ML18116A357

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Integrated Startup Test Program.
ML18116A357
Person / Time
Site: Surry Dominion icon.png
Issue date: 08/13/1979
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18116A356 List:
References
NUDOCS 7908160355
Download: ML18116A357 (48)
v • d • e


Text

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e LIST OF APPENDICES APPENDIX A STARTUP NETWORK APPENDIX B LIST OF MAJOR PREOPERATIONAL TESTS AND CHECKS APPENDIX C LIST OF MAJOR STARTUP TESTS AND CHECKS APPENDIX D PROCEDURE FOR CONDUCTING THE INTEGRATED STARTUP PROGRAM 50-28\

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7908160 355

e APPENDIX A STARTUP NETWORK

  • e STARTUP NETWORK SURRY UNIT NO. 2 ,

SEC. PRIMARY "~' LEAK ECCS FUEl- HOT HOT HYDRO HYDRO* TEST INTEGM D LDAD NCTION L NCTIO TEST START COMPLET Construction Preoperatlonal Test Phase Startup Test Phase Test Phase

('IOTg - All Construction tests ara not required prior to tho Preoperatlona/ test phase.

- - - - - - - - - - - - - - - - ~ - e * - - - - - - - - - - - * * - - - - - - - - - - - - - ~ - -- -- --- --------------

APPENDIX B LIST OF MAJOR PREOPERATIONAL TESTS AND CHECKS

APPENDIX B Pagel of 5 LIST OF PREOPERATIONAL TESTS AND CHECKS TITLE OF TEST OR CHECK PLANT CONDITION/PREREQUISITE TEST OBJECTIVE I. PLANT INSTRUMENTATION

1. Nuclear Instrumentation Prior to core loading Nuclear instruments are aligned and source range detector reponse to a neutron source checked as the primary source is loaded.
2. Process Instrumentation Ambient and/or at temperature Required equipment is aligned per station. procedure.a.

II. REACTOR COOLANT SYSTEM

1. Pressure Boundary Integrity Tests
a. Hydrostatic test Below 200°F (after Cold hydrostatic testing of each Reactor Coolant System verification of cleanliness loop will be performed at test pressures as specified and fill of system) by ASME standards for the system. Prior to pressuriza-tion, the effected portions of the system will be heated above the minimum temperature for pressurization. The pressure is then increased in increments, and at each increment inspections are made for leakage. Leaky valves or mechanical joints are not a basis for rejecting the test, Overpressure protection is provided during testing.
b. Baseline data for inservice During preoperational Systems and components that require inspection in accor-inspection testing dance with Section XI of the ASME Code are examined for base line data. Data from these inspections provide base line data for subsequent inservice inspections,
2. Component Tests
a. Pressurizer Safety Valve Ambient pressure The setpoints of the safety valves are verified using existing station procedures,

APPENDIX B Page 2 of 5 LIST OF PREOPERATIONAL TESTS AND CHECKS TITLE OF TEST OR CHECK PLANT CONDITION/PREREQUISITE TEST OBJECTIVE III. REACTIVITY CONTROL SYSTEMS

1. Automatic Reactor Power Control Preoperational testing The system alignment is verified at preoperational con-Test Systems ditions to demonstrate the repsonse of the system to simulated inputs. These tests are performed to verify that the systems will operate satisfactorily at power.

IV. REACTOR PROTECTION SYSTEMS

1. Reactor Protection System Prior to .core loading Prior to core loading the Reactor Protection is tested to demonstrate operability, proper logic, redundancy, and coincidence. The protection channels are verified through to tripping of the reactor trip breakers.
2. Engineered Safety Features Prior to core loading Prior to core loading the Engineered Safey Features logic systems are tested to demonstrate operability, proper logic, redundancy, and coincidence.

V, POWER CONVERSION SYSTEM Done under Startup Testing I'

VI. AUXILIARY SYSTEMS "I

1. Residual Heat Removal System Test Prior to core loading Thia aystem i!j tested by verifying pressure and flow.

111 1*, "* I 11*

APPENDIX B Page 3 of 5 LIST OF PREOPERATIONAL TESTS AND CHECKS TITLE OF TEST OR CHECK PLANT CONDITION/PREREQUISITE TEST OBJECTIVE characteristics of the pumps and operation of the iso-lation valves.

2. Containment Instrument Air System Prior to core loading The instrument air system. including air receivers and compressors. is tested to verify proper operation.
3. Neutron Shield Tank Cooling System Prior to core loading The system is operationally checked out to verify heat exchange operability.
4. Leak Detection System Tests Prior to and during Temperature detectors in the drain lines from pressurizer preoperational tests safety valves and the reactor vessel head 'seal and their alarm functions are checked. Pressurizer relief tank level and temperature sensors are calibrated and associ-ated alarms checked.

VII. ELECTRICAL SYSTEM

1. F.mergency Power Systems Prior to core loading The automatic starting and loading of the diesel genera-tors is demonstrated under loss of emergency bus alter-nating current power.

VIII. CONTAINMENT SYSTEMS

1. Reactor Containment Tests Prior to core loading Containment Type A leakage tests will be performend in accordance with USNRC approved topical report BN-TOP-1 Rev. 1, which provides for a reduced duration test.

Containment Type B & C leakage tests will be performed in accordance with Appendix J to 10CFRSO

  • e APPENDIX B Page 4 of 5 LIST OF PREOPERATIONAL TESTS AND CHECKS TITLE OF TEST OR CHECK PLANT CONDITION/PREREQUISITE TEST OBJECTIVE
2. Containment Isolation Tests Prior to core loading The operation of actuation systems and components used for containment isolation is verified.

IX. GASEOUS RADIOACTIVITY REMOVAL SYSTEMS Done under St:artup Testing X. EMERGENCY CORE COOLING SYSTEM

1. High pressure Safety Injection Tests Prior to core loading This system is operationally tested to verify pressure/

flow values. Tests are also conducted to check pump operating characteristics. More specifically that:

.\.:.::

a. Valves installed for redundant flow paths operate as desigend,
b. Pump operating characteristics are verified.
c. Valves and pumps operate on operator initiation and/or automatically on initiation of a safety injection signal.
d. Level and pressure instruments are properly cali-brated.
2. Low Pressure Safety Injection Tests Prior to core loading The low head Safety Injection System is checked to verify design flow, flow paths, and pump operating characteris-tics. More specifically that:
a. Valves installed for redundant flow paths operate as designed.

e APPENDIX B Page 5 of 5*

LIST OF PREOPERATIONAL TESTS AND CHECKS TITJ.E OF TEST OR CHECK PLANT CONDITION/PREREQUISITE TEST OBJECTIVE

b. Pump operating characteristics are verified with the reactor coolant system at ambient conditions.
c. Valves and motors operate on operator initiation and/or automatically on initiation of a safety in-jection signal.
d. Level and pressure instruments are properly cali-brated.

In addition a 100 hr. endurance test witl be performed, the pump disassembled and inspected.

XI. FUEL STORAGE AND HANDLING SYSTEM

1. Refueling Equipment (hand tools Prior to core loading Tests are performed prior to core loading to demonstrate and power equipment, including
  • the fun~tioning of the fuel transfer system.

protective interlocks)

XII. REACTOR COMPONENTS HANDLING SYSTEM Done during startup XIII. RADIATION PROTECTION SYSTEM

1. Criticality and area monitor tests Prior to core loading The radiation alarms aasociated with core loading are checked out and the alarm setpoints verified.

e APPENDIX C LIST OF MAJOR STARTUP TESTS AND CHECKS

APPENDIX C Page 1 of 11 LIST OF STARTUP TESTS AND CHECKS TITLE OF TEST OR CHECK PLANT CONDITION/ PREREQUISITE TEST OBJECTIVE I. PLANT INSTRUMENTATION I\*

I. Nuclear Instrumentation (excore) Prior to criticality Just before criticality all channels are checked to verify high level trip functions, alarm set points, audible count rates where applicable, and operation of strip chart re-corders, and any auxiliary equipment.

2. Process Instrumentation (Temperature, Ambient and/or at Equipment is aligned per station procedures, pressure, level, and flow instruments) temperature II. REACTOR COOLANT SYSTEM
1. Vibration and amplitude After fuel load Vibration sensors are placed on the main coolant pumps and main cooling piping in order to check for excessive vibration while starting and stopping the pumps. *
2. Expansion and Restraint During plant heat-up During the heat-up to operating temperature, selected point on components and piping of the Reactor Coolant System are checked at various temperatures to verify unrestricted expansion. Points of interference detected during the heat-up are corrected prior to increasing the temperature.
3. Integrated Hot Functional Tests Heat-up and at temperature The Reactor Coolant System is tested using pump heat to Hydrostatic testing has reverify heat-up procedures and to demonstrate satis-been satisfactorily com- factory performance of components and systems exposed to completed and Reactor reactor coolant system temperature. Proper operation of Coolant System instruments instrumentation, controllers and alarms, is checked aligned and operational. against design operating conditions of auxiliary systems Associated auxiliary systems and set points verified. Among the demonstrations per-shall be operational to the formed are:

APPENDIX C Page 2 of 11 LIST OF STARTUP TESTS AND CHECKS TITLE OF TEST OR CHECK PLANT CONDITION/PREREQUISITE TEST OBJECTIVE extent required to support hot functional testing,

a. To check that water can be charged by the Chemical and Volume Control System at rated flow against normal reactor coolant pressures,
b. To check letdown design flow rate for each operating mode,
c. To check response of system to change in pressurizer level, d, To check operation of the excess letdown and seal water flow paths.

e, To check steam generator level instrumentation re-sponse to level changes.

f. To check thermal expansion of selected system com-ponents and piping.

g, To perform isothermal calibration of resistance temperature detectors and incore thermocouples,

h. To operationally check out the Residual Heat Removal System,
4. Component Tests
a. Pressurizer At operating temperature, During the hot functional testing the pressure controlling capability of the pressurizer is demonstrated to be with-in the controlling band, With reactor coolant pumps operating and with full spray, the pressure-reducing capa-bility of the pressurizer is verified. With the spray secured and all heaters energized, the pressure-increasing

APPENDIK C .

Page 3 of 11 LIST OF STARTUP TESTS AND CHECKS I

..I TITLE OF TEST OR MEASUREMENT PLANT CONDITION/PREREQUISITE TEST OBJECTIVE capability of the pressurizer is verified. Pressurizer Relief valves are functionally checked.

b. Reactor Coolant Pumps and Motors At ambient conditions and As the pumps and motors are placed in operation they are during heat-up and at checked for:

temperature.

1. Direction of rotation (initial start only)*
2. Vibration
3. Power requirements
4. Lubrication
5. Cooling
6. Megger and hi pot test (as applicable)
7. Overload protection
8. Correct power supply voltage
c. Steam Generators At ambient conditions The proper operation of instrumentation and control and during heat-up and systems of steam generators are checked during heat-up at temperature. and at temperature. The heat transfer capability of the steam generators is demonstrated. The functioning of the blowdown system will be checked.
5. Pressure Test of Reactor Coolant System Prior to criticality Following core loading and installation of the Reactor Vessel head and torquing of the reactor vessel heads studs, pressure testing is performed in accordance to Tech. Spec.

APPENDIX C Page 4 of 11 LIST OF STARTUP TESTS AND CHECKS TITLE OF TEST OR CHECK PLANT CONDITION/PREREQUISITE TEST OBJECTIVE

6. Chemical Tests (to establish water Prior to heat-up during Water f<;>r Reactor Coolant System fill and makeup is quality) startup testing analyzed for chloride content, conductivity, total sus-pended solids, pH, clarity, and fluorides to requirements specified by the chemistry manual for ~SSS. Following core loading and prior to exceeding 250 F, hydrazine is added to scavenge oxygen prior to critical operation.

Prior to, at criticality, and during power escalation, chemical analysis is performed to verify requirements.

7. Reactor Coolant Flow Test Prior to plant criticality Following core loading, measurements are made of elbow tap differential pressures to make relative comparison.

At hot shutdown conditions following core loading, measurements of loop elbow differential pressure drops were made. Using these data with the reactor coolant pump performance curve, the calculated flow is verified to the design flow. Flow coastdown and transients following reactor coolant pump stoppages are also determined at shutdown conditions following core loading.

III. REACTIVITY CONTROL SYSTEMS

l. Chemical and Volume Control System At ambient and/or Makeup and letdown operations are conducted with the Tests at operating conditions. Chemical and Volume Control System to check out the dif-System components are ferent modes of dilution and boration and verify flows in operationally checked out, the different modes. The adequacy of heat tracing to main-tain the required Boric Acid concentration in solution is verified. The ability to adequately sample is demon-strated.
2. Emergency Boration System Teats During hot functional The pressure/flow characteristics of the emergency bora-testing. tion system are verified . by pumping into the Reactor Coolant System.

APPENDIX C Page 5 of 11 LIST OF STARTUP TESTS AND CHECKS TITLE OF TEST OR CHECK PLANT CONDITION/PREREQUISITE TEST OBJECTIVE

3. Incore Monitor System Test
a. Incore Thermocouples During heat-up and at During heat-up and at temperature the incore thermocouples temperature. are calibrated to the average of the Reactor Coolant System resistance temperature detectors. All readout and tempera-ture compensating equipment is checked during the calibra-tion and isothermal corrections for the operative thermo-couples are determined.
b. Moveable Detector System At ambient conditions After core loading, the installation checkout of the move-following core loading able detector system will be completed.

and critical testing.

4. Control Rod Systems Tests
a. Rod Control System Ambient conditions During the installation check of this system it is ener-following core loading gized and operationally checked out with mechanisms and hot conditions after connected to each power supply. The ability of the system core loading. ' to step the mechanism is verified, the alarm and inhibit functions checked out and the correct values of system parameters adjusted to specified values. After core load-ing the operation of each rod over its full range of travel is demonstrated.
b. Rod Drop Tests Cold and hot plant At cold and hot plant conditions following core loading conditions following the drop times of the full length rods are measured, The core loading, drop time is measured from the release of the rod until the rod enters the top of the dashpot. This time was verified to be less than the maximum value specified in the Technical Specifications.
c. Rod Position Indication At ambient conditions and During rod control system tests the position indication at temperature following system was aligned to provide rod movement indication.

core loading. Rod bottom set points will b!! adjusted during these tests.

After plant heat-up individual rod positions a["e cali-brated to within tolerances specified by the test proce-dure, i

Cl

  • LIST OF STARTUP TESTS AND CHECKS APPENDIX C Page 6 of 11 l

TITLE OF TEST OR CHECK PLANT CONDITION/PREREQUISITE TEST OBJECTIVE IV. REACTOR PROTECTION SYSTEM Done during Properational Testing V. POWER CONVERSION SYSTEM

1. System Tests
a. Vibration Frequency and Amplitude Hot Functional Testing When the main turbine is rolled, vibration readings are and/or plant heat-up monitored. * (Turbine vibrations are also monitored following criticality throughout the power escalation program.) Major equip-ment (e.g., feedwater pumps and condensate pumps are operated as they become available and are observed for indications of excessive vibration.
b. Expansion and Restraint **:::*
  • During heat-up, and at During heat-up to operating termperature, selected points temperature. on the components and piping of -the systems are checked at various temperatures to verify that they can expand un-restricted.
2. Components and Individual System
a. Steam Generator Pressure Pressure Conditions The set point of safety valves was verified by in-plant Relief and Safety Valves tests at pressure and temperature conditions when the unit was shut down. Setpoints were checked by using a pressure assist device which adds to the force due to pressure. Once the valve leaves the seated position the assist device was vented, allowing the valve to reseat immediately. Steam relief valve set point checks were made during instrument alignment
  • LIST OF STARTUP TESTS AND CHECKS APPENDIX C Page 7 of 11 TITLE OF TEST OR CHECK PLANT CONDITION/PREREQUISITE TEST OBJECTIVE
b. Emergency Feedwater Prior to citicality During bot functional testing prior to criticality the (Auxiliary) System emergency feedwater system is checked out to verify its ability to feed the steam generators. Automatic starting is checked during checkout of the safeguards logic system tests. The auxiliary feedwater piping is checked for excessive vibration while starting and stopping the auxi-liary -feedwater pump with normal operation of the associ-ated motor operated discharge valves in the auxiliary feedwater system,
c. T~rbine Control and Bypass Valves Hot Functional test:1.ng During hot functional testing the turnbine control system and/or power operat:l.on will be demonstrated in turbine operation up to and in-following criticality cluding a period of operation at synchronous speed, The turbine bypass valves to the condenser and their associat-ed control systems are operationally checked out during hot functional testing.
d. Feedwater and Feedwater Co** ,:-rol Hot functional testing The feedwater and condenstate pumps are operationally System and at Power checked out during hot functional testing. During* power escalation the power is increased and the ability of the feedwater pumps and control system to maintain level in the system generators are aligned prior to filling the system and during fill, the system is used to monitor level in the steam generator.
e. Condenser Circulating Water Prior to bot functional Prior to hot functional testing the main circulating water testing system valves are tested to verify operability.
f. Makeup Water and Chemical During Steam generator fill, The makeup system to the system generators is checked out hot functional testing and during hot functional testing and at Power at power. The chemical treatment system is checked out when chemicals are added to the steam generators at heat-up to steaming conditions.

LIST OF STARTUP TESTS AND CHECKS APPENDIX C Page 8 of 11 I

./

TITLE OF TEST OR CHECK PLANT CONDITION/PREREQUISITE TEST OBJECTIVE VI. AUXILIARY SYSTEMS 1, Reactor Coolant System Makeup See III REACTIVITY CONTROL SYSTEM, Item 1.

Test (CVCS)

2. Seal and Pump Cooling Water Prior to heat-up and Test (CVCS) Prior to reactor coolant pump operation and with the at temperature system pressurized flow to the pump seals and cooling water is set, flow is adjusted to specified values using installed instruments. During hot functional testing when at operating temperature and pressure, seal and cooling flows and temperatures are checked, *
3. Secondary Vent and Drain System Test During hot functional During hot functional testing following core loading the testing secondary system is vented while pressurizing the second-ary system, Secondary drains are tested for unrestricted flow in accordance with operating procedures,
4. Component Cooling System Test Ambient and/or hot Component cooling flow to the various components in the plant conditions affected systems is adjusted, the system operationally checked out, and set points verified,
5. Residual Heat Removal System Test Prior to and during hot Heat removal capability demonstrated, functional testing
6. Service Water System Test Prior to hot functional The system is operationally checked out to verify pressure and flow. Service water flow is verified to components in the system.
7. Control Rod Drive Mechanism and Rod Prior to and/or during The system is operationally checked out to verify air Position Indication Coil Cooling hot functional tesintg System Test flow, temperatures and motor current,
8. Primary Sampli~g System Prior to and/or during Operations are performed to:

hot functional testing

-.;"r'

LIST OF STARTUP TESTS AND CHECKS APPENDIX C Page 9 of 11 TITLE OF TEST OR CHECK PLANT CONDITION/PREREQUISITE TEST OBJECTIVE

a. Demonstrate that liquid and gas samples can be obtain-ed from sample points.
b. Demonstrate that valves, instruments, and controls funtion properly.
c. Verify power functioning of the sample cooler.

9, Primary Pressure Relief System Prior to hot functional

  • The pressurizer relief tanks associated valves, and in-testing and at pressure strumentation are checked out to verify performance of conditions design functions, For testing of pressurizer relief and safety valves see II REACTOR COOLANT SYSTEM. '

VII. ELECTRICAL SYSTEM TESTS Done during Preoperational Testing VIII. CONTAINMENT SYSTEMS 1, Containment Ventilation System Test Prior to and/or during The system is operated to balance air flows and to verify hot functional testing the ability to maintain temperatures below maximum allow-able limits, 2, Post Accident Heat Removal System Prior to criticality Testa are performed to verify pump operating charcteris-Tests (Containment Sprays) tics, and response to control signals, sequencing of the pumps, valves and controller, (and to ensure that spray nozzles were unobstructed,)

LIST OF STARTUP TESTS AND CHECKS APPENDIX C Page lO of 11 **

TITLE OF TEST OR CHECK PLANT CONDITION/PREREQUISITE TEST OBJECTIVE IX. GASEOUS RADIOACTIVITY REMOVAL SYSTEMS Done during Preoperational Testing X. EMERGENCY CODE COOLING SYSTEM

1. Accumulator Tests During hot functional Flow throught the accumlator lines is intiated to demon-strate that the check valves are free to open. Tests are also. made to verify that accumulator pressure could be maintained*.

........ <( XI. FUEL STORAGE AND HANDLING SYSTEM

l. Spent Fuel Storage Radiation Monitoring Equipment
.
f Prior to plant start-up Refer to Appendix B, Item 1.

XIII RADIATION PROTECTION SYSTEM,

  • ,:.. XII. REACTOR COMPONENTS HANDLING SYSTEM
l. Reactor Component Handling System Prior to use for Testing was conducted on the polar crane in accordance (Polar Crane) installation of components with standard crane testing procedures during steam within the containment generator replacement.

XIII. RADIATION PROTECTION SYSTEM Done during Preoperational Testing

LIST OF STARTUP TESTS AND CHECKS APPENDIX C Page 11 of 11 TITLE OF TEST OR CHECK PLANT CONDITION/PREREQUISITE TEST OBJECTIVE XIV. INITIAL CRITICALITY AND LOW POWER TESTS l, Initial Criticality Plant at hot shutdown -The objective is to bring the reactor critical from the plant conditions specified. Prior to start of rod with-drawal, the nuclear instrumentation had been aligned, checked, and conservative reactor trip set points made per procedures, At preselected points in rod withdrawal, data is taken and inverse count rate plots made to enable extrapolating to the expected critical rod position, In addition, the following teats associated with modified system will be performed: steam generator water hammer test, blowdown system capability test and thermal expan-sion monitoring.

XV. POWER ASCENSION

l. Power Ascension Criticality Normal poet refueling testing will apply for power ascen-sion, In addition the following design tests associated with modified systems will be performed.

steam generator carryover tests steam generator recirculation ratio test steam generator thermal and hydraulic perfomrance verifi-cation steam generator water level stability and control demon-stration condensate polishing performance testing load rejection testing with condensate polisher

I APPENDIX D PROCEDURE FOR CONDUCTING THE INTEGRATED STARTUP TEST PROGRAM

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I Issue Date: AUG 8 1979 PROCEDURE FOR CONDUCTING THE INTEGRATED STARTUP TEST PROGRAM FOR POST STEAM GENERATOR REPLACEMENT AND

  • P.O. & M. DESIGN CHANGES SURRY POWER STATION VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA Superintendent Operations:

Lead Advisory Engineer:

PO & M Resident Engineer:

A,HA!P.'.,,1/\N- SUR~ PO\NER STATION

.NlJCU.:1\R s.:1FET AND OPERATING

. COM.MiHEE DATE <j ~ l -79

I INTEGRATED STARTUP TEST PROGRAM TABLE OF CONTENTS

1. 0 Purpose and Scope 2 *0 References 3*0 Definitions 4, 0 Participating Organizations
5. 0 Construction Test Phase 5, l General
5. 2 Responsibilities
5. 3 Release for Preoperational Testing
6. 0 Preoperational Test Phase 6 .1 General
6. 2 Respons bili ties
6. 3 Release for Startup Testing 7, 0 Startup Test Phase 7 .1 General 7, 2 Responsibilities
7. 3 Startup Release Points
8. 0 Attachments

I SURRY UNITS 1 AND 2 VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA

1. 0 PURPOSE AND SCOPE 1.1 To provide a procedure for the accomplishment of the tests and checks to be completed prior to plant operations.
1. 2 To define the phases of the Integrated Startup Test program.
1. 3 To define the responsibilities of the organizations participating in the Integrated Startup Test program.
1. 4 To provide the necessary administrative controls to ensure all pre-requisites are complete prior to commencing the next phase of test-ing.
1. 5 To define responsibilies for the preparation of test procedures and test matrices.

2 .0 REFERENCES

  • 2.1
2. 2
2. 3 ES-119, Equipment and System Tagging, Surry Power Station Units Nos. 1 and 2 VEPCO Nuclear Power Station Quality Assurance Manual Stone & Webster Logic Diagrams and System Descriptions
2. 4 VEPCO Calibration Procedures
2. 5 Final Design Change Packages for each modification 3.0 DEFINITIONS 3 .1 Phases of the Integrated Startup Test Program The Integrated Startup Test program is divided into three phases:

Construction Tests, Preoperational Tests and Startup Tests. The objectives and responsibilities of each phase are defined below.

The Construction tests are under the direction of the Release Coordi-nator and are designed to assure proper construction of modified or new systems. Construction deficiencies are resolved by the Release Coordinator

  • I The Preoperational Tests are under the direction of the Startup Group and are designed to assure proper functioning of new, modified and existing equipment, subsystems and systems.

The Startup Tests are under the direction of Station Operations and are designed to assure the proper integrated operation of all re-quired systems prior to the next sequence of power operation.

3. 2 General Electrical, Instrument and Mechanical Test Procedures These procedures are referred to as TEP's TIP's and TMP's. These generic procedures are approved by the Station Nuclear Safety and Operating Committee and are used to verify proper installation and initial operability of equipment. These procedures are used during the Construction Test phase and Preoperation Test phase.
3. 3 Cleaning And Flushing
3. 3 .1 Cleaning Procedures Cleaning will be performed in accordance with issued guides and general procedures to ensure satisfactory cleanliness of systems and components. Cleaning will include mechanical cleaning and hand cleaning, The Station Nuclear Safety and Operating Committee shall designate cleanliness grades for individual systems via approved design change packages *
3. 3. 2 Flushing Procedures A written procedure to ensure strict compliance with cleanli-ness requirements for nuclear steam supply and safety related systems. Station Nuclear Safety and Operating Com-mittee approval is required for generic flushing procedures and design change controlling procedures.
3. 4 Electrical Checks Checks performed as part of design change package to ensure that an instrument or electrical control loop is complete and correctly connected. These checks shall include, but not be limited to, breaker tests, insulation tests, and motor control center tests to ensure the integrity of the control circuit or equipment.
3. 5 Mechanical Checks A set of checks performed for the purpose of verifying that a piece of mechnical equipment (pump, compressor, blower, etc.) is ready for initial startup. These checks shall include, but not be limited to, alignment, coupling, manufacturers' recommended lubri-cation, packing gland adjustment, etc., as applicable for the equip:-

ment being readied for startup *

  • 3. 6 Hydrostatic Test Pressure testing to meet the applicable erection code and to ensure

I system integrity. The Station Nuclear Safety and Operating Com-mittee approval is required for these generic procedures.

3.7 Calibration Quantitative adjustments of instruments and control devices, includ-ing characterization of analog signals, quantitive setting on all control and monitoring loop elements and verification of response characteristics.

It also applies to those calibration checks which verify quantitive accuracy and functional integrity of the devices or instruments loop previously calibrateq. by others, or to verify functional inte-grity of the devices or instruments which are not adjustable by normal means, such as thermocouples, conductivity cells, thermo-meters, etc.

3. 8 Calibrated Loop Check A set of tests performed for the purpose of verifying that an in-strument loop is acceptable in terms of quantitive agreements, proper inter-relationship, and expected responsiveness of several loop elements. This set of tests is performed with all loop com-ponents in place, individually calibrated and documented, and devices energized by applying simulated inputs and measuring or
  • 3 *9 observing loop performance .

Functional Loop Check A set of tests performed for the purpose of verifing that a control and/ or telemetering loop is acceptable in terms of functional in-tegrity and interrelationship of the several loop elements. This set of tests is performed with all loop components in place, structurally complete, and engergized, by applying simulated inputs and observ-ing loop performance. Loop elements need not be individually calibrated.

3 .10 VEPCO Electrical Check-Out VEPCO electricians, for 480 V circuit breakers, will perform contact inspection, dashpot and mechanism inspection, set trip valves with multi-amp tester, and megger insulation. For 4160V, they will perform contact and mechanism inspection and check trip and close times with analyzer. Additionally, dielectric checks will be made on 4160V cables, doble tests and ratio 4160 / 480V transformers and doble test 4160V circuit breakers.

3 .11 Preoperational Check-Out Test of an individual item of equipment, subsystem or minor system to verify readiness for operations *

  • 3 .12 Operating Procedure (OP)

A station procedure developed by VEPCO and approved by the

I Station Nuclear Safety and Operating Committee for normal opera-tion of equipment and systems.

3 .13 Periodic Test Procedure (PT)

A station procedure developed by Vepco and approved by the Station Nuclear Safety and Operating Committee to meet Tech.

Spec. or surveillance requirements for operability.

3.14 Special Test Procedure (ST)

A station procedure developed by Vepco and approved by the Station Nuclear Safety and Operating Committee to obtain data, associated equipment performance, or other technical data required for engineering or operational evaluation.

3 .15 Functional System Operability Procedure ( FSOP)

A procedure developed by the Startup Group to verify and docu-ment the functional operation of equipment and/or controls. It will verify and document the functional operation of critical controls.

FSOP's are generally written to utilize existing logic diagrams.

3.16 Electrical, Instrument and Mechanical Maintenance Procedures And Maintenance Operability Procedure

  • These generic station procedures are referred to as EMP's, IMP's, MMP's and MOP's. These procedures are used by station person-nel to checkout previously installed equipment that has undergone maintenance and to remove and replace safety related equipment in service.

3 .17 Test Matrix A matrix that indicates which TEP, TIP, TMP, and/or existing station procedure (OP, PT, ST, IMP, EMP, MMP or MOP) will be performed on an individual test loop, instrument, valve, device or component.

4.0 PARTICIPATING ORGANIZATIONS AND RESPONSIBILITIES 4.1 Station Nuclear Safety and Operating Committee Consisting of representatives from Surry Power Station as desig-nated in the Vepco Nuclear Power Station Q. A. Manual. The Station Nuclear Safety and Operating Committee reviews and approves all test procedures. The committee reviews a summary of test results and approves release of the next phase of Startup Testing.

4.2 VEPCO Operating Staff Consists of VEPCO employees engaged in the operation and main-tenance of systems, subsystems, or portions of the station under the supervision of the station manager.

I VEPCO Operating Staff may witness Construction tests as desired for correct operation, testing and verification of design performance during final construction testing. VEPCO Operating Staff will per-form necessary and timely inspections and perform evaluations as necessary to effect a smooth release of systems for Preoperational testing.

VEPCO Operating Staff will conduct Preoperational and Startup test-ing and is responsible for the operation of the plant and the per-manently installed plant process equipment connected to an ener-gized power source.

4. 3 Westinghouse Electric Corporation (W)

The term Westinghouse or W shall be limited to equipment and services furnished as part of or under the contract for the nuclear steam supply and turbine generator systems.

4.4 NUS Corporation (NUS)

The term NUS shall be limited to equipment and services furnished as a part of or under the contract between Vepco and NUS Corpora-tion. NUS shall furnish engineering services where required by Vepco.

4. 5 Stone & Webster Engineering Cor oration - Engineerin Department S&W-BOSTON S&W shall furnish engineering services where required by VEPCO.
4. 6 Daniel Construction Company ( Daniel)

Daniel shall furnish construction services as required by Vepco.

4. 7 Vepco Project Engineers This group of engineers is responsible to resolve component and system deficiencies discovered during the Construction Test and Preoperational Test phases.
4. 8 Quality Control Consists of Quality Control related functions as defined in approved design change packages and test procedures.

4.8.1 Vepco SGRP Q.C.

This group is responsible for quality control for all con-struction work and construction testing as defined in the Vepco Nuclear Power Station Quality Assurance Manual.

Daniel Q. C. supplements Vepco Construction Q. A, as directed by Vepco .

  • 4. 8. 2 Vepco Station Q. C.

This group is responsible for quality control during the Preoperation Test phase and Startup Test phase. The level and extent of Q. C. coverage is defined in the individual procedure,

4. 9 Startup Group The Startup Group is responsible for the development and implemen-tation of the Integrated Startup Test program. It consists of S &

W Advisory Engineers under the direction of the S & W Lead Advisory Engineer and designated VEPCO operators under the direction of the designated VEPCO Shift Supervisor each responsible to the Station Superintendent of Operations.

The S & W Lead Advisory Engineer is responsible for the implemen-tation of the Integrated Startup Test program described herein and as outlined in station directives and applicable regulatory guides.

In conjunction with the VEPCO Shift Supervisor, he will provide the technical direction and expertise to ensure the timely completion of the required testing. He will also be responsible for the develop-ment and management of the necessary documentation to support the Integrated Startup Test program.

The designated VEPCO Shift Supervisor is responsible for the execution of the Integrated Startup Test program. He will provide coordination with the operating staff for the safe operation and the interfacing of existing plant systems to support the Integrated Startup Test program. In conjunction with the Lead Advisory En-gineer, he will direct the assigned personnel and provide operational guidance to ensure the timely completion of the required testing.

The Startup Group is responsible for conducting the test and checks under their jurisdiction. The group will ensure that all required test procedures and test matrices are developed and are available for use. The Startup Group is responsible for assuring all tests in the Integrated Startup Test program are performed in accordance with approved test procedures and for reviewing and approving all test data through the Preoperational Test Phase. The group is responsible that all design change test procedures and test matrices are written and approved to support Construction, Preopera-tional and Startup testing. The group is responsible for records management for the Preoperational and Startup Test phases.

4 .10 VEPCO Construction Staff The construction program is functioning under the direction of two resident engineers, the Resident Engineer for the Steam Generator Replacement Project (SGRP) and the Resident Engineer for the Production Operation Modifications ( P. 0. M.) .

  • The Resident Engineer (SGRP) will be responsible for all rework associated with the Stearn Generator Replacement Project.

-- -- -- --~----- - -, - ---- --*----------------**------------~- --~----- ---~--- -----------*----

I All the rework associated with the other modfications and the Construction Test phase will be the responsibility of the Resident Engineer (P. 0 .M.) who is designated the Release Coordinator.

The Release Coordinator is responsible to the Superintendent of Operations for the Construction Test phase.

4.11 VEPCO Construction Test Group ( CTG)

The Construction Test Group is composed of designated individuals from each organization participating in the construction program,-

and is directed by the Release Coordinator.

The CTG is responsible for timely completion of all segments of the Construction Test phase. Also, the CTG will provide support, as required, to the Startup Group during the Preoperational and Startup Test phase.

4, 12 Superintendent of Operations The overall responsibility for the direction and management of the Integrated Startup Test program is under the control of the Station Superintendent of Operations. The responsiblity for the direction and management within the Construction Test and* Pre-operational Test phases is assigned to the Release Coordinator and Startup Group respectively .

  • 4 .13 Startup Coordinator The Startup Coordinator works directly for the Superintendent of Operations. His sole responsibility is to ensure the smooth day-to-da y operation of all phases of the Integrated Startup Test program.

4.14 Superintendent of Technical Services The Superintendent of Technical Services will provide the required engineering review and analysis of the Integrated Startup Test Program. He will be responsible for the development, safety analysis, engineering review and analysis of the selected Preopera-tional tests and the major Startup tests.

5.0 CONSTRUCTION TEST PHASE 5.1 General The Construction Test Phase for new and modified systems is the responsibility of the Release Coordinator and will be accomplished by construction personnel. The Construction Test Phase includes all nondynamic tests and checks included in the design change package to verify proper installation of equipment. A list of unre-

  • solved system deficiencies will be recorded during the test period and transmitted to the Startup Test Group with the system release.

All systems will be released as soon as possible to support pre-operational tests.

I All activities of the Construction Test Phase shall be performed in accordance with specifications and design change packages and other approved procedures, as applicable.

The tests associated with this phase include: insulation resistance measurements, control circuitry checkout, low-voltage switchgear inspection, MOV (static) checkout, Circuit breaker and overload checkout (Vepco A & C), 480V MCC inspection, I & C electrical checkout, I & C mechanical checkout, annunciatior checkout, heat trace checkout and general hydrostatic tests.

5. 2 Responsibilities 5.2.1 Vepco Construction Staff
5. 2 .1.1 Construction Test Group Works directly for the Release Coordinator and in conjunction with the Startup Group and is responsi-ble for ensuring the timely completion and testing of systems and components, The group is addi-tionally responsible for correction of outstanding construction deficiencies found as a result of accep-tance tests, or Q, C. inspection during the next phase of testing .
  • 5.2.1.2 All Category I deficiency corrections shall be docu-mented by a Daniel or VEPCO generated noncon-formance report.

Release Coordinator The responsibilities of the Release Coordinator are assigned to the PO&M

  • Resident Engineer for new and modified .systems.

He is responsible for seeing that System Releases are promptly processed and he will maintain a status of all outstanding design change deficiencies.

For operating systems that did not require modifica-tions, the Startup Group will maintain the status.

5.2.1.3 Responsible System Engineer As the Construction Test phase of the Design Change Package is completed, the responsible construction System Engineer will walkdown the release and ensure that all work has been completed and the system is ready for initial operation and Preoperational testing. Any items that are found to be incomplete shall be documented on a Deficiency List. Those deficiencies that limit Preoperational testing will be resolved prior to System Release.

I 5 , 2. 2 Startup Group The Startup Group is responsible to provide technical advice in the preparation of systems and components to support planned Construction Tests.

The Startup Group is responsible for assuring that all Elec-trical, Mechanical and Instrument Construction tests are performed in accordance with established test procedures (TEP, TIP and TMP's) and for reviewing and verifying com-pleteness of all test data. It is also responsible for writing additional detailed procedures as needed for implementation of general procedures. It will be responsible for obtaining resolutions for all deficiencies, The Startup Group shall verify that a System released by the Release Coordinator has reached a point of construction completion to be accepted for Preoperational testing.

5.2.3 Vepco Construction Quality Control Shall perform required inspections and audits to assure that the Construction Test Program is conducted in accordance with the design change packages.

5.2.4 Vepco Station Quality Control VEPCO station QC shall ensure the requirements for system documentation of the Station Nuclear Safety and Operating Cammi ttee are met, 5, 3 Release For Preoperational Testing When construction testing on a system or subsystem thereof is complete, the responsible system engineer will perform a walkdown of the system to ensure completion, markup II as-built" conditions on DC package drawings and generate a 1 deficiency list based on the test results and visual inspection.

The* system is presented to the Startup Group for Preoperational Testing via a (Design Change-Construction) System Release form

( Attachment 8 .1) and a Deficiency Punch List ( Attachment 8, 2).

The Startup Group either "accepts" or "rejects" the system release, A rejected system release is returned to the Release Coordinator for completion of Preoperational Test limiting deficiences, 6.0 PREOPERATIONAL TEST PHASE 6.1 General

  • When a system or subsystem is sufficiently complete and other re-lated systems have progressed for enough so it can perform its

I assigned function, the Startup Group, accepts the released system for Preoperational Testing.

Prior to signing the system release form ( Attachment 8 .1), the Startup Group will make a thorough review of all the attached documents and a member of the Startup Group will walkdown the system to insure that there is no outstanding item that will affect safe operation of equipment or system. If any items are found to be unsatisfactory the required acceptance signatures will then be withheld by the Startup Group until these items are resolved.

The Preoperational Test Phase for modified, new and existing systems is the responsibility of the Startup Group and will be accomplished by Vepco operations staff supplemented by construction personnel.

As the system releases for new and modified systems are accepted by the Startup Group, the required Preoperational testing will begin. During this phase, field changes will be generated to resolve problems discovered during testing and operations, These field changes will be forwarded to Release Coordinator for resolution and implementation. Any rework that is needed will be controlled by a "Rework Control Form" (Attachment 8.3) issued by the Start-up Group listing the required retests.

System release forms will be generated by the Startup Group for all remaining systems associated. with the Unit. The existing systems not associated with design changes can be classified as follows:

remained in service, removed from service for maintenance and re ...

turned to service, did not remain in service and is in the area of design change construction, and did not remain in the service but is not in an area affected by design change construction, The extent and level of testing assigned by the Startup Group to testing of these systems will be based on this classification.

Vepco I & C will calibrate instruments and controls as the precali-bration tests are completed by the Startup Group.

Preoperational testing includes all designated tests procedures (TIP, TEP and TMP) along with applicable station procedures (ST, PT, OP, MOP, EMP, IMP, MMP).

The tests associated with this phase include: dynamic MOV check-out, uncoupled and coupled motor runs, uncoupled and coupled vibration tests, I & C functional checkout, AOV / AOD setup and checkout, I & C hydrostatic test, AOV / AOD dynamic checkout, air balancing, pump curve verification, flushing and FSOP 1S.

I I

6. 2 Responsibilities 6.2.1 Construction Test Group
  • Responsible as noted on the Deficiency Punch List (Attach-ment 8. 2) for correction of construction deficiencies found as a result of testing or Q
  • C, inspection.

/

I 6, 2, 2 Startup Group The Startup Group is responsible for: ensuring the timely Preoperational testing of systems and components., documen-tation of discrepancies determined during testing; maintain-ing a status of all outstanding deficiencies for existing systems that did not require modification, providing technical direction in the preparation of systems and components to support planned Preoperational tests, assuring that all Electrical, Mechancial and Instrument tests are performed in accordance with established test procedures, (TEP, TIP and TMP's), reviewing and approving of all test data, writing additional detailed procedures as needed for implmentation of general procedures and obtaining resolutions for all defi-ciencies. The group will also be responsible for initial I & C and electrical setup of new equipment.

The Startup Group shall be responsible for determining if a system has reached a point where it can be presented to the Station for approval for unrestricted operation.

6.2.3 Vepco Station Quality Control This group shall perform required inspections and audits to assure that the Preoperational Test phase is conducted in accordance with the approved procedures

  • Vepco Station Q , C, shall ensure the requirements for system documentation of the Station Nuclear Safety and Operating Committee are met.

6.2.4 Vepco I & C and Electrical These groups shall perform calibration and maintenance on equipment per system test matrices. All TIP and TEP data sheets will be completed and returned to the Startup Group, 6, 3 Release For Startup Testing Upon successful completion of all Preoperational tests, the Startup Group will review all system documentation and test data as re-quired to verify the functional operability of the system, The Startup Group system engineer will walkdown the equipment to ensure the system is* ready for unrestricted operations by the station.

Any items found to be incomplete but not limiting for unrestricted operation will be documented on the Deficiency Punch List ( Attach-ment 8, 2). The Startup Group will then sign the System Release form (Attachment 8.1), The System Release and the required documentation will then be turned over to the Startup Coordinator for review and acceptance .

  • - - - -- -- ---=--------***----_-_-_-_ -

I Prior to the Superintendent of Operations review of the system, the Station Quality Control Department will review the documentation to insure that all documents are complete. Any deficient items will be turned back to the Startup Group for resolution. Upon completion and acceptable audit, the Station Quality Control Department will sign the required signature block on the release. The Station Superintendent of Operations will then review the deficiency list to approve the items to be carried on the Master Deficiency List. Any items that are not acceptable will be returned to the Startup Group for resolution. When all deficient items are acceptable to the Station Superintendent of Operations, he will then sign the transmittal accepting the Release for the Station allowing Unrestricted Opera-tions of the system.

7.0 ST ART UP TEST PHASE 7 .1 General When a system has completed Preoperational testing and is accepted by the station for unrestricted operations it is ready for Startup testing. Prior to initiation of the Startup Test phase the Station Nuclear Safety and Operating Committee will review the systems that are available for unrestricted operation to ensure safe operation and testing conditions.

The first event is fuel loading. The sequence for subsequent Startup testing is determined by the Integrated Startup Test Sche-dule and the initial conditions and prerequisites of the station startup procedures.

The Station Nuclear Safety and Operating Committee will review the status of systems and test results at major milestones throughout the Startup Test phase. At no time will the safety of the plant be totally dependent on the performance of untested structures, systems or components.

The comprehensive Startup Testing phase is to ensure that equip-ment and systems perform in accordance with design criteria. This phase includes tests, adjustments, calibrations, and system opera-tions necessary to ensure that criticality and subsequent power operation can be safely undertaken. These procedures will be normal station startup procedures, PT's, OP's supplemented as required by Special Tests.

Preoperational tests are performed to verify as near as possible, the performance of the system under actual operating conditions.

Where required, simulated signals or inputs are used to verify the full operating range of the system and to calibrate and align the systems and instruments at these conditions. During Startup testing, systems and instruments that are used for normal opera-tions are verified and calibrated under actual operating conditions.

Systems that are not used during normal plant operation, but must be in a state of readiness to perform safety functions, are checked under test conditions prior to unit startup.

e 7. 2 Responsibilities

7. 2 .1 VEPCO Operating Staff Virginia Electric and Power Company has the overall respon-sibility for development, supervis10n, performance, and documentation of all Startup Testing at the Surry Power Station. Test preparation and all test performance during Startup Testing are under control of VEPCO to ensure proper and effective emphasis is maintained on personnel and plant safety by all individuals participating in the testing program.

The Superintendent of Technical Services will be responsible for providing the safety analysis for all major tests and will provide engineering review and coverage to ensure the con-duct of the major tests satisfies the necessary design and safety criteria.

7. 2. 2 Startup Test Group The Startup Test Group will act as advisers and consultants to the VEPCO staff in all areas of the Startup Testing.
7. 3 Startup Release Points The following milestones in the Startup Test phase of the Integrated Startup Test Program Schedule require Station Nuclear Safety and Operating Committee review and approval prior to implementation:
a. Fuel Loading
b. Hot Functional Testing
c. Criticality and Low Power Physics Testing
d. Power Range Testing
e. Extended Full Power Operation The Startup Group and the Station Operations department will be responsible to present evidence that all required testing is success-fully complete and proper documentation available.

8.0 ATTACHMENTS 8 .1 Equipment Release for Checkout and Operation

8. 2 Deficiency Punch List
8. 3 Rework Control Form
8. 4 Overall System Test Matrix
8. 5 Test Program Flow Chart
8. 6 Organization Chart
8. 7 List of Construction and Preoperational Tests

.ATTACHMENT 8.1 SURRY POWER STATION UNIT NO.

SYSTEM RELEASE FOR PRF~l'ERATIONAL TESTING AND UNRESTRICTED OPERATI.ONS SYSTEM NO.

DESCRIPTION OF EQUIPMENT:

THE ATTACHMENTS WITH THIS RELEASE ARE INTENDED TO INDICATE THE BOUNDARIES OF THIS RELEASE. FUTURE CHANGES THAT MAY BE MADE TO THIS SYSTEM ARE INTENDED TO BE CON-SIDERED A PART OF THIS RELEASE IF WITHIN THESE ESTABLISHED BOUNDARIES.

ATTACHMENTS DEFINING. BOUNDARIES:

RELEASED FOR PREOPERATIONAL TESTING:

Daniel's Proj. Mgr/Asst. Proj. Mgr. Date SEO Project Engineer Date e Vepco Q. C. Date Release Coordinator Date The Following Items Are Attached:

Test Matrix Completed Construction Tests Construction Deficiency List ----

ACCEPTED FOR PREOPERATIONAL TESTING:

Vepco S/U Supervisor Date Lead Advisory Engineer Date All Documentation Received: (Initials)

RELEASED FOR UNRESTRICTED OPERATIONS:

Vepco S/U Supervisor Date Lead Advisory Engineer Date Vepco Q. C. Date The Following Items Are Attached:

Test Matrix Completed Construction Tests e Completed Pre-Op Tests Master Deficiency List ACCEPTED FOR UNRESTRICTED OPERATIONS:

S/U Coordinator Date Supt. of Operations Date

s~s. tio.

'JEPCO

.- ATTACHMENT 8. 2

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  • ATTACHMENT 8. 3 R!:'N O~l< CO NT!< Oi. FORM RCF = .-* ----

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~-----*-*-*------.-*--------*---***** ..

EQUl?,"EN*r1'CO'\PONEN-,

IV ystem Number EQUIPMENT S::R!AL.:::

i------:---------i------------+-----------+--------------

DRAWING/REVISION SPECIFICATION/REV. LOCATION F.C. ATTACHED YES D NO 0 REASON FOR REWORK:

WORK DESCRIPTION:

RETEST REQUIREMENTS:

ADVISORY ENGINEER DATE:

AUTHORIZATION FOR DISASSEMBLY ACKNOWLEGMENT 1------------~---=---------1,------------1-----------**

' ADVISORY ENGINEER FIELD QUALITY CONTROL R!:SIDENT ENGINEER REWORK COMPLETION STATUS REASSEMBLY RETESTS COMPLETE REASSEMBLY RETEST INSPECTIONS COMPLETE INSPECTIONS COMPLETE COMPLETE

+------- ----

Release DATE ADVISORY DATE FQC DATE FQC DAT e Coordinator ENGINE::R INSPECTION CHECKLIST ATTA.CHED YES D NO 0

Attachment 8.4 Page 1 of 5

  • SURRY POWER STATION UNIT NO. 2 SYSTEM MATRIX QUALITY.

SYSTEM NO. SYSTEM GROUP BASIS FOR TESTING 2-2-2-1 Gire. Water- affected by design change construction 2-2-2-2 Water Box Vac. Prim. affected by design change construction 2-2...:2-3 Gire. Water & Serv. Wtr. Rad. I remained in service Monitors 2-2-3-1 Disch. Vac. Prim. remained in service 2-2-4-1 Screen Wash Pps & Traveling affected by maintenance Screen 2-2-5-1 Condenser Tube Cleaning affected by design change construction 2-2-6-1 H.P. Heater Drain in the area of design change construction 2-3-1-1 Main Steam I affected by design change construction 2-3-2-1 Extraction Steam in the area of design change construction 2-3-3-1 Aux. Steam in the area of design change construction 2-3-3-2 Aux. Boiler & Controls remained in service 2-3-3-3 Fuel Oil Sys. I in the area of design change construction 2-4-1-1 Condensate Storage Tk affected by design change construction 2-4-1-2 Main Condenser affected by design change construction a-4-1-3 Condensate Sys. affected by design change construction W-4-2-1 L. P. Htr. Drns. affected by design change construction 2-4-2-2 Secondary Misc. Drns. in the area of design change construction 2-4-3 Condensate Polishing System affected by design change construction 2-4-3-1 C.P.S. SWGR & MCC's 2-4-3-2 Neutralization Sumps 2-4-3-3 Low Conductivity Sumps 2-4-3-4 Instrument Air Hdr.

2-4-3-5 C.P.S. Control Pnl (Interior) 2-4-3-6 Condensate By-Pass 2-4-3-7 Condenser Connection #57 2-4-3-8 Connecting Piping Turb.

Bldg.

2-4-3-9 Demineralizers 2-4-3-10 Resin. In/Out Demins.

2-4-3-11 8 11 Piping Demin. to Cond.

2-4-3-12 4 11 Piping Demin to L. C.

Sumps 2-4-3-13 Regen. & Demin. Piping to Sumps 2-4-3-14 Sluice Water & Air to Demin.

2-4-3-15 Air to Demin. Vessels 2-4-3-16 Regen. Vessels 2-4-3-17 Acid to Cation Vessel A-4-3-18 Caustic to Anion Vessel

  • -4-3-19 Water Rec. to Regen.

Vessels 2-4-3-20 Air Compressor 2-4-3-21 Air Compressor Cooling

-f **

Attachment 8.4 Page 2 of 5 e QUALITY SYSTEM NO. SYSTEM GROUP BASIS FOR TESTING 2-4-3-22 Water Recovery Tank 2-4-3-23 Spare 2 4-3-24 Regen Vessels Air Blower 2-4-3-25 Neut. Sumps Pumps to PND 2-4-3-26 Low Cond. Sump Pumps 2-4-3-27 Filters & Piping to CW Tunnel 2-4-3-28 Caustic Recovery Tk 2-4-3-29 Acid Rec. Tk 2-4-3-30 Aux. Control Pand 2-4-3-31 Fire Control Sys.

2-4-3-32 Floor Drainage 2-4-3-33 Caustic Storage 2-4-3-34 Acid Storage 2-4-3-35 Ammonia Storage 2-4-3-36 Ammonia to Anion Vessel

& Ammonia System 2-4-3-37 Neut. Caustic & Acid Feed Pumps 2-4-3-38 Sampling System 2-4-3-39 Heat Trace Sys.

4-3-40 Building Release

  • 4-3-41 URC 2-4-3-42 Control RM A/C 2-4-3-43 NUS Area Blowdown Fans 2-4-3-44 Main Bldg. Vent.

2-4-3-45 Storage Area Vent.

2-4-3-46 Misc. Fans 2-5-1-1 Cond. Air Removal in the area of design change construction 2-6-1-1 Feedwater affected by design change construction 2-6-3-1 Stm. Gen. Blowdown I affected by design change construction 2-6-4-1 Aux. Feedwater I in the area of design change construction 2-7-1-1 Radiation Monitors I remained in service 2-7-1-2 Manipulator Rad. Monitors affected by design change construction 2-7-2-1 CRD-MG Sets, Full I affected by design change construction Rod Controls 2-7-3-1 Nuclear Instrumentation I remained in service 2-7-4-1 Incore Instrumentation I in the area of design change construction 2-7-5-1 Rod Position Indication Racks I affected by design change construction

& Controls, RPI Indicators Systems & Controls 2-7-6-1 Solid State Protection Aux. I remained in service Relay Rack Input Logic &

Output Cabinets 2-7-6-2 Safeguards Test Cabinets & I remained in service Aux. Relay Circuits 67-6-3 Aux. Relay Cabinets & Panels remained in service

  • 9-1-1 Component Cooling I in the area of design change construction 2-9-2-1 Chilled Comp. Cooling I affected by design change construction 2-9-3-1 Chilled Water affected by design change construction

Attachment 8.4 Page 3 of 5 eSYSTEM NO. SYSTEM QUALITY GROUP BASIS FOR TESTING 2-9-4-1 Neutron Shield TK Cooling I affected by design change construction 2-9-5-1 Service Water I affected by design change construction 2-9-5-2 Service Water to R.S.Ht. Exch. I in the area of design change construction 2-9-5-3 Service Water to CH Pumps Coolers I remained in service 2-9-6-1 Bearing Cooling remained in service 2-12-1-1 Instrument Air Compressor remained in service 2-12-1-2 Instrument Air Sys. in the area of design change construction 2-12-2-1 Service Air Compressor remained in service 2-12-2-2 Service Air System in the area of design change construction 2-12-3-1 Containment Instru. Air. affected by design change construction 2 12-4-1 Air Start - Emerg. Diesels I remained in service 2-13-1-1 Chemical Feed affected by design change construction 2-13-2-1 Flash Evap. System affected by design change construction 2-13-2-2 Unit #2 M/U Demin.

2-13-2-3 Unit #2 Acid Supply 2-13-2-4 Unit #2 Caustic Supply 2-13-2-5 M/U & Dilution Water 2-13-2-6 #3 Demin.

~-13-3-1 M/U & Filtered Water TK

~-13-3-2 Influent & Effluent

~-13-3-3 Air Supply

~-13-3-4 Surface Wash 13-3-5 Backwash & Backwash Sump

  • 13-3-6 Evaporator Makeup

~-13-4-1 Caustic Supply - Waste Neut.

~-13-4-2 Acid Supply - Waste Neut.

~-13-4-3 Waste Neut. Supply from Demin. Sump

~-13-4-4 Waste Neut. Sys.

~-13-5-1 Distilate - Dilut. & Demin.

Supply

~-13-5-2 Distillate Truck Loading

~-13-5-3 Distillate - Cond. Pol.

Regen.

~-13-5-4 Distillate - Seal Water

~-13-6-1 Polyner Sys.

~-13-6-2 Hypochlorite Sys.

2-13-7-2 Unit 2 Blowdown Treat.

2-13-7-3 Drain TK & Stor. Area 2-14-1-1 Nitrogen Supply affected by design change construction 2-14-1-2 Hydrogen Supply remained in service

~-15-1-1 Fire Protection Pumps & Control I remained in service 2-15-1-2 Sprinkler & Deluge remained in service 2-15-1-3 Hose Reel Stations remained in service 2-15-3-1 Lo. Press. co Cable Vault remained in service 2-15-3-2 Lo. Press. Co 2 Emerg. Gen. remained in service 2-15-3-3 Lo. Press. Co 2 Charc. Filters remained in service 2

.15-3-4 Lo. Press. co - Turb. Gen. affected by maintenace 915-3-5 Lo. Press. Co 2 - Exciter affected by maintenance 2

2-15-3-6 Lo. Press. co Cable Trays remained in service 2

Attachment 8.4 Page 4 of 5 e QUALITY SYSTEM NO. SYSTEM GROUP BASIS FOR TESTING 2-15-5-1 Smoke Detector - Control Rm remained in service 2-15-5-2 Smoke Detector - System remained in service 2-15-5-3 Radiant Heat Sensors remained in service 2-16-1-2 Turb. Gen. Gland Stm & Seals affected by maintenance 2-16-2-1 Emgerg. Turb. Oil Pump remained in service 2-16-2-2 Bearing Oil Pump remained in service 2-16-2-3 HP Seal Oil Backup Pump remained in service 2-16-3-1 Turn. Lube Oil Sys. affected by maintenance 2-16-4-1 Turning Gear & Bearing Lift affected by maintenance 2-16-5-1 EH Control Fluids Sys. affected by maintenance 2-16-6-1 Generator Seal Oil remained in service 2-16-7-1 Generator H & co remained in service 2 2 2-16-8-1 Generator Leads remained in service 2-16-9-1 Main Gen. & Exciter & Controls affected by maintenance 2-16-9-2 Turbine Supervisory affected by maintenance 2-16-9-3 Main Turbine affected by maintenance 2-21-1-1 Turb. Plant Sampling remained in service 2-21-2-1 Reactor Sampling affected by design change construction 2-22-1-1 Station Transformers remained in service 2-22-4-1 4160V Busses & Controls affected by design change construction 2-22-5-1 Station Batteries & DC I remained in service Dist rib

  • 22-6-1 Emergency Diesels I remained in service
  • 22-7-1 480V Mcc's & Controls remained in service 2-22-7-2 480V Emerg. Bus & Mcc's I affected by design change construction 2-22-8-1 Vital Busses I remained in service 2-22-9-1 120V AC Distribution remained in service 2-22-10-1 Station Lighting remained in service 2-22-11-1 Heat Tracing (Borated Systems) I remained in service 2-22-11-2 Heat Tracing (NonBorated remained in service Systems) 2-22-12-1 Computer & Controls remained in service 2-22-13-1 Main Control Board (Unit 2) I remained in service 2-22-14-1 Secondary Plant Process Racks I remained in service 2-22-15-1 Primary Plant Process Racks I remained in service 2-22-16-1 RC#2 Electrical Penetrations I remained in service 2-23-5-2 Safeguards & Valve Pit Sumps remained in service 2-23-5-3 Containment Sumps affected by design change construction 2-23-5-4 Subsurface Sumps remained in service 2-23-5-5 RC Floor Drainage affected by design change construction 2-23-5-6 Turbine Sumps remained in service 2-24-1-1 CRD Cooling Fans I affected by design change construction 2-24-1-2 RC Air Recirc Fans I affected by design change construction 2-24-1-3 RC Iodine Fans I in the area of design change construction 2-24-1-4 Sfgd. Supply & Exhaust I remained in service 2-24-1-5 MCC Cable Vault Vent. remained in service 2-24-2-1 Switchgear Vent. remained in service 2-24-3-1 Turbine Exhaust remained in service A-24-4-2 Turbine Supply Air remained in service

~-24-6-1 Control & Relay Rm. A/C I remained in service 2-24-6-2 Control & Relay Rm. Vent. remained in service 2-24-7-1 Turb. Bldg. Stm. Heat in the area of design change construction

~----- -----*---

Attachment 8.4 Page 5 of 5 e SYSTEM NO. SYSTEM QUALITY GROUP BASIS FOR TESTING 2-24-7-2 Safeguard Bldg. Stm. Heat remained in service 2-24-8-1 RC Purge affected by design change construction 2-25-1-1 Reactor Coolant I affected by design change construction 2-26-1-3 Charging Letdown I in the area of design change construction 2-26-2-1 Charging High Head SI & Seal I in the area of design change construction Water

~-26-3-1 Boric Acid Storage & Controls I remained in service

~-26-3-2 Boric Acid Transfer I remained in service 2-26-3-3 Boric Acid Blender & Controls I remained in service 2-27-1-1 Low Head S. I. I affected by design change construction 2-27-1-2 S.I. Accumulators I in the area of design change construction 2-27-2-1 Residual Heat Removal I affected by design change construction 2-27-3-1 Containment Vacuum I in the area of design change construction 2-27-4-2 RWST Recirc. Pumps remained in service 2-27-4-3 Containment Spray I affected by design change construction 2-27-4-4 RWST I affected by design change construction 2-27-4-5 Chem. Add. TK I affected by design change construction 2-27-6-1 Outside Recirc. Spray I affected by design change construction 2-27-6-2 Inside Recirc. Spray I affected by design change construction 2-27-6-3 Post DBA H Recombiner in the area of design change construction 7

~-30~1-l Liquid Waste remained in service

~-30-2-1 Decontamination Sys. remained in service

  • -30-1-2 Liquid Waste Evaporation & remained in service Controls

~-30-3-1 Solid & Liquid Waste Drumming remained in service

~-30-4-1 Gaseous Waste I remained in service

~-30-4-2 Gaseous Waste Recombiners I remained in service

!2-30-5-1 Boron Recovery Gas Strippers I remained in service

~-30-5-2 Boron Recovery Evaps remained in service

~-30-5-3 Boron Recovery Sys. & Controls remained in service

~-30-6-1 Primary Grade Water remained in service

!:z:-30-6-2 PG Water to RC #2 in the area of design change construction 2-31-1-1 Primary Drains I affected by design change construction 2-31-4-1 Process Vents in the area of design change construction 2-33-1-1 Cont. L~akage Monitor remained in service 2-34-1-1 Refueling Purification affected by design change construction 2-34-1-2 Reactor Cavity affected by design change construction 2-34-1-3 Fuel Pit Cleanup & Cooling I remained in service 2-35-1-2 RC Elevator affected by design change construction 2-35-1-3 Personnel and Equipment Hatch I affected by design change construction 2-36-1-1 RC Polar Crane I affected by design change construction 2-36-1-2 RC Jib Cranes affected by design change construction 2-37-1-1 Fuel Transfer Sys. I in the area of design change construction 2-37-1-2 RC Cavity Manipulator Crane I affected by design change construction 2-38-1-1 S.G. Recirc. & Transfer affected by design change construction 2-40-1-1 Security Sys. affected by design change construction 2-41-1-1 Turb Bldg. affected by design change construction 2-42-1-1 Service Bldg. I remained in service

&-43-1-1 Aux. Bldg. I remained in service W-44-1-1 Reactor Containment I affected by design change construction 2-45-1-1 Excore Detectors I in the area of design change construction 2-46-1-1 Fuel Bldg. I remained in service 2-47-1-1 Decon. Bldg. I remained in service 2-48-1-1 Fire Pump House I remained in service

ATTACHMENT 8.5

- Perform Gonstr. Tests (TEP's, TIP's, hydros).,.-~~~,

as re uired b Conser. Forces Field Chang~s initiated as required SEO reviews, modifies, as required, approves Field Chan_ge rennests

"""',_._ _.___-tSEO returns Field Change to Constr. Forces for im lementation SEO review & approval 1-----~-i Const *. phase _of D.C. pkg on *system compl,.

SEO walk-down of system-. to insure completion and to generate deficiency*l-7-+-+-f'--r'-I~

list.

..?:~-- : ,, ..
  • >;{t;.t~.-~..;.:.';j sign-off Release Transmittal Release to Start-up Grp. with deficiency list, for PRE-OP TES ING

....----------------'Jlo,fStart-up Group reviews sys*tem* for*

ACCEPTANCE S/U Grp "Accepts" "Rejects" System returri Sys tell) to SEO for com-pletion of DISCREPANCIES S/U Grp. performs required,-...~~~~~~--~~--,

,---------iTEP 1 s, TIP's, TMP's for initial o eration VEPCO I & C S/U Grp performs require~ Field calibration as flushing and pump verification re uired.

performing require TEP's TIP's TMP's S/U Grp to perform necessary tests to insure proper functional opera- 1 of syste!ll* - bility of systems that may have been damaged during construction activities. 1 Review Released with deficiency list SU Grp sign-off system OPERATIONS for PLANT -~,......-~ transmittal.

START-UP

$ystem returned to .. OPERATIONS rejects OPERATIONS accepts S/U Grp for completio system sy~tem of discrepancies VEPCO Station & S/U Grp to perform re uired S/U Tests POWER OPERATION e

ATTACH~ 8.6 e ORGANIZATIONA. L CHART e *. ;-

INTEGRATED STARTUP TEST PROGRAM STATION SGRP MGR MGR SAFETY

COMMITTEE SUPT. SUPT. SUPT.

MAINT. TECH SER\i OPERATION: :

/ STARTUP / RELEASE COORD.

(MAINT. TEST) (I a C TESTS)

/* COORD.

(S/u , STARTUP

__ _JPROJECTENf __ -

1 - -1 CONST. CONST.

TEST TESTS GROUP GROUP ENG.

., (PREOP TESTS)

-__.ea.-

~CONST. TESTS)

MAINTENANO ~ INST. TECH OPERATIONS DANIEL

Attachment 8.7 CTG REQUIRED TESTS S/U GROUP REQUIRED TESTS CONSTRUCTION TEST PHASE PRE-OP TEST PHASE TEP-1 Insulation Resistance TEP-40 Dynamic MOV Checkout Measurements TEP-8 D.C. Motors TEP-7 Uncoupled Motor Runs TEP-2 Control Circuitry Checkout TEP-70 Coupled Motor Runs TEP-3 Low-Voltage Swgr TEP-llU Uncoupled Vibes Inspection TEP-llC Coupled Vibes TEP-4 Motor Operated Valve Check-Out (Static) TIP-3 I & C Functional Checkout TEP-5 (VEPCO A & C) Circuit TIP-4 AOV/AOD Setup and Checkout Bkr & 0/L's Checkout TIP-5 I & C Hydro TEP-9 Computer Point Checkout TIP-40 AOV/AOD Dynamic Checkout TIP-1 I & C Electrical Checkout TMP-2 Air Balancing TIP-2 I & C Mechanical TMP-3 Pump Curve Verification Checkout Flushing TMP-1 General Hydrostatic Tests FSOP's TEP-10 Annunciator Checkout TEP-12 Heat Trace Checkout

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