ML17326B386
| ML17326B386 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/24/1988 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| AEP:NRC:0980K, AEP:NRC:980K, NUDOCS 8806010110 | |
| Download: ML17326B386 (12) | |
Text
ACCELERLTED DIAIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8806010110 DOC.DATE: 88/05/24 NOTARIZED-NO DOCKET FACIL:50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana' 05000316 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.
Indiana Michigan Power Co. (formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
NRC No Detailed AffiliationGiven SUBZECT: Forwards description of integrated startup test program for review.
DISTRIBUTION CODE:
IE26D COPIES RECEIVED LTR ENCL SIZE:
TITLE: Startup Report/Refueling Report (per Tech Specs)
NOTES:
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1 RECIPIENT ID CODE/NAME PD3-1 PD NRR CHATTERTON NUDOCS-ABSTRACT RES/DRPS DEPY RGN2/DRSS/EPRPB NRC PDR COPIES LTTR ENCL 1
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Inniana Michigan Power Company P.O, Box 1663t Coiurnbus, OH 43216 INDIANA NICHIGAN POWER AEP:NRC:0980K Donald C.
Cook Nuclear Plant Unit 2 Docket No. 50-316 License No.
DPR-74 INTEGRATED STARTUP TESTING PROGRAM U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 ATTN:
T. E. Murley May 24, 1988
Dear Dr. Murley:
We are submitting, as Attachment 1 to this letter, the Donald C.
Cook Nuclear Plant Unit 2 Integrated Startup Test Program for your review.
The integrated startup test program describes in detail the tests that will be performed prior to and as a part of returning Unit 2 to safe operation following the Steam Generator Repair Project.
The integrated startup testing will be accomplished in three phases:
Construction Testing Phase, Preoperational Testing Phase and Startup Testing Phase.
Each phase will be integrated on a system basis with each phase consisting of a series of tests.
These tests are described in Tables 1-1 and 1-2 of Attachment 1.
These phases of testing, because of the nature of the modifications performed, may occur at different times within the project schedule and may overlap.
In order to allow us to meet our project schedule we would appreciate completion of your review by September 1,
1988.
To assist your staff in their review of the integrated startup test
- program, we are available to provide any supplementary information they may require, in presentation or written format, at their convenience.
SS060i0ii0 SS0524 PDR ADOCK 050003i6 P
DCD A(gs
((,
Dr. T.
E. Murley AEP:NRC:0980K This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, M. P. Ale ich Vice President edg Attachment cc:
D. H. Williams, Jr.
W.
G. 'Smith, Jr.
- Bridgman R.
C. Callen G.
Bruchmann G. Charnoff NRC Resident Inspector
- Bridgman A. B. Davis - Region III
ATTACHMENT 1 DONALD C.
COOK NUCLEAR PLANT UNIT 2 INTEGRATED STARTUP TESTING STEAM GENERATOR REPLACEMENT OUTAGE TEST PHASES The startup effort can be viewed as three testing phases:
construction
- testing, preoperational
- testing, and startup testing.
These testing phases will be integrated on a system basis with each phase consisting of a series of tests which are described below. It should be noted that these phases of testing, because of the nature of modifications performed, may occur at different times within the schedule and may overlap.
1.
Construction Testin Phase The tests in the construction testing phase are designed to provide assurance that construction and installation of equipment and components has been accomplished properly and in accordance with the requirements.
These tests are generally prepared as a part of the work package but may include existing procedures referenced in the work package.
These tests consist of non-dynamic instrument, electrical, and mechanical tests for new or modified systems or components.
The installed components and systems are tested and evaluated according to approved procedures.
Construction tests are performed to assure the quality implementation of the modification.
Any deficiencies, if found, will be corrected prior to satisfactory completion of these tests.
2.
Prep erational Testin Phase The tests in the Preoperational Testing Phase are designed to provide assurance that components and subsystems function safely within established design criteria.
The preoperational testing of new or modified systems is conducted after successful completion of construction testing and prior to declaring a system operable.
This test phase is generally conducted by the Plant operating
- staff, and has the dual purpose of verifying the adequacy of operating procedures on systems that were modified during the repair of the steam generators.
The Preoperational Phase Tests will be performed with the core off loaded.
Therefore, Unit 2 will be considered to be in Mode 6, as defined in Section 3 of the Steam Generator Repair Report, during the preoperational phase test.
The sequence of the individual tests is scheduled with the normal outage scheduling methods.
The Preoperational Testing Phase consists of tests, adjustments, calibrations, and system operations necessary to assure that subsequent operation and/or testing can be safely undertaken.
As an example, the hot primary system tests which are performed prior to reloading the core, include heatup of the primary system to operating, temperature and pressure, thermal expansion checks of affected systems, and a primary system hydrostatic test.
Mhere performance of components or systems deviates from predicted
- results, further.engineering evaluations, rework and/or retesting will be performed to resolve the discrepancies before the test is considered satisfactory.
Components and/or systems which have to be modified as a result of the preoperational testing will be retested to verify acceptable performance.
Preoperational
- testing, in accordance with approved procedures, is performed to verify as near as possible the performance of the systems under actual operating conditions.
Table 1-1 of this attachment lists the preoperational phase tests.
3.
Startu Testin Phase The Startup Testing Phase is designed to provide assurance that systems which were previously demonstrated as functioning safely and the newly modified systems will safely function under normal operating and transient conditions, without significant reduction in the safety margin for the protection of public health and safety.
This phase will be similar to a normal refueling startup and will consist of tests such as; fuel handling equipment tests, containment leakrate tests, safeguards
- tests, low power physics
- tests, and power escalation tests.
Table 1-2 of this attachment lists the Startup Phase Testing.
ORGANIZATIONALRESPONSIBILITIES The Steam Generator Repair Project Manager is responsible for conducting that portion of the outage directly related to replacing the steam generators, and restoring all components,
- systems, and structures to an original or modified status such that they are ready for preoperational tests.
The management and direction of the preoperational and startup testing effort is under the direct control of the Plant Manager.
The Production Supervisor
- Operations is responsible to the Plant Manager for managing, coordinating, and overviewing the overall outage and startup effort.
The Plant Manager has overall responsibility for the preparation and implementation of preoperational and startup test procedures.
Administrative control for making changes to approved procedures are also provided in the existing plant procedures-.
TABLE l-l PREOPERATIONAL PHASE TEST(l)
TITLE OF TEST TEST OBJECTIVE SECONDARY SYSTEM HYDROSTATIC TESTS Steam Generator (S/G) Secondary Side Integrity Test To verify the integrity of secondary side and associated piping following the installation of the new steam generator lower assemblies as specified by ASME Standards for the system.
HOT PRIMARY SYSTEM TESTS RCS Hydrostatic Test The pressure testing of the RCS will be performed at test pressures specified by the ASME standards for the system.
Process Instrumentation (Temperature,
- pressure, level, and flow instruments)
Plant equipment and instrumentation are calibrated, aligned and tested, as appropriate, in accordance with the Plant procedures.
Expansion and Restraints During the heatup to operating temperature, selected points on components and piping of the Reactor Coolant System are checked at various temperatures to verify unrestricted expansion.
Pressurizer During the course of the Plant
- heatup, the pressure controlling capability of the pressurizer will be demonstrated using normal plant operating procedure.
The Pressurizer Safety Valves are tested to verify setpoints using existing Plant procedures prior to reinstallation.
Reactor Coolant Pumps and Motors As the pumps and motors are placed in operation, routine preventive maintenance will be performed.
The reactor coolant pumps will be placed in service using normal Plant operating procedures.
Steam Generators The proper operation of the level indication of each steam generator is checked during heatup and at temperature using normal Plant operating procedure.
TABLE 1-1 (cont'd.)
TITLE OF TEST TEST OBJECTIVE HOT PRIMARY SYSTEM TESTS cont'd Chemical Tests to Establish Water Quality Water for Reactor Coolant System fill and makeup will be analyzed to ensure compliance with the requirements specified in the Plant procedures.
Steam Generator Safety Valves The setpoint of safety valves will be verified by tests at appropriate pressure and temperature conditions in accordance with existing Plant procedures.
Residual Heat Removal System The residual heat removal system's operation will be verified using normal operating and surveillance procedures."
Component Cooling Water (CCW)
System Operational Check The CCW will be placed in service to the components requiring CCW service as required.
Primary Sampling System Primary sampling will be performed as required during the test to support the chemistry requirements.
Note:
1.
The tests may not be performed in the same sequence as they are listed above.
TABLE 1-2 STARTUP PHASE TEST TITLE OF TEST TEST OBJECTIVE FUEL LOAD TESTS Reactor Component Handling System (Polar Crane)
Routine testing will be performed on the polar crane during the construction phase of the steam generator repair project.
Refueling Equipment (Hand Tools, Power Equipment and Associated Protective Interlocks)
Prior to core loading, tests and checks will be performed in accordance with existing Plant procedures to demonstrate the operability of the fuel handling equipment and Fuel Transfer System.
Nuclear Instrumentation System (Source Range)
Nuclear instruments are aligned and operability will be verified using existing Plant procedures.
Area Radiation Monitor Tests Prior to core loading, the Radiation Monitoring System alarms associated with core loading will be checked and the alarm setpoints verified.
Chemical and Volume Control System Makeup and letdown operations will be conducted with the Chemical and Volume Control System to check 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 will be verified.
In addition, the ability to adequately sample will be demonstrated using existing Plant procedures.
These evaluations will be accomplished using normal plant operating procedures.
Safety Injection System The ability of the Safety Injection System to inject borated water into the Reactor Coolant System, will be verified during refueling cavity fill and by appropriate existing Plant surveillance testing.
Primary Chemistry Sampling Prior to, during, and following core loading, primary sampling will be performed to verify that chemistry in the Reactor Coolant System is within Technical Specification limits.
TABLE 1-2 (cont'd.)
TITLE OF TEST TEST OBJECTIVE LEAK RATE TESTS Containment Test Integrated leakrate tests will be performed in accordance with the established Plant program on the requirements of Technical Specifications.
INTEGRATED SAFEGU DS TESTS(1)
Engineered Safety Features The Engineered Safety Features logic matrices will be tested to demonstrate operability, proper logic, redundancy and. coincidence in accordance with Technical Specification requirements and schedule.
Emergency Power Systems The automatic starting and loading of the emergency diesel generators will be demonstrated as part of the Safeguards testing.
Containment Isolation Systems The operation of actuation systems and components used for containment isolation will be verified as part of the Safeguards testing.
Auxiliary Feedwater System Automatic operation of pumps and valves will be verified as part of the Safeguards testing.
Safety Injection System Automatic operation of pumps and valves will be verified as part of the Safeguards testing.
Residual Heat Removal System Automatic operation of pumps and valves will be verified as part of the Safeguards testing.
Containment Spray System Automatic operation of pumps and valves will be verified as part of the Safeguards testing.
Service Water System Automatic operation of pumps and valves will be verified as part of the Safeguards testing.
TABLE 1-2 (cont'd.)
TITLE'F TEST TEST OBJECTIVE INTEGRATED SAFEGUARDS TESTS cont'd Control Room Ventilation Isolation System Automatic initiation of control Room Emergency Ventilation"System into the recirculation mode will be verified as part of the Safeguards testing.
Steam Line Isolation Operation of isolation valves will be verified as part of the Safeguards testing.
CRITICALITYAND LOW POWER PHYSICS TESTS Reactor Protection System Prior to criticality, this system will be tested to demonstrate operability, proper logic, redundancy and coincidence.
The operability of the protection channels will be verified using Plant procedures.
Nuclear Instrumentation (Excore)
Prior to criticality, all channels will be checked to verify high level trip functions, and alarm setpoints.
Control Rod Systems Tests A.
Rod Control System The ability of the system to move rods in the proper sequence both singly and as groups will be verified.
Also the alarm and inhibit functions will be tested and the setpoints verified to specific values.
B.
Rod Drop Tests At hot standby conditions, the drop times of full length rods will be tested.
The drop time is measured from the release of t'e rod until the rod enters the top of the dashpot.
This time will be verified to be less than the maximum value specified in the Technical Specifications.
C.
Rod Position Indication During Rod Control System tests, the Position Indication System will be aligned to provide rod movement'ndication.
At hot standby conditions, individual rod positions will be calibrated to within tolerances specified in existing Plant procedures.
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TITLE OF TEST TEST OBJECTIVE CRITICALITYAND LOWER POWER PHYSICS TESTS cont'd RCS Flow Prior to criticality, the RCS Flow and RTD Bypass Loop Flow will be verified using existing Plant procedures.
Steam Generator Blowdown System Test Blowdown will be verified using normal Plant operating procedures.
Initial Criticality The objective is to bring the reactor critical from the Plant hot standby condition.
Prior to start of rod withdrawal, the nuclear instrumentation will be aligned,
- checked, and conservative reactor trip setpoints made per existing Plant procedures.
At preselected points during rod withdrawal, data will be taken and inverse count rate plots made to enable extrapolation to the expected critical rod position.
Initial criticality and low.power physics tests will be performed in accordance with existing Plant procedures to verify core design parameters.
FULL POWER OPERATION TESTS Power Level Escalation Normal Post Refueling Technical Specification required testing will apply for power level escalation.
Power Conversion System (Turbine Generator)
A.
Vibration Frequency and Amplitude When the main turbine is rolled, using normal plant operating procedures, vibration levels will be continuously monitored and alarmed when excessive vibration is indicated.
(Turbine vibrations are also monitored throughout the Power Escalation Program.)
Major equipment (e.g.,
feedwater pumps and condensate pumps) will be operated as they become available and are observed, using normal plant operating procedures, for indications of, excessive vibration.
TABLE 1-2 (cont'd.)
TITLE OF TEST TEST OBJECTIVE B.
Feedwater and Feedwater Control System During power level escalation, the ability of the Feedwater Pumps and Control System to maintain level in the steam generators will be verified using normal Plant operating procedures.
C.
Steam Generator Makeup Water and Chemical Treatment The Makeup System to the steam generator is expected to remain operational.
The Chemical Treatment System will be checked when chemicals are added to the Condensate or Feedwater System.
Note:
(1)
Safeguards system tests will be conducted on designated trains in accordance with technical specification requirements and schedule.