ML17341A766
| ML17341A766 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/23/1981 |
| From: | UHRIG R E FLORIDA POWER & LIGHT CO. |
| To: | VARGA S A Office of Nuclear Reactor Regulation |
| References | |
| L-81-535, NUDOCS 8112280502 | |
| Download: ML17341A766 (102) | |
Text
f REGULATORY iNFORMATION DISTRIBUTION SY rEM (RIDS)ACCE'SSION NBR:8112?80502 DOC~DATE;81/1'2/23 NOTARIZED:
NO.FAOIL:50 250 Turkey Point<Pl anti"Uni:t 3i Florida IPower and Li'ght>C AUTH BYNAME AUTHOR AFFILIATION UHRIGi'R,ED Florida IPower 8 Li,ght Co,!REICIP~NAME'REC IP IENT AF F IL'I ATION VARGAg"S~A~Operating Reactors Branch 1 S IZE:.NOTES:
SUBJECT:
'Submits integrated startup test!program-for insp L testing to be completed iprior to returning uni!t lto operation after~steam:generator
~repair,programiper Amend 69'to OL.'Apps Ai'Bp C 8 D encl, WB~DI'STRIBUTION CODE: A027S>COPIES!RECEIVED:LTR
.ENCL, TITLE: Reactor Star tup Tes,t Repor t~DOCKET 05000250 RECIPIENT ID CODE/NAPE ACTION;ORB 01 BC 01 INTERNAL: AEOD MPA 09 NRR/PHFS DEPY07 NRR/DHFS/PTRB11 NRR/DSI/GP8 12!COPIES LTT'R ENCL 3 3 1 1 1 1 1 1-1 1 1 1 RECIPIENT ID'CODE/NAYE IE 06 NRC'PDR 02 NRR/DHFS DIR 08 GCS 1'5 EG F E 00 COPIES LVTR ENCL'2.2-.1 1 1 1 1 0 1 1 EXTERNALS ACRS NSIC 13 05 1 1 1 L'P.DR NT.I S 03 1 1 1'1 LS+I 0 TOTAL NUMBER OF iCOPIES REQUI'RED:
L>TT'R 18 ENCL 17 i'I'a f 0~y 4 T
.O.BOX 529100 MIAMI, F L 33152 ygllzz~Office of Nuclear Reactor Regulation Attention:
Mr.Steven A.Varga, Chief Operating Reactors Branch No.Division of Licensing U.S.Nuclear Regulatory Commission Washington, D.C.2055
Dear Mr.Varga:
Re: Turkey Point Unit No.3 Docket No.50-250 Inte rated Startu ,Test Pro ram FLORIOA POWER&LIGHT COMPANY December 23, 1981 L-81-535 We are submitting, for your review, our Integrated Startup Test Program for inspection and testing to be completed prior to returning Turkey Point Unit No.3 to operation after the Steam Generator Repair Program.This letter is to meet the requirements of Amendment No.69 to the Operating License for Turkey Point Unit No.3 to submit the test program sixty days prior to fuel loading.The Integrated Startup Test Program is comprised of two phases: Preoperational Tests and Startup Tests.The format of the program follows the intent of Regulatory Guide 1.68, Revision 2, August, 1978,"Preoperational and Initial Startup Test Programs for Water-Cooled Power Reactors".
In some cases inter-pretation is necessary since Turkey Point Unit No.3 is a previously licensed PWR plant that has undergone major equipment repair and modification rather than being new construction.
The tests in the Preoperational Test phase are designed to provide assurance that components and subsystems of new, modified, and original systems function safely wi thin established design: criteria.The Preoperational Tests on a new or modified system are conducted prior to fuel loading.This test phase also allows the plant operating staff to become familiar with the operation of a new or modified system and to verify by trial use, to the extent practical, that the operating procedures are adequate.The hot functional test of the plant will be performed during this test phase.The tests in the Startup Test phase are designed to provide assurance that systems that were previously demonstrated as functioning safely, and the new or modified systems will function to"(1)provide for safe normal operation and high tolerance for systems malfunctions and transients, (2)ensure that, in the event of errors, malfunctions, and off-normal conditions, the reactor protection systems and other design features will arrest the event or limit its consequences to defined and acceptable levels, and (3)ensure that adequate safety margins exist for events of extremely'ow probability or for arbitrarily postulated hypothetical events without reduction in the safety margin for the protection of public health and safety".The Startup Tests are performed after fuel loading to confirm the design basis and demonstrate that the plant will continue to operate in accordance with design.4o>7 8ii2280502 6000260 8ii223 J t'DR~DOC" pDR S', t'.t PEOPLE...SERVING PEOPLE I~~
Office of Nuclear Reactor Regulation Page:Five
SUMMARY
Th'is letter outl.ines the Integrated Startup Test:Program we plan to implement to demonstrate our ability to safety, return Turkey Point Plant Unit.No.3 to power.The Integrated Startup Test'Program will provide the necessary assurance.
that the plant can be operated in accordance with design requirements and in a manner that will not endanger the heal.th and safety of the public.'Very truly yours, Robert, E.Uhrig Vi'ce'President Advanced Systems 8 Technol'ogy REU/JEM/ah cc: J.P.O'Reilly,.
Regional Administrator, Region II Harold F.Rei's, Esquire LIST OF APPENDICES APPENDIX A STARTUP NETWORK APPENDIX B LIST OF MA3OR PREOPERATIONAL TESTS AND CHECKS APPENDIX C LIST OF MA3OR STARTUP TESTS AND CHECKS APPENDIX D PROCEDURE FOR CONDUCTING THE INTEGRATED STARTUP PROGRAMlIKgLgWP ll0l',il:iLk 3'Oil'7'gli zz@c 62 I L r1 APPENDIX A STARTUP NETV/ORK l J'g f' Per Criterion 1 of Appendix A to 10 CFR 50 all structures, systems, and components will be tested or demonstrated operable to levels commensurate with the importance of the safety functions.
In addition, the extent of testing will vary directly with the amount of modifications done to and around the particular equipment or system.The sequence of tests will be conducted so that the safety of the plant is never totally dependent on the performance of untested structures, systems or components.
The key points of the Integrated Startup Test Program are presented below.The attached Appendices provide, additional details of the program.Further information is available for the NRC site inspector at the Turkey Point Plant.These Appendices are working documents that will be revised as required within the framework of this letter.ORGANIZATION Appendix D contains the"Procedure for Conducting the Integrated Startup Test Program for Post Steam Generator Repair and Design Changes".This document defines the organizations, responsibilities, actions, and administrative controls for each phase of the program.The management and direction of the Integrated Startup Test Program is under the direct control of Florida Power R Light Company (FPL)with principal authority assigned to the Plant Manager-Nuclear for Turkey Point Plant.The Startup Department is composed of FPL Nuclear Operations and Maintenance personnel with outside consultants as needed.The Startup Department has overall responsibility for implementation and documentation of the program.The conduct and direction of the tests in the Preoperational Test phase are controlled by the Startup Department.
The conduct and direction of the tests in the Startup Test phase are controlled by Turkey Point Operations staff with technical support from the Startup Department.
In all cases the test procedures require approval of the Plant Nuclear Safety Committee prior to implementation.
Deviations to approved test procedures are documented and become part of the final test results.Administrative controls for making changes to approved procedures are provided in existing plant procedures.
The acceptance criteria for all tests are approved by the Plant Nuclear Safety Committee.
Design related deficiencies are resolved by the Startup Department with the assistance of the FPL project engineer and Turkey Point operations or outside consultants as deemed necessary.
TEST PHASES Preoperational and Startup Test Phases are shown on the network in Appendix A and defined in more detail in Appendix D.Each phase of the Integrated Startup Test Program is composed of a series of tests as described below: l.Prep erational Test Phase The Preoperational Test Phase consists of flushes and hydrostatic and functional tests of new, modified and affected original equipment and systems with no fuel in the reactor.This phase also includes a walkdown of existing plant systems adjacent to construction work areas for possible damage.The Hot Functional Test includes heatup of the primary system to hot shutdown conditions, thermal expansion checks of l l Y I 1'tl)I I~II affected systems, vibration testing of construction affected equipment, reactor coolant pump coast dow'n time checks and primary system operational pressure test.A primary system flush and clean-up will be performed during the Hot Functional Test at the recommendation of the NSSS supplier and to meet primary system chemistry requirements.
Any repairs and subsequent testing will be accomplished as necessary prior to fuel loading and startup testing.Major milestones during the Preoperational Test phase are outlined in Appendix A.Major Preoperational Tests are listed in Appendix B.The actual sequence of individual tests is formulated prior to performance of the tests considering equipment and system availability.
The Startup Department analyzes the preoperational test results.The acceptable criteria for all tests are approved by the Plant Nuclear Safety Committee.
In instances where performance of components of systems deviates from predicted results, further engineering evaluations, rework, and/or retesting is performed to resolve the discrepancies before the test is considered satisfactory.
Assistance from the FPL project engineer and Turkey Point operations or outside consultants is solicited as deemed necessary.
Systems which have to be modified as a result of the Preoperational Test are retested to verify acceptable performance.
The major prefuel loading Preoperational Tests are outlined in Appendix B.Components and systems are tested and evaluated according to approved testing procedures.
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.
2.Startu Test Phase The major testing milestones during the Startup Test phase are identified on the network (Appendix A)and discussed below.Major Startup Tests are listed in Appendix C.a.Post-Fuel Loadin Tests Systems that are not used during normal plant operations, but must be in a state of readiness to perform safety functions, are tested or demonstrated operable prior to plant conditions requiring them to be available as defined in the Technical Specifications.
Fuel loading will begin after all prerequisite system tests and operations are satisfactorily completed.
Upon completion of fuel loading, the reactor upper internals and pressure vessel head are installed.
Additional mechanical and electrical tests are performed on the rod control system, rod position indication, and in-core moveable detector system.The purpose of this segment of the Startup Test Phase is to prepare the system for nuclear operation and to establish that all design requirements necessary for operation are achieved.b.Criticalit and Low Power Ph sics Tests On completion of integrated safeguards testing, nuclear operation of the reactor begins.These final segments of Startup Testing include criticality and low power I'v I~1."'~1.~r.i'~'(ix:.c)a c.t all J+H'4 physics testing.The purpose of these tests is to verify the operational characteristics of the unit and core, and to acquire data for the proper calibration of set points, and to ensure that operation is within license requirements.
Appendix C includes the major Startup Tests which are performed from fuel loading to rated power.The actual sequence of tests is formulated by the Turkey Point startup and operating personnel considering test requirements and equipment availability.
Procedures are prepared to specify the sequence of tests and measurements and the conditions under which each is to be performed to ensure safety of operation and consistency of the results obtained.If significant deviations from design calculation exist, unacceptable behavior is revealed, or apparent anomalies develop, the testing would be suspended and the situation reviewed to determine whether a question of safety is involved prior to resumption of testing.c.Power 0 eration After the operating characteristics of the reactor and unit have been verified by low power physics testing, the plant will be brought to full rated power level in accordance with existing plant procedures.
d.At Power Testin Upon reaching full rated power level, the following at power tests are performed:
final steam generator carryover testing, secondary plant heat balance checks, condensate polishing chemistry performance testing, and load rejection testing with the condensate polisher in service, when the system becomes available.
EXTENT OF TESTING All Unit No.3 systems and systems common to both Unit No.3 and Unit No.0 are included in the Integrated Startup Test Program.The tests required for individual components within a system will be developed by the Startup Department or will be performed in accordance with existing plant procedures.
The Procedure Index for existing plant procedures is included as an Attachment to Appendix D.In areas such as Unit No.3 containment, where extensive work has been performed, all nuclear safety related equipment and systems will be checked by visual inspection during the Preoperational Testing or Startup Testing phase.In other areas, such as the Auxiliary Building where little work has been performed, selected system walkdowns will be employed in conjunction with normal plant startup procedures to verify the operability of the equipment.
Those systems that are new or have undergone major design basis changes will undergo complete component testing and performance testing to verify design and installation.
The accelerated start up schedule may preclude completion of previously planned modifications.
All components will be tested upon completion to insure system reliability prior to being placed into service.
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APPENDIX A STARTUP NETWORK TURKEY POINT UNIT 3 Secondary Hydro Hot Functional Test and RCS Flush Primary Hydro Fuel Load Type B 4 C Leak Rate Testing Integrated Safeguards Test Criticality and Low Power Physics Test Full Load Oper atio Construction Phase Preoperational Test Phase Startup Test Phase Power Operation sl'V I I/Y 1 ll 1 I j l I 1'I I j II l 0 APPENDIX B LIST OF MA3OR PREOPERATIONAL TESTS AND CHECKS I 1 I e Page I of 6 APPENDIX B LIST OF PREOPERATIONAL TESTS AND CHECKS I.H YDROSTATIC TESTING TITLE OF TEST OR CHECK TEST OR CHECK OB3ECTIVE 1.Steam Generator Secondary Side Integrity Test To verify the integrity of secondary side and associated piping following the installation of the new steam generator lower assemblies.
II.HOT FUNCTIONAL TEST I.The hot functional test is performed in accordance with Hot Functional Test Sequencing Document.The Reactor Coolant System is tested using pump heat to reverify heat-up procedures and to demonstrate satisfactory performance of components and systems exposed to reactor coolant system temperature.
Proper operation of instrumentation, controllers, and alarms, is checked against design operation conditions of auxiliary systems and setpoints verif ied.Among the demonstrations performed are: 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 response to level changes.f.To check thermal expansion of selected system components and piping.g.To perform isothermal calibration of resistance temperature detectors and incore thermocouples.
h.To operationally check out the residual Heat Removal System.NOTE: The sequence of tests and checks following is not necessarily in the order that they will be performed during the Hot Functional Test.
l I 1 Wr Page 2 of 6 APPENDIX B LIST OF PREOPERATIONAL TESTS AND CHECKS TITLE OF TEST OR CHECK TEST OR CHECK OB3ECTIVE 2.Process instrumentation (Temperature pressure, level, and flow instruments)
Equipment is aligned and calibrated using existing plant procedures.
3.Expansion and Restraint During the heat-up to operating temperature, selected points 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 recorded for correction af ter cool down or are corrected prior to increasing the temperature.
0.Pressurizer During the hot functional testing, the pressure controlling capability of the pressurizer is demonstrated to be within the controlling band.With reactor coolant pumps operating and with full spray, the pressure-reducing capability of the pressurizer is verified.With the spray secured and all heaters energized, the pressure-increasing capability of the pressurizer is verified.Pressurizer Power Operated Relief Valves are f unctionally checked at operating pressure.The Pressurizer Safety Valves are bench tested to verify setpoints using existing plant procedures prior to installation.
5.Reactor Coolant Pumps and Motors As the pumps and motors are placed in operation they are checked for: 1.Megger and hi pot test (as applicable) 2.Cooling 3.Lubrication 0.Power requirements including correct power supply voltage.5.Overload protection 6.Direction of rotation (initial start only)7.Vibration frequency and amplitude of motor shaft and motor frame l'I 1 P f/$t 0 Il i
'I'\Page 3 of 6 APPENDIX B LIST OF PREOPERATIONAL TESTS AND CHECKS TITLE OF TEST OR CHECK 6.Steam Generators 7.Chemical Tests to Establish'Pater Quality 8.Reactor Coolant Flow Test TEST OR CHECK OB3ECTIVE The proper operation of instrumentation and control system of steam generators are checked during heat-up and at temperature.
The functioning of the blowdown system will be checked.V/ater for Reactor Coolant System fill and makeup is analyzed for chloride content, conductivity, total suspended solids, pH, clarity, and fluorides to requirements specified by existing plant procedures.
During RCS heatup and prior to exceeding 250 F, hydrazine is added to scavenge oxygen from the RCS.Prior to, at hot shutdown and during heat-up, chemical analysis is performed to verify the R.C.S.chemistry is within specif ications.At cold shutdown conditions, measurements are made of elbow tap differential pressures to make relative comparison.
At hot shutdown conditions, measurement of loop elbow differential pressure drops are made.Using these data with the reactor coolant pump performance curve, the calculated flow is verified to the design flow.Flow coastdown and transients following reactor coolant pump stoppages are also determined during the hot functional testing.9.Chemical and Volume Control System System Tests 10.Emergency Boration System Tests (Safety Injection System)Makeup and letdown operations are conducted with the Chemical and Volume Control System to check out the different modes of dilution and boration and to verify flow in the different modes.The adequacy of heat tracing to maintain the required Boric Acid concentration in solution is verified.The ability to adequately sample is demonstrated.
The ability of the emergency borate system is verified by pumping boric acid into the Reactor Coolant System.
I I t I P$/I t t I ii<I'Pageos of 6 APPENDIX B LIST OF PREOPERATIONAL TESTS AND CHECKS TITLE OF TEST OR CHECK TEST OR CHECK OB3ECTIVE 11.Steam Generator Safety Valves 12.Auxiliary Feedwater System The setpoint of safety valves is verified by tests at appropriate pressure and temperature conditions in.accordance with existing plant procedures.
Setpoints are 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 is vented, allowing the valve to reseat immediately.
The auxiliary feedwater system is operationally checked out to verify its ability to provide water to the steam generators within the required time frame.13.Instrument Air System The instrument air system is tested to verify proper operation.
10.Leak Detection System Tests'(15.Residual Heat Removal System Test Temperature detectors in the drain lines from pressurizer safety valves and the reactor vessel head seal and their alarm functions are checked.Pressurizer relief tank level and temperature sensors are calibrated and associated alarms checked.The residual heat removal systems capability to remove, heat is'demonstrated.
16.Reactor Coolant Pump Seal and Cooling Water Test Prior to reactor coolant pump operation and with the system pressurized, flow to the pump seals and cooling water is set.Flow is adjusted to specified values using installed instruments.
When at operating temperature and pressure, seal and cooling flows and temperatures are checked.17.Condenser Circulating Water System Prior to hot functional testing, the main circulating water system is tested to verify operability.
18.Steam Generator Makeup Water and Chemical Treatment The makeup system to the steam generators is checked out to verify operability.
The chemical treatment system is checked out when chemicals are added to the steam generators.
j'Page 5 of 6 APPENDIX B LIST OF PREOPERATIONAL TESTS AND CHECKS TITLE OF TEST OR CHECK TEST OR CHECK OB3ECTIVE 19.Component Cooling Nater System Test 20.Primary, Sampling System Component cooling flow to the various components cooled by the CCW system is adjusted, the system operationally checked out, and setpoints verified.Operations are performed to: 1.Demonstrate that liquid and gas samples can be obtained from sample points.2.Demonstrate that valves, instruments, and controls function properly.3.Verify proper functioning of the sample cooler.21.Pressurizer Relief Tank The pressurizer relief tank and associated valves and instrumentation are checked out to verify performance of design functions.
22.Containment Ventilation System Test The system is operated to balance air flows and to verify the ability to maintain temperatures below maximum allowable limits, ability to cool Rx components and RCPs.23.Accumulator Tests Flow through the accumulator lines is initiated to demonstrate that the check valves are free to open.Tests are also made to verify that accumulator pressure could be maintained.
20.Containment Spray System Tests Tests are performed to verify pump operating characteristics, and response to control signals.25.Primary System Hydrostatic Test Hydrostatic testing of the reactor coolant system will be performed at test pressures as specified by ASME standards for the system.Prior to pressurization, the system will be heated to hot shutdown conditions.
The pressure is then increased to test pressure, maintained for the specified time period and inspection for leakage is made.Over pressure protection is provided during the test.
l I L 0 Page 6 of 6 APPENDIX B LIST OF PREOPERATIONAL TESTS AND CHECKS TITLE OF TEST OR CHECK TEST OR CHECK OB3ECTIVE 27.Incore Thermocouples and Resistance Temperature Detectors 28.Control Rod Drive Mechanism and Rod Position Indication Coil Cooling System Test All readout and temperature compensating equipment is checked during the calibration and isothermal corrections for the operative thermocouples are determined.
The cooling system is checked out to verify adequate air flow, proper temperatures and motor current.
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APPENDIX C LIST OF MA3OR STARTUP TESTS AND CHECKS I I 1 Page I of 5 APPENDIX C LIST OF STARTUP TESTS AND CHECKS TITLE OF TEST OR CHECK TEST OR CHECK OB3ECTIVE I.FUEL LOAD I.Refueling Equipment (Hand Tools, Power Equipment and Associated Protective Interlocks)
Prior to core loading,'tests and checks are performed in accordance with existing plant procedures to demonstrate the operability of the fuel handling equipment and fuel transfer system.2.Nuclear Instrumentation System Nuclear instruments are calibrated and source range detector response to a neutron source is checked as a primary source is loaded.3.Process Instrumentation (Temperature Pressure, Level and Flow Instruments) 0.Area Radiation Monitor Tests Equipment was aligned and calibrated during Preoperational Testing.Prior to core loading, the radiation monitoring system alarms associated with core loading are checked out and the alarm setpoints verified.5.Reactor Component Handling System (Polar Crane)6.Residual Heat Removal System Test Testing was performed on the polar crane during the Construction Phase of the steam generator repair.Testing was performed on this system during Preoperational Testing.7.Chemistry Tests, Prior to, during and following core loading, primary sampling will be performed to verify boron concentration in the reactor coolant system is within Tech Spec limits..S.Baseline Data for Inservice Inspections Systems and components that require inspection in accordance with Section XI of the ASME Codes are examined for baseline data.Information from these inspections provides baseline data for subsequent inservice inspections.
Note: This activity will be occurring throughout the entire test program.
~~~y Page 2 of 5 APPENDIX C LIST OF STARTUP TESTS AND CHECKS TITLE OF TEST OR CHECK TEST OR CHECK OB3ECTIVE II.LEAK RATE TESTING 1.Containment Tests Containment Type B and C leakage tests will be performed in accordance with Appendix 3 to 10 CFR 50 and approved plant procedures.
III.INTEGRATED SAFEGUARDS TEST 1.Engineered Safety Features 2.Emergency Power Systems 3.Containment Isolation Systems 0.Auxiliary Feedwater System 5.Safety Injection System 6.Residual Heat Removal System The Engineereed Safety Features logic matrices are tested to demonstrate operability, proper logic, redundancy and coincidence in accordance with Technical Specif ications.The automatic starting and loading of the emergency diesel generators is demonstrated during temporary loss of off-site power during the safeguards test.The operation of actuation systems and components used for containment isolation is verified during test.Automatic operation of pumps and valves is verified during test.Automatic operation of pumps and valves is verified during test.Automatic operation of pumps and valves is verified during test.7.Containment Spray System 8.Emergency Containment Coolers Automatic operation of pumps and valves is verified during test.Automatic operation of coolers, valves and required water flow is verified during test.
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Page 3 of 5 APPENDIX C LIST OF STARTUP TESTS AND CHECKS TITLE OF TEST OR CHECK TEST OR CHECK OB3ECTIVE 9.Emergency Containment Filters Automatic operation of filter fan is verified during test.10.Accumulator Check Valves Operation of check valves will be verified during test.IV.LOW POWER PHYSICS TESTS1.Reactor Protection System 2.Nuclear Instrumentation (Excore)Prior to criticality, this system is tested to demonstrate operability, proper logic, redundancy and coincidence.
The protection channels are verified through tripping of the reactor trip breakers.Prior to criticality, all channels are checked to verif y high level trip functions, alarm setpoints, operation of strip chart recorders and any auxiliary equipment.
3.Control Rod Systems Tests A.Rod Control System Prior to plant heatup or at hot shutdown, this system is energized and operationally checked out with mechanisms connected to each power supply.The ability of the system to step is verified, the alarm and inhibit functions tested and the system parameters adjusted to specified values.B.Rod Drop Tests C.Rod Position Indication At hot shutdown conditions, the drop times of full length rods are tested.The drop time is measured from the release of the rod until the rod enters the top of the dashpot.This time is verified to be less than the maximum value specified in the Technical Speci f ications.During rod control system tests, the position indication system was aligned to provide rod movement indication.
At hot shutdown conditions, individual rod positions are calibrated to within tolerances specified in existing plant procedures.
\7 I 4 5 s~li i".~Ie'II" ,I gt', (II O)Y 4Nt*t%tt~'Ill I+tA~ll-(I~~~s'ae\e s\w~t rt~I r~s+y II Pageos of 5 APPENDIX C LIST OF STARTUP TESTS AND CHECKS TITLE OF TEST OR CHECK TEST OR CHECK OB3ECTIVE 0.Steam Generator Blowdown System Test At hot shutdown conditions, a functional test is performed to verify blowdown flow is consistent with system design parameters.
This blowdown system flow test is also performed at 70%reactor power.5.Initial Criticality The objective is to bring the reactor critical from the plant hot shutdown conditions.
Prior to start of rod withdrawal, the nuclear instrumentation had been aligned, checked, and conservative reactor trip setpoints made per existing plant 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.Initial criticality and low power physics tests are performed in accordance with existing plant procedures to verify plant design parameters.
V.FULL POWER OPERATION 1.Power Ascension Normal post ref ueling Technical Specification required testing will apply for power ascension.
In addition the following design tests associated with modified systems will be performed:
l.Steam generator moisture carryover tests.2.Steam generator thermal and hydraulic performance verification.
3.Steam generator water level stability and control demonstration.
0.Condensate polishing performance testing, when polishing system is , available.
II p ,~~~h r a ()~~~\44+~4(~r.i I~I~4~'I/I~I 8 Page 5 of 5 APPENDIX C LIST OF STARTUP TESTS AND CHECKS TITLE OF TEST OR CHECK TEST OR CHECK OB3ECTIVE 5.Load rejection testing with condensate polisher, when polishing system is available.
2.Power Conversion System (Turbine Generator) 6.Steam generator blowdown system flow test at 70%reactor power, when heat recovery portion of the system is available.
A.Vibration Frequency and Amplitude B.Turbine Control and Bypass Valves When the main turbine is rolled, vibration readings are monitored, (Turbine vibrations are also monitored throughout the power escalation program).Major equipment (e.g., feedwater pumps and condensate pumps)are operated as they become available and are observed for indications of excessive vibration.
The turbine control system will be demonstrated in turbine operation up to and including a period of operation at synchronous speed.The turbine bypass valves to the condenser and their associated control systems are checked out to verify operability.
C.Feedwater and Feedwater Control System The feedwater and condensate pumps are operationally 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 is verified.D.Makeup Water and Chemical Treatment The makeup system to the steam generators was checked out during hot functional testing and at power operation.
The chemical treatment system is checked out when chemicals are added to the steam generators at heat-up to steaming conditions.
~i~~~t~~sr r I A A~IVI 0~~~%%~I%I~C Qt APPENDIX D PROCEDURE FOR CONDUCTING THE INTEGRATED STARTUP TEST PROGRAM l>I PROCEDURE FOR CONDUCTING THE INTEGRATED STARTUP TEST PROGRAM FOR POST STEAM GENERATOR REPAIR AND PC/M DESIGN CHANGES TURKEY POINT PLANT FLORIDA POWER AND LIGHT COMPANY MIAMI, FLORIDA L t'E r'(tf Page 1 of 6 TURKEY POINT UNIT 3 FLORIDA POWER AND LIGHT COMPANY MIAMI, FLORIDA 1.0 PURPOSE AND SCOPE 1.1 To provide guidelines for the accomplishment of the tests to be performed prior to plant operations.
1.2 To define the phases of the Integrated Startup Test Program.1.3 To delineate the responsibilities of the organizations participating in the Integrated Startup Test Program.1.0 To provide the administrative controls to ensure that the necessary prerequisites are completed prior to commencing the Integrated Startup Test Program.
2.0 REFERENCES
2.1 Administrative
Site Procedure ASP-11, Construction Turnover 2.2 Turkey Point Technical Specifications
3.0 DEFINITIONS
3.1 Inte rated Startu Test Pro ram Phases The Integrated Startup Test Program is divided into two phases.The objectives of each phase are defined below: PHASE I Preoperational Tests-Those test performed to demonstrate the proper functioning of new, modified and existing equipment, subsystems and systems through and including the Hot Functional Test of the plant prior to fuel loading.PHASE II Startup Tests-Those tests performed to assure the proper integrated operation of the plant and to demonstrate that the plant can be operated safely as designed from fuel loading to full power operation.
3.2 Plant
Procedures To the extent practical, the Integrated Startup Test Program will be conducted using existing plant procedures as they already include the electrical checks, mechanical checks, calibration checks, hydrostatic
- tests, 4~l p II~I'gl'1 l'(I I II Page 2 of 6 surveillance requirements, operating parameters, administrative policies, etc., necessary to perform the testing program.Additional procedures will be written as they are required.A copy of the Turkey Point Units 3 R 0 Procedure Index is attached.Three types of these existing plant procedures are defined below.3.2.1 Administrative Procedure (AP's)Written instructions which define the method by which the responsible person or persons direct the conduct of plant operations and the means and the limits required for the administration of the plant.3.2.2 0 eratin Procedure There are three general categories of Operating Procedures:
1.Normal Operating Procedures (OP's)which are written instructions which define the normal method, means, and limits of operation, in all modes, of the plant, plant, systems, or processes.
2.Off Normal Operating Procedure (ONOP's)which specify operator actions for restoring an operating variable to its normal controlled value when it departs from its range, or to restore normal operating conditions following a perturbation.
Actions taken under off-normal operating conditions are invoked following an operator observation or alarm to correct a condition which, if not corrected, could degenerate into a condition requiring action under an emergency.procedure.
3.Emergency Operating Procedures (EOP's)which are written instructions which specify actions, including operator manipulation of controls: (1)To avoid further degradation of off-normal conditions which in themselves do not constitute an accident but which could lead to'n accident.(2)To reduce the consequences of an accident or hazardous condition which has already occurred.3.2.3 Maintenance Procedure (MP's)Written instructions defining the policies and practices by which mechanical, electrical, instrumentation and control and fire protection systems of Units 3 and 0 are kept in a condition of good repair or efficiency so that they may satisfactorily perform their intended functions.
These procedures include those activities performed to maintain, modify, or repair nuclear safety related and fire protection equipment.
Related activities are those actions taken by operating personnel to determine that a planned maintenance activity can be safely performed under the existing plant conditions.
Procedures for these related activities by operations personnel are considered to be operating procedures, but may be included in maintenance procedures.
1 , II' Page 3 of 6 3.3 Administative Site Procedures (ASP's)Written instructions that define the policies and practices of the FPL Construction Department and their associated contractors when performing repairs and design changes on the plant.A copy of the Administrative Site Procedure Index is attached.3.0 Plant Chan e/Modifications (PC/M's)PC/M's are engineered design changes or modifications to plant systems or equipment.
A nuclear safety related PC/M is a design change or modification which has a direct effect on those plant features necessary to assure the integrity of the reactor coolant system pressure boundary, the capability to shutdown the reactor and maintain it in a safely shutdown condition, or the capability to prevent or mitigate the consequences of accidents which could adversely affect the environment.
0.0 PARTICIPATING
ORGANIZATIONS AND RESPONSIBILITIES Plant Nuclear Safet Committee (PNSC)Consists of management personnel from Turkey Point Plant as designated in the Plant Technical Specifications.
The PNSC reviews and recommends approval of all test procedures used during the integrated startup test program, and of items as delineated in the Technical Specifications.
0.2 Turke
Point 0 eratin Staff Consists of employees engaged in the operation and maintenance of systems, subsystems or portions of the plant under the direction of the Plant Manager-Nuclear.0.3 Westin house Electric Cor oration (W)The term Westinghouse or (W)shall be limited to equipment and services furnished as part of or under contract for the nuclear steam supply and turbine generator systems.Bechtel Power Cor oration (Bechtel)0.5 Bechtel shall furnish Engineering, Construction and Startup services as required by FPL.Daniel Construction Com an (Daniel)Daniel shall furnish Construction Quality Control services as required by the FPL Construction QC Department.
I 1 A' Page 0 of 6 0.6 FPL Construction De artment The Construction Department functions under the direction of the Project Site Manager.The Construction Department is responsible for all work associated with the Steam Generator Repair Project (SGRP)and other design change modif ications (PC/M's).~(Q)The Construction Quality Control Department is responsible for assuring that nuclear safety related components, system or partial systems are released in accordance with existing procedures for testing, that test data documentation is in compliance with contractors' procedure, and that retention control of documentation is adequate.This department is also responsible for verifying that nuclear safety related systems are built in accordance with approved design documents.
4 The Turkey Point Quality Control Department is responsible for the inspection, and witness of tests required during preoperational and startup testing, and shall maintain control of QC documentation for all activities affecting nuclear power plants.The level and extent of QC , involvement is defined in the individual procedures.
0.8 FPL Power Plant En ineerin (EPP)This department is responsible to resolve component and system deficiencies discovered during construction, the Preoperational Test Phase, the Startup Test Phase and during normal plant operations.
0.9 Startu
De artment The Startup Department is responsible for the development and implementation of the Integrated Startup Test Program.The department consists of selected plant personnel who are assisted by Bechtel Startup Engineers under the direction of the Startup Superintendent.
The Startup Superintendent reports directly to the Plant Manager-Nuclear.
The Startup Department is responsible for conducting the tests and checks under their jurisdiction, for assuring that testing is performed in accordance with approved procedures and for reviewing all test data through the Preoperational Test Phase.They will provide technical assistance, as necessary, to the Nuclear Operations Staff during the Startup Test Phase.0.10 Turnover Committee The purpose of this Committee is to determine the responsibility for resolving deficiencies discovered after turnover and during the Preoperational Test Phase and the Startup Test Phase.
E l I 1 Page 5 of 6 5.0 CONSTRUCTION PHASE The Construction Phase for new, modified or repaired systems is the responsibility of the FPL Construction Department.
All activities of the Construction Phase shall be performed in accordance with approved specifications, design change packages, (PC/M's)and procedures, as applicable.
As the construction phase of new, modified or repaired systems is completed, the FPL Construction Department will coordinate walkdown to ensure that the work is completed w'ith the Contractor and FPL Startup Department in preparation for turnover to the FPL Startup Department for Preoperational Testing.Any items that are found to be incomplete or deficient during the walkdowns shall be documented on a Punch List and resolved prior to turnover acceptance by the FPL Startup Department for Preoperational Testing.The turnover of new, modified or repaired systems shall be accomplished in accordance with an approved Administrative Site Procedure.
6.0 PREOPERATIONAL
TEST PHASE%hen a system or subsystem is sufficiently complete and related support systems are available so that the intended functions can be performed, the Startup Department will accept the system for preoperational testing.The Preoperational Test Phase is the responsibility of the Startup Department.
They will be assisted by the plant staff supplemented by construction crafts personnel as needed.The Startup Department is responsible for documentation of and maintaining a status list of discrepancies determined during preoperational testing.The discrepancies will be documented on a Punch List and the Punch List forwarded to the Turnover Committee for resolution prior to releasing the system for unrestricted operation.
The Startup Department is also responsible for assuring that all tests are performed in accordance with approved procedures, reviewing all test data through the preoperational testing phase and writing additional procedures as needed.Important plateaus in the Preoperational Test Phase are as follows: A.Individual Equipment and Systems Tests and Checks B.Required Equipment and Systems Aligned and Calibrated C.Hot Functional Test of Plant D.Primary System Overpressure Test E.Cooldown and Release for Startup Test PhaseUpon successful completion of preoperational testing, the Startup Department will review the documentation and test data as required to verify the functional operability of the equipment and systems.Any items found to be incomplete but not limiting for unrestricted operation will be documented on a Punch List and the Punch List forwarded to the Turnover Committee for resolution.
The plant is then released to the Turkey Point Operating Staff for the Startup Test Phase.
1 I I I a N>'1 J$~,)lf I Page 6 of 6 7.0 STARTUP TEST PHASE I%hen the preoperational testing is completed, preparation is made to return the plant to power operation.
The systems and equipment tested individually and during the hot functional test are now tested to demonstrate that they can operate safely as an integrated unit from fuel loading to full power operation.
The Startup Test Phase is the responsibility of the Turkey Point Operating Staff with technical assistance as required from the Startup Department.
Major milestones in the Startup Test Phase are listed below: A.Fuel Load B.Leak Rate Testing C.Integrated Safeguards Test D.Criticality and Low Power Physics Tests E.Power Operation The Startup Test Phase will be performed in accordance with existing plant prodedures that will be changed as necessary to incorporate the operation of new or modified systems and equipment.
Additional procedures will be developed should they be required.)Systems that are not used during normal plant operations, but must be in a state of readiness to perform safety functions, are checked under test conditions prior to plant startup.At no time will the safety of the plant be dependent on the performance of untested structures, systems or components.
The Startup Department and the Turkey Point Operating Staff will be responsible to present evidence that the required testing is completed and proper documentation is available.
8.0 ATTACHMENTS
t'.1 Turkey Point Units 3 and 0 Procedure Index.8.2 FPL Construction Administrative Site Procedure Index.
\I I T Id">I t II l'1 ,k~'ale>>'4 ll>a<o'd:~z>,"ea r t 1 1 I~k~wr~~i~>>q<i I~<f0 PROCEDURE NUMBER DATE TITLE Page 2 11 20/81 0103.2 0103.3 0103.4 0103.5 0103.6 0103.7 0103.8 0103.9 0103-10 01Q3.11 0103 12 0103.13 0103.15 J 0103.16 0109.1 010S.3 0109 6 0110.4 0149.1 0149 2 0190 1 0190.4 0190 9 0190.10 0190-12 0190-13 0190.14 Q190 15 0190.16 0190.17 0190.19 0190.Z1 0190.Z2 0190.23 0190.25 0190-26 0190 27 0190-28 0190.61 0190 62 0190.63 0190 67 10/1/81 5/21/81 10/23/81 7/30/81 6/26/80 6/26/80 8/8/78 4/24/79 5/28/81 8/14/81 4/2/81 5/15/80 10129/81 ll 5/Sl 3/26/81"-11/25/80.4/30/79 9/3/81-4/23/81.10/31/77 8/28/80.9/24/81.2/1/80 5/15/80 6/18/81 9/.24/81 8/28/80 10/23/81 5/18/79 2/15/80 5/2S/81 5/29/79 5/18/79 5/18/79 7/16/76 2/29/80 9/26/79 4/2/81 10/8/81 2/12/79 9/3/81 4/24/79 ADMI NI STRATI VE Responsibilities of Operators, on Shift and Maintenance of Operating Logs and Records Control and Use of Jumpers and Disconnected Leads In Plant Equipment Clearance Orders Administrative Control of Valves, Locks and Switches Reportable Occurrences Reports Required by Technical Specifications and 10 CFR Shutdown Rate Guidelines Facility Staff gualifications Using Plant Drawings Housekeeping Notification of Significant Event to NRC Fire Watch Patrol Operating Experience Feedback Onties and Responsibilities of the Shift Technical~Advisor Preparation, Revision, and Approval of Procedures On the Spot Changes to Procedures Temporary Procedures Plant Nuclear Safety Comittee-General Procedures Special Nuclear Material Accountabiliity.Determination of Average Annual Capacity Factor guality Assurance and guality Control Program and Organization at Turkey Point procurement Docunent gualfty Control.Control of Measuring.and Test Equipment Cleaning of Nuclear Safety Related.Systems and,Components (Mechanical)
Nonconforming Material, Parts, or Components.
Corrective Action for Conditions Adverse to guality Document Control and guality Assurance Records plant Projects-Approval, Implementation and Regulatory Requirements Scheduling and Surveillance of Periodic Tests and Checks Required by Technical Specifications Maintaining Records for Design Cycles Control of Maintenance on Nuclear Safety Related and Fire Protection Systems Nuclear Safety Hazards: Identification Changes, Tests, and Experiments Electrical Department Instrument Calibration Program Compliance Review Program Calibration Control of Installed Nuclear Safety Related I and C Equipment Electrical Department Installed'Instrument Calibration Program Mechanical Test Control (Post Maintenance)
Control of Liquid Penetrant Testing Requirements for Melding procedures and Melder gualificati ons Melding Filler Metal Control Procedures Melding and Cutting Safety Procedure F:PSR L I PROCEDURE NUMBER DATE TITLE Page 3 11 20/81 0190.70 0190.71 0190.72 0190.73 0190.76 0190.77 0190.78 0202.1 0202.2 0204.1 0204 2 ,0204.3 0204 5'0205-1 0205.2 0206-2 0206 3 0206.4 0206 5 0208.'1 0208'3 0208.4 0208-5 0208.6 0208.7 0208 8 0208.9 0208.10 0208.11 0208.12 0208.13 0208.14 0209-1 0209.3 0209.4 8/28/80 10 23 81 6/18/81 8/28/80 3/5/81 6/18/81 6/20/79 8/20/81 10/15/81 12/18/80 9/3/81 5/21/81 4/23/81 5/2/80 7/30/81 6/18/81 5/21/81 4/.10/80 10/30/80 4/23/81 5/7/81 5/7/81 4/30/79 5/7/81 4/10/80 5/7/81 5/7/81 2/12/79 8/28/80 8/28/80 10/1/8 1 I ll 0 9/24/81 9/24/81 11/21/79 ADMINISTRATIVE (cont'd)Inspection of.Maintenance Activities on Nuclear Safety Related and Fire Protection Equipment gualification of gualfty Control Inspectors Receipt Inspection, Identification, and Control of Nuclear Safety Related and-Fire Protection Parts, Materials, and Components
(}uality Control Surveillance Program Verification of Steam Gener'ator Tube'Plug Installation Ma9netic Particle Inspection (Electromagnetic Yoke Method)Inspection Procedure for Ultrasonic Material'Thickness Measurement GENERAL PLANT PROCEDURES Reactor Startup, Cold Conditions to Hot Shutdown Conditions Unit Startup, Hot Shutdown to Power Operation Secondary Plant Operating Checks and Tests Schedule of Periodic Tests, Checks, Calibrations and Operating Evolutions Initial Criticality After Refueling Nuclear Design Check Tests During Startup Sequence After Refuel ing Unit Shutdown, Full Load to Hot Shutdown Conditions Reactor Shutdown, Hot.Shutdown to Cold.Shutdown Conditions.Spent Resin'System Refueling Mater Storage Tank--Normal Operation Periodic Visual Leak Inspection of Systems Outside Che Containment for Control of Radioactive Material Leakage Visual Leak Inspection of Class III Systems.Shutdown Resulting from Reactor Trip or Turbine Trip Annunciator List-Panel A-Reactor Coolant Annunicator List-Panel B-Reactor Annunicator List-Panel C-Steam Generator and Reactor lri'ps Annunciator List-Panel D-Condensate and Feedwater Annunciator List.-Panel E-Turbine Generator Annunciator List-Panel F-Electrical Annunciator List-Panel G-Miscellaneous Annunciator List-Panel H-Safety Injection and Auxiliary Annunciator List-Panel I-Station Service Annunciator List-Panel X-Coamon Annunciator List-Maste/Boron Panels Deviation or Failure of Reactor Protection and Safety Related Hagan Instrumentation Channels Valve Exercising Procedure Inservice Pump Testing Program Implementation Procedure for Auxiliary Feedwater Pumps Inservice Testing-Valve Seat Leakage Testing F:PSR 1
P'I PROCEDURE NUMBER TITLE page 4 10/15/81 0301.0303 TRAINING PROCEDURES 8/20/81 Licensed Operator Requalification Program 4/25/77'uclear Operator and Nuclear Turbine Operator Training and Retraining program 0304 0305 0306 0307 0701.1 0701.2~0703.0707-1 0707.2 0707.8 0707.9 0707..10 8/20/81 11/14/80 12/12/80 6/19/81 8/14/81 9/3/81 12/8/78 10/4/79 2/24/81 5/22/80 12/7/79~9/24/81 Plant Training Emergency Team Training New Employee Indoctrination and Orientation Shift Technical Advisor Training Program MAINTENANCE PROCEDURE-GENERAL Welding Job Control List quarterly Calibration of Filler Metal (Melding Rod)Ovens Naintenance of Copes-Vulcan Air Operated Control Valves Series G Chempump Removal, Repair, and Replacement Snubber Inspection and Repair Periodic Calibration of Instrumentation Used in Station Heat Rate Determination Inspection of Swagelok Fittings-Reactor Trip and Generator Output Breakers: Inspection and Maintenance 0707-.'ll 0707.'13 0707.'14 0707.15 0707.16 0707.17 0707.18 0707.19 0707-20 0707-21 0707-25 0707.26 12/4/79 ll/21/79 5/19/78 1/23/79 1/23/79 12/4/79.5/19/78" 1/23/79 1/23/79 7/31/78 12/15/78 Tubes and Flanged'Tube Sheets Fischer-Porter Hagan'Pressure'Transmitters Alignment;,and Calibration Procedure Safety and Relief Valve Testing Procedure Fischer-porter Differential Transmitter Alignment, Naintenance, and Calibration Hagan Sumnators Repairs,and Calibration Hagan Single and Dual Comparators Repairs and Calibration Hagan Nanual/Automatic (M/A)Controller Calibration and Repair~;.*Hagan Manual/Auto Control Station Calibration-and Repair Hagan Isolators Repairs and Calibration Calibration of Hagan Optimac Analog.Computer Elements Hagan 40V and 45V Loop Power Supply Repair and Calibration 4160 Volt Motor Grounding and Testing Without the Use of'3/13/78"Tube Plugging-Auxiliary Heat.Exchangers with Stainless Steel 0707.27 12/15/78 0707-28 12/15/78 Nanufacturer's Ground and Test Device 4160 Volt Motor Grounding and Testing With the Use of Manufacturer's Ground and Test Device 4160/480 Volt Load Center Transformer Grounding and Testing Mithout the Use of Manufacturer's Ground and Test Device 0707.29 0707 31 0710.0 0710.1 0720 0724 9/18/80 9/18/81 4/10/80 10/19/76 2/5/79 4/10/80 Calibration of Rosemount Model 1153 Pressure Transmitter Installation of 4KV Switchgear Ground Attachments Liquid Penetrant Testing Liquid Penetrant Testing at Elevated Temperatures.Preventative Maintenance Program--Mechanical
'ent and Drain Flange Replacement with Swagelok Plugs F:PSR 1 I PROCEDURE NUMBER DATE TITLE page 5 10/23/81 0725 0726 0728 0729'731 0732 0733 0734 0735 J 0736 0737.1/9/81.11/9/78 7/22/80.1/22/81 8/31/79 12/4/79 10/2/80 4/2/81'/.13/81 10/15/81 6/18/81 MAINTENANCE PROCEDURE-GENERAL (cont'd)Fire vStop and Cable Tray Fireproofing Velan Pressure Seal Valves-Seal Ring Replacement
-.Valves 20139, 239, 339 Bushing Replacement on 5KV Penetration Canisters Safety Related MOV Motor Maintenance Calibration of Mechanical Department Measuring Test Equipment QC Check and Replacement of BFD/NBFD Relays in Reactor protection and Safeguards Systems Hagan's NV/I Amplifier Repairs and Calibration Safety Related Supports/Restraints Removal and Replacement Emergency Load Sequencer-General Electric Type-HFA Relay Coil Spool Visual Inspection Heavy Load~Hand11n Implementation Procedure for Installation of Output Test Points in Hagan Power Supplies 1001.1'1003.1 1004..1 1004 2 ,1004.3 3.004.4 1004.5'1005.1 1007-2 1007.3 1007.4 1007.5 1007.6 1008.2 1008 3 1008.4 1008.6 1008.7 1009.1 1009.3 1009.4 10/30/80 8/24/79 6/20/79 8/14/81 5/22/80 5/7/81 7/10/81 6/11/81 9/11/80~4/3/80 7/15/77 10/20/77 6/11/81 9/15/77 9/25/75 9/15/77 8/28/75 8/14/81 9/11/80 10/30/80 4/2/76 REACTOR AND REACTOR COOLANT SYSTEM Filling and Venting the Reactor Coolant System Netal.Impact Monitoring System-Verification of Alarms RCS-Periodic Leak Test Following RCS Opening Reactor'Protection System-Periodic Test Reactivity Deviations from Design Calculations Overpressure Mitigating System Functional
-'Test of Nitrogen Back-Up System Reactor Coolant pressure Isolation Valve Leakage Testing Draining the Reactor Coolant System Reactor Coolant Bypass Loop RTD Replacement Setting Reactor Protection Undervoltage Time Delay'Relays (UVTD)Replacement of RCS Flow Transmitter Above Permissive P-8 Daily and Meekly, Checks of Metal Impact Nonitoring System (NIMS)Sub-Cooled Margin Monitor System Maintenance and Calibration Excessive Reactor Coolant System Leakage Loss'f Reactor Coolant Flow Excessive RCS Activity Operation Outside the Axial Flux Difference Target Band Reactor Coolant System Natural Circulation Estimated Critical Conditions Shutdown Margin Calculation.Operation Within the Axial Flux Difference Target Band F:PSR I 1 PROCEDURE NUMBER DATE TITLE Page 6 10/15 81 REACTOR COOLANT PUMPS 1100.1 1107.1 1107.2 1107.3 1107.4 1107.7 1107.8 1108.1 6/6/80 11/15/76 12/4/79 9 24/81 12 5 80 9/11/80 7/9/80 7/22/80 Reactor Coolant Reactor Coolant Reactor Coolant Reactor Coolant Reactor Coolant Reactor Coolant Reactor Coolant Installation Reactor Coolant Pump Operation Pump Seal and Motor Removal Pump Seal Inspection Pump Impeller Removal and Replacement Pump Seal and Motor Replacement Pump-Refurbishing of Number 3 Seal Pump Motor-Motor Flywheel Removal and Pump Off-Normal Conditions 1200.'1 1207.1'207.6 1207.7 1207 8 1208.1 1208-2 1300.1 1407.1, 1407.-2 3.407.3 1407.4 1407.5'1407.6.:1407.'7 1407.8 1407.9 1407.10 1407.11 1407.12 1407.13 1407-14 1407.15 1407-16 1407-17 1407.18 1407.19 1407.20 1407.21 J 1407.23 6/6/80 f9924/81 4/10/80 7/31/80 7/31/80 7/9/80 3/3/76 5/2/80 12/7/79 1/5/79 8/27/81 8/29/78 6/7/78 3/26/81 12/5/80'/26/81 6/11/81 8/1/79 6/18/81 5/7/81 5/29/79 6/7/78 1/11/80 8/27/81 6/7/78 6/7/78 6/11/81 7/10/81~10 1/81 10/8/81 PRESSURIZER AND PRESSURIZER RELIEF TANK Pressur izer Steam Space Venting Pressurizer Safety Valve, Repair and Setting Replacement of Pressurizer Mini Spray Valves 524 and 525 Recalibration of Pressurizer Level Program Pressurizer Manway Cover Removal and Replacement Pressurizer Malfunction of Power Operated Relief or Safety Valves Pressurizer
-Malfunction of Level Control'Pressurizer Relief Tank Operation REACTOR VESSEL Reactor Vessel-Removal of Missile Shield Removal of Control Rod Drive Mechanism Cooling Reactor Vessel.-Removal of Rod Drive Electrical Cables Reactor Vessel-Removal of Instrument Ports Reactor Vessel-Removal of Head Insulation Installation.
of Reactor Vessel Cavity Seal Ring Reactor Vessel"Stud Tensioner, Closure/Nut/Stud Removal and Guide Stud Installation Reactor Vessel-Removal of Vessel Head Reactor Vessel-Removal of Upper Internals Reactor Vessel-Installing Upper Internals Reactor Vessel.-Installation of Vessel Head Reactor Vessel-Guide Stud Removal, Closure Stud/Nut Installation and Stud Tensioner Operation Removal of Reactor Vessel Cavity Seal Ring Reactor Vessel-Installation of Head Insulation Reactor Vessel-Installation of Instrument Ports Reactor Vessel--Installation of Rod Drive Electrical Cables Reactor Vessel-Installation of Control Rod Drive Mechanism Cooling Reactor Vessel-Installation of Missile Shield'eactor Vessel-Removal of Lower Internals.-Reactor Vessel-Installation of Lower Internals gefueling Activities Check-Off List Removal and installation of Spent Fuel pit Keyuay~Gate F:PSR 1 I PROCEDURE NUMBER.DATE TITLE'age 7 10 30 81 1502.1 1502.2 1504.3 1506.1 1506.2 1507.1 1507-2 1507.4 1507.5 1507.6 1507.7 1507.8 1507.9 1507.10 1507.11 1507-12 ,1508.2 8/8/78 7/31/80 9/19/75 7/31/80 3/13/81 7/10/81 3/26/81~10/8 81 8/8/78 5/7/81 8/1/79 8/21/80 4/3/80 2/1/80 11/25/80 8/21/80 4/25/80 STEAM GENERATOR Placing Steam.Generator in Service'Steam Generator Recirculation System Steam G nerator, Moisture Carryover Test Steam Generator Met Layup Steam Generator Pressure Test/Hydrostatic Test Steam Generator Safety Valve Repair and Setting Steam Generator Nanway Cover Removal and Replacement Recalibration of Steam Dump Reference Temperature Steam Generator, Safety Valve Removal and Reinstallation Steam Generator Secondary Nanway Cover Removal and Replacement Steam Dump Valves to Atmosphere
-Inspection and Repair Steam Generator Main Steam Isolation Valves-Disassembly, Repair and Reassembly Entry into Secondary Side of Steam Generators for Inspection and/or Repair.Entry into Primary Coolant..'Piping for.Visual Examination Steam Generator Handhole Covers and Tube Lane Blocking Device Inserts Removal and Instal'lation Nain Steam Check Valves Disassembly, Repair, and Reassembly Steam Generator Tube, Leak3.560 SECONDARY CHENISTRY 7/21/78'Secondary Chemistry-Precautions.and.Limits FULL LENGTH ROD CONTROL CLUSTER ASSEMBLIES 3.600.1 1604.1.1604.3 1604.4 1604.8.1604.9 1607.5.1607.7 1607-8 1607.10 1608.1 1804.1 1807.4 1807 5 F:PSR 5/2/80*7/10/81.10/14/77 9/19/79 4/24/79 6/20/79 4/10/80 7/15/77 2/1/80 7/9/80 7/10/81 10/25/79 1/23/79 8/20/79 Full Length Rod Control Mechanism-Motor Generator Operation Full Length RCC-Periodic Exercise At Power Measurement of"Moderator Temperature, Doppler and Power Coefficient Power Defect Measurement CRDM/RPI Stepping and Drop Time Test Reactor Full Length Control Rod System (CROM)Test Power Supply Replacement in Full Length Rod Control System Full Length RCC Position Determination and Lift Nechani sm Checkout Preventative Maintenance
-CRDM Inspection of CROM Notors and RPI Stacks and Cables Full Length RCC-Nalfunction ROD POSITION INDICATION Axial Flux, Rod Deviation and Rod Position Indication System-Nonthly Test RPI Amplifier and Indicator Adjustments
" Recalibration of Rod Insertion Limits I t 1 PROCEDURE NUMBER DATE TITLE Page 8 10/23/81 2101.1 2132.1 2140.1 2147.1 2147.2 2147.3 10/14/76 9/19/79 4/16/76 8/14/81 2/24/81 8/1/80 CHARGING AND LETDOWN CVCS-Charging and Letdown..-
Initial.,Valve Alignment CVCS'-Volume Control Tank Gas Space Concentration Control CVCS-Charging Pump Operation Charging pump packing Replacement Charging Pump Disassembly, Repair and Assembly Charging Pump Motor Overhaul and Maintenance CHEMICAL MIX SYSTEM 2402.1 ll/30/76 CVCS-Chemical Mix System-Chemical Addition HEAT TRACING2500.1 2504..1 ,2601.1 2603.1 2603.5.2603.6 2607..1.2608.1 2608.2 2803.1.2819.1 2860.1 2870.1.2879.1 3100.1 3104.1 3107.'1 3107.2 3107.3 3108.1 3108-2 3109-1 1/22/80 5/15/80 9/19/79'll/21/79 7/10/81 9/20/76 5/.19/78~10/1/81 10/14/76 9/19/79 0-11/28/72 1/3/79 9/19/79 4/10/80 2/24/78 8/14/81 4/3/80 4/3/80 4/3/80 6/23/76 2/15/80 3/12/76 Heat Tracing System-Normal Operation Heat Tracing System-periodic Test BORON CONCENTRATION CONTROL SYSTEM CVCS-Boric Acid.System Valve.Alignment CVCS-Boron Concentration Control System-Automatic Makeup CVCS-Boric Acid Batching and Transferring Tank Level.Bubbler Lines, Blowdown Foxboro Magnetic Flow Transmitters
-Removing from.and Returning to Service Chemical and Volume Control'System Emergency Boration CVCS--Malfunction of Boron Concentration Control System BORON RECYCLE SYSTEM CVCS-Boron Recycle System-Operating Instructions CVCS-Purge of CVCS Holdup Tanks CVCS-Gas Stripper Package CVCS-Boric Acid Evaporator Operation CVCS-Boric Acid Evaporator package Emergency Waste Processing COMPONENT COOLING SYSTEM Component Cooling System Normal Operation Component Cooling Water System-Periodic'Test of Pumps Component Cooling pump Seal Replacement Component Cooling Pump Disassembly, Repair and Assembly Component Cooling Water pump Motor Overhaul and Naintenance Component Cooling System-Loss of Component Cooling Flow High Activity in Component Cooling System Component Cooling System Chemical Addition F:PSR
~PROCEDURE NUMBER DATE TITLE Page 9 10/15 81 3204.1 3205.1 3206.2 3206.3 3207.1 3207.2 3207.4 3207.8.3208.1 3302.1 3308.1 3309.1'3404-2 3407.1 3407.3 3407'4 3407 6 3408-1 ,3408.2 3500.1 3501.1 3501.2 3507.1 3508.1 9/24/81 4/3/80 3/5/81 7/30/81 9/18/80 12/4/79 4/3/80 4/3/80 6/11/81 7/2/81 2/1/80 6/10/81 8/.14/81.10/30/80 10/17/80'7/22/80 5/22/80 8/1/79 5/28/81 7/30/81 5/15/80 9/22/77 8/1/80 6/11/81 RESIDUAL HEAT REMOVAL SYSTEM Residual Heat Removal System-Periodic TestIsolation for Maintenance of Low Head Safety Injection Check Valves (*-875A,*-875B, and*-875C)Residual Heat Removal System-'nnual Test Residual Heat Removal System Hydrostatic Test During Normal Unit Operation.-RHR Pump Seal Replacement RHR Pump Disassembly, Repair and Assembly RHR Motor Operated Stop Valves HOV-*-750 and MOV-*-751 Maintenance Residual Heat Removal Pump Motor Overhaul and Maintenance Malfunction of Residual Heat Removal System TURBINE PLANT COOLING MATER Turbine Plant Cooling Water System-Startup and Normal Operation Turbine Plant Cooling Water-Nalfunction Chemical Treatment of Turbine Plant.Cooling Mater System INTAKE COOLING MATER.Intake Cooling Water.System-Periodic Test of Pumps Intake Cooling Water-Pump Removal and Instal,lati on of spare Intake Cooling Mater Pump-Disassembly,'Repair, and Reassembly Intake Cooling Water.-Pump Motor Overhaul/Maintenance (Louis Allis Motor)Intake Cooling Water Pump Motor-Overhaul and,Maintenance (Siemens-Allis)
Intake Cooling Water-Malfunction Intake Cooling Mater-Failure Due to Steam Generator or Nain Transformer Transportation Incident SPENT FUEL PIT COOLING SFP Cooling System--Normal Operation Spent Fuel Pit Makeup Filling the Spent Fuel Pit Spent Fuel Pit Heat Exchanger Pump Motor Overhaul and Maintenance SFP Gooling-System-Failure of the Spent Fuel Pit Cooling P~p F:PSR l
,rROCEDURE NUMBER DATE TITLE Page 10 11 6 81 4004.1 4004.2 4004.4 4007.1 4008.1 4103.1 4104.1 4104.2 4107-3 4107.4 4107.5 4107.6 4107.-7 4204 2 4207--1 9/24/81 6/25/81 2/11/77 3/1/79 5/19/78 5/7/81 10 23/81 6/18/81 5/22/80 4/25/80 5/16/79~4/3/80 4/23/81 7/31/80-4/3/80 SAFEGUARDS Containment Spray Pumps-Periodic Test Safeguard Relay Rack Train A, B, and Emergency Load Sequencer Timer--Periodic Test Containment Isolation Rack gR50 and gR51-Periodic Test Emergency Load Sequencer Time Delay Relay Test, at Refueling Re-energizing Safeguards after Loss of a Single Power Supply SAFETY INJECTION High Head Safety Injection and Containment Spray Lineup for Automatic Operation High Head Safety Injection System-Periodic Test Engineered Safeguards and Emergency Power Systems-Integrated Test Safety Injection System-Check Valve Naintenance Safety Injection System-Lapping of Rockwell 2" Check Valves Electrical Preparations for Integrated Test of Engineered Safeguards and Emergency Power Systems Safety Injection Pump Notor Overhaul and Maintenance High Head SIS Pump Dis-assembl
, Replacement of Rotating Element and Reassemb y CONTAINMENT SPRAY Containment Spray.System Nozzle Functional Test Containment.Spray System Pump Motor Overhaul and Naintenance EMERGENCY DIESEL GENERATOR 4303.1 4304.1 4304-2 4307.3 4307.4 4307.5 10/31/78 6/26/80 2/15/80 3/16/79 10/25/79'/18/80 Emergency Diesel Emergency Diesel Emer gency Diesel Emergency Di esel Emergency Diesel Emergency Diesel ACCUMULATORS Generator-Normal Standby Condition Generator-Periodic Test Load on 4 KY Bus Generator Operability Test Generator-Annual Inspection (Nechanical)
Generator-Annual Inspection (Electrical)
Generator-Fuel Oil Pump Replacement 4504.1 10/1/81 Accumulator Check Valves Backleakage
-Periodic Test EMERGENCY CONTAINMENT COOLERS AND FILTERS4700 4704.1 4704 2 4704-3 4/10/80 9/11/80 7/21/78 1/23/79'L Emergency Coolers and Emergency Containment Inspection Emergency Containment Evaluation Emergency Containment Performance Test Filters-Normal Operation Procedure Filter-System Operating Test and Charcoal Filters-Surveillance Specimen Filter Systems: HEPA Filters F:PSR j
PROCEDURE NUMBER DATE TITLE Page ll 10/23/81 (47O4.4 4704.5 4704.6 4707.1 4707-2 5110.1 5120 5150.3 5163.1 5163-2 5163.4 5167 1 5323.1.5333.1 c'5333.4 5503.1 5504.1-5504 2 5504-3 5508'1 5508.2 5510 1 5523.1 5530 1 5537.1 6103 1 6108.1 6108 2~F:PSR 3/8/79 4/3/80 6/11/81 7/31/80 7/31/80 12/5/80 3/13/81 2/26/76 8/31/79 10/1/81 ll 21 79 ,.7/14/78 8/31/79 4/23/81 9/26/79 10/25/79 9/12/78 1/30/79 1/30/79 11/21/79 4/10/80 5/11/79 3/26/81 4/16/76 4/16/76 9/11/78 3/12/76 4/6/79 EMERGENCY CONTAINMENT COOLERS AND FILTERS Emergency Containment Filter Systems: Adsorber Cells Performance Test Emergency Containment Coolers-Performance Test at Refueling Emergency Containment Coolers-Periodic Test Emergency Containment Filter Fan Motor Maintenance Emergency Containment.
Cooler Fan Motor Maintenance WASTE DISPOSAL SYSTEM-LI UID WASTES MDS-Reactor Coolant Drain Tank Operation WDS-Laundry, Hot Shower and Chemical Drain.System Operation MDS-Evaporators Number 2 and 3 Operation MDS-Waste Condensate Tank, Polishing Demineralizer and Monitor Tank Operation MDS-Controlled Liquid Release to Circulating Water Waste Disposal System,.Waste Liquid Demineralizer Operation Disassembly and Reassembly of Liquid Waste Release Monitor WASTE DISPOSAL SYSTEM-SOLID WASTES MDS-Baler Operations WDS.-Transferring Spent Resin Storage Tank to Shielded Shipping Cask WDS-Solidification of.Evaporator Concentrates with Cement WASTE DISPOSAL SYSTEM-GASEOUS MDS--Gaseous Disposal System Operation Post Accident Containment Vent System-Equipment Inspection and Operating Tests Post Accident Containment Vent System-Adsorber Cell Performance Test Post Accident Containment Vent System-HEPA Filter Performance Test WDS-Accidental Release of Radioactive Gas MDS-Off Normal Operation-Gaseous Waste Disposal System MDS-Operation of Gas Analyzer and Gas Sampling Procedures MDS-Gas Decay Tank Controlled Release to Atmosphere MDS-Operation of Waste Gas Compressor MDS-Waste Gas Compressor
-Placing in Service and Removing from Service MAIN CONDENSER Amertap Condenser Tube Cleaning System Operation Main Condenser-Loss of Mater Box Prime Main Condenser-Loss of Vacuum/
1 PROCEDURE NUMBER.DATE TITLE Page 12 10/23/81 6108.4 4/25/80-Condenser L'eak Procedure Normal.Power Operation CONDENSER CIRCULATING WATER 6200.1 8/28/80 Condenser Circulating Water System-Startup/Shutdown
.AIR EJECTORS 6600 6703 7001.1 7100.1 12/4/79 4/7/80 4/3/80.3/17/80 Operation of Steam Jet Air Qector System Including Hogging Jet CATHODIC PROTECTION Cathodic Protection
-Intake and Condenser-Operating Instructions CONDENSATE SYSTEM Condensate and Feedwater System-Valve Alignment for Normal~Operation Condensate Pumps Operating Instructions FEEDWATER SYSTEM 7,200.1 11/1/76'team Generator Feed Pump-Operating.'Instructions AUXILIARY FEEDWATER SYSTEM C 7300.2 7300.3 7304.1 7307.2 7307 3 7307.4 7308.1 11/16/78 7/9/80 9/24/81 9/,18/80$110/8 81 2/29/80 6/25/81 Auxiliary Feedwater System-N2 Backup System Operation Auxiliary Feedwater System-Operating Instructions Auxiliary Feedwater System-Periodic Test Aux.Feedwater Pump, Disassembly,.Inspection, Repair and Assembly Auxiliary Feedwater Pump Turbine Overhaul Aux.Feedwater P~p Turbine Throttle Trip Value Overhaul Malfunction of the Auxiliary Feedwater System FEEDMATER HEATERS 7400.1 10/19/76 Feedwater Heaters-Removing from and Returning to Service HEATER DRAINS 7500.1 8001-1 8004.1 1/7/77 2/9/77 1/5/74 Heater Drain pumps-Removing and Returning to Service\'TURBINE GENERATOR placing Turbine on Turning Gear Turbine Generator-Overspeed Trip Test I 1
)ri v PROCEDURE NUMBER DATE.TITLE Page 13 11/27/81 8110.1 TURBINE SEAL SYSTEMS 10/27/76 Turbine Seal System-Operating Instructions LUBE OIL PURIFICATION AND STORAGE 8500.1 8700.1 8702.1 8703.'1 J 870'.'2 9104.1 9108.1 9204el 9207.1 9208.1i'9304.1 9307-1 9308.1 9400.1 9407.1 9407.2 9407.3 5/14/81 12/15/78 6/21/79.10/26/81-"10/26/81.10/15/81 10/1/81 9/27/77 6/18/81 12/15/78 9/27/77 3/13/81 12/15/78 9/27/77 1/11/80*7/30/81 ,.12/15/78 12/18/80 Turbine Lube Oi.l System.-Transfer, Purification and Cooling GENERATOR Power Generator Grounding for Safety and Test Preparation GENERATOR COOLING SYSTEM E Turbine Generator-Operation of Seal Oil System Turbine Generator-Charging Generator with Hydrogen Purging Hydrogen Crom Generator Turbine Generator Reactivating Hydraulic.gas
~Dr er I MAIN TRANSFORMER
~~Main'Transf ormer-'Peri odi c'Test Main Transformer
-Nal function AUXILIARY'TRANSFORMER Auxiliary.
Transformer
-Periodic'Test Auxiliary Transformer
--Grounding for Safety and Test Preparation Without the Use of Manufacturer's Ground Test Device Auxiliary Transformer
-Nal function STARTUP TRANSFORMER Startup Transformer
-Periodic'Test Startup Transformer
-Grounding for Safety and Test Preparation Without the Use of Manufacturer's Ground Test Device Startup Transformer
-Nal function 4KV SMITCHGEAR Operation of 4160 Volt and 480 Volt LCC Switchgear 4160 Volt Switchgear Triennial Inspection 4160 Volt,Bus Grounding for Safety and Test Preparation Without the Use of Manufacturer's Ground Test Device 4160 Volt Switchgear Cubicle Component Inspection F:PSR PROCEDURE NUMBER DATE TITLE Page 14 10/15/819507.1 9507.-2 9600.1 9604.1=9607.1 9608.1 9654.1 9654.2 9659.1 9659.2 9700.1 9707-1 9900 10100 10107.1., 10200 12/7/79 12/18/80-'/2/78 9 24/81 12/22/78 7/14/78 10/14/80 10/20/80 10/17/80 10/20/80 5/27/77~9/24/81 11/22/74 9/.3/81 8/10/79 0-3/23/71 480 V SMITCHGEAR 480 Volt Switchgear
-Periodic Inspection 480 Volt Circuit Breaker Mounting Modifications Applicable to 480 Volt Motor Control Centers DC SYSTEM DC Electrical System-Normal System Lineup and Operation of Batteries and Char gers DC System-Periodic Tests and Inspections 125 VDC Load Center Undervoltage Alarm Relay Test/Calibration for 3A, 3B;4A, and 4B DC Load Centers 125 V DC System-Location of Grounds ,125 V DC Battery Load Test for 3A and 48 Batteries 125 V DC Battery Load Test for 3B and 4A Batteries 3A and 4B Batteries-Removing from and Returning to Service 3B and 4A Batteries-Removing and Returning to Service INSTRUMENT AC POMER SUPPLY Instrument AC Power Supply-Operation of Normal and Spare Inverters Inverter Annual Inspection
'ISOLATED PHASE BUS Iso-Phase Bus.Cooling System Oper ation CONTAINMENT VENTILATI OH Containment Ventilation and Containment Purge Repair of Containment Purge Valves AUXILIARY BUILDING VEHTILATIOH Auxiliary Building Ventilation CONTROL BUILDING HEATING VEHTILATIOH AHO IR C NDITIOHING 10304.1 10304.2.10307.1 10308.1 1/30/79 1/30/79 Control Room Post MHA Air Conditioning System-HEPA Filter Performance Test Control Room Post MHA Air Conditioning System-Adsorber Cell Performance Test 5/14/76 Emergency'Filter
-HEPA and Adsorber Post MHA Air Cleaning Systems Filter Installation, Removal and Repair 5/30/78'ontrol Building Heating Ventilation and Air Conditioning
-" System-Off-Normal Procedure F:PSR I l PROCEDURE NUMBER DATE TITLE Page 15 11 6 81 11100 11104.1 11107.1 11108.1 11200 11204.1 11207.1 11208.1 ,11500 11550.1 11550.2 11550.4 11550.5 11550.10 ,11550..11
'11550.13 11550.16'1550.17 11550.18 11550.20 11550.21 11550.22 11550.23 11550 24 11550.25 11550.30 11550.31 11550.32 11550.33 11550.34 11550.41 11550.42 11550.43 11550.45 11550.46 11550.47 11550.50 2/29/80 9/26/79 5/7/81 2/15/80 11/15/76 6/18/81 9/18/81 10/1/76:9/18/80 12/5/80 11/25/80 4/2/81 1/5/79 10 23 81.'2/1/80 8/20/81 ,12/7/77 8/27/81 2/1/80 10/25/79'9/7/78'2/31/80 9/7/78 9/7/78 10/8/81 8/20/81 12/4/79 12/5/80 6/13/80 12/4/79 10/4/79 10/4/79 4/25/80 12/5/80 10/1/81 8/27/81 6/28/79 PROCESS RADIATION MONITORING Process Radiation Monitoring System-Operating Instructions Process Radiation Monitoring System-Periodic Test Process Radiation Monitoring System-Maintenance and Calibration Process Radiation Monitoring System-Off-Normal Condition Operati on AREA RADIATION MONITORING RADIATION PROTECTION Health'P-1 HP-2 HP-4 HP-5 HP-10-Physics Manual Radiation Work Permit Radiation Rules of Practice Scheduling of Periodic Health Physics Activities Man-Rem Reporting Calibration and Operation.of Health'Physics Laboratory Counting Equipment Operation of Portal Monitors.and Hand.and Foot Monitors Portable Survey'Instruments Count Rate Instrument Calibration Use of the Eberline Multiple Source Gamma Calibrator Model 1000B Calibration of Portable Gamma Survey Instruments Radiation Surveys Surface Contamination Surveys Airborne Contamination Surveys Environmental and Radiation Controlled Areas-Radiation Monitoring Shielding Surveys Conducting Surveys of Areas Outside the Radiation Controlled Area Personnel Monitoring of External Dose Personnel Monitoring of Internal Dose-Bioassays Pocket Dosimeter Source and Drift Check Operation of the Mhole-Body Counter Matrix Calibration of the Whole-Body Counter hbvement of Material Inside the Radiation Controlled Area Handling and Storage of Radioactive Waste Inventory and Leak Testing of Sealed Sources Release of Material from the Radiation Controlled Area Radioactive Waste Shipping.Compacting Solid Waste Use and Maintenance of Protective Clothing HP-'ll-HP-13-HP-16-HP-17-HP-18-HP-20.-;.HP.-,21-HP-22-HP-23-HP-24-HP-25-HP-30-HP-31-HP-32-HP-33-HP-34'-HP-41-HP-42-HP-43-HP-45-HP-46-HP-47-HP-50-Area Radiation Monitoring System-(ARMS)General Instructions Area Radiation Monitoring System-Periodic Test Area Radiation Monitoring.System-Calibration Area Radiation Monitoring System (ARMS)-Off-Normal Operation F:PSR 1 I PROCEDURE NUMBER..DATE TITLE Page 16 11 6 81 RADIATION PROTECTION (cont'd)11550.55 11550.60 11550.61 10/8/81 7/10/81 2/17/78 11550.64 2/17/78 11550.65 11550.66 11550.67 11550.68 11550.70 11550.71 11550.80 11550.81.11550.90 l1550.91 11550.101 6/13/80 2/1/80 5/29/79 10/31/78 4/25/80 9/7/78 9/3/81 10/30/80 6/11/81 10/15/81 6/11/81 11550.53 4/10/80 HP-53-HP-55-HP-60-HP-61-HP-64-HP-65-HP-66-HP-67-HP-68-HP-70-HP-71-HP-80-HP-81--HP-90-HP-91-HP-10}-Iodine-131 Air Activity Determination By Use-of Whole Body Counter Temporary Shielding Respiratory Protection Manual-Full Face Respirator, Air purifying Type, Scott, Series 801450 and 801500 Full Face Respirators, Airline Type, Mine Safety Appliances Model 93524m Respirator Equipment Maintenance Program Selection,'se, Issue, Control and MPC Hour Accountability of Respiratory Protection Equipment Full-Face Respirator, Self-Contained Breathing Apparatus Type, Scott Pressur-Pak II Operation of the Sodium Chloride Respirator Test Booth Decontamination-of Personnel Decontamination of Tools, Equipment, and Areas gualification of Health Physics personnel Health Physics Training Inventory of Emergency Equipment Emergency Radiation Team Response Radiological Incident Reports.12104.2 12107 1 12107.2 12108 10 23/81 11/.13/80 12/4/79 10/1/76 SOURCE'RANGE NUCLEAR INSTRUMENTATION Source Range'Nuclear Instrumentation
-Periodic Channel Functional Test Source Range Nuclear Instrumentation
-High Voltage and Discriminator Voltage Adjustments Source Range Nuclear Instrumentation
>>Adjustments Source, Range Nuclear Instrumentation Malfunction INTERMEDIATE RANGE NUCLEAR INSTRUMENTATION 12207.1 12207 2 12208 10/8/81 11/13/80 3/3/76 12204.2 10/23/81 Intermediate Range Nuclear'Instrumentation
-Periodic Channel Functional Test Intermediate Range Nuclear Instrumentation
-Compensating Voltage Adjustments Intermediate Range Nuclear Instrumentation
-Checkout and Adjustments Intermediate Range Malfunction F:PSR
~~
C PROCEDURE NUMBER DATE TITLE Page 17 11 6/81 12304.2 10/23/81 12304.3 12304.4 12304.6 12304.8 12307.2 12307.3 6/18/81 6/3/75 6/18/81 7/31/80 4/23/81 ll/13/80 12308 12308.2 10/1/81 8/6/81 22404.1:12404.2 3.2404.3 12407.1 12407.2 8/28/80 1/22/81 3/26/81",3/26/81 12/7/79 12401.2 12/15/77 POWER RANGE NUCLEAR INSTRUMENTATION'ower Range Nuclear'nstrumentation
-Periodic Channel Functional Test Power Range Nuclear Instrumentation
-Shift Checks and Daily, Calibrations Power Range Nuclear Instrumentation
-Channel Check and Calibration Power Range Nuclear Instrumentation
-Calculation of Target Flux Difference Inducing Xenon Oscillation to Produce Various Incore Axial Offsets Power Range Overpower Trip High Range Adjustments quarterly Calibration of the Nuclear Power Range Instrumentation, Axial Flux Deviation Process Instrumentation to OPSP and OTSP, and Nuclear Power Range Axial Flux Deviation Alarm Power Range Nuclear Instrumentation Malfunction Power Range Nuclear-Instrumentation
-Verification of Upper, Lower, and Channel Deviation Alarms ,Incore Nuclear Instrumentation
-Determination of Upper and Lower Limit Switch.Settings Power Distribution"Surveillance Using Incore Movable.Detector System Determination of Effective Axial Peaking'Factor Implementation of Augmented.Surveillance Retracting and Inserting Incore.Instrumentation Thimbles Incore Flux Detector Drive¹chanism Repair and Detector'3.2407.3 9/19/78 Replacement.Incore Flux Mapping System'Thimble Cleaning and Lubrication INCORE THERMOCOUPLES 12607.2 2/15/80 Incore Thermocouple
.-Maintenance Checkout EXCORE NUCLEAR INSTRUMENTATION 12702.1 12707.1 12707.2 13100.1'3100.2 13104.1 13108.1 9/19/79 5/22/80 4/6/79.3/16/79 1/12/81 12/15/78 7/10/81 Normal Alignment of Reactivity Computer'xcore Nuclear Instrumentation
-Receipt, Pre-Installation and Post-Installation Inspections and Test of Detectors Excore Nuclear Instrumentation Installation of Detectors CONTAINMENT LEAKAGE SURVEILLANCE
~, Containment Integrated Leak Rate Test-Unit 3 Contai.nment Integrated Leak Rate Test-Unit 4 Containment Purge Valve Leak Test Loss of Containment Integrity F:PSR PROCEDURE NUMBER DATE TITLE Page 18 11 20 81 CONTA!NMENT TENDONS 13404.1 13404.2 13513 13514.1 13514.2 13523 13531.1 13537.2 10/30/80 12/15/78 11/21/79 8/20/81 6/25/81 2/15/80 1/23/79 3/19/75 PENETRATIONS Containment Boundary Isolation Valves-Local Leak Rate Test Electrical Penetration Canisters-Local Leak Rate Test CONTAINMENT HATCHES Personnel Access Hatch-Operating Instructions Personnel.and Emergency Air Locks-Local Leak Rate Tests Containment Access Hatch-Local.Leak Rate Test (Vacuum Test)Emergency Access Hatch-Operating Instruction Equipment Access Hatch-Local Leak Rate Test Personnel and Emergency Access Hatches-Preventative Maintenance PROCESS INSTRUMENTATION
.14004.1 14004.2 14004.3 14004.4 140O4.5 14007.5 14007-'14007.11 14007..12 14007.13 14007.14 6/13/80 3/26/81 9/18/81~ll/5 811~4/3/80 10/23/81.6/ls/81 I 10/23/81 4/23/81 6/18/81 11/12/81.4/2/81 14007.16 14007.17 14007.18 14007.19 14007'20 14007.21 14007.22 8/27/81 12/7/79 9/18/80 11/14/77 12/22/78 7/31/78 12/22/78 14007.'23 11/14/77 F:PSR 14007.L5 12/5/80 Steam Generator Protection Channels-Periodic Test Reactor Coolant Flow Protection Channels-Periodic Test'Tavg and Delta T Pratection Channels-Periodic Test Pressurizer Pressure.and.Mater Level.Protection Channels-=Periodic'Test Seismograph
-:Periodic Test:Recalibration of High Delta T Alarm Setpoint'Tref Program-Recalibration'avg Alarms-Recalibration Reactor Coolant Temperature Reac"or Coolant Flow.Instrumentatfon Calibration During Refueling Pressurizer Water Level Instrumentation Calibration Pressurizer Pressure Instrumentation.Calibration During Refuel i ng Rod Position Indication Instrumentatfon Ca1ibration During Refueling Steam Generator Level Feedwater Flow and Steam Flow Instrunentation Calibration During Refueling Charging Flow Instrumentation Calibration During Refueling Residual Heat Removal Pump Flow Instrmentatfon Calibration Boric Acid Tank Level Instrumentation Calibration During Refuel i ng Refueling Mater Storage Tank Level Instrumentation Calibration Volume Control Tank Leve'1 Instrunentatfon Calibration.During'Ref uel i ng Containment Pressure (Wide and Narrow Range)Instrumentation Calibration During Refuelfng Containment Sump Level Instrumentation Calibration During Refuel f ng l l l I PROCEDURE NUMBER DATE TITLE Page 19 11 20/81 14007.24 14007.25 14007.26 14007.27 jl/14/77 9/18/80 8/27/81 1/22/80 14007.29 4007.30 14007.31 130 79 11/12/81 11/12/81 14007.28'1jj/12/81 PROCESS INSTRUMENTATION (cont'd)Accumulator Level Instrumentation Calibration During Refueling Accumulator Pressure Instrumentation Calibration During Refueling Steam Line, Steam Header and Turbine 1st Stage Pressure Inst runentati on'al ibr ati on Boric Acid Blender Control System Instrumentation Test During, Refuel i ng Tavg and aT Control Loops Calibr ation Check and Adjustments Recalibration of Over Power Delta T Setpoint'(OPSP)'Auxiliary Feedwater Flow Indication and Control Instrumentation Cal ibrati on Replacement of NBFD Relays in Reactor Protection.and Safeguards System During Refuel ino WATER TREATHENT PLANT 15100 15103 15200.15209 1'5307'1 15307.2 15500 15524 ,15525" 15527.1 15537.}15537.2 15537.3 1 15537.4 15538 15543 15549.1 15600.1 15607.1 15608.1 15650 8/27/81 8/27/81 6/25/81 7/1/81 1/23/79.10/15/81.
- 3/13/81 6/18/81 8/20/81.10/24/78 10/1/81 7/16/81 5/2/80 11/5/81 7/30/81 10/8/81 3/25/77 6/18/81 7/22/80 2/24/81.9/3/81 Mater Treatment Plant (MTP)-Pretreatment Section Startup and.Shutdown WTP Pretreatment
.,Section-Normal Operation WTP Demineralizer Section-Normal Operation WTP Demineralizer Section-Abnormal Operation.-Raw-Mater Supply to Carbon Filkers Primary.Water Hakeup Pump Motor Overhaul and Maintenance Replacing Carbon in Activated Carbon Pressure Filters PRIMARY WATER SYSTEH FIRE PROTECTION SYSTEH Fire Protecti on Program Fire Protection Pump and Power Supply-Periodic Test Fire Protection Underground Piping~Periodic Flow Test Fire Pump Motor Overhaul Fire and Smoke Detec ion System-Semi-Annual
'Test Periodic Surveillance of Fire Protection Equipment Surveillance of Penetration Fire Barriers (Fire Stops)Annual Fire Hose Hyr d~oTest Fire and Smoke Detection System-Operating Instruc.ions Normal Operation of Hain, Auxiliary, Startup Transformers and H" Seal Oil System Deluge Fire Protection System Resetting Deluge Fire Protection System After Actuation of SUPROTEX Automatic Valve INSTRUMENT AIR SYSTEM Instrument Air System-Operating Instructions Instrument Air Compressor Maintenance Loss of Instrument Air Breathing Air System Operating Instruction POLAR CRANE F:PSR
PROCEDURE NUMBER DATE TITLE Page 20 11 13 81 16000.1 16001.2 16002.5 16002.6 16002.7 16004.1 16004.2 16007.1 16008.1 16008.2 16009.1 16009.2 4/24/79 8/20/81 3/13/81 6/11/81 10/30/80 12/15/78 6/11/81 12/20/79 10/23/75 10/23/75 12/4/79 2/15/80 16100 16104.1 16122 16125.1 16125.2 3.6125-3 3.6129.1 16129.3 16200 16204.1 16207.1 16300 16304.1 16400 a6404.1 16404.2 16450 16500 16504.1 16700 16701.1 16702.1)6702 2 16702.3 16702.4 16702.5 12/5/80 12/18/80 3/26/81 5/14/81 aS/4/77 ll/1/?9 10/12/79 10/14/76 12/4/79 8/20/81 3,2/7/79 5/21/76 11/13/80 0-10/13/70 12/4/79 1/30/79 5/21/76 8/4/77 12/4/79 9/11/79 6/11/81 8/27/81 4/12/77 7/16/81 12/22/78 10/25/79 J 1600S.6'l/5/81 FUEL HANDLING Limits and Precautions for Handling Fuel Assemblies Technical Specification Surveillance Requirements for Core Refueling Refueling Core Shuffle Preparations and Precautions for Refueling Fuel Shuffle Refueling Pre-Shuffle in Spent Fuel+it Fuel Transfer Tube Flange Local Leak Rate Test Refueling System Interlocks Verification Fuel Transfer Tube-Installation of Blind Flange Accident Involving New Fuel Accident Involving Spent Fuel Receipt and Handling of New Fuel Containers Site Removal of New Fuel.Assemblies from Shipping Containers and Handling of Shipping Containers On-Site Unpacking Inspection and Manual Loading of Burnable Poison Rod Assemblies Fuel Trans er System Normal Operation Fuel Transfer System-Periodic Test Filling the Refueling Canal and Reactor Refueling Cavity Draining Refueling Cavity Using RHR.System.Draining Refueling Cavity below the Reactor Vessel Flange ,Level via the Reactor Coolant Drain Tank Draining the=Refueling Cavity and SFP:Canal below the Reactor Vessel Flange Level to the RMST using the.Emergency SFP Pump Purifying Reactor.Coolant and Refueling Cavity, During Refueling Using a CVCS Mixed Bed Demineralizer Reactor Cavity Filtration System-Operation and Filter Changeout Manipulator Crane Operating Instructions Manipulator Crane and RCC Change Fixture Periodic Tests Manipulator Crane-Removal and Installation.of Inner Mast and Gripper Spent Fuel Pit Bridge Crane Operating Instructions Spent Fuel Pit Bridge Crane-Periodic Test New Fuel Elevator Operating Instructions New Fuel Elevator-Periodic Test New Fuel Monorail Hoist-Periodic Test New Fuel Monorail Hoist Operating Instructions New Fuel Bridge Crane Operating Instructions New Fuel Bridge Crane-Periodic Test Cask Crane Operating Instructions Gantry Crane-Inspection and Preventative Maintenance Spent Fuel Shipment Using Model NFS-4.Shipping Cask Spent Fuel Transfer Spent Fuel Transfer (NAC and NFS Shipping Cask)Thimble Plug Transfer Spent Fuel Shipment Using National Lead Industries (NLI)--Shipping Cask F:PSR I I PROCEDURE E NUMBER'ATE TITLE Page 21 10 30 81 16707.1 16708.1 16711.1.16900.1 16900.3 16900.4 16900.5 16900.6 16900.9~DELETED 16900.11 16900.12 16900.13 16900.15 16900.16 j.8000 ,20000 20001 20002.20003 ,20004 20005 20006 20101 20102'20103'0104 20105 20106 20107 20109 20110 20111 20112 20113 20125 20126 20201 8/11/78 6/23/76 10/9/74 3/26/81 1/30/75 9/17/74 7/31/78 9/19/74 3/3/76 12/5/80 9/17/74 5/14/81 1/20/78 9/3/81.3/5/81-3/5/81 3/5/81 3/,5/81 6/ll/81 4/25/80 4/23/81 8/20/81.8/14/81 4/23/81 10/8/81 3 26 81 3/26/81 5/7/81 3/26/81 3/26/81 3/26/81 3/26/81 3/26/81 3/26/81 10/15/81 26 81 FUEL HANDLING=(cont'd)Operation of Spent Fuel Building Sliding Door Spent Fuel Cask Emergency Cooling Irradiation Surveillance Capsule Handling Cask DOT-55-14300 Uncoupling Full Length Control Rods Thimble Plug Assembly Handling Tool Spent Fuel Assembly Handling Tool-Operating Instructions Irradiation Specimen Handling Tool Operation and Specimen Contai ner.Transfer Guide Tube Cover Handling Tool-Operating Instructions RCC.Change Fixture Operation Burnable Poison Rod-Assembly Handling Tool Manual Type New Fuel Assembly Handling Fixture Operating Instructions Core Napping Following Core Loading Coupling of Full Length Control Rods Rod Cluster Control Change Tool SAMPLE SYSTEM.DIGITAL DATA PROCESSING SYSTEM EMERGENCY PROCEDURES
(.E-0)-Immediate'Actions and,Diagnostics (E-1)-Loss of Reactor Coolant E-2)-Loss of Secondary Coolant (E-3)-Steam Generator Tube Rupture Loss of Offsite Power Control Room Inaccessability Loss of Feedwater Flow or Steam Generator Level Duties of Emergency Coordinator Duties of an Individual Who Discovers an Emergency Condition Classification of Emergencies and Criteria for Evacuation Emergency Roster On-Site Support Centers Natural Emergencies Fire and Explosion Emergencies Criteria For, and Conduct of Local Evacuation Criteria For, and Conduct of Owner Controlled Area, Evacuation Re-entry Communications Network Nai ntaining Emergency Preparedness, Emergency Exercises, Drills, Tests and Evaluations On-Site Emergency Organization loss of Coolant Accident Dose Calculation Naintaining Emergency Preparedness
-Radiological Emergency Plan Training s
PROCEDURE NUMBER DATE TITLE Page 22 11/20/81-OFF-SITE EMERGENCY ORGANIZATION 1101 1102 9/8/81 9/8/81 Duties of the Emergency Control Officer-Off-Site Emergency Organization Duties of the Recovery Manager, Off-Site Emergency Organization 1103 1104 4/1/81'uties of the Emergency Information Manager;Off-Site Emergency Organization 4/1/81 Duties of.the Emergency Security Manager 1105 1106 1107 1212 ,.1301 4/1/81 4/1/81~4/1/81 4/1/81.9/8/81'10/23/81 Duties of the Emergency Technical Manager Duties of the Governmental Affairs Nanager'Duties and Responsibilities of the Emergency Plan Administrator
~e Activation and Use of the Emergency News Center{Turkey.Point)Activation-and.Use of the Interim Emergency Operations Facility (Turkey Point)Emergency Roster-Off-Site.Emergency.Organi zati on F:PSR
PROCEDURE NUMBER DATE'ITLE Page 23 10/2/81 MP-1A 8/14/81 MP1-AT 8/14/81 WP6-A 8/14/81 MP1-8-AT(1) 8/14/81 MP-8-AT~8/14/81 MP1-T'/14/81 MP1-8-T 8/14/81 MP8-T 8/14/81 WELDING PROCEDURES (Limited Distribution Only)Manual Shielded Netal-Arc Process-For Welding Carbon Steel Plate and Piping Nanual, Combination Process-Melding Tungsten Inert Gas and Shielded Netal Arc-Naterials Group Pl to Pl Manual Shielded Netal-Arc Process-For Melding 12>Chromium Steel Plate and Piping Nanual, Combination Process Melding Tungsten Inert Gas and Shielded Netal Arc Naterialsl Group P8 to Pl Manual, Combination Process Melding, Tungsten Inert Gas and Shielded Netal Arc Naterials Group P8 to P8 Gas Tungsten-Arc Melding-For Naterials in the P-1 Grouping of Section IX of the ASNE Boiler and Pressure Code Gas Tungsten-Arc Welding-For Materials in the P-1 and P-8 Grouping of Section IX of the ASNE Boiler and Pressure Code Gas Tungsten-Arc Melding-GTAM Process For Naterials to be Welded in the P-8 Grouping of Section IX.of the ASNE Boiler and Pressure Code F: PSR
<<)'October 6, 1981 2&2 CONST.~UC:OY,)t:-S::=".-HG~'u~WDW~I I~~test Revision AS."<<1 0."a.~-io..or M.tenace/Be
~Wo.k Pre~~tion o;Site."roceciur>IPx"ess She ts Doc~men Co.."."ol PEP-5 ASP-&7 Chanm Request/Notic Control"."ield Sk hach Preps't'cn WelQ~Control PrO lL~~~~Corr c"='ve Acti~C" er iD.Contr ol:acoctrm~"~
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11/27/81 TURKEY POINT PLANT UNITS 3 and 4 PROCEDURE INDEX LIST OF'EFFECTIVE PAGES: P.ave Date Parcae Date Paae Date 1 2.3 11/27/81 11/20/81.11/20/81 ,10/15/81 3,0/23/Bl.10/15/81 10/30/81.10/23/81 9.10/15/81'.10 11/6/81'1l 10/23/81 12 10/23/81 13.11/27/81.14 3.0/25/81;15'11/6/81.16,,3:1'/6/Bl 17 18 19.20:21'22.23 11/6/81 11/20/81 11/20/81.11/13/81 ,10/30/81 1'1/20/81 3,0/2/81 F:PSR
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