will be halted when criticality is achieved;g.Slightly above the level at which criti cality was achieved, power level will be stabilized using regulating CEA group specified; andh.After plant conditions have stabilized, the following data for ju st critical condition will be recorded:1.CEA positions 2.System pressure3.System temperature 4.Pressurizer level 5.Boron concentration 6.Indicated power level 7.Reactor coolant system flow 8.Routine chemistry analysis for RCS MPS2 UFSAR13.10-1Rev. 35 13.10 LOW POWER PHYSICS TESTINGThe purpose of the Low Power Physics Testing program was to obtain as-built reactor characteristics and to verify Te chnical Specification, sa fety limits, and physic s design parameters.

Administrative control of the Low Power Physics Te st proc edures was as described in Section 13.3 of this chapter. After completion of each procedural ste p, approval was obtained from the Millstone Startup Engineer before the next procedural step was initiated. Low Power Physics Testing was conducted under the direction of the organization described in Section 13.3 of this chapter.

Initial conditions which will be established prior to the start of the low-power tests are: a.Initial Approach to Criticality has been completed; b.The reactor is critical with excess reactivity as close to zero as practical and a reactor startup rate of zero;c.Boron concentration and CEA position is as remaining from initial criticality;d.The reactor coolant system temperature is being maintained by pump heat and by dumping steam to the atmosphere and/or to the condenser;e.System pressure is being maintained by control of the backup and proportional pressurizer heaters and spray valves;f.Pressurizer level is being maintained by operating the charging pump and proper positioning the letdown stop valves and the letdown control valves; and g.Reactor protective system ca libration tests have been pe rformed subsequent to the most recent alteration to any part of that system.

Precautions which shall be observe d during the low-power tests are: a.The specified low-power power level as indicated by the wide-range logarithmic channels will not be exceeded;b.If any abnormal conditions develop dur ing this procedure which could or do significantly affect core reactivity or increase reactor power above the low-power power level, the reactor operator will trip the reactor, borate if necessary, and restore the plant to a safe normal condition;c.When increasing neutron level, particular note of reactor plant temperature, pressure, pressurizer level, and char ging rate changes will be taken that might indicate reactor operation in the sensible heat region; MPS2 UFSAR13.10-2Rev. 35d.While maintaining criticality during pr imary coolant system borations and/or dilutions, adjustment will be made of the boration or dilution ra te as required when approaching the desired end point to prev ent overshoot. Pressurizer spray will be provided during boron concentration ch anges to equalize pressurizer boron concentration with l oop boron concentration;e.Prior to commencing a specific test, it wi ll be required that all CEA's in a group are within a specified band of each other unless a test condition specifies that a CEA is at other than bank height;f.All plant parameters other than those to be changed during a given operation will be maintained as constant as possible; andg.Tests involving abnormal CEA configurati ons will be performed in accordance with Technical Specifications, and the appropriate special operating precautions will be observed. Te sts to be performed as part of the Low Power Physics Testing program are:

a.Neutron and gamma radiation surveys;b.Verification of radiation monitor response to known source;c.All rods out, clean core, critical boron concentration;d.Temperature coefficient of reactivity with various CEA group configurations;e.Nonoverlapped regulating and shutdown CEA group worths; f.Composite regulating CEA group wo rth with normal group sequencing;g.Worth of the most reactive CEA for a dropped rod situation to verify safety analysis;h.Worth of the most reactive CEA for an ejected rod situation occurring with a full power and a zero power configurat ion to verify safety analysis;i.Worth of the most reactive CEA for a stuck rod situation to verify safety analysis;j.Part-length CEA group worth measurement; k.Chemistry and radiochemistry tests to verify control of water q uality;l.Boron reactivity worth measurement; and m.Shutdown margin determination.

MPS2 UFSAR13.11-1Rev. 3513.11 POWER ASCENSION TESTING The power test procedures descri be the detailed steps required for the initial plant startup from completion of the Low Power Physics Tests phase to full-rated power level, including those tests necessary to demonstrate safe pl ant operation within design specific ations. Administrative control of this phase of the program was as described in Section 13.3 of this chapter. After completion of each step of the procedure, approval was obtained from the Millstone Startup Engineer before the next procedural step will be initiated.

Power Ascension testing was conduc ted under the direction of the organization described in Section 13.2 of this chapter.

Initial conditions which will be established prior to the ascension to power are: a.All preoperational, hot functional, an d low power physics testing have been completed;b.System c heck lists completed for the In itial Approach to Criticality Procedure need not be repeated on any system unle ss that system was removed from service or abnormal valving was performed on that system;c.The reactor coolant system temperature is being maintained by pump heat and by bypassing steam to the main condenser;d.Pressurizer pressure control is in automatic maintaining system pressure;e.The chemical and volume control system is automatically maintaining programmed pressurizer water level;f.Steam generator water level is being maintained within the normal operating range;g.The required reactor coolant pumps are operable; h.The gain sensitivity switches for the linear nuclear instrument power channels are in the X10 position;i.Main condenser vacuum is being maintained;j.The turbine-generator unit is on turning gear; andk.The applicable requirements of the Tec hnical Specifications for plant startup are satisfied.

MPS2 UFSAR13.11-2Rev. 35During the ascension to power, the foll owing precautions will be observed: a.If an unplanned reactor trip should occur during the conduct of this procedure, the plant will be returned, after necessary co rrective measures have been taken, to the conditions which existed at the beginning of the procedure step during which the trip occurred following appr oved operating procedures; andb.All operations where certain plant conditi ons are being established for the first time shall be performed slowly and de liberately to avoid sudden changes in parameter affecting reactor behavior.

The types of tests that are expected to be pe rformed are listed below. The individual test procedural steps will include instructions and precautions fo r establishing special conditions necessary for conducting tests.

TEST POWER LEVELS (%)NSS Test Data Record 10, 20, 30, 40, 50, 60, 70, 80, 90, 100 Core Power Distribution Data Record 10, 20, 30, 40, 50, 60, 70, 80, 90, 100 Transient Test Data Record 20, 50, 80, 100 Xe Equilibrium ARO 20, 50, 80, 100 Xe Equilibrium Rods Inserted 20, 50, 80, 100 NSSS Calorimetric 20, 50, 80, 100 Nuclear and T Power Calibration 20, 50, 80, 100Chemistry & Radiochemistry Tests 20, 50, 80, 100 Radiation Surveys and Shielding Effectiveness20, 50, 80, 100 Process Radiation Monitor Calibration Check20, 50, 80, 100Variable T avg Test 20, 50, 80, 100MCB Reactor Trip 20RCS T Power Determination 20Static "Ejected" CEA20Power Range Subchannel Calibration20Generator Trip100Shutdown Outside Control Room25-40Reactor Regulating System50 Partial Loss of RC Flow80Total Loss of RC Flow40 MPS2 UFSAR13.11-3Rev. 35Natural Circulation0Loss of Offsite Power40Dropped CEA50Turbine Runback80, 90 Part Loop Operation 47, 78.5Induced Oscillation80Minimum DNBR50, 80Turbine Trip 50 (a)Warranty 100(a).The Generator Trip at 100% power will result in a Turbine Tr ip, thus, verifying trip response.

TESTPOWER LEVELS (%)

MPS2 UFSAR13.12-1Rev. 35 13.12 PIPING OPERATIONAL TESTING The seismic Category I piping syst ems designed to ASME Nuclear Classes l and 2 are listed in Table 13.12-1.

The following discusses the stress analysis techniques used to evaluate the dynamic effects in piping systems. The discussion covers the dynamic effect produced by valve operations and pump trips.Valve OperationsWhen dynamic effects are expected in a piping syst em, excluding the pressu rizer safety/relief and shutdown cooling piping systems, due to valve operation, the st ress analysis is done using maximum forces created by valve closures by mean s of a static analysis with a dynamic loading factor of 2 applied for the c onservative dynamic loads. For such closed discharging piping systems, supports are installed to take the dynamic transi ent force from rapid valve closure and/or relief valve opening on each straight leg of piping and to cause th e piping to have its fundamental frequency in the axial direction above the mini mum acceptable natural frequency to make the method of static analysis valid.

The magnitude of the fo rces created by valve openings in cl osed piping system is estimated by determining the change in momentum in each section of straight piping with linear increased valve flow rate. For valve closures, a pressure wave is generated in the system which causes a dynamic response of the system. The maximum magni tude of the pressure wave is calculated from Ap = eV C, where e is fluid density, V is flow velocity change and C is velocity of sound. The stresses caused by these dynamic transient forces are appropriately combined with those caused by seismic, deadweight, and pressure. The total stress is limited to less than those allowed by the applicable codes.

The pressurizer and shutdown cool ing piping systems, which are subject to rapid relief valve openings, are analyzed on a time-his tory basis. The loading (forcing function) as a result of valve operation is calculated on a time-dependent basis and applied to a dynamic model of the system. The load is applied at specific locations in the system with respect to the time it takes the pressure wave to reach that location. It is this time-depe ndent application of the load which results in the excitation of the piping system.

The stress evaluation due to the loads developed by rapid relief opening is performed by using the rules for Class I piping according to Section III of the ASME BPVC, NB-3650, as modified by Code Case 1569. The value of Mi in equations 9 through 14 includes the reaction force moment as a result of relief valve opening.Pump Trip The stress analysis includes the dynamic effects of pump trips if estimated to be significant. However, coastdown time for a centrifugal pump is usually of sufficient duration that water hammer effects in the piping systems are normally negligible.

MPS2 UFSAR13.12-2Rev. 35 The following discusses the dynami c acceptability of the piping systems covered in Table 13.12-1.Main Steam System The analysis of the main steam system included the transient conditions of rapid turbine stop valve closure and main steam relief valve lifting. As a result of a turbine stop valve closure, a pressure wave is generated with in the steam line which causes a dynamic response of the system.

An instantaneous stop valve clos ure is assumed, and the magnitude of t@e pressure wave is calculated from p = e V C.The main steam relief valve system is designed so that blowdown force is transmitted directly to the structure and not through the piping by use of mechanical/str uctural devices. These relief valves are provided with discharg e stacks to direct the steam flow to atmosphere. The stacks are designed so that back pressure does not cause a valve reaction force.

The stresses caused by the dynamic transient forces when combined with those caused by seismic, dead weight and pressure are less than 1.2 S h , which is allowed by ANSI B31.7.

From past experience, flow induc ed steady state vibration in the main steam line has been shown to be insignificant by actual measurements with remote instrumentation. This was verified for Millstone 2 by the startup test program.

Main Feedwater An analysis of the feedwater system has been done to determine any potenti al for damage due to water hammer. The area of most concern is the pr essure waves caused by rapid changes in flow velocity. The feedwater control va lve closure time of 20 seconds or pump coas tdown time is much too slow to cause water hammer.

On the basis of the above discussion, water hammer effects in the feedwater system are negligible.Pressurizer Relief/Safety Valves and Shutdown Cooling SystemsThese systems are being analyzed by the force-time history approach with respect to relief valve opening. The piping will be sufficiently re strained to carry the imposed loading.Charging LineThe reciprocating type charging pumps will produce vibratory response in the charging system. To minimize these effects, each charging pump wi ll be provided with a pulsation dampener at the pump discharge connection to limit the pressure pulsations to less than 4 percent of the working pressure. These dampeners are expected to limit the dynamic effect s in the piping system to an acceptable level. The startup test pr ogram was used to verify the above.

MPS2 UFSAR13.12-3Rev. 35 Other SystemsThe dynamic effects experienced by the letdown, safety injection, containment penetration, boric acid, and reactor coolant sampling piping systems are expected to be insignificant. Therefore, the stress analyses for these system s did not include any transient conditions. Verification of the above assumption will be made by the test program.

Acceptance CriteriaSteady state vibration of piping systems, excl uding the pressurizer relief/safety and shutdown cooling piping systems, was measured in the field. The actual displacements were compared with allowable displacements.

Allowables are define d as those displacements which produce stresses whose amplitudes are less than one-half the endurance limits as defined in ASME Section III. A start-up test program wa s established to perform the above measurements.Since the force-time history appr oach was utilized for the pressurizer relief/safety valve and shutdown cooling piping systems, these systems wi ll be excluded from th e startup test program.

Conclusions The stress analysis performed for the piping system subjected to dynamic effects is believed adequate to insure the integr ity of seismic Category I piping systems which ar e in accordance with ASME Section III, Classes l and 2. A startup test program was established to verify that the analysis and predictions concerning dynamic effects in piping systems are correct.For the systems listed in Table 13.12-1, either the transient effect were proven to be minimal or a test program was conducted. A location for measur ement of deflection wa s selected for each system to be tested. The location selected was determined by reviewing the existing analyses and determining which portion of the system will respond to imposed transient conditions.

The instrumentation was located at the specific points defined in Item l above and was monitored during plant warm-up to indica te that actual pipe moveme nts are following anticipated movements. (This indicated that supports inte nded to deflect during nor mal heat-up are free.)

During imposed plant transients, visual observation of the specific li nes was made and the deflections observed and recorded.

The measured deflections were co mpared to the calculated deflections and determination made as to acceptability.

The criteria for acceptability will be as follows:a.Class I Systems: The allowable variati on of the resultant deflection shall be determined for each system.

MPS2 UFSAR13.12-4Rev. 35

• Note: Calculated thermal expansion st ress for operating condition investigatedb.Class 2 Systems:

In order to conservatively estimate these dynamic effects, valve opening times, pump coastdown times, etc., have been conservatively estimated.MeasuredCalculated

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3S M C 2 M i Do-------------

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-MeasuredCalculated---------------------------------

-S A SE---------

MPS2 UFSAR13.12-5Rev. 35TABLE 13.12-1 SEISMIC CATEGORY I-ASME SECTION III CLASSES 1 AND 2 PIPING SYSTEMS Main steam Main feedwaterCharging Letdown Steam generator blowdown

Shutdown cooling Safety Injection

Containment penetration piping Pressurizer relief / safety valve

Boric acid Reactor Coolant sampling

Pressurizer spray

Auxiliary Pressurizer spray Reactor coolant pump controlled bleedoff

Reactor coolant MPS2 UFSAR13.13-1Rev. 35 13.13 ACTIVE VALVES OPERATIONAL TESTING Active valves are those whose opera bility is relied upon to perform a safety function such as safe shutdown of the reactor or mitigati on of the consequences of a postul ated pipe break in the reactor coolant pressure boundary. These valves are loca ted within the engineered safety features systems, vital support systems, a nd containment isolati on system and are automatically actuated during a post-incident condition to perform their intended function.

Pneumatically actuated valves wit hout air accumulators are exclude d from the above definition of active valves since the compress ed air system is a nonessential sy stem and is not relied upon to function during post-incident conditions. Pneumati cally actuated valves, whether receiving an automatic signal or not, are assu med to be operated by spring action to their respective safe position. Pneumatic actuated valves which are not required to re main operational following a seismic disturbance are classified as passive components. A listing of all safety-related pneumatically actuated valves, in cluding those with air accumulator , is tabulated in the response to AEC Question 9.32 in Amendment 15. Pneumatically actuated valves provided with air accumulator are consider ed active valves even though their operation is require d during the long term post-incident condition. The air accumulator is provided to assure an adequate supply of compressed air for valve operation during the post-incident ca se assuming the normal compressed ai r system is operable. In addition, valves with air accumulator that are located in areas which are accessibl e during LOCI conditions are provided with handwheels for manual operation as backup.

The air accumulator package consists of tanks, t ubing and check valve which are connected to the normal compressed air supply arra ngement. The check valve preven ts loss of accumulator air following a postulated loss of the normal compressed air system. The package is completely separate from the va lve pneumatic operator except for the air tubing connection to the operator.

The accumulator package is designed as a vita l system with all components through the check valve analyzed for operation during and after a seismic event. The electric motor-operated valves which are required for post-incident operation for vital processes or for containment isolation are consider ed active valves. A tabulation of active process motor-operated valves is give n in the response to AEC Qu estion 4.4 in Amendment 15. The electric motor operators for these valves are all of the Limitorque SMB series and have a history of qualification testing to verify their reliability and operability. Extensive testing has been carried out by the valve opera tor manufacturer and by an independent institute.

The testing has been done over a number of years, and the most recent testing in the summer of 1972 bears out the operability confirmed initially. 1.MANUFACTURER'S TESTS A.Electric Motor Operator Qualification Testing Shock and Vibration Testing In August, 1970, a Limitorque SMB Seri es operator was mounted on a test stand having a threaded valve stem driven by the operator simulating MPS2 UFSAR13.13-2Rev. 35 opening and closing a valve. The operator was electrically connected so as to stop at the full close position by me ans of a torque switch and stop at the full open position by means of a geared limit switch. The operator had a 4-train geared limit switch installed and all contacts not being used for motor control were wired to electric i ndicating lights at a remote panel. The unit successfully completed a 5.3 g shock level at 32 Hz with no discrepancies noted. An exploratory s can of 5 Hz to 35 Hz was made and no critical resonant frequencies were noted on the operator. The unit was shocked and vibrated in each of three different axes a total of 2 minutes on, 1 minute off, 3 times per axis. The unit was operated electrically to both the full-open and full-close posi tion, and all torque switches and limit switches functioned properly. None of the auxiliary limit switches wired to indicating light ever flic kered or indicate d they were opening or flickering. All electrical and mechanical devices on the operator worked successfully.

B.Heat Testing In January 1969, a completely asse mbled and operational SMB series operator was placed in an oven where the temperature was maintained at approximately 325

°F for a duration of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The unit was electrically operated every thirty minutes for a period of approximately two minutes per cycle, and the geared limit switches were used to stop the actuator at the full-open and full-closed position of travel. Indicating light circuits were also wired to the geared limit switches. The test was successful in every resp ect. There were no malfunctions of the operator and upon inspection of the component parts used, there was no noticeable deterioration or wear.

C.Live Steam Testing In January 1969, a complete SMB series operator was set up for electrical operation, and live steam was piped into he conduit taps on the top of the limit switch compartment. One of th e bottom conduit taps was left open to drain off any condensate. The operato r was set up on a timer basis for operation over a period of approximate ly nine hours and operating every thirty minutes for two minut es per cycle. During this test, the live steam in the switch compartment seemed to have no effect whatev er on the function of the torque and limit switches in th eir control of the operator at the full-open and full closed position of travel. In addition, the limit switches were wired up to indicating lights which operated satisfactorily.

The test was successful and there was no noticeable effect on the function of any of the parts in the limit switch compar tment.

MPS2 UFSAR13.13-3Rev. 35 D.Life Cycle Testing In January 1969, the operator was mounted on a stand inside a test chamber and a 150 cycle (anticipated equivalent to 40 year life of valve) load test was made on the unit. This test cycle consisted of stroking a 2-3/8 inch diameter valve stem at a speed of 6 inches per minute for a total of approximately 12 inches in two minutes. The valve stem in the full closed position produced a thrust of 16,500 pounds on a rigid plate securely bolted to the test chamber. The unit was wired so that the closing direction and the open position geared limit switch stoppe d the unit in the full open position.

After the life cycle testing was comp leted, the unit was inspected and found to be in excellent condition. There was no noticeable wear on any of the

parts. E.Simulated Accident Environment Testing An electric motor operator was tested under conditions which simulated the temperature humidity and chemi cal environments that could be expected to exist in the containmen t following some postulated accident such as the rupture of a major reactor coolant pipe. The operator was placed in an Autoclav e type chamber and subjected to 90 psig saturated steam. At specified in tervals, the operator was cycled to assure proper operation. Forty minutes after the introduction of steam, a 1.5% boric acid solution was sprayed on the operator assembly. The operator continued to operate satisfactorily. Later , the steam pressure was periodically reduced to simulate pos t-accident conditions. The boric acid spray was allowed to continue for four hours. The steam pressure was eventually reduced to 15 psig. The test continued for 7 days.

During this time, the operation of the operator became erratic. The corrosive effects of the steam and boric acid spray caused electrical contact malfunctions which were bypassed by the use of an appropriate jumper.

The valve continued to cycle during the seven day period. A design change was made to the limit switch in order to correct the erratic operation, and it was tested under similar accident conditions and found to operate satisfactorily. This design change has been incorporated into all subsequent applicable models of this operator. 2.INDEPENDENT TESTING A.Franklin Institute Tests

MPS2 UFSAR13.13-4Rev. 35More recent tests on a Limitorque SMB series operator were conducted during the summer of 1972 by the Franklin Institute Research Laboratories.*

The following testing was conducted: 1.The previous Simulated Accident Environment Test (Item 1-E above) was reconducted with the Limitorque operators exposed to gamma radiation (200 megarads) and increased steam/chemical exposure time from 7 days to 12 days.

2.The previous Live Steam Testing (Item 1-C above) was reconducted in a steam environment as high as 340

°F during the first day of tests and increased exposure time from 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> to 30 days. 3.The previous shock and Vibration Test (Item 1-A above) was reconducted.

During all of these tests, as appr opriate, the operator was periodically cycled and was found to operate satisfactorily. *1.Qualification Test of Limitorque Valve Operator M otor Brake, and other Units in a Simulated Reactor Containment Post-Accident Environment, Final Report F-C3327, July 1972. 2.Qualification Test of Limitorque Valve Operators in a Simulated Reaction Containment Post-Accident Steam Environment, Final Report F-C3441, September 1972. 3.VALVE PURCHASE SPECIFICATION All safety-related valves, including pneumatically actuated valves with and without air accumulators, receive extensiv e preoperational testing prior to initial fuel loading and periodic surveillance testing after startup. These valves must comply with the purchase specification requirements for testing and seismic analysis. The purchase specifications for these valves require that they be hydrostatically tested, leak tested and cycl ed from the extremes of allowed movement of opened or closed.

The valve vendor is also requi red to submit calculations which show that when the valve assembly is subjected to a 3g inerti al load in any direction that stresses incurred are within the code allowable stre sses. It is also verified that the first natural frequency is above 20 cps for all valves.

MPS2 UFSAR13.13-5Rev. 354.PREOPERATIONAL TESTINGTesting procedures for valves that require operation to meet engineered safety feature requirements were quite extens ive during the preoperational testing program. These tests demonstrated prope r installation, strength and functional performance of valves. Subsequent to satisfactory preoperational testing, surveillance testing requirements have be en established to assure continued satisfactory operation of thes e valves. A planned surve illance program of valve motor operator testing through the whole operating cycle will be undertaken to prove the operability and setting of the torque and limit switches.

A.System Electrical Tests The purpose of these tests was to verify electrical characte ristics of valve operators in performing their func tion. Preliminary checkout of the operator valve assembly requires that th e valve be free to move and that if the motor-operated valve travels in the wrong direction from its midtravel position, its breaker must be tripped immediately, as there would be no torque limit protection. The valve can be operated manually with a handwheel to ascertain it s freedom of movement.

The phase rotation of the operator was checked. During valve operation, verification was obtained that the va lve travel and motor are stopped by opening the torque limit switch. Similarly, the opening of the valve is terminated by the opening of the limit switch.

In checking the valve fo r engineered safety feat ure actuation, the valve was placed in the position opposite to its e ngineered safety feature position, and then the appropriate signa l is simulated. The valve moves to its engineered safety feature position.

Acceptance criteria for these electrical tests are: 1.Valves must open, close, and tr avel in the proper direction in response to control and engineer ed safety features signals. 2.The valve open and clos ed indicating lights must indicate correctly. 3.Valve motor resistance-to-ground reading must be within specification.4.The specified valve travel time is within specification requirements.

B.System Engineered Safety Features Tests

MPS2 UFSAR13.13-6Rev. 35The performance of these tests wa s to demonstrate actual valve performance for its intended Engineered safety feature use. Initially, all valves were placed in their nonengineer ed safety feature po sition prior to simulating an engineered safety feature signal. Upon initiation of an engineered safety feature signal, the tests for the subject valve demonstrated that the valve trav els to its post-incident position.

C.System Functional Testing The purpose of this testing was to ve rify that the valves perform as intended for normal operation. Cycling the valves under conditions of specified differential pressure and/or flow that may be encountered during plant operation verified that the valve motor did not exceed maximum operating current and cycle time.

D.Integrated Actuation Test The purpose of this test, for which these valves are used to perform, was to demonstrate the full operational sequence that would bring the emergency core cooling systems and the contai nment cooling systems into action, including the transfer to alternate power sources.

General acceptance criteria for this test are: 1.Upon actuation of the appropriate safety feature, the systems operate as described in the FSAR. 2.Upon loss of normal station power, the safety feature systems continue to perform their designed functions without interruption. 5.THE TECHNICAL SPECIFICA TIONSThe Technical Specification testing re quires that these valves be operated periodically to assure their continued availability and reliability. During the life of the facility, these valves will require maintenance, inspection, repair, and possibly replacement or modification. In summary, the entire scope of te sting verified the valves operabi lity from conditions of extreme duress to normal operation, and the results of the earliest environmental, vibratory, and load testing have been repeatedly verified in later testing by independent research.

MPS2 UFSAR13.A-1Rev. 35 13.A PREOPERATIONAL TEST DESCRIPTIONS 13.A.1 SYSTEM: 125 VOLT DC SYSTEM 13.A.1.1 ObjectiveTo demonstrate that the 125V DC System is capable of pr oviding power during normal and abnormal conditions.

13.A.1.2 Prerequisitesa.480V, 3, 60 cycle supply is available. b.Battery room ventil ation is operational. c.Batteries and DC distribution system, in cluding protective devices, are checked for operation and are in service. d.Ammeters and voltmeters are calibrated and are in place. e.Battery chargers are inst alled and are operational.

13.A.1.3 Methoda.Energize the battery chargers. b.Adjust alarms and interlocks.

c.Discharge the batteries at a controlled rate to determine ampere-hour capacity. d.Adjust chargers to supply DC load and charge batteries.

13.A.1.4 Acceptance Criteriaa.The DC System is capable of supplyi ng the loads connected on a loss of AC power. b.The chargers are capable of recharging the batteries and carrying the normal DC loads. c.Alarms and interlocks function as designed.

MPS2 UFSAR13.A-2Rev. 35 13.A.2 SYSTEM: RESERVE STATION SERVICE TRANSFORMER 13.A.2.1 ObjectiveTo verify that the Reserve Station Service Transformer 15G-22S(U

3) can be ener gized from the 345 kV switchyard, also that all interlocks and protective devices function properly.

13.A.2.2 Prerequisitesa.Feeder breakers from reserve station se rvice transformer racked out and tagged.

b.All meters, relays and protectiv e devices calibrated and tested. c.125V DC and 480V AC available. d.All construction work complete on transformer and switchgear.

13.A.2.3 Methoda.Install phase rotation indicators and voltmeters on 6.9-kV and 4,160V secondary winding power transformers. b.Energize RSS transformer 15G-22S(U3).

c.Record voltage and ve rify phase relationship.

13.A.2.4 Acceptance Criteriaa.RSS transformer is capable of being energized from the 345-kV switchyard and proper phase relationship is exhibited. b.The RSS transformer responds correctly to a loss of station power and a reactor safeguards signal.

13.A.3 SYSTEM: PRIMARY WATER TREATMENT SYSTEM 13.A.3.1 ObjectiveTo demonstrate that the water treatment system is capable of meeting the requi rement of high purity water for makeup to the pr imary loop and for various other services throughout the plant, the greatest demand occu rring during refueling.

13.A.3.2 Prerequisites a.480V, 3, 60 cycle supply is available.

MPS2 UFSAR13.A-3Rev. 35b.120V, 60 cycle AC is available. c.125V DC is available. d.Domestic water system is functional. e.Instrument and station ai r systems are functional. f.The water treatment system shall be operable.

g.Laboratory equipment for making various chemical analysis are available.

13.A.3.3 Method a.Line up the system for operation. b.Adjust alarms and interlocks. c.Domestic water booster pumps are started to feed the system with water of known quality. 13.A.3.4 Acceptance Criteria a.Pump characteristics curves are in accordance with manufacturer's specification. b.Alarms and interlocks operate as designed. c.The quality of treated wate r meets the design requirement. d.The system is capable of supplying maximum operating requirement.

13.A.4 SYSTEM: 4,160 VOLT ELECTRICAL SYSTEM 13.A.4.1 ObjectiveTo verify that 4160V buses A1 through A5 can be energized from thei r respective normal and alternate source and to verify that all interl ocks and protective devices function properly.

13.A.4.2 Prerequisitesa.All feeder breakers to the 4160V buses are racked out and tagged. b.Meters, relays, and protective devices calibrated and tested. c.125V DC available.

MPS2 UFSAR13.A-4Rev. 35 13.A.4.3 Methoda.Install phase rotation indi cators and voltmeters on 4160V bus power transformers. b.Rack in and close 4160V breakers to energize associated 4160V buses. c.Record voltage and ve rify phase relationship.

13.A.4.4 Acceptance Criteriaa.The 4160V buses are capable to being energized from their normal and alternate source and that proper phase relationship is exhibited.

b.The 4160V System responds correctly to a loss of st ation power and a reactor safeguards signal.

13.A.5 SYSTEM: 480-VOLT ELECTR ICAL LOAD CENTERS 13.A.5.1 ObjectiveTo verify that the 480V safeguard and non safeguard buses can be energized from their normal and alternate sources and also that all interl ocks and protective devices function properly.

13.A.5.2 Prerequisitesa.All breakers on 480V load center buses B1 through B6 racked out and tagged. b.Meters, relays, and protective devices calibrated and tested. c.125V DC and 4.16 kV buses A1 through A4 energized.

13.A.5.3 Methoda.Install phase rotation indicators and voltmeters on Bus PT's.

b.Close 4.16 kV breakers to energize load center transformers and buses. c.Measure voltage and verify phase relationship.

13.A.5.4 Acceptance Criteriaa.480V safeguard and nonsafeguard buses are capable of being energized from their normal and alternate sources and that proper phase relationship is exhibited. b.The 480V load centers respond correctly to a loss of station power and a reactor safeguards signal.

MPS2 UFSAR13.A-5Rev. 35 13.A.6 SYSTEM: SERVICE WATER SYSTEM 13.A.6.1 ObjectivesTo demonstrate the capability of the service water system to resp ond to a SIAS signal; also to provide adequate cooling water to th e turbine building and reactor building.

13.A.6.2 Prerequisitesa.Instrument air system operational. b.Required electrical systems operational.

13.A.6.3 Methoda.With system in normal operation, insert a safety injection actuation signal.

13.A.6.4 Acceptance Criteriaa.Pump characteristic curves are in accordance to manufacturer specifications.

b.System must respond as designed to SIAS signal. c.Flow capability of the system is in accordance with design.

13.A.7 SYSTEM: CLEAN LIQUID RADWASTE SYSTEM 13.A.7.1 ObjectiveDemonstrate the capability of the clean liquid ra dwaste system to operate as designed during normal operation or high radiation conditions.

13.A.7.2 Prerequisitesa.Clean liquid radwaste system operable. b.Instrument air system operable. c.Required electrical systems operational. d.Safety injection actuation system operational.

13.A.7.3 Methoda.Line up system for normal operation.

MPS2 UFSAR13.A-6Rev. 35b.Simulate low- and/or high-level si gnal to appropriate valves and pumps. c.Simulate low- and/or high-temper ature signal to appropriate valves. d.Simulate high radiation si gnal to appropriate valves. e.Initiate containment is olation actuation signal.

13.A.7.4 Acceptance Criteriaa.Upon appropriate level signal, pumps and valves must respond as designed.

b.Upon appropriate temperature signal, appropriate valves must respond as designed. c.On high radiation signal, radiat ion isolation valves will close. d.On initiation of a containment isolati on actuation signal, system will respond as designed.

13.A.8 SYSTEM: AERATED LIQUID RADWASTE SYSTEM 13.A.8.1 ObjectiveDemonstrate the capability of the aerated liquid radwaste system to operate as designed during normal or high radiation conditions.

13.A.8.2 Prerequisitesa.Aerated liquid radwaste system operable. b.Instrument air system operable. c.Required electrical systems operable.

13.A.8.3 Methoda.Line up system for normal operation.

b.Simulate low level signal to appropriate pumps. c.Simulate a high radiation signal to appropriate valves.

MPS2 UFSAR13.A-7Rev. 35 13.A.8.4 Acceptance Criteriaa.Pump characteristic curves must be in accordance with manufacturer's specifications. b.Pumps must respond as designed to low level signal. c.Appropriate valves must respond as designed to a high-radiation signal.

13.A.9 SYSTEM: 480-VOLT MOTOR CONTROL CENTERS 13.A.9.1 ObjectiveTo verify that the 480V safeguard and non-safeguard motor control centers can be energized from their normal source. Also that all interlocks and protective devices function properly.

13.A.9.2 Prerequisitesa.All breakers on motor control centers to be energized off and tagged.

b.Meters, relays and protective devices calibrated and tested. c.125V DC available. d.480V buses B1 through B6 energized.

13.A.9.3 Methoda.Install phase rotation indicator in MCC starter.

b.Close associated MCC supply breake r and verify phase relationship.

13.A.9.4 Acceptance Criteriaa.Safeguard and non-safeguard motor control centers are capable of being energized from their normal source and that pr oper phase relations hip is exhibited.

13.A.10 SYSTEM: TURBINE BUILDING CL OSED COOLING WATER SYSTEM 13.A.10.1 ObjectiveTo demonstrate the capability of turbine building closed cooling water system to provide adequate cooling water to the various equipment in the turbine building.

MPS2 UFSAR13.A-8Rev. 35 13.A.10.2 Prerequisitesa.480V, 120V AC and 125V DC elec trical systems are available. b.Service water system is functional. c.Instrument air system is functional.

d.Chemical addition tank is available.

e.Turbine building closed cooling water system is operable.

13.A.10.3 Methoda.Line up the system for operation.

b.Adjust alarms and interlocks. c.Surge tank level should be carefully watche d to note loss of water which would be indicative of leakage. d.Establish required cooling wate r flow to various equipment.

13.A.10.4 Acceptance Criteriaa.Pump characteristic curves are in accordance with manufacturer's specifications. b.Alarms and interlocks function as designed.

c.Surge tank level remains steady. d.Flow capability of the syst em meets the design requirement. 13.A.11 SYSTEM: FIRE PROTECTION SYSTEM13.A.11.1 ObjectiveTo demonstrate that the fire protection system is capable of provi ding a firm supply of water for firefighting under all conditions, incl uding loss of electrical feed. 13.A.11.2 Prerequisitesa.480V AC and 125V DC electri cal supplies are available. b.Adequate water is available in fire water storage tank.

MPS2 UFSAR13.A-9Rev. 35c.Fire protection system is operable. 13.A.11.3 Test Methoda.Line up the system for operation. b.Adjust alarms and interlocks.

c.Check sprinkler systems. 13.A.11.4 Acceptance Criteriaa.Pump characteristic curve is in accordance with manufacturer's specification.

b.Alarms and interlocks function as designed. c.Fire water is available from Unit 3 loop in case of failure of Unit 2 electric driven fire pump. d.The system is capable of providing required flow to the sprinkler systems.

13.A.12 SYSTEM: RECOVERED BORIC ACID SYSTEMThe testing requirements for this system are covered under the Clean Liquid Radwaste System.

13.A.13 SYSTEM: INSTRUMENT AIR SYSTEM 13.A.13.1 ObjectivesTo demonstrate the capability of the instrument air system to pr ovide adequate low-moisture air for the plant.

13.A.13.2 Prerequisitesa.Turbine building closed cooling water system operational. b.Require electrical systems available.

13.A.13.3 Methoda.Line up system for normal operation. b.Simulate a low pressure signal to the normally operating instrument air compressor. c.Simulate a low-low-pressure signal to the standby instrument air compressors.

MPS2 UFSAR13.A-10Rev. 35d.Simulate a low-pressure signal to instrument air cross-connect valve.

13.A.13.4 Acceptance Criteriaa.All three instrument air compressors mu st respond as designed to a low pressure signal. b.The instrument air cross-connect valve must respond to a low-pressure signal as designed. c.Instrument air flow and quality must be in accordance to system design.

13.A.14 SYSTEM: PRIMARY WATER STORAGE SYSTEM 13.A.14.1 Objective Demonstrate that the primary wate r storage system is capable of providing an adequate supply of deaerated water.

13.A.14.2 Prereq uisitesa.Primary water storage tank operable.

b.Domestic water system operational.

c.Water treatment system operational. d.Instrument air operational. e.Required electrical systems functional.

13.A.14.3 Methoda.Line up system and pl ace in normal operation.

b.Simulate low- and/or high-pressure si gnal to the primary water transfer pumps. c.Simulate a low- and/or hi gh-level signal to the appropriate level control valves. d.Simulate a low temperature signal to the primary water circulation pumps.

13.A.14.4 Acceptance Criteriaa.All pumps and level control valves must operate in accordanc e with design when receiving the appropriate simulated signal.

MPS2 UFSAR13.A-11Rev. 35 13.A.15 SYSTEM: 120-VOLT INSTRUMENT AC SYSTEM 13.A.15.1 ObjectiveTo demonstrate that the 120V Instrument AC System is capable of supplying non-essential instrument and control load requiring voltage regulation.

13.A.15.2 Prerequisitesa.480V AC supply is available.

b.120V Instrument AC System is operable.

13.A.15.3 Methoda.Line up the system for operation.

b.Adjust regulator transforme rs to supply non-essential in strument and control load.

13.A.15.4 Acceptance Criteriaa.Voltage regulation meet s the design requirement. b.The system is capable of carrying non-essential instrument and control requiring voltage regulation.

13.A.16 SYSTEM: 120-VOLT VITAL AC SYSTEM 13.A.16.1 ObjectiveTo demonstrate that the system is capable of supplying power to essential instrumentation and control under all operating conditions.

13.A.16.2 Prerequisitesa.125V DC power is available. b.120V instrument AC is available. c.Inverters are installed and operational. d.120V vital AC system is operable.

13.A.16.3 Methoda.Line up the system for operation.

MPS2 UFSAR13.A-12Rev. 35b.Adjust inverters to supply vital AC load. c.Adjust alarms and interlocks. d.Test the transfer capability of the static switch.

13.A.16.4 Acceptance Criteriaa.Alarms and interlocks function properly. b.Inverters are capable of carrying the vital AC loads.

c.The static switch will transfer to the backup electrical source upon manual initiation.

13.A.17 SYSTEM: GASEOUS RADWASTE SYSTEM 13.A.17.1 Objectives Determine the capability of the gaseous radwas te system to respond to CIAS and to a high-discharge radiation level.

13.A.17.2 Prerequisitesa.Instrument air system operational.

b.Required electrical systems operational.

c.Reactor building closed cooli ng water system operational.

13.A.17.3 Methoda.Line up system and pl ace in normal operation.

b.Simulate a containment isolation actuation signal. c.Simulate a high discharge radiation signal. d.Through use of compressor controller, simu late a high- and/or low-pressure signal to each waste gas compressor. 13.A.17.4 Acceptance Criteriaa.Appropriate valves must respond to containment isolation actu ation signal (CIAS) according to design.

MPS2 UFSAR13.A-13Rev. 35b.Appropriate valves must respond to a high discharge ra diation signal in accordance with design.

c.Each waste gas compressor must operate in accordance with design. d.Systems must meet all design criteria.

13.A.18 SYSTEM: CONDENSATE STORAGE SYSTEM 13.A.18.1 ObjectiveTo demonstrate the capability of the condensate storage system to transf er water in accordance with design.

13.A.18.2 Prerequisitesa.Condensate storage tank operational. b.Instrument air and appropriate electrical systems operationa

l. 13.A.18.3 Methoda.Line up system for normal operation.

b.Simulate low-temperature signal to actuate recirculation pump. c.Simulate low level to actuate proper level control valves.

13.A.18.4 Acceptance Criteriaa.Pump characteristic curves are in accord ance with manufacturer specifications. b.Recirculation pump and level control va lves respond to level and temperature signals as designed.

13.A.19 SYSTEM: AUXILIARY AND EMERGENCY FEEDWATER SYSTEM 13.A.19.1 ObjectiveTo demonstrate that the auxiliary and emergency feedwater sy stem is capable of providing feedwater for the removal of decay heat of the primary system. Also to supply feedwater to the steam generators when the feed pumps are inoperative.

13.A.19.2 Prerequisitesa.4.16 kV, 480V AC and 125V DC pow er sources are available.

MPS2 UFSAR13.A-14Rev. 35b.(Deleted.) c.Condensate storage system is functional. d.Steam generator syst em is functional. e.Instrument air system is functional. f.Auxiliary and emergency feedwater system is operable. 13.A.19.3 Methoda.Line up the system for operation.

b.Adjust interlocks.

c.(Deleted.)

13.A.19.4 Acceptance Criteriaa.Pump characteristic curves are in accordance with manufacturer's specification. b.Control valves operate smoothly and can be actuated from the control room and emergency shutdown cooling panel. c.All interlocks function properly. d.(Deleted.)

e.Feedwater flow capability of the system meets the design requirements.

13.A.20 SYSTEM: STEAM GENERATOR FEEDWATER SYSTEM 13.A.20.1 ObjectiveTo prepare the steam generator feedwater system for operation. The feedwater pump turbines will be tested uncoupled duri ng hot functional tests. The feedwater system will be f unctionally tested during power ascension tests.

13.A.20.2 Prerequisitesa.480V, 120 VAC and 125V DC power sources are available. b.Feedwater turbine lube oil system is operational. c.Instrument air system is operational.

MPS2 UFSAR13.A-15Rev. 35 13.A.20.3 Methoda.Using simulated signals, verify alarms , interlocks and operation of turbine controls, lube oil system and valves.

13.A.20.4 Acceptance Criteriaa.Turbine lube oil system is in accordance with manufacturer's specifications. b.Turbine controls are in accordance with manufacturer's specifications. c.System valves with postioners ope rate in accordanc e with design.

13.A.21 SYSTEM: CONDENSATE SYSTEM 13.A.21.1 ObjectiveTo demonstrate that the condens ate system is capable of tran sferring adequate quantity of condensate water from condensate hotwel l to steam generator feedwater system.

13.A.21.2 Prerequisitesa.6.9 kV, 120V AC and 125V DC power sources are available. b.(Deleted.) c.Instrument air system is functional.

d.(Deleted.) e.Turbine building closed c ooling water is functional. f.Condensate system is operable.

13.A.21.3 Methoda.Line up the system for operation. b.Adjust alarms and interlocks.

13.A.21.4 Acceptance Criteriaa.Pump characteristic curves are in accordance with manufacturer's specification. b.Alarms and interlocks function properly.

MPS2 UFSAR13.A-16Rev. 35c.Condensate water flow capability of the system meets the design requirement.

13.A.22 SYSTEM: FEEDWATER HEATER DRAINS AND VENTS 13.A.22.1 ObjectiveTo demonstrate that the heater dr ains and vents system will functi on in accordance with the design intentions and to check the functions of pum ps, valves, instrumentation and interlocks.

13.A.22.2 Prerequisitesa.4.16 kV, 120 VAC, 125 VDC power sources are available. b.Compressed air system available. c.Floor drain system functional. d.(Deleted.)

e.(Deleted.) f.(Deleted.) g.(Deleted.)

13.A.22.3 Methoda.Using simulated signals, verify alarms, interlocks and operation of feedwater heater level control valves.

13.A.22.4 Acceptance Criteriaa.Alarms and interlocks must function properly. b.(Deleted.)

c.Control valves operate smoot hly at designed set points. d.Pump performance curves must meet manufacturer's specifications.

13.A.23 SYSTEM: MAIN STEAM 13.A.23.1 Objective Demonstrate the capability of the main steam system components to operate in accordance with design intentions and to check the functions of valves, instrumentation and interlocks.

MPS2 UFSAR13.A-17Rev. 35 13.A.23.2 Prerequisitesa.480 VAC, 120 VAC, 125 VDC power sources are available. b.Instrument air system functional. c.(Deleted.)

d.Main steam system operable.

e.Engineered Safety Features Actuation Systems functional. f.Electro-hydraulic contro l system functional. g.Steam dump/bypass control system functional.

13.A.23.3 Methoda.(Deleted.)

b.Simulate CIAS and MSI signals to appropriate equipment.

c.Initiate a steam dump signal. d.Simulate a low steam generator pressure signal. e.Initiate a high-radiation signal.

13.A.23.4 Acceptance Criteriaa.On initiation of a Containment Isolation Actuation signal appropriate valves must close. b.On a high-radiation signal appr opriate valves must close. c.On initiation of a Main Steam Isolati on Signal appropriate valve must close.

13.A.24 SYSTEM: SAMPLING SYSTEM 13.A.24.1 Objectives Demonstrate the capability of the sampling syst em to operate under nor mal conditions and to respond to a high radiation signal or a c ontainment isolation actuation signal.

MPS2 UFSAR13.A-18Rev. 35 13.A.24.2 Prerequisitesa.Sampling system operable. b.Required electrical systems functional. c.Instrument air system functional.

d.Containment isolation actuation system functional.

13.A.24.3 Methoda.Line up system for normal operation.

b.Initiate a containment isolat ion actuation signal (CIAS). c.Simulate a high-radiation signal.

13.A.24.4 Acceptance Criteriaa.On initiation of a containment isolati on actuation signal, the appropriate valves must close. b.On initiation of a high-radiation signal, the appropriate valves must close. c.System must meet design criteria.

13.A.25 SYSTEM: SPENT FUEL COOLING AND PURIFICATION 13.A.25.1 ObjectiveTo demonstrate that the spent fu el pool and refueling pool cooling and cleanup system flow paths are as designed and to verify the capability of supplying makeup and c ooling water from the emergency cooling and makeup systems.

13.A.25.2 Prereq uisitesa.480V, 120V AC and 125V DC elec trical systems are available. b.Service water system is functional.

c.Water treatment system is functional.

d.Reactor building closed cooli ng water system is functional. e.Instrument air system is functional.

MPS2 UFSAR13.A-19Rev. 35f.Spent fuel pool and refueling pool c ooling and cleanup system is operable.

13.A.25.3 Methoda.Line up the system for operation. b.Adjust alarms, interlocks and recorders.

13.A.25.4 Acceptance Criteriaa.Pump characteristic curves are in accordance with manufacturer's specifications. b.Alarms and interlocks function properly.

c.Ensure cooling, skimming and purification flow paths are as designed.

d.Ensure emergency cooling and makeup flow paths are as designed. These flow paths consist of the following:

1.Makeup from refueli ng water storage tank. 2.Makeup from condensate storage tank.

3.Emergency cooling by way of the low-pressure safety in jection pumps and shutdown heat exchangers.

13.A.26 SYSTEM: REACTOR BUILDING CLOSED COOLING WATER SYSTEM 13.A.26.1 ObjectiveTo demonstrate that the reactor building closed cooling water system is capable of providing adequate cooling water to systems and com ponents containing radio active or potentially radioactive fluids during react or operation and after shutdown.

13.A.26.2 Prerequisitesa.4.16 kV, 480V AC and 125V DC pow er supplies are available. b.Water treatment system is functional.

c.Instrument air system is functional.

d.Chemical addition tank is available. e.Reactor building closed cooli ng water system is operable.

MPS2 UFSAR13.A-20Rev. 35 13.A.26.3 Methoda.Line up the system for normal operation. b.Adjust alarms, interlocks and recorders. c.Operate the system on all possible modes of operation. d.Simulate safety injection actua tion and sump recirculation signals. e.Surge tank level should be carefully watched.

13.A.26.4 Acceptance Criteriaa.Pump characteristic curves are in accordance with manufacturer's specification. b.Alarms and interlocks function properly. c.The system responds to SIAS and SRAS signals. d.Flow capability of the system is according to design.

e.Surge tank level remains steady duri ng any particular mode of operation.

13.A.27 FUEL HANDLING SYSTEM PREOPERATIONAL TEST - DESCRIPTION 13.A.27.1 PurposeTo conduct a complete checkout of the fuel handl ing equipment including ope ration of the system over its full range of capability.

13.A.27.2 General Prerequisites a.Refueling equipment installation and in stallation checks have been completed. b.The reactor vessel internals with the exception of the fuel and the upper guide structure are installed in the reactor. c.The reactor vessel head is removed and th e refueling cavity is capable of being f illed. d.Refueling equipment has been checked to insure that all components are captured to prevent inadvertent introduction of any part of the equipment to the reactor vessel. e.The refueling machine alignment has been completed.

MPS2 UFSAR13.A-21Rev. 35 13.A.27.3 Test Methoda.Operate the refueling machine using ma nual drive and normal power drive while checking all interlocks and controls on the bridge, trolley, and hoist. b.Operate the transfer system in ma nual drive and normal power drive while checking all interlocks and controls. c.Use the refueling equipment to handle a dummy fuel bundle or e quivalent from the spent fuel storage area into the reactor and ve rify selected posit ions and orientation of the dummy when installed in the core support barrel.

13.A.27.4 Acceptance CriteriaThe fuel handling equipment performs in accordance with the Fuel Handling Technical Manual.

13.A.28 SAFETY INJECTION SYSTEM PREOPERATIONAL TEST - DESCRIPTION 13.A.28.1 PurposeTo demonstrate the proper functi oning of SIS components prior to performing the integrated Pre-Core Hot Functional Test.

13.A.28.2 General Prerequisitesa.Construction, flushing and hydrostatic te sting of the SIS has been completed. b.The SIS has been released for operation.

c.Installation and calibration checks of SI S instrumentation have been completed. d.Cycling of manual valves has been performed to demonstrate freedom of movement and proper indi cation where appropriate. e.The SIS has been lined up for normal operation in accordance with the SIS Piping and Instrumenta tion Diagram. f.The RCS and the reactor cavity are ready to receive water. g.Initial run-in and operation of SIS equi pment has been performed where possible. h.The refueling water storage tank contains at least 450,000 gallons of Grade A water. i.The plant computer and those input sections associated with the SIS are operational.

MPS2 UFSAR13.A-22Rev. 35 13.A.28.3 Test Methoda.Operate all actuator operated valves in the SIS from the appropriate control locations and verify proper operations , indications, and fail positions. b.Operate low- and high-pressure safety injection pumps unde r both recirculation flow and full-flow conditions. c.Fill, pressurize and discharge the safety injection tanks. d.Operate the shutdown cooling system. e.Verify satisfactory operation of any alarm and interlock circuitry not verified during the previous operations.

13.A.28.4 Acceptance CriteriaThe SIS system components operate in accordance with the FSAR description, the SIS system description, and the appropriate vendor manual.

13.A.29 SYSTEM: DIESEL FUEL OIL TRANSFER SYSTEM 13.A.29.1 ObjectiveTo demonstrate that the diesel fu el oil system is capable of transferring ad e quate quantity of fuel oil from underground diesel oil storag e tank to diesel oil day-supply tank.

13.A.29.2 Prerequisitesa.480V AC and 125V DC electrical systems are available.

b.Fire protection water system is functional.

13.A.29.3 Methoda.Line up the system for operation.

b.Adjust alarms and interlocks.

13.A.29.4 Acceptance Criteriaa.Alarms and interlocks function properly.

b.Fuel transfer capability of th e system is according to design.

MPS2 UFSAR13.A-23Rev. 35 13.A.30 SYSTEM: DIESEL GENERATORS 13.A.30.1 ObjectiveTo demonstrate the capability of the Emergency Diesel Generators to start, accept load, and perform according to design. This will include a test of the e ngine controls as well as the generator controls.

13.A.30.2 Prerequisitesa.480V, 120 VAC and 125 VDC power available. b.Ventilation in Diesel Room operational. c.Mechanical checks of engine completed.

d.Engine auxiliaries and support systems operational. e.Generator and electrical tests of regulator and exciter completed. f.Relays calibrated and all normal bus protection checked for operation and in service. 13.A.30.3 Methoda.Engine controls are operated to verify capability to control engine in all modes of operation. b.Generator controls are operated to veri fy capability of re sponding to under voltage and engineering safeguard system signals. c.Circuit breakers and protective relayi ng respond to distribution system signals.

13.A.30.4 Acceptance Criteriaa.Exciter and Field Control1.Regulator functions to regulate and maintain voltage in all modes of operation. 2.Generator local and remote cont rols function according to design. 3.Engine and support systems function according to design.

MPS2 UFSAR13.A-24Rev. 354.Emergency diesel generators respond to engineering safeguard signal, bus undervoltage signal, and maintains safeguard buses on loss of offsite power. 13.A.31 SYSTEM: CONTAINMENT SPRAY SYSTEM 13.A.31.1 Objective Demonstrate that the containment spray system will respond to a containment spray actuation signal (CSAS) as designed. Dem onstrate spray nozzles are open.

13.A.31.2 Prerequisitesa.Refueling water storage tank operable. b.Required electrical systems operable.

13.A.31.3 Methoda.Line up system to recirculate to the refueling water storage tank. b.Initiate a simulated contai nment spray actuation signal. c.Force air or smoke through each spray header.

13.A.31.4 Acceptance Criteria a.Pump characteristic curves are in accordance with manufacturer's specifications. b.System must respond as de signed to simulated containm ent spray actuation signal. c.Spray nozzle flow paths are open.

13.A.32 SYSTEM: SHUTDOWN COOLING SYSTEM 13.A.32.1 Test ObjectivesTo demonstrate that the shutdown cooling system and components have the capacity to maintain the design flow.

13.A.32.2 Prereq uisitesa.4.16-kV, 480V AC, 125V DC pow er supplies available. b.Instrument air system functional.

MPS2 UFSAR13.A-25Rev. 35c.RBCCW system operational. d.RX coolant system operational.

13.A.32.3 Methoda.Line up the system for normal operation.

b.Adjust alarms, interlocks and recorders.

c.Measure flow thro ugh heat exchangers. d.Check operation of auto flow controller.

13.A.32.4 Acceptance Criteriaa.Pump/characteristic curves are in accordance with manufacturer's specification.

b.Alarms and interlocks function properly. c.Flow of the system according to design.

13.A.33 SYSTEM: ENGINEERED SAFEGUARDS ACTUATION SYSTEM 13.A.33.1 Objectives Demonstrate that the engineered safeguards actuating system will , when initiated, function as designed to protect against the accidental re lease of radioactivity to the atmosphere.

13.A.33.2 Prerequisitesa.Required electrical systems operational. b.All systems with engineered safeguard actuation signals as control must be operable.

13.A.33.3 Methoda.Place all safety-related systems in nor mal (depending on plant conditions at the time the test is conduc ted) operating mode. b.Initiate signal from engineered safeguards actuating system.

MPS2 UFSAR13.A-26Rev. 35 13.A.33.4 Acceptance Criteriaa.Upon initiation of an engineered safe guards actuation signal, the following response is required: 1.All system components (pump, fan, et c.) must respond to the signal as designed. 2.All valves must respond to the signal as designed.

13.A.34 REACTOR COOLANT SYSTEM PREOPERATIONAL TEST - DE SCRIPTION 13.A.34.1 Test ObjectiveTo demonstrate that the RC S components are operating prope rly prior to performing the integrated Pre-Core Hot Functional Test.

13.A.34.2 General Prerequisitesa.The RCS construction, flushi ng and cleaning is completed. b.The RCS has been released for operations.

c.The reactor internals with the exception of the fuel and the upper guide structure are installed. d.The reactor vessel head is removed and the refueling cavity is ready to be filled. e.Preoperational tests on all necessary auxiliary syst ems have been completed. f.Installation and calibration checks of RC S instrumentation have been completed.

g.Pressurizer safety valves have been set in accordance with Technical Specifications. h.Cycling of manual operated valves has b een performed to dem onstrate freedom of movement and proper indi cation where applicable. i.RCS valves are lined up for normal opera tion in accordance with the RCS Piping and Instrumentation Diagram.

j.Pressurizer heater breakers and reactor coolant pump breakers are in the Test position.

k.Initial run-in and operation of RCS auxiliary equipment has been performed where possible.

MPS2 UFSAR13.A-27Rev. 35l.The plant computer and the input sectio n concerned with the RCS are operational.

13.A.34.3 Test Methoda.Operate all actuator operated valves in th e RCS from applicable control locations and check the fail posit ions of these valves. b.Operate the reactor coolan t pump auxiliary systems to verify proper operation and to demons trate that the associated proce ss instrumentation interlocks and controls are operating. c.Operate the quench tank to demonstrat e operation of level, pressure, and temperature instrumentation. d.Test process instrumentation to verify setpoints and indications. e.Operate pressurizer pressure and leve l control systems to demonstrate proper operation.

13.A.34.4 Acceptance CriteriaAll RCS valves, instrumentation, and auxiliary systems perform in accordance with the FSAR description, the RCS system descript ion, and appropriate vendor manuals.

13.A.35 REACTOR REGULATING SYSTEM PREOPERATIONAL TEST - DESCRIPTION 13.A.35.1 Purpose To insure that the Reactor Regulating System has been properly installed and functions as designed prior to act ual reactor operation.

13.A.35.2 General Prerequisitesa.The Reactor Regulating System has been installed and has been thoroughly inspected for damaged or loose components and other discrepancies. b.All associated interconnecting wiring ha s been completed and has been checked for continuity, shorts, grounds, insulation resistance, etc. c.All process instrumentation channels providing inputs to the Reactor Regulating System have been checked and calibrated.

d.The CEDS and power range control channe ls have been inst alled and calibrated. e.The results of all factory testing on the Reactor Regulating Syst em are available.

MPS2 UFSAR13.A-28Rev. 35 13.A.35.3 Test Methoda.Energize equipment. b.Perform a static test of the Reactor Regulating System. c.Perform the dynamic test of the Reactor Regulating System.

13.A.35.4 Acceptance CriteriaThe Reactor Regulating System performs in accordance with the FSAR description, the Reactor Regulating System description, a nd the appropriate vendor manuals.

13.A.36 REACTOR PROTECTIVE SYSTEM PREOPERATIONAL TEST - DESCRIPTION 13.A.36.1 Purpose a.To demonstrate that the RPS has been pr operly installed and f unctions as designed in all modes of operation. b.To demonstrate that the RPS is properly interfaced with the nuclear instrumentation, the protective system process instrumentation, and the control element drive mechanism power supply.

13.A.36.2 General Prerequisites a.The RPS has been installed in the control room, all exte rnal connections have been made, and the complete RPS assembly ha s been thoroughly inspected for damage or loose components and other discrepancies. b.All external wiring to the RPS has been checked for continuity, short circuits, grounds, insulation resistance, etc. c.All NSSS parameter measurement channels which provide input signals to the RPS have been installed and are operable.

d.Both CEDM motor generators (MG) have been installed and are ready for operation. e.Main control board reactor trip and a nnunciator buttons have been installed and are operable. f.The control circuitry for th e following interlocks and act uations has been installed and is operable: CEA withdraw al prohibits, automatic wit hdrawal prohibits, diesel generator start, power-operated relief va lve actuation, turbine runback actuation, and turbine trip.

MPS2 UFSAR13.A-29Rev. 35 13.A.36.3 Test Methoda.Energize equipment and veri fy operation of indicating lights, alarms, and proper voltages. b.Perform system conditioning on the nuclear instrumentation by checking the indication of the syst ems when operating the function switches. c.Perform system conditioning on the bistable trip units utilizing the trip tester. d.Perform measurement channel functional tests on all parameters providing trip singles to the RPS. e.Perform an overall system functional check verifying proper operational trip setpoints, pretrip setpoints, bistable calibrations, output of the Reactor Protective System, and the operation of all BYPASS switches.

13.A.36.4 Acceptance Criteria The RPS and all associated equipment perform in accordance with the FSAR description, the RPS system description, and appropriate vendor manuals.

13.A.37 CHEMICAL AND VOLUME CONTROL SYSTEM PREOPERATIONAL TEST -

DESCRIPTION 13.A.37.1 Test ObjectiveTo demonstrate that the CVCS components are operating prope rly prior to performing the integrated Pre-Core Hot Functional Test.

13.A.37.2 General Prerequisitesa.CVCS construction, flushing and hydr ostatic tests have been completed. b.The CVCS has been re leased for operation. c.Installation and calibration checks of process instrumentation have been completed. d.Cycling of manual valves has been performed to demonstrate freedom of movement and proper indi cation where applicable. e.CVCS valve lineup for normal operation has been performed in accordance with the CVCS P&ID. f.The RCS or an alternate flow patch is ready to receive wa ter from the CVCS.

MPS2 UFSAR13.A-30Rev. 35g.Initiate run-in and opera tion of CVCS components has been performed where possible. h.The plant computer and those input sections concerned with the CVCS are operational.

13.A.37.3 Test Methoda.Operate all actuator-operated valves in the CVCS from the appropriate control locations and check the fail positions of these valves. b.Check the performance of the primary makeup system including the boric acid batching tank, concentrated boric acid pumps, and the concentrated boric acid storage tanks. This section will also incl ude gravity feed chec ks of the system. c.Check the performance of the volume control tank including process instrumentation, level indication, alarms and control systems. Check the performance of the volume control tank nitrogen and hydrogen pressurization

systems. d.Check the performance of the char ging pumps and auxiliary systems. e.Check the performance of all other CVCS temperature, pressure and flow controls and interlocks.

13.A.37.4 Acceptance Criteria The CVCS performs in accordance with the FSAR description, the CVCS sy stem description, and appropriate vendor manuals.

13.A.38 NUCLEAR INSTRUMENTATION SYSTEM PREOPERATIONAL TEST -

DESCRIPTION 13.A.38.1 PurposeTo demonstrate that the nuclear instrumentation system has been properly installed and functions as designed.

13.A.38.2 General Prerequisitesa.The nuclear instrumentation system has been installed. b.Installation of preamplifier s, cables, connectors, and de tectors has been completed and all wiring has been checked for discont inuities, shorts, grounds, and insulation resistance.

MPS2 UFSAR13.A-31Rev. 35 13.A.38.3 General Test Methodsa.Perform resistance measurements on all de tectors and associated cabling including preamplifiers. b.Perform alignment checks for the wi de-range nuclear instrumentation. c.Check response of the wide-range nuclear instrumentation to the startup source. d.Perform an alignment check of the power- range nuclear instrumentation. e.Using simulated input signals, verify th e proper performance of both wide-range and power-range nuclear instrumentation including output signals to the reactor regulatin g system, reactor protective system, and remote meters.

13.A.38.4 Acceptance Criteria The nuclear instrumentation system performs in accordance with the FSAR description, the nuclear instrumentation system descri ption and appropriate vendor manuals.

13.A.39 IN-CORE INSTRUMENTATION PREOPERATIONAL TEST - DESCRIPTION 13.A.39.1 PurposeTo verify the proper wiring of the signal cabling for the in-core inst rumentation and to verify the detector assembly resistance values.

13.A.39.2 General Prerequisitesa.Cabling between the refueling disconnect panel and the plant computer has been run and has been checked for continuity, shorts, grounds, and insulation resistance. b.The plant computer has been checked out and programmed for the in-core program with the appropriate constants entered. c.All in-core detector assemb lies have been received and are available for checkout.

13.A.39.3 Test Methoda.Measure the insulation resistance of each cable between the refuelin g disconnect panel and the plant computer. b.Obtain background readings for all cables by use of the plant computer. c.Using a simulated input check the comput er readout for each detector assembly.

MPS2 UFSAR13.A-32Rev. 35d.Measure the insulation resistance of each detector assembly.

13.A.39.4 Acceptance Criteria Measurements made during this test agree with th e specifications for the in-core instrumentation and in-core instrumentation wiring.

13.A.40 SYSTEM: PROCESS RADIATION MONITORING SYSTEMS 13.A.40.1 ObjectiveTo check and adjust the system, fluid flows, alarms, self checking f eatures and interlock functions. To check calibration and calibrate the sy stem to primary radioactivity calibration data.

13.A.40.2 Prerequisitesa.Radiation monitoring system operable. b.Process systems being monitored must be in operation before final adjustments can be made. c.Required electrical systems operable.

13.A.40.3 Methoda.Using secondary standard radioactiv e sources, calibrate output to primary radioactivity calibration data. b.Adjust alarms, interlocks and recorders.

c.Verify sampling valve sequences and self checking functions.

13.A.40.4 Acceptance Criteriaa.Outputs must be in agreement with primary calibration data. b.Proper sampling, alarm, interlock and self checking functions must operate as designed.

13.A.41 SYSTEM: AREA RADIATION MONITORING SYSTEM 13.A.41.1 ObjectiveTo determine the system alarms, self checking f eatures and interlocks ar e functional. Also to verify manufacturer' s initial calibration.

MPS2 UFSAR13.A-33Rev. 35 13.A.41.2 Prerequisitesa.Radiation monitoring system operable. b.Required electrical systems operable.

13.A.41.3 Methoda.Using standard radiation sour ce check detectors calibration. b.Check alarms, self-checking feat ures, interlocks and recorders.

13.A.41.4 Acceptance Criteriaa.Detector outputs must be in agreemen t with standard source radiation levels. b.System must demonstrate proper alarm, interlock and self checking functions.

13.A.42 BORONOMETER AND PROCESS RADIATION MONITOR PREOPERA TIONAL TEST - DESCRIPTION 13.A.42.1 PurposeTo verify the proper installation, calibration, and operation of the boronometer and process radiation monitor.

13.A.42.2 General Prerequisites a.Installation of the boron ometer and process radiat ion monitor have been completed. b.All wiring to the boronometer and proce ss radiation monitor have been checked for continuity , short circuits, grounds, and insulation resistance. c.All associated remote meters and wiring the control room have been installed and are operational. d.The RCS has been filled.

13.A.42.3 Test Methodsa.Verify proper operation of the process radi ation monitor using the electrical test switches and the check source button. b.Adjust the alarm setpoints of the process radiation mon itor to the proper setpoints.

MPS2 UFSAR13.A-34Rev. 35c.Verify calibration of the boronometer using the electrical test switches.

d.Verify proper operation of the boronomet er using a standardized solution of borated reactor coolant-grade water.

13.A.42.4 Acceptance Criteria The boronometer and process ra diation monitor perform in accordance with the system description and the technical manuals.

13.A.43 SYSTEM: MAIN AND NORMAL STATION SERVICE TRANSFORMERS 13.A.43.1 Test ObjectivesTo demonstrate the capability of the main and normal station service tr ansformers to supply electrical power to the 345 kV switchyard and plant buses. To verify operation of protective devices, calibration and functional opera tion of controls and interlocks.

13.A.43.2 Prerequisitesa.All meters, relays and protectiv e devices calibrated and tested. b.125V DC and 480V AC available. c.All erection work on transforme rs and switchgear complete. d.Transformer oil and gas systems tested and in se rvice. e.Isolated phase bus tested and ready for service.

f.Breaker controls and transfer scheme verified. g.PT & CT circuits checked for polarity and continuity.

13.A.43.3 Methoda.Simulate signals to temperature controls and verify operation of transformer oil pumps and fans. b.Simulate signals to verify annunciators for transformer protective devices.

c.Energize transformers fr om the 345 kV switchyard.

d.Verify transfer to reserve station serv ice transformer when normal station service transformer is deenergized.

MPS2 UFSAR13.A-35Rev. 35 13.A.43.4 Acceptance Criteriaa.Transformers are capable of supplying power to plant loads and switchyard. b.Normal station service transformer loads transfer to the reserve station service transformer on a turbine trip.

13.A.44 SYSTEM: ENCLOSURE BUILDING FILTRATION AND HYDROGEN REMOVAL SYSTEM 13.A.44.1 Objective To demonstrate that the encl osure building filtration and H 2 removal system is capable of minimizing environmental activity levels resulting from all sources of containment leakage and maintaining H 2 concentration in the containment below the lower flammability limit following any postulated incident.

13.A.44.2 Prerequisitesa.480V, 120VAC and 125VDC power sources are available. b.Instrument and service ai r systems are functional. c.Enclosure building filtration and H 2 removal system is operable.

13.A.44.3 Methoda.Line up the system for operation.

b.Adjust alarms, recorders and interlocks.

c.Simulate enclosure building filtration actuation signal and auxiliary exhaust actuation signal. d.Simulate high H 2 concentration in the containment. e.Simulate containment is olation actuation signal.

13.A.44.4 Acceptance Criteriaa.Alarms, recorders and interlocks function properly. b.The system responds to differen t actuating signals as designed. c.The system performance meets design requirement.

MPS2 UFSAR13.A-36Rev. 35d.The fans and dampers must respond according to the containment isolation activation signal.

13.A.45 CEDS SIMULATOR BOX OPERATION - DESCRIPTION 13.A.45.1 PurposeTo verify the proper installati on and operation of the CEDS prior to performing the Post-Core Hot Functional Test.

13.A.45.2 General Prerequisitesa.The CEDS and the RRS have been installed and are operational.

b.All interconnecting cabling between the CEDS and the refueling panel disconnect has been installed and has been checked for continuity, shorts, grounds, and insulation resistance.

c.The CEDS test box and the reed switch test box are available. d.A high-speed optical recorder has been pr operly set up for use in reading out the coil power arrangements.

13.A.45.3 Test Methodsa.Verify the proper operation for each CEA of the second ary position indication and limit switch actuation usi ng the reed switch test box. b.Using the CEDS test box, verify proper operation for each CEA of the CEDS and the primary position indication system.

c.Verify proper group operation for each group of CEAs by observing CEA digital displays and pulse counters at CEDS panels. d.Verify proper sequential operation of the regulating groups of CEAs by observing CEA digital displays and pulse counters at CEDS panels.

13.A.45.4 Acceptance Criteria The CEDS performs in accordance with the FSAR description, the CEDS system description, and the appropriate technical manuals.

MPS2 UFSAR13.A-37Rev. 35 13.A.46 SYSTEM: SOLID RADWASTE SYSTEMS 13.A.46.1 Test ObjectivesTo demonstrate the capability of the solid radwaste drumming system to operate as per design criteria.

13.A.46.2 Prereq uisitesa.Solid radwaste drum ming equipment operable.b.480 volt power supply availabl e to solid radwaste area.c.Actual shielding in phase.

13.A.46.3 Methoda.Line up equipment for normal operation.

b.Fill a 55 gallon drum with simulated waste material.c.Mix and pour concrete shield plug.

d.Cap waste barrel.

13.A.46.4 Acceptance Criteriaa.All equipment operates as per design specifications.b.Operation can be performed in a timely manner.

13.A.47 SYSTEM: CONTAINMENT BUILDING INTEGRATED LEAK RA TE TEST 13.A.47.1 ObjectiveDemonstrate that the potential leakage from the containment buildi ng is within acceptable limits, under the conditions stated below

.13.A.47.2 Prerequisitesa.Penetrations are installed.

b.Penetration local leak tests must be completed before the integrated leak rate test. c.Reactor building closed cool ing water system functional.

MPS2 UFSAR13.A-38Rev. 35 13.A.47.3 Methoda.Penetration local leak tests by pressurizing betwee n the appropriate boundaries and observing the pressure decay.b.The containment building leak rate will be determined at calculated peak accident pressure and at one-half calcul ated peak accident pressure.

13.A.47.4 Acceptance Criteria The leak rates must not exceed allowable limits.

13.A.48 SYSTEM: CONTAINMENT BUILDING STRUCTURAL INTEGRITY TEST 13.A.48.1 ObjectiveDemonstrate the structural integrity of the containment building at 115% of design pressure.

13.A.48.2 Prereq uisites Completion of containment penetrations local leak tests.

13.A.48.3 Method The containment building will be pressurized in steps up to a maximum of 115% of design pressure. At selected pressure levels, data will be recorded and in spec tions will be made to verify the structural integrity. After remaining at 115% of design pressure for approximately one hour, depressurization will begin. Data test, visu ally inspect containment building, hatched, penetrations and gaskets.

13.A.48.4 Acceptance CriteriaStructure must be capable of withstanding an internal pressure of 1.15 times the design pressure.

13.A.49 SYSTEM: CONTAINMENT PENETRATION VENTILATION SYSTEM 13.A.49.1 ObjectiveTo demonstrate the containment penetration ventilation system is capable of supplying the required amount of air as designed.

13.A.49.2 Prerequisitesa.Required electrical systems operational.

MPS2 UFSAR13.A-39Rev. 35 13.A.49.3 Methoda.Line up system and put into normal operation.

13.A.49.4 Acceptance Criteriaa.Fans must meet the design criteria.

13.A.50 SYSTEM: CONTAINMENT PURGE SYSTEM 13.A.50.1 ObjectivesTo demonstrate the capability of the containment purge sy stem to operate under normal conditions and to respond to a CIAS.

13.A.50.2 Prereq uisitesa.Instrument air system operational.b.Required electrical systems operational.

13.A.50.3 Methoda.Line up system and pl ace in normal operation.

b.Initiate a simulated containment isolation actuation signal (CIAS).c.Initiate a simulated high-radiation signal.

13.A.50.4 Acceptance Criteriaa.The fans and dampers must re spond to the CIAS as designed.b.The dampers must respond to the high-radiation signal as designed.

13.A.51 SYSTEM: CONTROL ELEMENT DRIVE ASSEMBLY VENTILATION 13.A.51.1 Objective Demonstrate that the control elem ent drive assembly ventilation system is capable of providing adequate ventilation to the control element drive assembly.

13.A.51.2 Prereq uisitesa.Required electrical systems functional.

MPS2 UFSAR13.A-40Rev. 35 13.A.51.3 Methoda.Line up system and pl ace in normal operation.

13.A.51.4 Acceptance Criteriaa.The fans and dampers must respond as designed.b.The fans must meet design criteria.

13.A.52 SYSTEM: CONTAINMENT AIR RECIRCULATION SYSTEM 13.A.52.1 ObjectivesTo demonstrate the capability of the containment air recirculation system to operate in accordance to design and to recirculate the required amount of air.

13.A.52.2 Prerequisitesa.Required electrical systems available.

13.A.52.3 Method a.Line up system for normal operation.

13.A.52.4 Acceptance Criteriaa.Fans and dampers must operate in accordance with design.

13.A.53 SYSTEM: CONTROL ROOM AIR CONDITIONING SYSTEM 13.A.53.1 Objectives T o demonstrate that the control room air conditioning system is cap able of providi ng a controlled environment during normal and abnormal conditions.

13.A.53.2 Prerequisitesa.Instrument air system functional.b.Heating and cooling coils functional.

c.Verify that particulate filters are installed.d.Charcoal and abso lute filters are not to be installed during testing.

MPS2 UFSAR13.A-41Rev. 35 13.A.53.3 Methoda.Line up system for normal operation.b.Simulate smoke detection si gnal and recirculation signal.

13.A.53.4 Acceptance Criteriaa.The dampers and fans must respond to smoke detection and recirculation signals as designed. b.Heating and cooling coils must meet design specifications.

13.A.54 SYSTEM: NON-RADIOACTIVE VENTILATION SYSTEM 13.A.54.1 ObjectiveTo demonstrate that the ventil ation system to the 480V unit s ubstation, controlled access area, cable vault, battery rooms and switchgear rooms is ca pable of providing ade quate ventilation to each room.

13.A.54.2 Prerequisitesa.Instrument air system available.b.Required electrical systems functional.

13.A.54.3 Methoda.Line up system and pl ace in normal operation.

13.A.54.4 Acceptance Criteriaa.The fans and dampers must respond as designed.

13.A.55 SYSTEM: DIESEL GENERATOR VENTILATION SYSTEM 13.A.55.1 ObjectiveTo demonstrate that the diesel generator ventilation system will operate during normal or abnormal conditions.

13.A.55.2 Prerequisitesa.Required electrical systems functional.

MPS2 UFSAR13.A-42Rev. 35b.Instrument air system available.

13.A.55.3 Methoda.Line up system for normal operation.b.Simulate diesel generator start signal.

13.A.55.4 Acceptance Criteriaa.Fans and dampers must respond as designed in response to diesel generator start.

13.A.56 SYSTEM: MAIN EXHAUST SYSTEM 13.A.56.1 ObjectivesTo demonstrate the capability of the main exhaust system to discharge the proper amount of air from the plant in accordance with design.

13.A.56.2 Prereq uisitesa.Required electrical systems operational.

13.A.56.3 Methoda.Line up system and pl ace in normal operation.

13.A.56.4 Acceptance Criteriaa.All fans must operate to design criteria.

13.A.57 SYSTEM: FUEL HANDLING AREA VENTILATION SYSTEM 13.A.57.1 ObjectiveTo demonstrate that the fuel handling area ventilation system is capable of providing adequate ventilation during normal and abnormal conditions.

13.A.57.2 Prerequisitesa.Instrument air system available.

b.Required electrical systems functional.

MPS2 UFSAR13.A-43Rev. 35 13.A.57.3 Methoda.Line up system and pl ace in normal operation.b.Initiate simulated auxiliar y exhaust actuation signal.

13.A.57.4 Acceptance Criteriaa.Fans and dampers must respond as designed.b.In normal operation, fans must meet design criteria.

13.A.58 SYSTEM: RADWASTE VENTILATION SYSTEM 13.A.58.1 ObjectiveTo demonstrate that the radwaste ventilation syst em is capable of providing adequate ventilation to the radwaste area during norma l or abnormal operating conditions.

13.A.58.2 Prerequisitesa.Instrument air system available.

b.Required electrical systems functional.

13.A.58.3 Methoda.Line up system and pl ace in normal operation.

b.Simulate an enclosure build ing filtration actuation signal.

13.A.58.4 Acceptance Criteriaa.The fans and dampers must respond as designed.

13.A.59 SYSTEM: PRIMARY CHEMICAL ADDITION SYSTEM 13.A.59.1 ObjectiveTo demonstrate that the system will function in accordance with design specifications.

13.A.59.2 Prerequisitesa.Required electrical systems functional.

b.Water treatment system functional.

MPS2 UFSAR13.A-44Rev. 35 13.A.59.3 Methoda.Line up system and pl ace in normal operation.

13.A.59.4 Acceptance Criteriaa.Verify that the chemical addition metering pumps start and stop manually.b.Ensure valves operate properly

.13.A.60 SYSTEM: POST-INCIDENT RECIRCULATION SYSTEM 13.A.60.1 Objective T o demonstrate the capability of the post-incident recirculation sy stem to provide containment air recirculation as design ed.13.A.60.2 Prerequisitesa.Required electrical systems operational.

13.A.60.3 Methoda.Line up system and pl ace in normal operation.

13.A.60.4 Acceptance Criteriaa.Fans must operate in ac cordance to design criteria.

13.A.61 REACTOR COMPONENTS HANDLING SYSTEM 13.A.61.1 PurposeTo conduct a checkout of the r eactor component handling system in accordance with the guidelines provided in Section 4 of the Millstone Unit 2 Reactor Internals Instruction Manual and Section 5 of the Millstone Unit 2 Reactor Vessel Assembly Instruction Manual Volume 1.

13.A.61.2 General Prerequisitesa.The reactor vessel and the vessel internals are installed as necessary to complete the various phases of testing.

b.The polar crane will be fully tested before any reactor components are fitted.c.The reactor vessel head is removed and th e refueling cavity is capable of being filled.

MPS2 UFSAR13.A-45Rev. 35 13.A.61.3 Test Methoda.Operate the polar crane in all modes and load test the main a nd auxiliary hoist and hooks.b.Operate the polar crane in conjunction with various tools to accomplish the follo wing:1.Coupling and uncoupling of CEA extension shafts.2.Insertion and withdrawal of in-core detector and installation and removal of the Upper Guide Structure.

3.Installation and removal of core support barrel assembly.4.Removal of surveillance samples.

5.Installation and removal of neutr on source and instrument thimbles.6.Installation and removal of the reactor vessel head.

13.A.61.4 Acceptance Criteria The reactor component handling equipment performs in accordance with the Reactor Internals and Reactor Vessel Assembly Instruction Manuals.