ML17341A766

Submits Integrated Startup Test Program for Insp & Testing to Be Completed Prior to Returning Unit to Operation After Steam Generator Repair Program,Per Amend 69 to Ol.Apps A,B, C & D Encl

ML17341A766
Person / Time
Site:	Turkey Point
Issue date:	12/23/1981
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Varga S 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 DOCKET

.FAOIL:50 BYNAME 250 Turkey Point <Pl anti "Uni:t 3i Florida IPower and Li'ght >C 05000250 AUTH 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

SUBJECT:

'Submits integrated startup test !program -for insp L testing to be completed iprior to returning uni!t lto operation after

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steam:generator ~repair,programiper Amend 69 'to OL.'Apps Ai'Bp C 8 D encl, WB~

DI'STRIBUTION CODE: A027S >COPIES !RECEIVED:LTR . ENCL, S IZE:.

TITLE: Reactor Star tup Tes,t Repor t ~

NOTES:

RECIPIENT !COPIES RECIPIENT COPIES ID CODE/NAPE LTT'R ENCL ID 'CODE/NAYE LVTR ENCL ACTION; ORB 01 BC 01 3 3 INTERNAL: AEOD 1 1 IE 06 '2 .2 MPA 09 1 1 NRC 'PDR 02 -.1 1 NRR/PHFS DEPY07 1 1- NRR/DHFS DIR 08 1 1 NRR/DHFS/PTRB11 1 1 GCS 1'5 1 0 NRR/DSI/GP8 12 1 1 EG F E 00 1 1 EXTERNALS ACRS 13 1 1 L'P. DR 03 1 1 NSIC 05 1 NT.I S 1 '1 LS+I 0 TOTAL NUMBER OF iCOPIES REQUI'RED: L>TT'R 18 ENCL 17

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FLORIOA POWER & LIGHT COMPANY December 23, 1981 L-81-535 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 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 t'.t 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.

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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 PROGRAM lIKgLgWP ll0l',i l:iLk 3'Oil'7

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APPENDIX A STARTUP NETV/ORK

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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

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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

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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 Criticality and Secondary Hot Functional Primary Fuel Load Type B 4 C Leak Integrated Low Power Full Load Hydro Test and RCS Flush Hydro Rate Testing Safeguards Test Physics Test Oper atio Construction Preoperational Test Phase Startup Test Phase Power Operation Phase

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APPENDIX B LIST OF MA3OR PREOPERATIONAL TESTS AND CHECKS

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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 To verify the integrity of secondary side Integrity Test 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 The Reactor Coolant System is tested accordance with Hot Functional Test using pump heat to reverify heat-up Sequencing Document. 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 verified. 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.

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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 Equipment is aligned and calibrated using pressure, level, and flow instruments) 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 functionally 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

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Page 3 of 6 APPENDIX B LIST OF PREOPERATIONAL TESTS AND CHECKS TITLE OF TEST OR CHECK TEST OR CHECK OB3ECTIVE

6. Steam Generators 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.

7. Chemical Tests to Establish 'Pater V/ater for Reactor Coolant System fill Quality 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.

8. Reactor Coolant Flow Test 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 Makeup and letdown operations are System Tests 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.

10. Emergency Boration System Tests The ability of the emergency borate (Safety Injection System) system is verified by pumping boric acid into the Reactor Coolant System.

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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 TESTS

1. Reactor Protection System 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.

2. Nuclear Instrumentation (Excore) Prior to criticality, all channels are checked to verify high level trip functions, alarm setpoints, operation of strip chart recorders and any auxiliary equipment.

3. Control Rod Systems Tests Prior to plant heatup or at hot shutdown, A. Rod Control System 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 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 fications.

C. Rod Position Indication 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.

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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 At hot shutdown conditions, a functional Test 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.

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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.

6. Steam generator blowdown system flow test at 70% reactor power, when heat recovery portion of the system is available.

2. Power Conversion System (Turbine Generator)

A. Vibration Frequency and Amplitude 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.

B.Turbine Control and Bypass Valves 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 The feedwater and condensate pumps are System 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 The makeup system to the steam Treatment 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.

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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

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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,

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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.

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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)

Bechtel shall furnish Engineering, Construction and Startup services as required by FPL.

0.5 Daniel Construction Com an (Daniel)

Daniel shall furnish Construction Quality Control services as required by the FPL Construction QC Department.

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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).

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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.

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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 Phase Upon 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.

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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.

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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 Turkey Point Units 3 and 0 Procedure Index.

t'.1 8.2 FPL Construction Administrative Site Procedure Index.

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PROCEDURE Page 2 NUMBER DATE TITLE 11 20/81 ADMINI STRATI VE 0103.2 10/1/81 Responsibilities of Operators, on Shift and Maintenance of Operating Logs and Records 0103.3 5/21/81 Control and Use of Jumpers and Disconnected Leads 0103.4 10/23/81 In Plant Equipment Clearance Orders 0103.5 7/30/81 Administrative Control of Valves, Locks and Switches 0103.6 6/26/80 Reportable Occurrences 0103.7 6/26/80 Reports Required by Technical Specifications and 10 CFR 0103.8 8/8/78 Shutdown Rate Guidelines 0103.9 4/24/79 Facility Staff gualifications 0103-10 5/28/81 Using Plant Drawings 01Q3.11 8/14/81 Housekeeping 0103 12 4/2/81 Notification of Significant Event to NRC 0103.13 5/15/80 Fire Watch Patrol 0103.15 10129/81 Operating Experience Feedback J 0103. 16 ll 5/Sl 3/26/81 Onties and Responsibilities of the Shift Technical ~Advisor Preparation, Revision, and Approval of Procedures 0109.1 010S.3 " - 11/25/80. On the Spot Changes to Procedures 0109 6 4/30/79 Temporary Procedures 0110.4 9/3/81 Plant Nuclear Safety Comittee - General Procedures 0149.1 -4/23/81 Special Nuclear Material Accountabiliity 0149 2 .10/31/77 .Determination of Average Annual Capacity Factor 0190 1 8/28/80 guality Assurance and guality Control Program and Organization at Turkey Point 0190.4 .9/24/81 procurement Docunent gualfty Control 0190 9 .2/1/80 .Control of Measuring .and Test Equipment 0190.10 5/15/80 Cleaning of Nuclear Safety Related .Systems and,Components (Mechanical) 0190-12 6/18/81 Nonconforming Material, Parts, or Components.

0190-13 9/.24/81 Corrective Action for Conditions Adverse to guality 0190.14 8/28/80 Document Control and guality Assurance Records Q190 15 10/23/81 plant Projects - Approval, Implementation and Regulatory Requirements 0190.16 5/18/79 Scheduling and Surveillance of Periodic Tests and Checks Required by Technical Specifications 0190.17 2/15/80 Maintaining Records for Design Cycles 0190.19 5/2S/81 Control of Maintenance on Nuclear Safety Related and Fire Protection Systems 0190.Z1 5/29/79 Nuclear Safety Hazards: Identification 0190.Z2 5/18/79 Changes, Tests, and Experiments 0190.23 5/18/79 Electrical Department Instrument Calibration Program 0190.25 7/16/76 Compliance Review Program 0190-26 2/29/80 Calibration Control of Installed Nuclear Safety Related I and C Equipment 0190 27 9/26/79 Electrical Department Installed 'Instrument Calibration Program 0190-28 4/2/81 Mechanical Test Control (Post Maintenance) 0190.61 10/8/81 Control of Liquid Penetrant Testing 0190 62 2/12/79 Requirements for Melding procedures and Melder gualificati ons 0190.63 9/3/81 Melding Filler Metal Control Procedures 0190 67 4/24/79 Melding and Cutting Safety Procedure F:PSR

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PROCEDURE Page 3 NUMBER DATE TITLE 11 20/81 ADMINISTRATIVE (cont 'd) 0190.70 8/28/80 Inspection of. Maintenance Activities on Nuclear Safety Related and Fire Protection Equipment 0190.71 10 23 81 gualification of gualfty Control Inspectors 0190.72 6/18/81 Receipt Inspection, Identification, and Control of Nuclear Safety Related and -Fire Protection Parts, Materials, and Components 0190.73 8/28/80 (}uality Control Surveillance Program 0190.76 3/5/81 Verification of Steam Gener'ator Tube'Plug Installation 0190.77 6/18/81 Ma9netic Particle Inspection (Electromagnetic Yoke Method) 0190.78 6/20/79 Inspection Procedure for Ultrasonic Material'Thickness Measurement GENERAL PLANT PROCEDURES 0202.1 8/20/81 Reactor Startup, Cold Conditions to Hot Shutdown Conditions 0202.2 10/15/81 Unit Startup, Hot Shutdown to Power Operation 0204.1 12/18/80 Secondary Plant Operating Checks and Tests 0204 2 9/3/81 Schedule of Periodic Tests, Checks, Calibrations and Operating Evolutions

,0204.3 5/21/81 Initial Criticality After Refueling 0204 5 4/23/81 Nuclear Design Check Tests During Startup Sequence After Refuel ing

'0205-1 5/2/80 Unit Shutdown, Full Load to Hot Shutdown Conditions 0205.2 7/30/81 Reactor Shutdown, Hot.Shutdown to Cold .Shutdown Conditions 0206-2 6/18/81 .Spent Resin 'System 0206 3 5/21/81 Refueling Mater Storage Tank-- Normal Operation 0206.4 4/.10/80 Periodic Visual Leak Inspection of Systems Outside Che Containment for Control of Radioactive Material Leakage 0206 5 10/30/80 Visual Leak Inspection of Class III Systems 0208.'1 4/23/81 .Shutdown Resulting from Reactor Trip or Turbine Trip 0208 '3 5/7/81 Annunciator List - Panel A Reactor Coolant 0208.4 5/7/81 Annunicator List Panel B - Reactor 0208-5 4/30/79 Annunicator List - Panel C - Steam Generator and Reactor lri'ps 0208.6 5/7/81 Annunciator List - Panel D - Condensate and Feedwater 0208.7 4/10/80 Annunciator List .- Panel E Turbine Generator 0208 8 5/7/81 Annunciator List - Panel F - Electrical 0208.9 5/7/81 Annunciator List - Panel G - Miscellaneous 0208.10 2/12/79 Annunciator List - Panel H - Safety Injection and Auxiliary 0208.11 8/28/80 Annunciator List - Panel I - Station Service 0208.12 8/28/80 Annunciator List - Panel X - Coamon 0208.13 10/1/8 1 I Annunciator List - Maste/Boron Panels 0208.14 ll 0 Deviation or Failure of Reactor Protection and Safety Related Hagan Instrumentation Channels 0209-1 9/24/81 Valve Exercising Procedure 0209.3 9/24/81 Inservice Pump Testing Program Implementation Procedure for Auxiliary Feedwater Pumps 0209.4 11/21/79 Inservice Testing - Valve Seat Leakage Testing F:PSR

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'I PROCEDURE page 4 NUMBER TITLE 10/15/81 TRAINING PROCEDURES 0301 .

8/20/81 Licensed Operator Requalification Program 0303 4/25/77 'uclear Operator and Nuclear Turbine Operator Training and Retraining program 0304 8/20/81 Plant Training 0305 11/14/80 Emergency Team Training 0306 12/12/80 New Employee Indoctrination and Orientation 0307 6/19/81 Shift Technical Advisor Training Program MAINTENANCE PROCEDURE - GENERAL 0701.1 8/14/81 Welding Job Control List 0701.2 9/3/81 quarterly Calibration of Filler Metal (Melding Rod) Ovens

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0703 12/8/78 Naintenance of Copes-Vulcan Air Operated Control Valves

. 0707-1 10/4/79 Series G Chempump Removal, Repair, and Replacement 0707.2 2/24/81 Snubber Inspection and Repair 0707.8 5/22/80 Periodic Calibration of Instrumentation Used in Station Heat Rate Determination 0707.9 12/7/79 Inspection of Swagelok Fittings 0707..10 ~9/24/81 -Reactor Trip and Generator Output Breakers: Inspection and Maintenance 0707-.'ll '3/13/78 "Tube Plugging - Auxiliary Heat.Exchangers with Stainless Steel Tubes and Flanged 'Tube Sheets 0707.'13 12/4/79 Fischer-Porter Hagan 'Pressure 'Transmitters Alignment;,and Calibration Procedure 0707.'14 ll/21/79 Safety and Relief Valve Testing Procedure 0707.15 5/19/78 Fischer-porter Differential Transmitter Alignment, Naintenance, and Calibration 0707.16 1/23/79 Hagan Sumnators Repairs,and Calibration 0707.17 1/23/79 Hagan Single and Dual Comparators Repairs and Calibration 0707.18 12/4/79. Hagan Nanual/Automatic (M/A) Controller Calibration and Repair 0707.19 5/19/78" ;.*Hagan Manual/Auto Control Station Calibration -and Repair

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0707-20 1/23/79 Hagan Isolators Repairs and Calibration 0707-21 1/23/79 Calibration of Hagan Optimac Analog .Computer Elements 0707-25 7/31/78 Hagan 40V and 45V Loop Power Supply Repair and Calibration 0707.26 12/15/78 4160 Volt Motor Grounding and Testing Without the Use of Nanufacturer's Ground and Test Device 0707.27 12/15/78 4160 Volt Motor Grounding and Testing With the Use of Manufacturer's Ground and Test Device 0707-28 12/15/78 4160/480 Volt Load Center Transformer Grounding and Testing Mithout the Use of Manufacturer's Ground and Test Device 0707.29 9/18/80 Calibration of Rosemount Model 1153 Pressure Transmitter 0707 31 9/18/81 Installation of 4KV Switchgear Ground Attachments 0710.0 4/10/80 Liquid Penetrant Testing 0710.1 10/19/76 Liquid Penetrant Testing at Elevated Temperatures 0720 2/5/79 .Preventative Maintenance Program -- Mechanical 0724 4/10/80 'ent and Drain Flange Replacement with Swagelok Plugs F:PSR

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PROCEDURE page 5 NUMBER DATE TITLE 10/23/81 MAINTENANCE PROCEDURE - GENERAL (cont'd) 0725 .1/9/81. Fire vStop and Cable Tray Fireproofing 0726 11/9/78 Velan Pressure Seal Valves - Seal Ring Replacement -. Valves 20139, 239, 339 0728 7/22/80 Bushing Replacement on 5KV Penetration Canisters 0729 .1/22/81 Safety Related MOV Motor Maintenance

'731 8/31/79 Calibration of Mechanical Department Measuring Test Equipment 0732 12/4/79 QC Check and Replacement of BFD/NBFD Relays in Reactor protection and Safeguards Systems 0733 10/2/80 Hagan's NV/I Amplifier Repairs and Calibration 0734 4/2/81 Safety Related Supports/Restraints Removal and Replacement 0735 '/.13/81 Emergency Load Sequencer - General Electric Type - HFA Relay Coil Spool Visual Inspection J 0736 10/15/81 Heavy Load ~Hand11n 0737 6/18/81 Implementation Procedure for Installation of Output Test Points in Hagan Power Supplies REACTOR AND REACTOR COOLANT SYSTEM 1001.1 10/30/80 Filling and Venting the Reactor Coolant System

'1003.1 8/24/79 Netal .Impact Monitoring System - Verification of Alarms 1004..1 6/20/79 RCS - Periodic Leak Test Following RCS Opening 1004 2 8/14/81 Reactor 'Protection System - Periodic Test

,1004.3 5/22/80 Reactivity Deviations from Design Calculations 3.004.4 5/7/81 Overpressure Mitigating System Functional -'Test of Nitrogen Back-Up System 1004. 5 7/10/81 Reactor Coolant pressure Isolation Valve Leakage Testing

'1005.1 6/11/81 Draining the Reactor Coolant System 1007-2 9/11/80 Reactor Coolant Bypass Loop RTD Replacement 1007.3 ~

4/3/80 Setting Reactor Protection Undervoltage Time Delay 'Relays (UVTD) 1007.4 7/15/77 Replacement of RCS Flow Transmitter Above Permissive P-8 1007.5 10/20/77 Daily and Meekly, Checks of Metal Impact Nonitoring System (NIMS) 1007.6 6/11/81 Sub-Cooled Margin Monitor System Maintenance and Calibration 1008.2 9/15/77 Excessive Reactor Coolant System Leakage 1008 3 9/25/75 Loss'f Reactor Coolant Flow 1008.4 9/15/77 Excessive RCS Activity 1008.6 8/28/75 Operation Outside the Axial Flux Difference Target Band 1008.7 8/14/81 Reactor Coolant System Natural Circulation 1009.1 9/11/80 Estimated Critical Conditions 1009.3 10/30/80 Shutdown Margin Calculation 1009.4 4/2/76 .Operation Within the Axial Flux Difference Target Band F:PSR

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PROCEDURE Page 6 NUMBER DATE TITLE 10/15 81 REACTOR COOLANT PUMPS 1100.1 6/6/80 Reactor Coolant Pump Operation 1107.1 11/15/76 Reactor Coolant Pump Seal and Motor Removal 1107.2 12/4/79 Reactor Coolant Pump Seal Inspection 1107.3 9 24/81 Reactor Coolant Pump Impeller Removal and Replacement 1107.4 12 5 80 Reactor Coolant Pump Seal and Motor Replacement 1107.7 9/11/80 Reactor Coolant Pump - Refurbishing of Number 3 Seal 1107.8 7/9/80 Reactor Coolant Pump Motor - Motor Flywheel Removal and Installation 1108.1 7/22/80 Reactor Coolant Pump Off-Normal Conditions PRESSURIZER AND PRESSURIZER RELIEF TANK 1200.'1 6/6/80 Pressur izer Steam Space Venting 1207.1 f9924/81 Pressurizer Safety Valve, Repair and Setting

'207.6 4/10/80 Replacement of Pressurizer Mini Spray Valves 524 and 525 1207.7 7/31/80 Recalibration of Pressurizer Level Program 1207 8 7/31/80 Pressurizer Manway Cover Removal and Replacement 1208.1 7/9/80 Pressurizer Malfunction of Power Operated Relief or Safety Valves 1208-2 3/3/76 Pressurizer - Malfunction of Level Control 1300.1 5/2/80 'Pressurizer Relief Tank Operation REACTOR VESSEL 1407.1, 12/7/79 Reactor Vessel - Removal of Missile Shield 1407.-2 1/5/79 Removal of Control Rod Drive Mechanism Cooling 3.407.3 8/27/81 Reactor Vessel .- Removal of Rod Drive Electrical Cables 1407.4 8/29/78 Reactor Vessel - Removal of Instrument Ports 1407.5 6/7/78 Reactor Vessel - Removal of Head Insulation

'1407.6. 3/26/81 Installation. of Reactor Vessel Cavity Seal Ring

1407.'7 12/5/80 Reactor Vessel"Stud Tensioner, Closure/Nut/Stud Removal and Guide Stud Installation 1407.8 '/26/81 Reactor Vessel Removal of Vessel Head 1407.9 6/11/81 Reactor Vessel - Removal of Upper Internals 1407.10 8/1/79 Reactor Vessel - Installing Upper Internals 1407.11 6/18/81 Reactor Vessel .- Installation of Vessel Head 1407.12 5/7/81 Reactor Vessel Guide Stud Removal, Closure Stud/Nut Installation and Stud Tensioner Operation 1407.13 5/29/79 Removal of Reactor Vessel Cavity Seal Ring 1407-14 6/7/78 Reactor Vessel - Installation of Head Insulation 1407.15 1/11/80 Reactor Vessel - Installation of Instrument Ports 1407-16 8/27/81 Reactor Vessel -- Installation of Rod Drive Electrical Cables 1407-17 6/7/78 Reactor Vessel - Installation of Control Rod Drive Mechanism Cooling 1407. 18 6/7/78 Reactor Vessel - Installation of Missile Shield 1407.19 6/11/81 'eactor Vessel - Removal of Lower Internals 1407.20 7/10/81 .- Reactor Vessel - Installation of Lower Internals 1407.21 ~10 1/81 gefueling Activities Check-Off List J 1407.23 10/8/81 Removal and installation of Spent Fuel pit Keyuay ~Gate F:PSR

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PROCEDURE NUMBER . DATE TITLE

'age 10 30 81 7

STEAM GENERATOR 1502.1 8/8/78 Placing Steam. Generator in Service 1502.2 7/31/80 'Steam Generator Recirculation System 1504.3 9/19/75 Steam G nerator, Moisture Carryover Test 1506.1 7/31/80 Steam Generator Met Layup 1506.2 3/13/81 Steam Generator Pressure Test/Hydrostatic Test 1507.1 7/10/81 Steam Generator Safety Valve Repair and Setting 1507-2 3/26/81 Steam Generator Nanway Cover Removal and Replacement 1507.4 ~10/8 81 Recalibration of Steam Dump Reference Temperature 1507.5 8/8/78 Steam Generator, Safety Valve Removal and Reinstallation 1507.6 5/7/81 Steam Generator Secondary Nanway Cover Removal and Replacement 1507.7 8/1/79 Steam Dump Valves to Atmosphere - Inspection and Repair 1507.8 8/21/80 Steam Generator Main Steam Isolation Valves - Disassembly, Repair and Reassembly 1507.9 4/3/80 Entry into Secondary Side of Steam Generators for Inspection and/or Repair .

1507.10 2/1/80 Entry into Primary Coolant..'Piping for .Visual Examination 1507.11 11/25/80 Steam Generator Handhole Covers and Tube Lane Blocking Device Inserts Removal and Instal'lation 1507-12 8/21/80 Nain Steam Check Valves Disassembly, Repair, and Reassembly

,1508.2 4/25/80 Steam Generator Tube, Leak SECONDARY CHENISTRY 3.560 7/21/78 'Secondary Chemistry - Precautions .and .Limits FULL LENGTH ROD CONTROL CLUSTER ASSEMBLIES 3.600. 1 5/2/80 Full Length Rod Control Mechanism - Motor Generator Operation 1604.1 *7/10/81 Full Length RCC - Periodic Exercise

.1604.3 .10/14/77 At Power Measurement of"Moderator Temperature, Doppler and Power Coefficient 1604.4 9/19/79 Power Defect Measurement 1604.8 4/24/79 CRDM/RPI Stepping and Drop Time Test

. 1604.9 6/20/79 Reactor Full Length Control Rod System (CROM) Test 1607.5 4/10/80 Power Supply Replacement in Full Length Rod Control System

.1607.7 7/15/77 Full Length RCC Position Determination and Lift Nechani sm Checkout 1607-8 2/1/80 Preventative Maintenance - CRDM 1607.10 7/9/80 Inspection of CROM Notors and RPI Stacks and Cables 1608.1 7/10/81 Full Length RCC - Nalfunction ROD POSITION INDICATION 1804.1 10/25/79 Axial Flux, Rod Deviation and Rod Position Indication System-Nonthly Test 1807.4 1/23/79 RPI Amplifier and Indicator Adjustments 1807 5 8/20/79 " Recalibration of Rod Insertion Limits F:PSR

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PROCEDURE Page 8 NUMBER DATE TITLE 10/23/81 CHARGING AND LETDOWN 2101.1 10/14/76 CVCS - Charging and Letdown..- Initial.,Valve Alignment

'- Volume Control Tank Gas Space Concentration Control 2132.1 9/19/79 CVCS 2140.1 4/16/76 CVCS - Charging Pump Operation 2147.1 8/14/81 Charging pump packing Replacement 2147.2 2/24/81 Charging Pump Disassembly, Repair and Assembly 2147.3 8/1/80 Charging Pump Motor Overhaul and Maintenance CHEMICAL MIX SYSTEM 2402.1 ll/30/76 CVCS - Chemical Mix System - Chemical Addition HEAT TRACING 2500.1 1/22/80 Heat Tracing System Normal Operation 2504..1 5/15/80 Heat Tracing System - periodic Test BORON CONCENTRATION CONTROL SYSTEM

,2601. 1 9/19/79 CVCS - Boric Acid .System Valve .Alignment 2603.1 'll/21/79 CVCS - Boron Concentration Control System Automatic Makeup 2603. 5 7/10/81 CVCS Boric Acid Batching and Transferring

.2603.6 9/20/76 Tank Level .Bubbler Lines, Blowdown 2607..1 5/.19/78 Foxboro Magnetic Flow Transmitters Removing from .and Returning to Service

.2608.1 ~10/1/81 Chemical and Volume Control 'System Emergency Boration 2608.2 10/14/76 CVCS -- Malfunction of Boron Concentration Control System BORON RECYCLE SYSTEM 2803. 1 9/19/79 CVCS - Boron Recycle System Operating Instructions

.2819.1 0-11/28/72 CVCS - Purge of CVCS Holdup Tanks 2860.1 1/3/79 CVCS - Gas Stripper Package 2870.1 9/19/79 CVCS - Boric Acid Evaporator Operation

.2879.1 4/10/80 CVCS - Boric Acid Evaporator package Emergency Waste Processing COMPONENT COOLING SYSTEM 3100.1 2/24/78 Component Cooling System Normal Operation 3104.1 8/14/81 Component Cooling Water System - Periodic 'Test of Pumps 3107.'1 4/3/80 Component Cooling pump Seal Replacement 3107.2 4/3/80 Component Cooling Pump Disassembly, Repair and Assembly 3107.3 4/3/80 Component Cooling Water pump Motor Overhaul and Naintenance 3108.1 6/23/76 Component Cooling System - Loss of Component Cooling Flow 3108-2 2/15/80 High Activity in Component Cooling System 3109-1 3/12/76 Component Cooling System Chemical Addition F:PSR

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PROCEDURE Page 9 NUMBER DATE TITLE 10/15 81 RESIDUAL HEAT REMOVAL SYSTEM 3204.1 9/24/81 Residual Heat Removal System - Periodic Test 3205.1 4/3/80 Isolation for Maintenance of Low Head Safety Injection Check Valves (*-875A, *-875B, and *-875C) 3206.2 3/5/81 Residual Heat Removal System -'nnual Test 3206.3 7/30/81 Residual Heat Removal System Hydrostatic Test During Normal Unit Operation 3207.1 9/18/80 .-RHR Pump Seal Replacement 3207.2 12/4/79 RHR Pump Disassembly, Repair and Assembly 3207.4 4/3/80 RHR Motor Operated Stop Valves HOV-*-750 and MOV-*-751 Maintenance 3207.8 4/3/80 Residual Heat Removal Pump Motor Overhaul and Maintenance

.3208.1 6/11/81 Malfunction of Residual Heat Removal System TURBINE PLANT COOLING MATER 3302.1 7/2/81 Turbine Plant Cooling Water System - Startup and Normal Operation 3308.1 2/1/80 Turbine Plant Cooling Water - Nalfunction 3309.1 6/10/81 Chemical Treatment of Turbine Plant .Cooling Mater System INTAKE COOLING MATER

'3404-2 8/.14/81 .Intake Cooling Water .System - Periodic Test of Pumps 3407.1 .10/30/80 Intake Cooling Water - Pump Removal and Instal,lati on of spare 3407.3 10/17/80 Intake Cooling Mater Pump - Disassembly, 'Repair, and Reassembly 3407'4 '7/22/80 Intake Cooling Water.- Pump Motor Overhaul/Maintenance (Louis Allis Motor) 3407 6 5/22/80 Intake Cooling Water Pump Motor Overhaul and,Maintenance (Siemens-Allis) 3408-1 8/1/79 Intake Cooling Water - Malfunction

,3408.2 5/28/81 Intake Cooling Mater - Failure Due to Steam Generator or Nain Transformer Transportation Incident SPENT FUEL PIT COOLING 3500.1 7/30/81 SFP Cooling System -- Normal Operation 3501.1 5/15/80 Spent Fuel Pit Makeup 3501.2 9/22/77 Filling the Spent Fuel Pit 3507.1 8/1/80 Spent Fuel Pit Heat Exchanger Pump Motor Overhaul and Maintenance 3508.1 6/11/81 SFP Gooling -System - Failure of the Spent Fuel Pit Cooling P~p F:PSR

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'ROCEDURE Page 10 NUMBER DATE TITLE 11 6 81 SAFEGUARDS 4004.1 9/24/81 Containment Spray Pumps - Periodic Test 4004.2 6/25/81 Safeguard Relay Rack Train A, B, and Emergency Load Sequencer Timer -- Periodic Test 4004.4 2/11/77 Containment Isolation Rack gR50 and gR51 - Periodic Test 4007.1 3/1/79 Emergency Load Sequencer Time Delay Relay Test, at Refueling 4008.1 5/19/78 Re-energizing Safeguards after Loss of a Single Power Supply SAFETY INJECTION 4103.1 5/7/81 High Head Safety Injection and Containment Spray Lineup for Automatic Operation 4104.1 10 23/81 High Head Safety Injection System - Periodic Test 4104.2 6/18/81 Engineered Safeguards and Emergency Power Systems - Integrated Test 4107-3 5/22/80 Safety Injection System - Check Valve Naintenance 4107.4 4/25/80 Safety Injection System - Lapping of Rockwell 2" Check Valves 4107.5 5/16/79 Electrical Preparations for Integrated Test of Engineered Safeguards and Emergency Power Systems 4107.6 ~

4/3/80 Safety Injection Pump Notor Overhaul and Maintenance 4107.-7 4/23/81 High Head SIS Pump Dis-assembl , Replacement of Rotating Element and Reassemb y CONTAINMENT SPRAY 4204 2 7/31/80 Containment Spray. System Nozzle Functional Test 4207--1 -4/3/80 Containment .Spray System Pump Motor Overhaul and Naintenance EMERGENCY DIESEL GENERATOR 4303.1 10/31/78 Emergency Diesel Generator - Normal Standby Condition 4304.1 6/26/80 Emergency Diesel Generator - Periodic Test Load on 4 KY Bus 4304-2 2/15/80 Emer gency Diesel Generator Operability Test 4307.3 3/16/79 Emergency Di esel Generator - Annual Inspection (Nechanical) 4307.4 Emergency Diesel Generator - Annual Inspection (Electrical)

Generator - Fuel Oil Pump Replacement 10/25/79'/18/80 4307.5 Emergency Diesel ACCUMULATORS 4504.1 10/1/81 Accumulator Check Valves Backleakage Periodic Test EMERGENCY CONTAINMENT COOLERS AND FILTERS

'L 4700 4/10/80 Emergency Coolers and Filters - Normal Operation Procedure 4704.1 9/11/80 Emergency Containment Filter - System Operating Test and Inspection 4704 2 7/21/78 Emergency Containment Charcoal Filters - Surveillance Specimen Evaluation 4704-3 1/23/79 Emergency Containment Filter Systems: HEPA Filters Performance Test F:PSR

j PROCEDURE NUMBER DATE TITLE Page 10/23/81 ll EMERGENCY CONTAINMENT COOLERS AND FILTERS

( 47O4.4 3/8/79 Emergency Containment Performance Test Filter Systems: Adsorber Cells 4704.5 4/3/80 Emergency Containment Coolers - Performance Test at Refueling 4704.6 6/11/81 Emergency Containment Coolers - Periodic Test 4707.1 7/31/80 Emergency Containment Filter Fan Motor Maintenance 4707-2 7/31/80 Emergency Containment. Cooler Fan Motor Maintenance WASTE DISPOSAL SYSTEM - LI UID WASTES 5110.1 12/5/80 MDS - Reactor Coolant Drain Tank Operation 5120 3/13/81 WDS - Laundry, Hot Shower and Chemical Drain .System Operation 5150.3 2/26/76 MDS - Evaporators Number 2 and 3 Operation 5163.1 8/31/79 MDS - Waste Condensate Tank, Polishing Demineralizer and Monitor Tank Operation 5163-2 10/1/81 MDS - Controlled Liquid Release to Circulating Water 5163.4 ll 21 79 Waste Disposal System,.Waste Liquid Demineralizer Operation 5167 1 ,

. 7/14/78 Disassembly and Reassembly of Liquid Waste Release Monitor WASTE DISPOSAL SYSTEM - SOLID WASTES 5323.1 8/31/79 MDS Baler Operations

.5333.1 4/23/81 WDS .- Transferring Spent Resin Storage Tank to Shielded Shipping Cask

'5333.4 9/26/79 WDS Solidification of .Evaporator Concentrates with Cement c WASTE DISPOSAL SYSTEM - GASEOUS 5503.1 10/25/79 MDS-- Gaseous Disposal System Operation 5504. 1 9/12/78 Post Accident Containment Vent System - Equipment Inspection and Operating Tests

-5504 2 1/30/79 Post Accident Containment Vent System - Adsorber Cell Performance Test 5504-3 1/30/79 Post Accident Containment Vent System - HEPA Filter Performance Test 5508'1 11/21/79 WDS - Accidental Release of Radioactive Gas 5508.2 4/10/80 MDS - Off Normal Operation - Gaseous Waste Disposal System 5510 1 5/11/79 MDS - Operation of Gas Analyzer and Gas Sampling Procedures 5523.1 3/26/81 MDS - Gas Decay Tank Controlled Release to Atmosphere 5530 1 4/16/76 MDS - Operation of Waste Gas Compressor 5537.1 4/16/76 MDS - Waste Gas Compressor - Placing in Service and Removing from Service MAIN CONDENSER 6103 1 9/11/78 Amertap Condenser Tube Cleaning System Operation 6108.1 3/12/76 Main Condenser - Loss of Mater Box Prime 6108 2 4/6/79 Main Condenser - Loss of Vacuum

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1 PROCEDURE Page 12 NUMBER . DATE TITLE 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 12/4/79 Operation of Steam Jet Air Qector System Including Hogging Jet CATHODIC PROTECTION 6703 4/7/80 Cathodic Protection - Intake and Condenser - Operating Instructions CONDENSATE SYSTEM 7001.1 4/3/80 Condensate and Feedwater System - Valve Alignment for Normal

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Operation 7100.1 .3/17/80 Condensate Pumps Operating Instructions FEEDWATER SYSTEM 7,200.1 11/1/76 'team Generator Feed Pump - Operating .'Instructions AUXILIARY FEEDWATER SYSTEM C 7300.2 11/16/78 Auxiliary Feedwater System - N2 Backup System Operation 7300.3 7/9/80 Auxiliary Feedwater System - Operating Instructions 7304.1 9/24/81 Auxiliary Feedwater System - Periodic Test 7307.2 9/,18/80 Aux. Feedwater Pump, Disassembly, .Inspection, Repair and Assembly 7307 3 $ 110/8 81 Auxiliary Feedwater Pump Turbine Overhaul 7307. 4 2/29/80 Aux. Feedwater P~p Turbine Throttle Trip Value Overhaul 7308.1 6/25/81 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 1/7/77 Heater Drain pumps - Removing and Returning to Service

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'TURBINE GENERATOR 8001-1 2/9/77 placing Turbine on Turning Gear 8004. 1 1/5/74 Turbine Generator - Overspeed Trip Test

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) ri PROCEDURE Page 13 NUMBER DATE . TITLE 11/27/81 TURBINE SEAL SYSTEMS 8110.1 10/27/76 Turbine Seal System - Operating Instructions LUBE OIL PURIFICATION AND STORAGE 8500.1 5/14/81 Turbine Lube Oi.l System.- Transfer, Purification and Cooling GENERATOR 12/15/78 Power Generator Grounding for Safety and Test Preparation GENERATOR COOLING SYSTEM E

8700.1 6/21/79 Turbine Generator - Operation of Seal Oil System 8702.1 .10/26/81 Turbine Generator - Charging Generator with Hydrogen 8703.'1 -

"10/26/81 Purging Hydrogen Crom Generator J 870'.'2 .10/15/81 Turbine Generator Reactivating Hydraulic.gas ~Dr er I

MAIN TRANSFORMER

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9104.1 10/1/81 Main 'Transf ormer 'Peri odi c 'Test 9108.1 9/27/77 Main Transformer Nal function AUXILIARY'TRANSFORMER 9204el 6/18/81 Auxiliary.Transformer - Periodic 'Test 9207.1 12/15/78 Auxiliary Transformer -- Grounding for Safety and Test Preparation Without the Use of Manufacturer's Ground Test Device 9208.1i 9/27/77 Auxiliary Transformer - Nal function STARTUP TRANSFORMER

'9304.1 3/13/81 Startup Transformer - Periodic 'Test 9307-1 12/15/78 Startup Transformer - Grounding for Safety and Test Preparation Without the Use of Manufacturer's Ground Test Device 9308.1 9/27/77 Startup Transformer - Nal function 4KV SMITCHGEAR 9400.1 1/11/80 Operation of 4160 Volt and 480 Volt LCC Switchgear 9407.1

• 7/30/81 4160 Volt Switchgear Triennial Inspection 9407.2 ,. 12/15/78 4160 Volt,Bus Grounding for Safety and Test Preparation Without the Use of Manufacturer's Ground Test Device 9407.3 12/18/80 4160 Volt Switchgear Cubicle Component Inspection F:PSR

PROCEDURE Page 14 NUMBER DATE TITLE 10/15/81 480 V SMITCHGEAR 9507.1 12/7/79 480 Volt Switchgear - Periodic Inspection 9507.-2 480 Volt Circuit Breaker Mounting Modifications Applicable to 480 Volt Motor Control Centers 12/18/80-'/2/78 DC SYSTEM 9600. 1 DC Electrical System - Normal System Lineup and Operation of Batteries and Char gers 9604.1 =

9 24/81 DC System - Periodic Tests and Inspections 9607.1 12/22/78 125 VDC Load Center Undervoltage Alarm Relay Test/Calibration for 3A, 3B; 4A, and 4B DC Load Centers 9608.1 7/14/78 125 V DC System - Location of Grounds 9654.1 10/14/80 ,125 V DC Battery Load Test for 3A and 48 Batteries 9654.2 10/20/80 125 V DC Battery Load Test for 3B and 4A Batteries 9659.1 10/17/80 3A and 4B Batteries - Removing from and Returning to Service 9659.2 10/20/80 3B and 4A Batteries - Removing and Returning to Service INSTRUMENT AC POMER SUPPLY 9700.1 5/27/77 Instrument AC Power Supply - Operation of Normal and Spare Inverters 9707-1 ~9/24/81 Inverter Annual Inspection

'ISOLATED PHASE BUS 9900 11/22/74 Iso-Phase Bus .Cooling System Oper ation CONTAINMENT VENTILATIOH 10100 9/.3/81 Containment Ventilation and Containment Purge 10107.1 ., 8/10/79 Repair of Containment Purge Valves AUXILIARY BUILDING VEHTILATIOH 10200 0-3/23/71 Auxiliary Building Ventilation CONTROL BUILDING HEATING VEHTILATIOH AHO IR C NDITIOHING 10304.1 1/30/79 Control Room Post MHA Air Conditioning System - HEPA Filter Performance Test 10304.2 1/30/79 Control Room Post MHA Air Conditioning System - Adsorber Cell Performance Test

.10307.1 5/14/76 Emergency'Filter - HEPA and Adsorber Post MHA Air Cleaning Systems Filter Installation, Removal and Repair 10308.1 5/30/78

'ontrol Building Heating Ventilation and Air Conditioning System - Off-Normal Procedure F:PSR

I l PROCEDURE Page 15 NUMBER DATE TITLE 11 6 81 PROCESS RADIATION MONITORING 11100 2/29/80 Process Radiation Monitoring System - Operating Instructions 11104.1 9/26/79 Process Radiation Monitoring System - Periodic Test 11107.1 5/7/81 Process Radiation Monitoring System - Maintenance and Calibration 11108.1 2/15/80 Process Radiation Monitoring System - Off-Normal Condition Operati on AREA RADIATION MONITORING 11200 11/15/76 Area Radiation Monitoring System - (ARMS) General Instructions 11204.1 6/18/81 Area Radiation Monitoring System - Periodic Test 11207.1 9/18/81 Area Radiation Monitoring .System - Calibration 11208.1 10/1/76 Area Radiation Monitoring System (ARMS) - Off-Normal Operation RADIATION PROTECTION

,11500 :9/18/80 Health Physics Manual 11550.1 12/5/80 'P-1 Radiation Work Permit 11550.2 11/25/80 HP-2 Radiation Rules of Practice 11550.4 4/2/81 HP-4 Scheduling of Periodic Health Physics Activities 11550.5 1/5/79 HP-5 Man-Rem Reporting 11550.10 10 23 81 HP Calibration and Operation .of Health 'Physics Laboratory Counting Equipment

,11550..11 .'2/1/80 HP-'ll- Operation of Portal Monitors .and Hand .and Foot Monitors

'11550.13 8/20/81 HP Portable Survey 'Instruments 11550.16 ,12/7/77 HP Count Rate Instrument Calibration

'1550.17 8/27/81 HP Use of the Eberline Multiple Source Gamma Calibrator Model 1000B 11550.18 2/1/80 HP Calibration of Portable Gamma Survey Instruments 11550.20 10/25/79 HP-20 .- Radiation Surveys 11550.21 '9/7/78'2/31/80

.HP.-,21- Surface Contamination Surveys 11550.22 HP Airborne Contamination Surveys 11550.23 9/7/78 HP Environmental and Radiation Controlled Areas-Radiation Monitoring 11550 24 9/7/78 HP Shielding Surveys 11550.25 10/8/81 HP Conducting Surveys of Areas Outside the Radiation Controlled Area 11550.30 8/20/81 HP Personnel Monitoring of External Dose 11550.31 12/4/79 HP Personnel Monitoring of Internal Dose - Bioassays 11550.32 12/5/80 HP Pocket Dosimeter Source and Drift Check 11550.33 6/13/80 HP Operation of the Mhole-Body Counter 11550.34 12/4/79 HP-34 '- Matrix Calibration of the Whole-Body Counter 11550.41 10/4/79 HP hbvement of Material Inside the Radiation Controlled Area 11550.42 10/4/79 HP Handling and Storage of Radioactive Waste 11550.43 4/25/80 HP Inventory and Leak Testing of Sealed Sources 11550.45 12/5/80 HP Release of Material from the Radiation Controlled Area 11550.46 10/1/81 HP Radioactive Waste Shipping .

11550.47 8/27/81 HP Compacting Solid Waste 11550.50 6/28/79 HP Use and Maintenance of Protective Clothing F:PSR

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PROCEDURE Page 16 NUMBER. .DATE TITLE 11 6 81 RADIATION PROTECTION (cont 'd) 11550.53 4/10/80 HP Iodine-131 Air Activity Determination By Use -of Whole Body Counter 11550.55 10/8/81 HP Temporary Shielding 11550.60 7/10/81 HP Respiratory Protection Manual-11550.61 2/17/78 HP Full Face Respirator, Air purifying Type, Scott, Series 801450 and 801500 11550.64 2/17/78 HP Full Face Respirators, Airline Type, Mine Safety Appliances Model 93524m 11550.65 6/13/80 HP Respirator Equipment Maintenance Program 11550.66 2/1/80 HP Selection,'se, Issue, Control and MPC Hour Accountability of Respiratory Protection Equipment 11550.67 5/29/79 HP Full - Face Respirator, Self-Contained Breathing Apparatus Type, Scott Pressur - Pak II 11550.68 10/31/78 HP Operation of the Sodium Chloride Respirator Test Booth 11550.70 4/25/80 HP Decontamination -of Personnel 11550.71 9/7/78 HP Decontamination of Tools, Equipment, and Areas 11550.80 9/3/81 HP gualification of Health Physics personnel 11550.81 10/30/80 HP-81-- Health Physics Training

.11550.90 6/11/81 HP Inventory of Emergency Equipment l1550.91 10/15/81 HP Emergency Radiation Team Response 11550.101 6/11/81 HP-10}- Radiological Incident Reports SOURCE 'RANGE NUCLEAR INSTRUMENTATION

.12104.2 10 23/81 Source Range 'Nuclear Instrumentation - Periodic Channel Functional Test 12107 1 11/.13/80 Source Range Nuclear Instrumentation - High Voltage and Discriminator Voltage Adjustments 12107.2 12/4/79 Source Range Nuclear Instrumentation >> Adjustments 12108 10/1/76 Source, Range Nuclear Instrumentation Malfunction INTERMEDIATE RANGE NUCLEAR INSTRUMENTATION 12204.2 10/23/81 Intermediate Range Nuclear 'Instrumentation - Periodic Channel Functional Test 12207.1 10/8/81 Intermediate Range Nuclear Instrumentation - Compensating Voltage Adjustments 12207 2 11/13/80 Intermediate Range Nuclear Instrumentation - Checkout and Adjustments 12208 3/3/76 Intermediate Range Malfunction F:PSR

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C PROCEDURE Page 17 NUMBER DATE TITLE 11 6/81 POWER RANGE NUCLEAR INSTRUMENTATION'ower 12304.2 10/23/81 Range Nuclear'nstrumentation - Periodic Channel Functional Test 12304.3 6/18/81 Power Range Nuclear Instrumentation - Shift Checks and Daily, Calibrations 12304.4 6/3/75 Power Range Nuclear Instrumentation - Channel Check and Calibration 12304.6 6/18/81 Power Range Nuclear Instrumentation - Calculation of Target Flux Difference 12304.8 7/31/80 Inducing Xenon Oscillation to Produce Various Incore Axial Offsets 12307.2 4/23/81 Power Range Overpower Trip High Range Adjustments 12307.3 ll/13/80 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 12308 10/1/81 Power Range Nuclear Instrumentation Malfunction 12308.2 8/6/81 Power Range Nuclear -Instrumentation - Verification of Upper, Lower, and Channel Deviation Alarms 12401.2 12/15/77 ,Incore Nuclear Instrumentation - Determination of Upper and Lower Limit Switch .Settings 22404.1 8/28/80 Power Distribution "Surveillance Using Incore Movable .Detector System

12404.2 1/22/81 Determination of Effective Axial Peaking 'Factor 3.2404.3 3/26/81 Implementation of Augmented .Surveillance 12407.1 ",3/26/81 Retracting and Inserting Incore .Instrumentation Thimbles 12407.2 12/7/79 Incore Flux Detector Drive ¹chanism Repair and Detector Replacement

'3.2407.3 9/19/78 .Incore Flux Mapping System 'Thimble Cleaning and Lubrication INCORE THERMOCOUPLES 12607.2 2/15/80 Incore Thermocouple .- Maintenance Checkout EXCORE NUCLEAR INSTRUMENTATION 12702.1 9/19/79 Normal Alignment of Reactivity Computer 12707.1 5/22/80 'xcore Nuclear Instrumentation - Receipt, Pre-Installation and Post - Installation Inspections and Test of Detectors 12707.2 4/6/79 Excore Nuclear Instrumentation Installation of Detectors CONTAINMENT LEAKAGE SURVEILLANCE

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.3/16/79 Containment Integrated Leak Rate Test - Unit 3 13100.1'3100.2 1/12/81 Contai.nment Integrated Leak Rate Test - Unit 4 13104.1 12/15/78 Containment Purge Valve Leak Test 13108.1 7/10/81 Loss of Containment Integrity F:PSR

PROCEDURE Page 18 NUMBER DATE TITLE 11 20 81 CONTA!NMENT TENDONS PENETRATIONS 13404.1 10/30/80 Containment Boundary Isolation Valves - Local Leak Rate Test 13404.2 12/15/78 Electrical Penetration Canisters - Local Leak Rate Test CONTAINMENT HATCHES 13513 11/21/79 Personnel Access Hatch - Operating Instructions 13514.1 8/20/81 Personnel .and Emergency Air Locks - Local Leak Rate Tests 13514.2 6/25/81 Containment Access Hatch - Local .Leak Rate Test (Vacuum Test) 13523 2/15/80 Emergency Access Hatch - Operating Instruction 13531.1 1/23/79 Equipment Access Hatch - Local Leak Rate Test 13537.2 3/19/75 Personnel and Emergency Access Hatches - Preventative Maintenance PROCESS INSTRUMENTATION

.14004.1 6/13/80 Steam Generator Protection Channels - Periodic Test 14004.2 3/26/81 Reactor Coolant Flow Protection Channels - Periodic Test 14004.3 9/18/81 'Tavg and Delta T Pratection Channels - Periodic Test 14004.4 ~ll/5 811 Pressurizer Pressure .and .Mater Level. Protection Channels-

=Periodic 'Test 140O4.5 ~

4/3/80 Seismograph :Periodic Test 14007.5 10/23/81 :Recalibration of High Delta T Alarm Setpoint 14007-' .6/ls/81 'Tref Program - Recalibration'avg I 10/23/81 Alarms Recalibration 14007.11 4/23/81 Reactor Coolant Temperature 14007..12 6/18/81 Reac"or Coolant Flow .Instrumentatfon Calibration During Refueling 14007. 13 11/12/81 Pressurizer Water Level Instrumentation Calibration 14007.14 .4/2/81 Pressurizer Pressure Instrumentation .Calibration During Refuel i ng 14007.L5 12/5/80 Rod Position Indication Instrumentatfon Ca1ibration During Refueling 14007. 16 8/27/81 Steam Generator Level Feedwater Flow and Steam Flow Instrunentation Calibration During Refueling 14007.17 12/7/79 Charging Flow Instrumentation Calibration During Refueling 14007.18 9/18/80 Residual Heat Removal Pump Flow Instrmentatfon Calibration 14007.19 11/14/77 Boric Acid Tank Level Instrumentation Calibration During Refuel i ng 14007'20 12/22/78 Refueling Mater Storage Tank Level Instrumentation Calibration 14007.21 7/31/78 Volume Control Tank Leve'1 Instrunentatfon Calibration .During

'Ref uel i ng 14007.22 12/22/78 Containment Pressure (Wide and Narrow Range) Instrumentation Calibration During Refuelfng 14007.'23 11/14/77 Containment Sump Level Instrumentation Calibration During Refuel f ng F:PSR

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PROCEDURE Page 19 NUMBER DATE TITLE 11 20/81 PROCESS INSTRUMENTATION (cont 'd) 14007.24 jl/14/77 Accumulator Level Instrumentation Calibration During Refueling 14007.25 9/18/80 Accumulator Pressure Instrumentation Calibration During Refueling 14007.26 8/27/81 Steam Line, Steam Header and Turbine 1st Stage Pressure Inst runentati on 'al ibr ati on 14007.27 1/22/80 Boric Acid Blender Control System Instrumentation Test During, Refuel i ng 14007.28 '1jj/12/81 Tavg and aT Control Loops Calibr ation Check and Adjustments 14007.29 130 79 Recalibration of Over Power Delta T Setpoint '(OPSP) 4007.30 11/12/81 'Auxiliary Feedwater Flow Indication and Control Instrumentation Cal ibrati on 14007.31 11/12/81 Replacement of NBFD Relays in Reactor Protection.and Safeguards System During Refuel ino WATER TREATHENT PLANT 15100 8/27/81 Mater Treatment Plant (MTP) - Pretreatment Section Startup and.

Shutdown 15103 8/27/81 WTP Pretreatment .,Section - Normal Operation 15200 6/25/81 WTP Demineralizer Section - Normal Operation

.15209 7/1/81 WTP Demineralizer Section Abnormal Operation .- Raw -Mater Supply to Carbon Filkers 1'5307'1 1/23/79 Primary. Water Hakeup Pump Motor Overhaul and Maintenance 15307.2 .10/15/81. Replacing Carbon in Activated Carbon Pressure Filters PRIMARY WATER SYSTEH FIRE PROTECTION SYSTEH 15500 ;3/13/81 Fire Protecti on Program 15524 6/18/81 Fire Protection Pump and Power Supply - Periodic Test

,15525 8/20/81 Fire Protection Underground Piping ~ Periodic Flow Test 15527.1 .10/24/78 Fire Pump Motor Overhaul 15537.} 10/1/81 Fire and Smoke Detec ion System - Semi-Annual 'Test 15537.2 7/16/81 Periodic Surveillance of Fire Protection Equipment 15537.3 5/2/80 Surveillance of Penetration Fire Barriers (Fire Stops) 1 15537.4 11/5/81 Annual Fire Hose Hyrd~oTest 15538 7/30/81 Fire and Smoke Detection System - Operating Instruc.ions 15543 10/8/81 Normal Operation of Hain, Auxiliary, Startup Transformers and H" Seal Oil System Deluge Fire Protection System 15549.1 3/25/77 Resetting Deluge Fire Protection System After Actuation of SUPROTEX Automatic Valve INSTRUMENT AIR SYSTEM 15600.1 6/18/81 Instrument Air System - Operating Instructions 15607.1 7/22/80 Instrument Air Compressor Maintenance 15608.1 2/24/81 Loss of Instrument Air 15650 .9/3/81 Breathing Air System Operating Instruction POLAR CRANE F:PSR

PROCEDURE Page 20 NUMBER DATE TITLE 11 13 81 FUEL HANDLING 16000.1 4/24/79 Limits and Precautions for Handling Fuel Assemblies 16001.2 8/20/81 Technical Specification Surveillance Requirements for Core Refueling 16002.5 3/13/81 Refueling Core Shuffle 16002.6 6/11/81 Preparations and Precautions for Refueling Fuel Shuffle 16002.7 10/30/80 Refueling Pre-Shuffle in Spent Fuel +it 16004.1 12/15/78 Fuel Transfer Tube Flange Local Leak Rate Test 16004.2 6/11/81 Refueling System Interlocks Verification 16007.1 12/20/79 Fuel Transfer Tube - Installation of Blind Flange 16008.1 10/23/75 Accident Involving New Fuel 16008.2 10/23/75 Accident Involving Spent Fuel 16009.1 12/4/79 Receipt and Handling of New Fuel Containers 16009.2 2/15/80 Site Removal of New Fuel. Assemblies from Shipping Containers and Handling of Shipping Containers J 1600S.6 'l/5/81 On-Site Unpacking Inspection and Manual Loading of Burnable Poison Rod Assemblies 16100 12/5/80 Fuel Trans er System Normal Operation 16104.1 12/18/80 Fuel Transfer System - Periodic Test 16122 3/26/81 Filling the Refueling Canal and Reactor Refueling Cavity 16125.1 5/14/81 Draining Refueling Cavity Using RHR .System 16125.2 aS/4/77 .Draining Refueling Cavity below the Reactor Vessel Flange

,Level via the Reactor Coolant Drain Tank 3.6125-3 ll/1/?9 Draining the =Refueling Cavity and SFP:Canal below the Reactor Vessel Flange Level to the RMST using the .Emergency SFP Pump 3.6129.1 10/12/79 Purifying Reactor .Coolant and Refueling Cavity, During Refueling Using a CVCS Mixed Bed Demineralizer 16129.3 10/14/76 Reactor Cavity Filtration System - Operation and Filter Changeout 16200 12/4/79 Manipulator Crane Operating Instructions 16204.1 8/20/81 Manipulator Crane and RCC Change Fixture Periodic Tests 16207.1 3,2/7/79 Manipulator Crane - Removal and Installation .of Inner Mast and Gripper 16300 5/21/76 Spent Fuel Pit Bridge Crane Operating Instructions 16304.1 11/13/80 Spent Fuel Pit Bridge Crane - Periodic Test 16400 0-10/13/70 New Fuel Elevator Operating Instructions a6404.1 12/4/79 New Fuel Elevator - Periodic Test 16404.2 1/30/79 New Fuel Monorail Hoist - Periodic Test 16450 5/21/76 New Fuel Monorail Hoist Operating Instructions 16500 8/4/77 New Fuel Bridge Crane Operating Instructions 16504.1 12/4/79 New Fuel Bridge Crane - Periodic Test 16700 9/11/79 Cask Crane Operating Instructions 16701.1 6/11/81 Gantry Crane - Inspection and Preventative Maintenance 16702.1 8/27/81 Spent Fuel Shipment Using Model NFS-4 .Shipping Cask

)6702 2 4/12/77 Spent Fuel Transfer 16702.3 7/16/81 Spent Fuel Transfer (NAC and NFS Shipping Cask) 16702.4 12/22/78 Thimble Plug Transfer 16702.5 10/25/79 -- Spent Fuel Shipment Using National Lead Industries (NLI)

Shipping Cask F:PSR

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PROCEDURE NUMBER 'ATE TITLE 10 30 81 FUEL HANDLING =(cont'd) 16707.1 8/11/78 Operation of Spent Fuel Building Sliding Door 16708.1 6/23/76 Spent Fuel Cask Emergency Cooling 16711.1 10/9/74 Irradiation Surveillance Capsule Handling Cask DOT-55-14300

.16900.1 3/26/81 Uncoupling Full Length Control Rods 16900.3 1/30/75 Thimble Plug Assembly Handling Tool 16900.4 9/17/74 Spent Fuel Assembly Handling Tool - Operating Instructions 16900.5 7/31/78 Irradiation Specimen Handling Tool Operation and Specimen Contai ner. Transfer 16900.6 9/19/74 Guide Tube Cover Handling Tool - Operating Instructions 16900.9 3/3/76 RCC. Change Fixture Operation

~DELETED 16900.11 12/5/80 Burnable Poison Rod-Assembly Handling Tool Manual Type 16900.12 9/17/74 New Fuel Assembly Handling Fixture Operating Instructions 16900.13 5/14/81 Core Napping Following Core Loading 16900.15 1/20/78 Coupling of Full Length Control Rods 16900.16 9/3/81 Rod Cluster Control Change Tool SAMPLE SYSTEM j.8000 . DIGITAL DATA PROCESSING SYSTEM EMERGENCY PROCEDURES

,20000 .3/5/81 (.E-0) Immediate 'Actions and,Diagnostics 20001 -

3/5/81 (E-1) Loss of Reactor Coolant 20002 3/5/81 E-2) - Loss of Secondary Coolant

.20003 3/,5/81 (E-3) - Steam Generator Tube Rupture

,20004 6/ll/81 Loss of Offsite Power 20005 4/25/80 Control Room Inaccessability 20006 4/23/81 Loss of Feedwater Flow or Steam Generator Level 20101 8/20/81 Duties of Emergency Coordinator 20102 .8/14/81 Duties of an Individual Who Discovers an Emergency Condition

'20103 4/23/81 Classification of Emergencies and Criteria for Evacuation

'0104 10/8/81 Emergency Roster 20105 3 26 81 On-Site Support Centers 20106 3/26/81 Natural Emergencies 20107 5/7/81 Fire and Explosion Emergencies 20109 3/26/81 Criteria For, and Conduct of Local Evacuation 20110 3/26/81 Criteria For, and Conduct of Owner Controlled Area, Evacuation 20111 3/26/81 Re-entry 20112 3/26/81 Communications Network 20113 3/26/81 Nai ntaining Emergency Preparedness, Emergency Exercises, Drills, Tests and Evaluations 20125 3/26/81 On-Site Emergency Organization 20126 10/15/81 loss of Coolant Accident Dose Calculation 20201 26 81 Naintaining Emergency Preparedness - Radiological Emergency Plan Training

s PROCEDURE Page 22 NUMBER DATE TITLE 11/20/81 OFF-SITE EMERGENCY ORGANIZATION 1101 9/8/81 Duties of the Emergency Control Officer - Off-Site Emergency Organization 1102 9/8/81 Duties of the Recovery Manager, Off-Site Emergency Organization 1103 4/1/81 'uties of the Emergency Information Manager; Off-Site Emergency Organization 1104 4/1/81 Duties of .the Emergency Security Manager 1105 4/1/81 Duties of the Emergency Technical Manager 1106 4/1/81 Duties of the Governmental Affairs Nanager 1107 ~

4/1/81 'Duties and Responsibilities of the Emergency Plan Administrator

~ e 4/1/81 Activation and Use of the Emergency News Center {Turkey .Point) 1212 .9/8/81 Activation-and .Use of the Interim Emergency Operations Facility (Turkey Point)

, .1301 '10/23/81 Emergency Roster Off-Site .Emergency .Organi zati on F:PSR

PROCEDURE NUMBER DATE'ITLE Page 23 10/2/81 WELDING PROCEDURES (Limited Distribution Only)

MP-1A 8/14/81 Manual Shielded Netal-Arc Process - For Welding Carbon Steel Plate and Piping MP1-AT 8/14/81 Nanual, Combination Process - Melding Tungsten Inert Gas and Shielded Netal Arc-Naterials Group Pl to Pl WP6-A 8/14/81 Manual Shielded Netal-Arc Process - For Melding 12> Chromium Steel Plate and Piping MP1-8-AT(1) 8/14/81 Nanual, Combination Process Melding Tungsten Inert Gas and Shielded Netal Arc Naterialsl Group P8 to Pl MP-8-AT ~8/14/81 Manual, Combination Process Melding, Tungsten Inert Gas and Shielded Netal Arc Naterials Group P8 to P8 MP1-T '/14/81 Gas Tungsten - Arc Melding - For Naterials in the P-1 Grouping of Section IX of the ASNE Boiler and Pressure Code MP1-8-T 8/14/81 Gas Tungsten - Arc Welding - For Materials in the P-1 and P-8 Grouping of Section IX of the ASNE Boiler and Pressure Code MP8-T 8/14/81 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

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October 6, 1981 2&2 CONST.~UC:OY,

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~ I I 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 Chanm Request/Notic Control PEP-5 "."ield Sk hach Preps't'cn ASP-& WelQ~ Control 7 PrO lL ~~~~

Corr c"='ve Acti~

C" er iD .Contr ol

acoctrm~"~ cn md 'Tr ~~g ASP-11 Corstwction Tv~ove.

A~- i2 Q.A. Recorcs KP-13 Housekeep' P~-14 Control of'~terial Temporarily Hooved frcm Noma~

Ope~~tirg Posi" ion ASP-16 Calibration and Control of Heasuring and Test Equip.

ASP-17 'ir e Prevention

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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 11/27/81 9 .10/15/81 17 11/6/81 2 11/20/81 '.10 11/6/81 18 11/20/81

.3 .11/20/81 '1l 10/23/81 19 11/20/81

,10/15/81 12 10/23/81 .20 .11/13/81 3,0/23/Bl 13 .11/27/81 :21 ,10/30/81

.10/15/81 .14 3.0/25/81 '22 1'1/20/81 10/30/81 ;15 '11/6/81 .23 3,0/2/81

.10/23/81 .16,,3:1'/6/Bl F:PSR

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