ML20039G601

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Forwards Draft FSAR Chapter 14 Pages & Answers to Questions, Per NRC 811218 Request
ML20039G601
Person / Time
Site: Clinton  Constellation icon.png
Issue date: 01/13/1982
From: Plunkett T
ILLINOIS POWER CO.
To: John Miller
Office of Nuclear Reactor Regulation
References
NUDOCS 8201180479
Download: ML20039G601 (100)


Text

ILLINDIS POWER COMPANY IP CLINTON POWER STATION, R.R. n3 BOX 228. CLINTON. IL 61727 January 13, 1982 yet \*/ Q Mr. James R. Miller, Chief M JN D D\

0 Standardization and Special Projects Branch y JAN 151982' q

'""""!m"Wp' Divison of Licensing /

US Nuclear Regulatory Commission %m b: El -

Washington, DC 20555 \.S . /

Dear Mr. Miller:

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Subject:

FSAR Chapter 14 Review ,

Attached are answers to the questions of your December 18, 1981 letter, and a draft copy of the FSAR Chapter 14 pages to be revised. This should satisfy the open items relating to Chapter 14 from the December 2, 1981 meeting at the G.E. offices in Bethesda, Maryland.

I am also sending a copy of this letter and attachments to Walter Apley of Battelle Pacific Northwest Labs as suggested by Mr. Don Fisher of the NRC.

Please call Dave Vincent at 217-937-1111, ext 2443 if you have specific questions on our reply.

Sincerely, o

T. F. Plunkett Plant Manager Clinton Power Station RR 3, Box 228 Clinton, Illinois 61727 TFP/DRV:awd Attachments as stated 300lg cc: G. Wuller I (

J. Greene W. Apley hp[k$ 0 k A

O 640.6:

The information from Table 14.2.-S has been incorpor-ated onto Figure 14.2.6. The reference to " load line" in TC5 has been changed to " rod line",

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O 640.13' Item 3:

a)' Subsection 14.2.12.1.53 will be revised to include as a prerequisite the' completion of the containment drywell structural integrity test.

b) Subsection- 14.2.12.1.52 has been revised to-indicate that_the drywell structural ~ integrity. test. completion is a prerequisite to the 3.0 psig leak rate test.

The drywell structural integrity test is performed in-conjunction with the 30 psig leak rate test'so it can-not be a prerequisite for that test.

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Q. 640.14:

The items identified in listings (2) through (21) have been either clarified or changed to use the phraseology of listing (1).. As you. suggested in your. letter, we have made statements in 14.2.12.1.,and.14.2.12.2 con--

cerning the use of those terms and provided lists of documents from which'the acceptance criteria is obtained.

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0 640.15 Item 2.d:

Our earlier response to this item was in error. The test description reference should have been to 14.2.12.1.39 not 14.2.12.1.9.

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! O 640.15 Item 5.z:

Our original response to this item was in error. The test description referenced should have been 14.2.12.2.2, not 14.2.12.2.1.

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Q 640.16 Item 4 Subsection 14.2.12.1.26'has been revised to describe testing which will demonstrate adequate NPSH and ensure

.vortexing does not occur. This testing will be performed at both normal lake. level and minimum design ultimate heat sink levels. The test will'be performed by actual lowering of the water level, i- ,

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Q 640.16 Item 5:

CPS-FSAR'Section 1.8 states that the project will comply with Regulatory Guide 1.108. Table 14.2-1 will be modified to include Regulatory Guide 1.108.

Specifically subsection 14.2.12.1.36 reflects the require-ments of Regulatory Guide 1.108 in that:

1) Test Procedure item 3. and Acceptance Criteria item 3.l corresponds to part C.2.a.(3) of Regulatory Guide 1.108.
2) _ Test Procedure item 7. and Acceptance Criteria item
3. corresponds to part C.2.a. (9) of Regulatory Guide 1.108.

This preoperational test, as all preoperational_ tests, will be provided for NRC review approximately'60 days prior to performing the test.

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S h Q 640.19 Item 1:

The table of Subsection 14.2.12.2.5 will be revised to include the pressure conditions for position indicator testing.

0 640.19 Item 8:

In addition to the previous response, add to item "C" the following:

"If the analysis is shown to be non-conservative, additional acceptance criteria will be added".

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General:

Tables 14.2-2 and 14.2-3 have been expanded to reflect the current scope of preoperational and startup test pro-cedures.

Future changes will incorporate additional tests being considered.

A new table 14.2-6 has been added to show the content of the Acceptance Test Procedure section 14.2.12.3.

Pages 14-iii and 14-iv have been uodated.

Reading Errata:

The values in degrees Centigrade were incorrect. They were also unnecessary to the test descriptien and have been eliminated from subsection 14.2.12.2.14.4. Note, the setpoint of 145 F has been changed to 100*F.

CPS-FSAR CHAPTER 14 - INITIAL TEST PROGRAM

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k- TABLE OF CON'"ENTS (Cont'd.)

PAGE 14.2.11 Test Program Schedule 14.2-18 14.2.12 Individual Test Descriptions 14.2-18 14.2.12.1 Preoperational Test Procedures 14.2-18

, 14.2.12.2 Startup Test Procedures 14.2-91 14.2.12.3 Acceptance Test Precedures 14.2-?? l

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CPS-FSAR CHAPTER 14 - INITIAL TEST PROGRAM r

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LIST OF TABLES NUMBER TITLE 'PAGE 14.2-1 Regulatory Guides Used In the Development of the Initial Test Program 14.2-145 14.2-2 Properational Tests 14.2-146 14.2-3 Startup Tests 14.2-149 14.2-4 Startup Test Program 14.2-???

14.2-5 Deleted 14.2-???

14.2-6 Acceptance Tests 14.2-???

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CPS-FSAR RMENDMENT 10 NOVEMBER 1981 CHAPTER 14 - INITIAL TEST PROGRAM

{. 3, LIST OF FIGURES NUMBER TITLE 14.2-1 Illinois Power Company Clinton Project Management Organization 14.2-2 Clinton Power Station Startup Group Organization 14.2-3 Baldwin Associates' Clinton Power Station Construction Organization 14.2-4 Calibration and Checkout, Preoperational Test, and Startup Schedule for Unit 1 14.2-5 RCIC Acceptance Criteria Curves for Capacity and Actuation Time 14.2-6 Startup Test Condition Power Flow Map 14.2-7 Deleted k

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CHAPTER 14- INITIAL TEST PROGRAM o

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14.0 INTRODUCTION

This chapter provides information on the initial test program for structures, systems, components, and design features for both the nuclear portion of the plant and the balance of the plant. The .

information addresses major phases of the test program, including re/<,fg preoperational tests, initial fuel loading and initial criticality, ,

low-power tests, and power-ascension tests. The technical aspects .y of the initial test program are described in sufficient detail to _q show that the test program will adequately verify the functional i 7

requirements of plant structures, systems, and components. The :3 sequence of testing is such that the safety of the riant is not 's dependent on untested structures, systems, or components. Also j4 described are the measures taken to ensure that (1) the initial jt" test program will be accomplished with adequate numbers of quali-fied personnel, (2) adequate administrative controls are estab-lished to govern the initial test program, (3) the test program is D

used, to the extent practicable, to train and familiarize the plant operating and technical staff in the operation of the facility, and (4) the adequacy of plant operating and emergency procedures are verified during the period of the initial test program.

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CPS-FSAR heating to rated temperature and pressure; 3) testing from rated temperature and pressure to 1007,of rated output, and 4) war-k.jjp ranty demonstrations. Startup Tests are conducted to verify the performance of equipment under actual operating conditions. These tests also verify interrelated system performance and overall reactor and station operation and control. Systems and components which cannot be checked out fully during the Preoperational Phase are tested during the Startup Phase.

Beginning with the Startup Phase, the Plant Staff assumes overall responsibility for plant testing. The Facility Review Group exer-cises test procedure review and approval responsibilities begin-ning with approval for initial fuel load.

During this phase, reactor operator and senior reactor operator licenses must be held by the required number of personnel on each shift as described in Section 13.1.

During the Startup Phase, the IP Startup Group provides support to the Plant Staff during test performance. This support includes the provision of interface assistance, where required, with General Electric, Baldwin Associates, Sargent & Lundy, various vendors, and other groups within Illinois Power Company. The Startup Group provides test coordination, collects data, and certifies the performance of test steps and results, as required.

Startup personnel act in an advisory capacity to the Shift Super-visor and may, at his discretion, be used to assist in test

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v 14.2.2 Organization and Staffing Sargent & Lundy is the Architect-Engineer for the Clinton Power Station. General Electric Company is the Nuclear steam Supply System (NSSS) Vendor, and Baldwin Associates the Constructor. All of these organizations plus various other vendors, contractors and consultants will be involved to varying degrees in each phase of the test program.

Overall test program coordination is the responsibility of the IP Startup Group.

I 14.2.2.1 Illinois Power Company Organization The Illinois Power Company organizations involved in planning, con-struction, testing and operation of the Clinton Power Station are depicted in Figure 14.2-1.

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To assure that the Startup Program is conducted in an efficient and timely manner, it is directed by the IP Startup Group which plans, executes, and documents the startup activities occurring between the construction phase and commercial operation of the s ta tiori . The Startup Group is also involved in scheduling, test definition, system boundary definition, and other activities that (ygg affect construction phase testing. .. .,ggg

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4. Reviews and provides GE concurrence with nuclear system test results and reports.
5. Provides advice in the on-the-scene training of nuclear plant operating personnel.
6. Obtains home-office and vendor assistance relative to equipment furnished by GE.
7. Provides administrative support to GE site personnel involved in the test program.

14.2.2.4.2 General Electric Test Personnel Should GE personnel be directly involved in testing, they will be integrated into the Startup Group for startup program administra-tive purposes.

14.2.2.5 Staffing Enginecrs involved in testing.are certified as qualified per a Startup Administrative Procedure which is based on ANSI Standard N45.2.6-1973 which is endorsed by NRC Regulatory Guide 1.58.

Levels of certification are assigned based on education and exper-ience. Persons within the Startup Group are certified to at least the level required by the testing or other task to which they are assigned. A copy of the certification of each engineer assigned

{ to the Startup Group is maintained in a controlled manner. l 14.2.3 Test Procedures In general, testing during all phases of the initial test program is conducted using written procedures to control the conduct of each test. Such test procedures include appropriate methods to control test performance (including the sequencing of testing),

specify acceptance criteria by which the test is to be evaluated, and provide for or specify the format by which data or observations are to be recorded.

14.2.3.1 Test Procedure Preparation, Review and Approval

( Preparation, review and approval of procedures used by the Startup Group are governed by a detailed Startup Administrative Procedure.

Construction Tests Procedures related to construction testing are prepared and approved in accordance with the Saldwin Associates' Project Pro-cedures Manual. In addition to review and approval by Baldwin Associates technical and QA personnel, when appropriate, test procedures and any revisions are reviewed and approved by Illinois Power Company, General Electric and/or Sargent & Lundy.

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1. Title t ,

' The title of the procedure shall be descriptive of the nature of the test, include a revision number, and indicate approval status.

2. Objectives This section shall clearly and concisely state the purpose of the test. This section also specifies the general method to be used to accomplish the state d objectives .
3. Acceptance Criteria This section shall clearly identify acceptable stand- /

ards against which the test is judged. In some cases, qualitative criteria is given and in other cases quantitative values are designated as acceptance criteria.

Acceptance criteria is specified for every test or portion of a test where success or failure is to be determined.

4. References
c. This section includes the primary references used to (f prepare the test procedures.
5. Prerequisites This section should identify those activities such as construction completion and component testing which shall be completed prior to conducting the test.
6. Initial Conditions This section shall list those conditions which must be satisfied just prior to commencement of testing. When appro-priate, this shalJ include the configuration and operat-ing status of components within the system undergoing testing, and shall include a list of any special equip-ment, such as measuring and test equipment needed for the test. Where environmental conditions other than ambient are necessary for the test or a portion of the test, such conditions are specified in this section.
7. Special Precautions This section lists any special precautions for the safety of personnel or equipment to be observed during the performance of the test.

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CPS-FSAR The FPR is routed to the IP Supervisor - Construction Engineer-r- ing who obtains concurrence of the cognizant design organization k prior to disposition. Retesting required as a result of a plant modification is accomplished using approved procedures and con-trols in the same manner as previously described testing.

14.2.4.2 Maintenance Maintenance performed on equipment under the IP jurisdictional control is initiated and administered by the use of work requests.

Work requests are reviewed by responsible parties prior to and subsequent to the performance of maintenance. Work requests are not closed until all retesting requirements are satisfied.

14.2.4.3 Performance of Tests Test conduct is governed by a Startup Administrative Procedure.

All testing is accomplished by written procedure. Changes to procedures are documented and subject to approval by persons with qualifications equal to those authorized to approve the original procedure. Approval.for procedure changes must be obtained prior to evaluation of tes~. results..

14.2.5 Review, Evaluation, and Approval of Test Results Construction Phase (E The responsibility for documenting and reviewing all safety-

related testing lies with the Baldwin Associates' Manager of Quality Control and/or the Manager of Technical Services and the IP Site Activities Organization.

Checkout and Initial Onaration Phase Test results obtained during the phase are subject to an evalua-tion to determine whether test performance is accurately and completely documented, that test data is on proper forms, re-quired data is supplied, test results satisfy the stated accept-ance criteria, and that all incomplete items are clearly and properly identified. ,

Generic test results are evaluated by a responsible startup engineer and the Compliance Department. The results of C&IO test l procedures, other than generics, are evaluated by the responsible startup engineer, and the Compliance Department. Acceptance of l results is the responsibility of the Supervisor - Startup.

Should test results prove unacceptable, the cause is determined and corrective action such as maintenance, is authorized per CPS procedures.

Preoperational Phase Preoperational test results are evaluated by the responsible  : _

Lead Startup Engineer, the Compliance Department, and the< responsible.'

design organization. Approval is the responsibility of the Plant :Q[ t iw -- y p x;;ghf my 2_ - MLhwss

CPS-FSAR Acceptance Tests are evaluated by the responsible Lead Startup

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Engineer, and the Compliance Department, and approval is the re-sponsibility of the Plant Manager.

Should test results prove unacceptable, the cause is determined and corrective action is initiated per CPS procedures.

Startup Phase Startup phase results are evaluated b'y the Lead Startup Engineer, Compliance Department, and responsible design organization. Add-itionally, the Facility Review Group evaluates the result. Approval is the responsiblity of the Plant Manager.

Should test results prove unacceptable, the cause is determined and corrective action is initiated per CPS procedures.

Test Release The mechanism used to authorize th e performance of a tes t is the test release. No test may be performed that has not been re-leased for performance. A test release ensures that the approved test procedure has been evaluated against the as-built system and current plant conditions before authorization is given to commence testing. The review also ascertains that test data required as a prerequisite to performance of a test or change in power test plateau has been evaluated and approved.

I Retests When the cause of unacceptable test results has been resolved, a retest is performed covering the portion of the original test in question.

Plant modifications and maintenance are reviewed to ensure that previous test results have not been invalidated by such work and retests are utilized as necessary. Retests will be accomplished per a Startup Administrative Instruction that covers initiation, review, approval, and implementation.

14.2.6 Test Records l r Completed test records are filed in the CPS Document / Records Center. ANSI N45.2.9-1974 is used as a guide in determining retention requirements.

14.2.7 Conformance of Test Programs with Regulatory Guides Table 14.2-1 contains a list of Regulatory Guides used in the development of the Initial Test Program. The program complies with the intent of these regulatory guides , with exceptions as described in Section 1.8.

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CPS-FSAR 14.2.10.1.2 Routine Surveilldace Testing There will be intervals of various lengths between the comple-tion of specific preoperational tests and routine operation of the subject systems. The surveillance program undertaken to satis fy the requirements of the Technical Specifications will be instituted prior to fuel loading tc ensure that routine checks

-are current at fuel loading and through subsequent plant opera-tion.

14.2.10.1.3 Startup Checklists Detailed lists of items that must be complete will be compiled and the items will be verified for completion just prior to fuel load and at significant milestones such as heatup, opening MSIV's and power operation. The lists will consist of items such as preoperational test completions, work request completions, retest completions, test result approvals, Field Problem Report dispositions, Condition Reports dispositions, design change com-pletions and surveillance testing requirements.

14.2.10.1.4 Initial Fuel Loading Fuel loading requires the movement of the full core complement ,!

of assemblies from the fuel pool to the core, with each assembly identified by number before being placed in the correct coordin-

,- are position. The procedure controlling this movement is ye- arranged so that shutdown margin and subcritical checks are made at predetermined intervals throughout the loading, thus ensuring safe loading increments. Specially sensitive in-vessel neutron monitors, that are maintained at the loading face as loading progresses, serve to provide indication for the shutdown margin measurements. They also allow the recording of the core flux level as each assembly is added. A complete check is made of the fully loaded core to ascertain that all assemblies are pro-perly installed, correctly oriented, and are occupying designated positions.

14.2.10.1.5 Zero Power Level Tests At this point in the Initial Test Program a number of tests are conducted which are best described as initial zero power level tests. Chemical and radiochemical tests have been made in order to check the quality of the reactor water before fuel is loaded, and to establish base and background levels which will be required to facilitate later analysis and instrument calibrations. Plant and site radiation surveys are made at specific locations for later comparison with the values obtained at the subsequent operat-ing power levels. Shutdown margin checks are repeated for the fully loaded core, and criticality is achieved with the prescribed rod sequence, data being recorded for each rod withdrawn. Each rod drive is subjected to scram and performance testing. The (jj; initial setting of the Intermediate Range Monitors (IRMs) is at maximum gain. x, .-

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CPS-FSAR 14.2.12 Individual Test Description 14.2.12.1 Preoperational Test Procedures The following test descriptions are provided for each individual preoperational test that will be conducted. During the final con-struction phase, it may be necessary to modify preoperational test methods as operating and preoperational test procedures are developed.

Consequently, methods described in the following descriptiens are general, not specific. Actual test procedures will, of course, be more detailed and will not be limited in scope to what is contained in these descriptions.

When phrases such as "per design, design specifications, consistent with design intent, as designed, ete" are used in the acceptance criteria, that information is taken from the following sources:

General Electric Design Specifications General Electric Design Specifications Data Sheets General Electric Test Specifications General Electric Instrument Setpoint Data Sheets Sargent & Lundy Design Criteria Sargent & Lundy System Descriptions Sargent & Lundy Electrical Schematics Sargent & Lundy Instrument Data Sheets Sargent & Lundy P&ID's Vendor Manuals Supplied by General Electric or Sargent

& Lundy The FSAR Technical Specifications The specific documents used in the preparation of each tests are listed in the reference section of that test procedure. The tests will demonstrate that the installed equipment and systems perform within the limits of these specifications.

Table 14.2-2 provides a listing of the preoperational tests.

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CPS-FSAR 14.2.12.1.1 FEEDWATER SYSTEM l k

Test Objectives

1. To demonstrate operation of the controls, support systems, safety devices, alarms and annunciators for the steam driven and motor driven reactor feed pumps.
2. To verify pump and system hydraulic characteristics.
3. To verify operation and response of the feedwater control system.

Prereauisites and Initial Conditions

1. C&IO testing is complete.
2. The condensate and condensate booster systems are available.
3. Turbine building closed cooling water is available.
4. Circulating water is available.
5. A steam supply for feedpump operation and shaft sealing is available.

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6. Pump, motor and turbine auxiliaries are available.
7. Instrument air is available.

Test Procedure

1. The feedwater control system will be tested to verify oper-ational capability using simulated signals. System align-ment will be accomplished by:
a. Verifying system response to abnormal signal inputs by alarms, interlocksland signal outputs.
b. Verifying response to turbine driven reactor feed pump speed regulators and control to varying steam, feed, and level signals.
c. Verifying response of the motor driven reactor feed pump regulating valve to varying steam, feed, and level signals.
d. Verifying response in run mode, single element mode and manual control.

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2. Feedpump turbines, motor and auxiliaries will be operation-ally tested.
3. Feedwater flow performance will be verified to the maximum extent possible.
4. Pump minimum flow rates and valve operation will be verified.
5. Feedwater heater controls will be tested.
6. Operability of alarms, trips and interlocks will be verified.
7. Valve operation and timing will be verified.

Acceptance Criteria

1. Feedwater controls function as designed.
2. Pump, motor, turbine and auxiliary equipment perform as designed. l
3. Hydraulic performance falls within design limits.
4. Alarms, trips, and interlocks function as designed. j
5. Valve operation and timing (including isolation) falls within L . design tolerances.

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CPS-FSAR 14.2.12.1.2 REACTOR WATER CLEANUP SYSTEM f x Test Objectives

1. To demonstrate the integrated operation of the reactor water cleanup system.
2. To operationally check the pumps, control stations, cleanup filter demineralizers, interlocks, and alarms.

Prereauisites and Initial Conditions

1. C&IO testing is complete.
2. Component cooling water is available.
3. Resin and filter aid is available.

4 A sufficient quantity of chemically acceptable water is available.

5. The Reactor Pressure Vessel, main condenser and liquid rad-waste system are available to receive water.

Test Procedure

1. System performance will be checked at ambient reactor pres-sure and temperature.
2. Blowdown to radwaste and the main condenser will be demon-strated.
3. The backwash and precoat operations of the filter-demineral-izers will be demonstrated.
4. Operability of interlocks, isolations, controls and alarms will be verified.

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5. Leak detection circuitry associated with the reactor water cleanup system will be checked.
6. Valve operation will be verified.

Acceptance Criteria

1. Pump and system performance will indicate that the reactor water cleanup system should perform as designed at rated temperature i and pressure.
2. Interlocks, isolations, controls and alarms will perform as

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CPS-FSAR 14.2.12.1.3 STANDBY LIQUID CONTROL SYSTEM '

r' i Test Objectives

1. To verify the operability of the system.
2. To demonstrate system test modes.

Prereauisites and Initial Conditions

1. C&IO testing has been completed.
2. A sufficient quantity of chemically acceptable water is avail-able to conduct the test.
3. The reactor vessel is capable of accepting demineralized water during the test.
4. The inboard and outboard isolation valves for the reactor water cleanup system are available for testing.
5. Service air is available.
6. The setpoints of the standby liquid control pumps' discharge relief valves have been verified.

,C Test Procedure

1. The standby liquid control storage tank will be filled with demineralized water and the following checks performed:
a. The tank level and temperature alarms will be verified.
b. The tank temperature controls and air sparger will be checked.
c. The standby liquid control pumps will be operated.
2. The test tank will be filled with demineralized water and the following accomplished'. '
a. The standby liquid control pumps will be operated in the test mode.
b. Pump packing will be adjusted to minimize leakage.
3. Each loop will be started using the keylock switch. Flow rates to the reactor will be measured. Isolation of the reactor water cleanup system will be verified during this test.
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4. Prior to fuel loading the standby liquid control tank will e' be filled with the required boron solution, mixed and sampled.
5. Heat tracing will be functionally tested.

Acceptance Criteria

1. All alarms will actuate at points within tolerances set forth in the station instrument data sheets.
2. Temperature will be maintained in the standby liquid control storage tank.
3. The air sparger will function as designed.
4. The system functions per design in the test mode.
5. All design actions and interlocks will take place when the keylock switch is placed in run and in stop.
6. Flow rates to the reactor are within limits set by design.
7. Pump packing leakage is within design limits.
8. The solution in the standby liquid control tank will be verified by normal sampling means to meet the chemistry

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9. Heat tracing will perform its design function.

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, 14.2.12.1.4 NUCLEAR BOILER SYSTEM

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Test Obiectives

1. To verify nuclear boiler instrumentation functions.
2. To verify functional operation of the main steam isolation valves, main steam relief valves and auto-depressurization.
3. To verify operation of controls, interlocks, and alarms associated with the nuclear boiler system including automatic containment isolation capability.
4. To verify leak detection circuitry associated with nuclear boiler piping.
5. To verify the nuclear steam supply system operation.

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Prerequisites and Initial Conditions

1. C&IO testing is complete.
2. Instrument air is available.
3. The reactor and main steam lines can accept water.

Test Procedure

1. Nuclear boiler controls, alarms, and interlocks will be verified.
2. Main steam isolation valve operation will be checked.
3. Main steam isolation valves will be operated by remote con-trol and in the auto-isolation mode.
4. Main steam relief valve's will'be functionally tested.
5. Reactor vessel water level will be varied and nuclear boiler level instrumentation verified.
6. Safety / relief and MSIV accumulators will be capacity tested.
7. Leak detection circuitry will be tested.
8. MSIV cold operating times will be check'd.
9. Nuclear steam supply shutoff system logic and valve operation will be verified.

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CPS-FSAR 14.2.12.1.5 RESIDUAL HEAT REMOVAL SYSTEM

'a i Test Objectives

1. To verify proper operation of controls, interlocks, and alarms associated with each mode of operation.
2. To verify the capability of the residual heat removal system to deliver sufficient flow during various modes of operation.
3. Verify proper operation of the leak detection circuitry asso-ciated with the residual heat removal system components and piping.
4. Demonstrate actions upon receipt of isolation signals.

Prerequisites and Initial Conditions

1. Checkout and initial operation phase testing has been completed.
2. A sufficient supply of chemically acceptable water is available in the suppression pool and the reactor vessel.
3. The reactor vessel is available to receive water during the LPCI, and the shutdown cooling modes of operation.

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4. Shutdown service uater is available.
5. The reactor recirculation system and pumps are available for operation during the shutdown cooling mode test.
6. The RCIC system is available for testing.

Test Procedure

1. Logic and interlock tests will be performed for all modes of operation. With the pumps locked out, each mode will be actuated from each possible source and all associated events will be monitored. Valve timing will be checked. The modes to be checked are low pressure coolant injection, suppression pool cooling, reactor steam condensing, shutdown cooling, con-tainment spray, and test.
2. The RHR pumps will be performance tested.
3. Using a simulated LPCI automatic initiation signal, establish f1cw. Monitor system characteristics with the various com-binations of one , two or three pumps operating.

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4. Align the system for the suppression pool cooling mode. Head C.Jg C versus flow curves will be obtained for each pump.
5. Using simulated signals, the interlocks and controls associated with the reactor stcam condensing mode will be verified.
6. The system will be aligned in the shutdown cooling mode. System flow parameters will be checked.
7. Establish a flow of gas through the containment spray nozzles.

Flow through individual nozzles will be verified by the use of ,

smoke bombs, flags or some other means. Verify the path be-tween the containment spray isolation valve and the air test connection by either pressurizing the line with water from the flushing water header upstream of the containment spray isolation valves and obtaining flow at the air test connection or by pressurizing the line with air and obtaining air flow at a vent or test connection upstream of the containment spray isolation valves.

8. The system will be placed 'in the test mode. Flow curves will be obtained to use as a basis for evaluating performance during future testing. .
9. Area and valve leak detection sensors and logic associated with the RHR system will be checked for proper operation.

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' 10. Verify the system standby mode including water leg pump operation.

11. Remote shutdown control capability will be verified.
12. Verify that paths for the air-flow test of containment spray nozzles overlap the water-flow test _ paths of the

.' pumps to demonstrate that there is no blockage in the flow path.

Acceptance Criteria -

1. Logic and interlocks will perform per design specifications.
2. Valves will operate within time limits specified by design.
3. Pump performance results will indicate performance of design functions. t
4. Flow and pressures during each mode will be consistent with design intent. Flow orifice size will be verified to be. correos, i 4 u.c o,J7me e as.1 A ed ur s m .
5. Performance data will be acquired to use as a reference when testing the system during plant operation.
6. Area and valve leak detection circuitry will perform per design specifications.
7. Leak detection flow sensors and logic will perform per design. .
8. The system standby mode and unter lag pump cra demonstrated N' =ric f = = L: il-r to opero+e a'r Sc 3 & e<l _

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Test Objectives

1. To verify the operation of the controls, alarms, interlocks, and valves associated with the RCIC system.
2. To verify automatic and manual system activation.
3. To verify automatic and manual system isolation.
4. RCIC turbine operation and pump flow parameters will be deter-mined to the extent possible with an auxiliary steam supply.

Prerequisites and Initial Conditions

1. Checkout and initial operation phase testing has been completed.
2. A source of steam is available for RCIC turbine operation.
3. The suppression pool is available to receive the RCIC turbine.

exhaust.

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4 Chemically acceptable water is available in the RCIC storage tank and suppression pool in sufficient quantity to perform the test.

5. The reactor vessel is available to receive water.

Test Procedure

1. Alarns, controls, and interlocks will be checked.
2. Automatic valves will be cycled and timing checked.
3. The system will be activated manually and by introduction of the automatic initiation signal.
4. The standby mode will be tested.
5. With auxiliary steam, RCIC turbine operation will be checked and pump operation will be verified with suction from the RCIC storage tank and with suction from the suppression pool.
6. Leak detection associated with the RCIC system will be tested.
7. Remote shutdoun control capability will be verified, kb? .

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CPS-FSAR Acceptance Criteria r.

( l. All alarms, controls, and interlocks will perform their design function.

2. Automatic valves will operate as designed and within time limits specified by design. l
3. Valve actuations will take place as designed when each system activation or isolation signal is introduced.
4. Turbine parameters will be consistent with the vendors instruction manual.

5.

ThestandbymodeincludingRCICwaterlekpumpperformance will be verified to be in accordance wic design. l

6. Leak detection circuitry performs within design specifications.
7. Flow will be verified ro be in accordance with design, through '

the flow paths to the reactor vessel and suppression pool using j auxiliary steam to drive the pump turbine.

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CPS-FSAR 14.2.12.1.7 REACTOR RECIRCULATION SYSTEM

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Test Objectives

1. To demonstrate the functional capability of the recirculation system controls, motors, MG sets, pumps and valves to work as a system to deliver recirculation flow.
2. To the extent possible, under cold conditions with no fuel in the reactor vessel, preliminary performance data of the re-circulation pumps, jet pumps, and recirculation system will be obtained.

Prereauisites and Initial Conditions

1. Checkout and initial operation phase testing has been completed.
2. Component cooling water is available.
3. Seal water is available from the control rod drive system.
4. The support systens for pumps and motors are operable.
5. The raactor vessel is available for testing.
6. A sufficient quantity of chemically acceptable water is availcble.

Test Procedure

1. Valves will be tested for proper operation including timing, interlocks, and indication.
2. With the recirculation pumps operating within the limits dictated by the system. conditions:
a. Instrumentation, controls, and interlocks will be checked.
b. Recirculation and jet pump performance characteristics will be tested to the extent practicable.
c. Flow control valve operation will be demonstrated.
3. Leak detection associated with the reactor recirculation system will be tested.
4. Recirculation pump vibration will be monitored.

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Acceptance Criteria

1. Jet pump characteristics will be within manufacturers' speci-fications.
2. System valves will operate per design specifications.
3. Iaterlocks, controls, and instrumentation function in accord-ance with design specifications.
4. Measured pump and system performance. will be analyzed for t possible indications of design perfr6mance deficiencies under expected system operating conditions.
5. Leak detection circuitry will perform within design specifica-tions.
6. Recirculation pump vibration will be within design specified limits for speeds at which it is monitored .

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CPS-FSAR 14.2.12.1.8 ROD CONTROL AND INFORMATION SYSTEM x

Test Objectives

1. To verify operation of the rod control and information system including relays, control circuitry, switches and indicating lights, and control valves.

Prerequisites and Initial Conditions

1. Checkout and initial operation phase testing has been completed.
2. The CRD system is operational.

Test Procedure

1. Rod blocks, interlocks, and alarms will be verified.
2. The rod control and information system capability will be demonstrated by individual and integrated tests of the following:

, a. rod pattern controller t-

b. rod interface system
c. rod activity control system
d. rod gang drive system
e. rod position information system Acceptance Criteria
1. Rod blocks, interlocks; and alarms function as designed.
2. The rod control and information system functions as designed.
3. Valve timing, rod inhibit logic, rod pattern control, and valve drive commands will function as designed.

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14.2.12.1.9 CONTROL ROD DRIVE SYSTEM  !

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(!d Test Objectives l l

1. To verify the performance characteristics of the control rod drive water pumps.
2. To demonstrate that the CRD system is fully operational.
3. To insure that flow control valves are adjusted for correct drive speeds.

Prerequisites and Initial Conditions

1. Checkout and initial operation phase testing has been completed.
2. Chemically acceptable water is available in sufficient quantity to perform the test.

3.

The test.

reactor vessel is available to receive water use for the

4. The rod control and information system is functional and available.

,( . , 5. The reactor protection system is available.

6. Instrument air is available.
7. Nitrogen is available.

Test Procedure

1. The control rod drive water pumps ~will be checked for flow, pressure, and vibration.
2. Proper hydraulic functions will be verified for charging accumulators, drive water, cooling water, and discharge water headers during single and ganged rod modes of operation.

3.

Pressure differentials across filters and strainers and their associated alarm functions will be verified.

4. Proper seal flow to drive water and reactor recirculation pumps will be verified.
5. CRD notch control including latching and position indication will be verified.

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6. Withdrawal and insertion speeds of each rod will be verified

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and flow control valves will be adjusted as necessary. .

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7. Scram testing of control rods, with the reactor at atmos-e' pheric pressure, will be accomplished.

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, 8. Transient response data for the total system will be compiled during insertion, withdrawal and scram functions.

Acceptance Criteria

1. Pump performance and vibration shall fall within the manu-facturer's specification limits.
2. Hydraulic flows and pressures shall fall within designspecificationl limits.

4

3. Pressure differentials across filters and the strainer will be within I designed. design specified limits and alarms will function as i
4. Seal water flows will be within the range necessary to perform as specified by design.  :
5. Scram time, rod insert and withdrawal times will be within the limits set by the technical specifications.
6. Transient response will be analyzed to insure that performance is within design specified limits. l i

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7. Scram discharge volume capacity is adequate to perform its designed J functions. l
8. Scram discharge volume instrumentation alarm, rod block and scram functions operate as designed.

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CPS-FSAR 14.2.12.1.10 FUEL HANDLING AND VESSEL SERVICING EQUIPMENT 3

(. l Test Objectives

1. To demonstrate operation of the fuel handling vessel servic-ing equipment.
2. To demonstrate operation of the fuel transfer system and equipment.

Prerequisites and Initial Conditions

1. Checkout and initial operation phase testing has been completed.
2. The service air system is available.
3. The fuel pool and containment pools are available for testing.
4. The reactor protection system is available for testing.
5. The rod control and information system is available.

. AS 6. Slings and lifting devices are certified at design loads.

Test Procedure

1. Demonstrate operation of the refueling bridge and auxiliary platform including interlocks and logic.

! 2. Demonstrate operation of equipment used to transfer fuel between the containment and fuel buildings.

3. Demonstrate operation of the_ transfer tube valves.

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4. Demonstrate operation of the fuel handling platform including
interlocks and logic.
5. Verify operability of the following equipment:
a. cell disassembly tools
b. channel replacement tools
c. instrument handling tools
d. vacuum cleaning equipment s

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CPS-FSAR 14.2.12.1.11 LOW PRESSURE CORE SPRAY SYSTEM

--PREOPERATIONAL TEST.

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_ Test Objectives

1. To demonstrate operability of the low pressure core spray system.
2. To verify the core spray pattern. '
3. To verify proper operation of controls, interlocks, and alarms associated with system operation.

. 4. To verify operation in the test mode.

Prereauisites and Initial Condition

1. Checkout and initial operation phase testing has been completed.
2. A sufficient supply of chemically acceptable water is avail-able in the suppression pool.
3. The reactor vessel is available to receive water.
. 4. The RHR system is available for testing.

( .... Test Procedure

1. Logic and interlock checks including manual and automatic actuations will be performed. ' -
2. The LPCS pump will be performance tested.
3. The system will be placed' in the core spray mode for flow and spray' pattern verification. The spray pattern will be photographed for analysis of core coverage. l
                                                                                                                                                                          )
4. The system will be placed in'the test mode. Pump and system .

parameters will be recorded.

5. Remote valve operation will be verified.
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                        "       Leak detection  ~~           instrumentation associated with LPCS will be
                                ~tes ted. '                             .
7. The standby lineup and water leg pump'bperation will be demonstrated. -

Acceptance Criteria (}. .

1. Logic, interlocks, and alarms will operate per design specifications. .
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2. Pump and system fl[w' performance will be per design
     %.                         specifications.
3. Valve operating times will be within design limits.
4. Leak detection instrumentation will function in accordance with design specifications.
5. Core spray photographs have been reviewed by GE to determine that the spray pattern gives total core coverage. ,

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  • ~' CPS-FSAR 14.2.12.1.12 HIGH-PRESSURE CORE SPRAY SYSTEM ,

PREOPERATIONAL TEST (v;..h : Test Objectives

1. To demonstrate the operability of the high pressure core spray system.
2. To verify the core spray pattern and flow rate. .
3. To verify proper operation of controls, interlocks, and ~

alarms associated with system operation.

4. To verify operation in the test mode.

Prercouisites and Initial Conditions

1. Checkout and initial operation phase testing has been completed.
                                                                                        .t
2. A sufficient supply of chemically acceptable water is avail-able in the suppression pool and.the RCIC storage tank.
3. The reactor vessel is available to receive water.
4. Diesel IC.is available for testing.

Test Procedure - s-

1. Logic and interlock checks including.-manual and automatic actuations will be performed,.
2. The HPCS pump will be performance tested.
3. The system will be placed in the core spray mode for flow and spray pattern verification. The spray pattern will be photo- ji graphed for analysis of core coverage, , q
4. T he system will be placed in the test mode. Pump and system parameters will be recorded.
5. Remote valve operation will be verifie,d.
                    ~6.       I;eak detectiun instrumentation associated with HPCS will be tested.                                                                       ,

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7. The standby lineup and water leg pump'joperation will be demonstrated. _,
8. Diesel interlocks will be verified.

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9. Pump and motor tests with normal and diesel power supplies will be perform 6d. .
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CPS-FSAR Acceptance Criteria r v 1. Logic, interlocks, and alarms will operate per design speci-fications.

2. Pump and system flow performance will be per design speci-fications.
3. Valve operating times will be within design limits.
4. Leak detection instrumentation will function in accordance with design specifications.
5. Diesel interlocks will perform in accordance with design specifications.
6. Diesel performance will be within design limits.
7. Core spray photographs have been reviewed by GE to determine l that the spray pattern gives total core coverage.  !

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g. 14.2.12.1.13 FUEL POOL COOLING AND CLEANUP SYSTEM ,
      ,Of                                         ,PREOPERATIONAL TEST                                                                                   j
  • Test Objectives
1. To demonstrate the capability of the fuel pool cooling and cleanup system to maintain and alter pool levels as required.
2. To demonstrate the operability of pool instrumentation.
3. To demonstrate functional operation of the system equipment.
4. To demonstrate operation of interlocks within the system and with other systems.
5. To demonstrate functional operation of the suppression pool l mahoup system.

I Prercouisites and Initial Conditions

1. C&IO testing is complete.
2. A sufficient quantity of chemically acceptable water is avail-able for the test.

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3. Component cooling. water is available.
4. The portion of the RHR system required for the test is available.
                                                                                        .s        .

Test Procedure 7

1. Pool instrumentation, alarms, and interlocks will be demonstrated. -
2. The fuel pool cooling and cleanup, system will be demon-strated in all operational modes. ,
3. System interlocks will be tested.
4. The RHR fuel pool cooling mode will'be verified.
         . . . . . . ( ~.            .
5. Tlie suppression pool makeup system Valve operation and logic will be tested. .! '

3

6. The leak detection circuit will be tes'ted.
. Acceptance Criteria
    ,}

k,U l. Pool instrumentation performs as designed. .

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CPS-FSAR

2. The fuel pool cooling and cleanup system will maintain and
/*             alter pool levels in accordance with the design.

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3. Interlocks operate as designed.
4. Flow through the RHR interconnection is within design.
5. The suppression pool makeup system valve operation and logic perform as designed.
6. Leak detection circuitry performs per design.

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CPS-FSAR 14.2.12.1.14 LIQUID RADWASTE Test Obj ectives

1. To demonstrate the operation of the liquid radwaste system.
2. To verify design flow rates within the liquid radwaste system.

Prereauisites and Initial Conditions

1. C&IO testing is complete.
2. Compacent cooling water is available.
3. Auxiliary steam is available.
4. The cycled condensate system is operable.
5. A supply of water is available.
6. The process sampling system is available.
7. The solid radwaste reprocessing and disposal system is avail-able to receive effluent.
8. Process monitoring units interlocked with the liquid radwaste system are available for testing.

Test Procedure

1. The system will be operated to demonstrate flows, control and interlock operation, and overall system operation using water.
2. Demonstrate filter and demineralizer regeneration cycles.
3. Demonstrate evaporator operation to the extent possible.
4. Demonstrate sample technique' and discharge flow control.

Acceptance Criteria

1. Process flow rates fall within design tolerances.
2. Interlocks and automatic operations function per design.
3. System and component functions are demonstrated to operate as designed.
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CPS-FSAR 14.2.12.1.15 SOLID RADWASTE Test Objectives

1. To demonstrate the capabilities of the solid radwaste system.

Prerequisites and Initial Conditions

1. C&IO testing is complete.
2. The liquid radwaste system i; available.
3. A sufficient quantity of solidification material is available.

Test Procedure

1. Trash compacting and handling equipment will be demonstrated.
2. Solidification material handling equipment operation will be demonstrated.
3. Solid radwaste mixing and drumming operations will be demon-strated with various solidification material to metered waste ratios.
4. The method for detecting free water after solidification will be demonstrated.
5. Remote operation of equipment will be demonstrated.

Acceptance Criteria

1. Alarms, interlocks, and automatic operations perform as designed.
2. Remote operations will:be demonstrated to operate as designed.

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3. System operation from receipt of waste and solidification materials to completion of the handling process will be demonstrated to perform in accordance with design. l
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CPS-FSAR

      -          14.2.12.1.16                REACTOR PROTECTION SYSTEM U                                                                                                                                                    '
                                                 ,PR OPERATIONAL TEST
   @T            Test Objectives
1. To demonstrate the capability of the reactor protection sys-tem to provide reactor scrams as designed.
2. To obtain applicable scram response times.
3. To verify RPS operation with normal and alternate power supplies. i Prereauisites and Initial Conditions
1. C&IO testina is complete.
2. A-C and D-C power is available.

l Test Procedure

1. RPS logic, inclusive of all applicable bypasses, interlocks, seal-ins, reset permissive and Mode Switch to shutdown time delays, alarms, indicators and permissives will be test'd.
2. Input instruments will be loop calibrated and/or functionally 3
     .J tested to demonstrate proper trip action into RPS logic.
3. Reactor Recirculation Circuit Breaker trips will be tested.
4. Pilot Scram Valve and Scram Valve operation will be tested.
5. Backup Scram Valve operation will be tested.
6. Scram Discharge Volume isolation valve operation will be tested.
7. Main Condenser Vacuum Pump trips for Main Steam Line Radiation trip inputs will be tested, j
8. Manual Scram inputs to the RPS logic and Pilot Scram Valve -

Solenoid breakers will be tested.

9. Logic power supplies will be tes.ted for proper operation.
10. The proper. system operation with normal and alternate power supplies will be tested, including operation during switching,
11. Fail Safe operation will be tested.

g 12. Response times for applicable logic channels from the J process variable (with the exception of neutron sensors) to the de-energization of the Pilot Scram Valve Solenoids (2 . will be verified.

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fih 13. Final functional testing to demonstrate proper trip points, logic, operability of scram breakers and valves, and opera-bility of manual scram functions will be performed. Acceptance Criteria

1. RPS logic, inclusive of all applicable bypasses, interlocks, seal-ins, time delays, alarms, indicators and permissives will perform per design specifications.
2. Input instrumentation setpoints and trip action will be  ;

consistent with design specifications.

3. Equipment activated by the RPS logic will perform per the design specifications.
4. Manual Scrams will perform per the design specifications.
5. Power supplies and power distribution equipment will be within tolerances ,specified by design for proper operation of the in- j strumentation. l
6. The RPS " Fail Sate" f eature will perform per the design specifi-cation.
7. Response times will be consistent with the design response times o used in the safety analysis. . <

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         '14.2.12.1.17        NEUTRON MONITORING SYSTEM                        [
     ^
                                -,.PREOPERATIONAL- TEST                        i Test Obj.ctives To demonstrate the capability of the neutron monitoring system to function in accordance with design specifications. The source range monitor, intermediate range monitor, local power range monitor and average power range monitor subsystems are included.

Prereauisites and Initial Conditions

1. Checkout and initial operation phase testing has been completed.
2. Calibrations of instruments within the scope of this test are current.

Test Procedure .

1. The traversing mechanisms for the SRM and IRM detectors will be functionally demonstrated.
2. SRM, IRM, and APRM channels including indication, recorders, trips, bypasses, interlocks, and alarms will be tested by the (f.. introduction of simulated signals.
3. The recirculation flow bias subsystem will be demonstrated using simulated inputs.
         -Acceptance Criteria i
1. The detector traversing mechanisms and associated interlocks operate within design tolerances.

i

2. Each neutron monitoring channel functions within design tolerances. ,  ;
3. The recirculation flow bias circuitry functions within design limits.

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CPS-FSAR 14.2.12.1.18 TRAVERSING INCORE PROBE SYSTEM l [~ tREOPERAT.IONAb* TEST I s Test Objectives  !

1. To demonstrate operation of the traversing incore probe system.

l

2. To verify positioning mechanism operation; interlock operation and alarm functions. l
                                                                                                \

Prereauisitec and Initial Conditions  !

1. C&IO testing is complete.
2. Nitrogen is available.
3. Instrument air is available.

Test Procedure

1. Operation of the drive control units will be verified.
2. Control, interlock, alarm, and indication functions will be 7 verified.

i.'

3. Purge operation will be verified.

Acceotance Criteria

1. All modes of operation will be demonstrated to perform as designed. [
2. Interlocks, alarms, and indications perform per design criteria.
3. The purge system performs per design.

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CPS-FSAR 14.2.12.1.19 PROCESS RADIATION MONITORING SYSTEM (0 ,PREOPERATIONAI;4 TEST i Test Objectives

1. To demonstrate the operability of the following radiation monitoring subsystems:
a. rain steam line
b. containment vent exhaust plenum
c. off-gas pretreatment
d. radwaste effluent
e. component cooling water effluent
f. carbon bed vault .
g. RHR loop A service water
h. RHR loop B service water
1. service water effluent J- j. fuel pool heat exchanger 1A shutdown service water
k. fuel pool heat exchanger 1B shutdown service water
1. off-gas post treatment 1
m. common station,I' HVAC vent stack
2. To verify interlocks, alarms an d controls.

Prerequisites and Initial Conditions

1. C&IO testing is complete
2. Check sources are in place.

Test Procedure i

1. Radiation monitor performance will be tested using check sources.
2. Functional tests will be performed to demonstrate operability of pumps, valves, controls, and instrumentation.
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CPS-FSAR 14.2.12.1.20 AREA RADIATION MONITORING SYSTEM y) J REOPERATIONAL-TEST-Test Objective 1

1. To verify operation of the area radiation monitoring equipment.

Prerequisites and Initial Conditions

1. Checkout and initial operation phase testing has been completed.

Test Procedure

1. Each area monitor will be tested for indicating and alarm functions.
2. Interlocks will be checked,.

Acceptance Criteria

1. Channel accuracy shall be within design tolerances.

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2. Alarm and interlock functions will take place atas pecified I

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CPS-FSAR e-14.2.12.1.21 0FF-GAS SYSTEM PREOPERATIONAL'" TEST' (% (, . j Test Objectives

1. To functionally demonstrate operation of the off-gas system equipment.
2. To demonstrate the operability of the off-gas hydrogen analyzers.

Prerecuisites and Initial Conditions

1. C&IO testing is complete.
2. The instrument air system is available.
3. Steam is available.
4. The plant chilled water system is available.

Test Procedure

1. Operation of the refrigeration units will be demonstrated.

bs 2. ' Operation of the dryers will be demonstrated.

3. Interlocks, controls, and alarms will be checked.
4. Integrated operation of the off-gas system equipment will be demonstrated to the extent possible.
5. The hydrogen analyzers-will be tested.
6. Operation of remotely operated valves will be tested.
7. Filter efficiency will be tested.

I Accpetance Criteria

1. Alarms, controls, and interlocks function within design limits.
2. The refrigeration units and dryers perform the intended design functions.
3. Off-gas system parameters are within design limits.
4. The hydrogen analyzers perform as designed.

(t,- 5. Valve operation from remote stations will be verified;6 Ic a euoa/aue wid de > h,. .

6. Filter efficiency will fall within design limits.

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CPS-FSAR 14.2.12.1.22 MSIV LEAKAGE CONTROL SYSTEM

      )                        f PREOPERATIONAL , TEST                        !
  • j Test Objectives
1. To verify MSIV leakage control logic.
2. To verify operation of interlocks and alarms associated with the MSIV leakage control system.
3. To functionally demonstrate MSlv leakage control equipment.

Prereauisites and Initial Conditions

1. C&IO testing is complete.

Test Procedure 4

1. Controls, interlocks, and ala'ms r will be tested.
2. Valves, heaters, and blowers will be tested for proper operation.

f (, Acceptance Criteria i

1. Controls, interlocks, and alarms will function as designed.
2. Valves, heaters, and blowers will operate per design.
3. Valve operating times will fall within design specified limits.

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CPS-FSAR i v 14.2.12.1.23 SUPPRESSION POOL MAKEUP SYSTEM tCc - pgPREOPERATIONAL) TEST Test Objectives

1. To verify suppression pool makeup system logic.
2. To observe the transfer of water from the upper containment pool to the suppression pool.

Prerecuisites and Initial Conditions

1. C&IO testing is complete.

j 2. The fuel pool cooling and cleanup system is available.

3. The containment monitoring system is available.

Test Procedure

1. Initiation logic will be checked for operation alarms, controls, and interlocks.

l- 2. A timed dump of water from the upper pool to the suppression (t. pool will be observed. , Acceptance Criteria

1. Logic perforrs within design tolerances.
2. The dumping of the upper pool to the suppression pool occurs within design time limits.

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CPS-FSAR 14,2.12.1.24 CONTAINMENT COMBUSTIBLE GAS Ih

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CONTROL SYSTEM PREOPERATIONAL'iTEST ' Test Objectives

1. To demonstrate the operation of the hydrogen recombiners.
2. To demonstrate the operation of the hydrogen mixing system.
3. To demonstrate the operation of the drywell/containmen't ,

vacuum breakers. Prerequisites and Initial Conditions

1. C&IO testing is' complete.
2. Shutdown service water is available.
3. The suppression pool contains a sufficient quantity of water.

Test Procedure ,

1. Dontrol, alarms, and interlocks will be checked for operation.
2. Valve operation will be demonstrated.
3. The hydrogen mixing compressor and valves will be operation-(- .

ally demonstrated.

4. The operation of the hydrogen recombiner units will be demonstrated in the test mode.
5. The setpoint and operability of the'dtfwell/ containment vacuum breakers will be demonstrated. l
.                  Acceptance Criteria                                .
1. Controls, alarms, and interlocks will operate within design l tolerances. -
2. Valve operation will conform to design specifications.

i  ; .

3. The hydrogen mixing compressor and valves perform within design specifications.
4. Hydrogen recombiner performance is sithin design tolerances.
                                                .j
5. The drywell/ containment vacuum breaked,s will operate within design specifications. ,,.
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CPS-FSAR 14.2.12.1.25 COMPONENT COOLING WATER SYSTEM pc PREOPERATIONAL= TEST

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Test Objectives

1. To demonstrate the capability of the component cooling water system to provide flow to components.
2. To demonstrate automatic transfer of cooling functions to the shutdown service y. iter system.

Prerecuisites and Initial Conditions

1. C&IO testing is complete.
2. Plant service water is available.
3. Shutdown service water is available.

Test Procedure

1. Pump and system flow characteristics will be verified.
2. Con trols , interlocks and alarms will be verified.
/'

q 3. Automatic transfer of cooling loads to the shutdown service water system under dynamic conditions will be demonstrated.

4. Valve operation will be demonstrated.

Acceptance Criteria

1. Pump and system flow characteristics are within design limits.
2. Controls, interlocks , and alarms perform as designed.
3. The transfer of heat loadst to the shutdown service water system is }

demonstrated to operate in accordance with design. , I

4. Valve operation and timing is within design limits.

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CPS-FSAR 14.2.12.1.26 SHUTDOWN SERVICE WATER H Test Objectives

1. To demonstrate the ability of the shutdown service water system to supply water to the various components it serves.
2. To demonstrate proper operation of the automatic actuations and interlocks associated with the system.
3. To demonstrate that the shutdown service water pumps-will not be subjected to vortexing at either normal lake level or design minimum ultimate heat sink (UHS) levels.
4. To demonstrate that the shutdown service water pumos have ade-quate NPSH at both noraml lake level and design minimum UHS t levels.

Prerequisites and Initial Conditions

1. C&IO testing has been comoleted.
2. The heat exchangers served by shutdown service water will be available for the test.

Test Procedure

1. The pumps will be performance tested.
2. Auto start and interlock features will be tested.
3. Flow paths will be verified.
4. Operation from the remote shutdown panel will be demonstrated.
5. Pumps will be operated at normal lake level and design minimum UHS level to verify sufficient NPSH and the absence of vortexing.

I Acceptance Criteria

1. Pump performance shall meet desian specifications.
2. All auto start and interlock features shall perform per design specifications.
3. Flow rates will be verified to all equipment served by the shut-down service water system.
4. Valve operation and timing is within design tolerances.
5. Pumps operate per design with no signs of vortexing at normal '

lake level and design minimum UHS level.

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1 1 CPS-FSAR 14.2.12.1.27 SHUTDOWN SERVICE WATER VENTILATION 4 SYSTEM FREOPERATIONAL-TEST Test Objectives

1. To demonstrate the capability of the shutdown service water ventilation system.

Prerequisites and Initial Conditions

1. C&IO testing is complete.
2. The shutdown service water system is available for operation.

Test Procedure

1. Auto-start, alarm, and interlock features will be checked.
2. The system will be operationally tested.
3. Control from the remote shutdown panel will be verified.

Acceptance Criteria (,

l. Auto-start, alarm, and interlock functions perform as designed.
2. The ability of the system to cool the shutdown service water pump rooms will be demonstrated to perform in accordance with design.
3. Air and water flow will be within design tolerances.

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CPS-FSAR 14.2.12.1.28 ESSENTIAL SWITCHGEAR HEAT REMOVAL f- "PREOPERATIONAL-TEST-I

   \k                   Test Objectives                                                                                    "

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1. To verify the operational capability of the switchgear heat removal system during normal and abnormal conditions.
2. To verify battery room exhaust fans will exhaust sufficient air to ensure dilution of hydrogen generated by the dharging batterie:

t Prerequisites and Initial Conditions

1. C&IO testing is; complete.
2. Plant chilled water is available.
3. Shutdown service water and plant service water is available.
4. The auxiliary building HVAC system is available.

Test Procedure

1. Verify fan, filter and damper controls, interlocks, and alarms.
2. Verify refrigeration equipment operation.

(' 3. Demonstra'te system carabil:ty to maintain switchgear and battery room atmospheres.

4. Verify battery room exhaust air-fl'6w rate.

Acceptance Criteria J

1. Fan, filter and damper controls, interlocks and alarms will perform per design specifica'tions.

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2. The refrigeration system will perform as designed,
3. Temperature and humidity will be consistent with design expectations. .

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4. Air flow will be within design tolerances.
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CPS-FSAR 14.2.12.1.29 CONTROL ROOM HVAC SYSTEM e- PREOPERATIONAL TEST l l Test Objectives

1. Demonstrate the operation of the control room HVAC equipment during normal and abnormal plant operating conditions.
2. Confirm the proper operation of system interlocks, controls, and alarms.

Prerequisites and Initial Conditions

1. C&IO testing is complete.
2. Flow and leak tightness tests are complete.
3. Shutdown service water is available.
4. Demineralized water is available.
5. Radiation monitors, chlorine monitors, and smoke detectors interlocked with the control room HVAC are operational and available for testing.

k Test Procedure

1. Verify fan, damper, heater, humidifier, and air conditioner controls, interlocks, permissives, trips, and alarms .
2. Verify isolation damper operation.
3. Verify actuations from radiation monitors, chlorine monitors, and smoke detectors.
4. Verify control room atmospheric pressure dif ferential with surrounding area. j
5. Demonstrate operation in all modes.

Acceptance Criteri_a

1. Fans, dampers, heaters, humidifiers, and air conditioning units function as designed.
2. Dampers operate as designed and within design specified time limits.

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3. Actuations from radiation monitors, chlorine detectors, and s, smoke detectors are correct as designed.
4. Control room atmospheric pressure is greater than the surround-ing areas.
5. The control room HVAC will operate as designed in all modes.

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                                             ' CPS-FSAR 14.2.12.1.30        ECCS EQUIPMENT COOLING HVAC SYSTEM i

Test Objectives

1. Demonstrate operation of the various ECCS equipment room cooling units.
2. To determine the heat removal capacity of the ESF cooler during post-accident conditions.

Prerequisites and Initial Conditions

1. C&IO testing is complete.
2. Shutdown service water is available.
3. The ECCS equipment required for performance of this test is available.

Test Procedure

1. Verify fan and valve controls, interlocks, and alarms.
2. Evaluate the ability of each cooler to maintain area temperatures.
3. Perform a heat balance on the respective cooler'while the'ESF f equipment is operating. The heat balance will consist of, but not limited to, measuring water and air flow-rates and temperature differentials.

Acceptance Criteria

1. Fan and valve controls, including auto-starts function as designed.
2. The coolers maintain respective area temperatures within design requirements.
3. The ESF cooler is capable of removing the postulated post-accident design heat loads.

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4. Extrapolations, based on the heat capacity of the ESF coolers, of the normal operating coniition measurements will be made to address the maximum design heat load expected in the compartments during post-accident conditions. i e
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CPS-FSAR 14.2.12.1.31 DIESEL GENERATOR ROOM HVAC

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                                            .g.EREOPERATIONALTEST-v-
                  ' Test Objectives
1. To demonstrate operation of fans and dampers.
2. To demonstrate operation of the heater and cooler.
3. To demonstrate controls, interlocks, and alarms.

Prerecuisites and Initial Conditions

1. C&IO phase testing is complete.
2. The plant chilled water system is available.

Test Procedure -

1. Functionally test the fans and dampers including controls and alarms.
2. Demonstrate operation of the heatec and cooler and controls.
3. Test system interlocks with the fire protection system and diesels.

Acceptance Criteria

1. The fans and dampers operate in accordance with design.
2. The heater and cooler perform per design intent.
3. Extra- and intra-system interlocks operate in accordance with

!- the design. t l f 1 i

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CPS-FSAR 14.2.12.1.32 DRYWELL PURGE VENTILATION SYSTEM _PREOPERATIONAL_ TEST. 4 I,(Gg

     . s-                                                                                 l Test Objectives
1. To demonstrate operation of the drywell purge system.
2. To demonstrate system logic and interlocks.

Prereauisites and Initial Conditions

1. C&IO testing has been completed.
2. Portions of the nuclear boiler and radiation monitoring systems required for the test are available.

Test Procedure

1. Controls, interlocks, and alarms will be functionally tested.
2. Manual and automatic signals will be used to activate the system. Fan, damper, instrument, alarm, and interlock action will be checked.

(( 3. Damper and valve timing will be verified.

4. Airflow will be verified.

Acceptance Criteria

1. Controls, interlocks, and alarms will function as designed.
2. The system will function as designed.

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3. Damper and valves will operate within^specified times. /

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4. Airflow will be within design limits.
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CPS-FSAR 14,2.12.1.33 DRYWELL COOLING SYSTEM g PREOPERATIONAL TEST-o. Test Objectives

1. To demonstrate operation of the drywell cooling system.
2. To demonstrate system logic and interlocks.

Prerecuisites and Initial Conditions

1. C&IO testing is complete.
2. Plant service water is available.

Test Procedure

1. Con trols , interlocks, and alarms will be functionally tested.
2. Airflows will be verified.

Accentance Criteria -(

l. Controls, interlocks and alarms will function as designed.
2. Airflow will fall within design tolerances.

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CPS-FSAR 14.2.12.1.34 CONTAINNENT BUILDING HVAC SYSTEM l aFRE0PERATIONALETEST- l C)- s Test Objectives,

1. To demonstrate operation of the containment building HVAC system.
2. To demonstrate system logic and interlocks.
3. To demonstrate system ability to maintain containment pressure negative with respect to the outside atmosphere.

Prerecuisites and Initial Conditions

1. C&IO testing is complete.
2. The plant chilled water system is available.
3. Portions of the nuclear boiler and radiat on monitoring systems required for the test are available.
4. The drywell purge system is available for testing.

(i - Test Procedure

1. Controls, interlocks, trips, and alarms will be functionally tested.
2. Isolation valves will be functionally tested.
3. Fan capacities will be verified.
4. Airflows to various areas will be checked.
5. Normal and purge configurations will be demonstrated.

i Acceptance Criteria

1. Controls, interlocks, trips, and alarms will function as designed.
2. Isolation valve operation and timing will be within design limits.
3. Fan cepacities and area air flows will be within design requiremen ts .
4. The system will perform design functions in each configuration.

(s 5. The system will maintain containment pressure within design limits. saw.u.4:ws:m,a+m.mA4.2-E : += .oggar,i.twgh%i[}

CPS-FSAR 14.2.12.1.35 STANDBY GAS TREATMENT SYSTEM ( ?$ tPREOPERATIONAL-TEST l (V - v Test Objectives

1. To demonstrate operation of the standby gas treatment system trains.
2. To demonstrate system logic and interlocks.
3. To demonstrate system ability to maintain a negative pressure in the secondary containmant.

Prereauisites and Initial Conditions

1. Checkout and. initial operation phase testing has been completed.
2. The areas served by SGTS are completed and intact.
3. Portions of the nuclear boiler and radiation monitoring systems required for the test are available.

Test Procedure If i 1. Controls, interlocks, and alarms will be functionally tested.

2. Manual and automatic signals will be used to activate the

! system. Fan, damper, instrument, alarm, and interlock action will be checked.

3. Each train will be tested for the capability of maintaining the secondary containment at a specified negative pressure.
4. Damper operations will be timed.
5. Airflow through each train will be checked.

I

6. Fan capacities will be verified.

Acceptance Criteria

1. Con trols , interlocks, and alarms will function as designed.
2. The system will operate as designed during manual and auto -

matic start conditions.

3. Each train will maintain secondary containment pressure per design specification.

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4. Dampers will operate within time limits specified by design.

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 \i>           5. Airflows and fan capacities will be within design limits.

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CPS-FSAR 14.2.12.1.36 DIESEL GENERATOR SYSTEM j .EREOPERATIONAL-TEST-Test Obj ectives

1. To demonstrate the ability of each diesel to start and acquire emergency loads during simulated accident conditions.
2. To demonstrate the operability of the diesel-generator auxi-liary systems, i.e., fuel oil transfer, lube oil, cooling system. starting air supply system.

Prereauisites and Initial Conditions

1. Checkout and initial operation phase testing has been completed.
2. The makeup water system is available.
3. Shutdown service water is available.
4. The portion of the fire protection system covering the diesel-generator rooms is operable.
5. Diesel generator room HVAC is available.
f. Test Procedure
1. All diesel starting and trip sequences will be tested to assure proper operation.
2. All auxiliary systems will be functionally demonstrated.
3. Demonstrate the manual and automatic operation of the diesel-generator, including measurement of time to rated voltage and frequency and load test at full load for a specified time period.

i

4. All interlocks, controls, indications, and alarms will be veri-fied to operate in accordance with design specifications.
5. Load rejection and load shedding tests shall be conducted to assure continuous diesel operation during accident.or loss-of-load conditions.
6. Demonstrate starting ability with design minimum starting air available.
7. Conduct a consecutive start reliability test.
8. Demonstrate synchronization and load transfer capabilities.

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CPS-FSAR Acceptance Criteria

  !,J          1. The automatic sequence test loads the generators in the proper design-                          4 sequence and time interval.
2. All auxiliary systems perform intended design functions.
3. Rated load and frequency can be attained and maintained for a design specified time period.

4 Load rejection does not result in exceeding design specified speedsandnominalvoltageandfrequencyarerestoredwithindesignj specified times.

5. Load shedding performs as designed.
6. The diesels will start with design minimum starting air capacity available.
7. The diesels will perform the required number of consecutive starts specified by design without failure. i
8. Synchronization and load transfers will be demonstrated to perform f in accordance with design.

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I CPS-FSAR ~ 14.2.12.1.37 REACTOR VESSEL _ FLOW INDUCED VIBRATION Q) 1%p- ^ Test Objectives

1. To verify that structural integrity of the reactor internals remains intact during and after flow induced vibrations.

Prerecuisites and Initial Conditions

1. C&IO testing is complete.
2. The recirculation system testing is completed sufficiently to allow safe operation of the recirculation pumps at rated volumetric flow for an extended period of time.
3. The capability exists to maintain reactor water temperature equal to or greater than 1500F during the test.
4. Capability to maintain the reactor pressure vessel 100 psi greater than saturation is provided.

Test Procedure r

   \;     1. A preflow vessel internal inspection will be conducted. This will include visual inspection of selected internal structures and component parts and a sample of effluent from the draining of the RPV and flush of the bottom head drz in piping.
2. A flow test will be completed. The extent :f the test and monitoring will be consistent with NRC Regulatory Guide 1.20 recommendations.
3. A postflow vessel internal inspection will be conducted. A sample will be collected from the bottom vessel drain line and a visual inspection will be performed subsequent to vessel draining.

1 Acceptance Criteria

1. Vibration data will be evaluated for consistency with the values l

predicted in the design. I

2. Evidence of defects, loose parts, or excessive wear will be evaluated for effect on plant operation.
3. Flush cloths must not show more than slight particulate speckling.
4. No extraneous material shall be parmitted in the jet pump annulus
 \' ' ;

or the plenum region as a result of specified flow testing. #, 46+? GEN [5h

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CPS-FSAR 14.2.12.1.38 125 VDC SYSTEMS s .

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j i (.:- Test Objectives To demonstrate that the batteries and battery chargers will supply direct current power as required. Prerecuisites and Initial Conditions

l. C&IO testing is complete.
2. A load is available for the performance of battery capacity checks.
3. Ventilation for the battery rooms is operational.

Test Procedure

1. The capability of each batter'y charger to individually maintain a float charge on the battery and to provide an equalizing charge while maintaining a normal load on the associated D-C bus will be tested.
2. The ability of' each ' battery to accept load will be demonstrated' (f.

by de-energizing the battery charger while design D-C load is being carried on the bus.

3. A test discharge will be carried out on each battery to verify capacity. , , , ,
4. The-DC loads will be verified to remain operable at_the minimum i voltage level established in the discharge test.
5. The batteries will b.e rechabged after the test discharge.

1cceptance Criteria '

1. The battery chargers will provide battery float and equalizing charges while maintaining gormal bus loads.
2. Each battery will maintain normal bus loads upon loss of battery chargers per design specifications.
3. Each battery will contain sufficient capacity to perform its emergency function specified by design, while individual cell limits are not exceeded.
4. The DC' loads remain in operation at the minimum voltage level established in the discharge test. l
5. After the discharge test, the batteries will be restored to '

normal charge within the rated recovery time specified by design. ', .. j _jp;;' ' .

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CPS-FSAR 14.2.12.1.39 CONTAIM4ENT MONITORING SYSTEM

      .)                           - PREOPERATIONAL-TEST                                       j
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l Test Objectives

1. Demonstrate the operability of the containment monitoring system equipment.

Prerequisites and Initial Conditions

1. Checkout and initial operation phase testing has been completed.

Test Procedure

1. Suppression pool level instrumentation will be tested.
2. Containment and drywell atmosphere temperature, pressure, hydrogen and humidity monitoring instrumentation will be tested.
3. Leak detection instrumentation for areas in the containment will be tested.

[t Acceptance Criteria

1. Instruments, recorders, interlocks, and alarms function in accordance with design specifications.
2. Leak detection instrumentation performs within design limits.

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CPS-FSAR 14.2.12.1.40 ELECTRICAL DISTRIBUTION

                                                 ;PREOPERATIONAL . TEST

(,,f y Test Objectives

1. Demonstrate integrated A-C system performance to simulated partial and full loss of off-site power.

2. Demonstrate power independence sources. among redundant on-site A-C and D-C '

3. Verify voltage drop on system down to the 120/208 level.

j Prereauisities and Initial Conditions .

1. C&IO testing is complete on main power, 6900 VAC, 4160 VAC, 480 VAC, 120 VAC and 125 VDC distribution systems.

2. The emergency diesels have been preoperationally tested and are available.

3. ~

345 kV and 138 kV off-site power is available. 4. Reliable test. communications exist between control points for the 5.

   '.,                   Permission for . loss of power testing has been obtained from the IP system dispatcher.

6. All station to 307. distribution buses down to the 120/208 level are loaded minimum. l Test Procedure 1. Simulated be performed. partial and full loss of off-site power tests will 2. Independence between redundant Class 1E power sources and load groups will be demonstrated. t

3. Load shedding will be demonstrated.
4. Re-energization sequencing 'Ind timing of ECCS loads will be ~

verified.

5. Grid and bus voltages down to the 120/208 volt level will be recorded 1 at steady state, and during the startlng of a large class lE and non-class lE load. .

Acceptance Criteria j 1.

                                           ~

The A-C di.stribution system of off-site power tests. will perform as designed during loss 2. Independence between redundant Class lE power sources and load groups will exist. 3. ({, s,

            \          Load shedding design                and re-energization operations will perform per specifications.
4. , _ ,

Test voltage shall not be lower than 37. of the values specified I by engineering analysis and never less than class lE equipment , rated voltage. 1

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CPS-FSAR 14.2.12.1.41 AUXILIARY BUILDING HVAC

 -                                EREW W ' M l

Test Objectives

1. To demonstrate the capabilities of the auxiliary building HVAC system.

Prerequisites and Initial Conditions

1. C&IO testing is complete.
2. Plant chilled water is available.

Test Procedure

1. Verify fan, filter, and damper controls , interlocks, and alarm operation. -
2. Measure the pressure of various areas within the auxiliary building with respect to outside ambient.
3. Measure the differential pressure between selected areas within the auxiliary building.
4. Demonstrate the system's ability to supply airflow to the various areas.

Acceptance Criteria

1. Fans, filters, and damper controls, interlocks, and alarms perform per design specifications.
2. Differential pressures will be consistent with design requirements.
3. Proper airflows to various areas will be verified to be in j accordance with design.  ;
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CPS-FSAR 14.2.12.1.42 RADWASTE BUILDING HVAC

                                                                             - PREOPERATION/tL.-TEST
',.-C                                                                                                                      j Test Objectives
1. To demonstrate the capability of the radwaste building HVAC system.

Pgereaufsites and Initial Conditions

1. CE,IO testing is complete.
2. Plant chilled water is available.

Test Procedure

1. Verify fans, filters, and damper controls, interlocks, and alarm operation.
2. Demonstrate system capability to supply airflow to the various areas.
3. Verify that airflow is from relatively clean areas to areas with a potential for higher radioactive contamination.

(-* 4. Measure the pressure in the radwaste building with respect to the outside ambient. Acceptance Criteria

1. Fans, filters, and damper controls, interlocks, and alarms will perform per design specifications.
2. Airflows will be consistent with design.
3. Radwaste building pressure ,will be negative with respect to the outside ambient and consistent with design limits.

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CPS-FSAR 14.2.12.1.43 FUEL BUILDING HVAC SYSTEM ( 1%%M L . My Test Objectives

1. Demonstrate operation of the fuel building HVAC equipment.
2. To confirm proper operation of system interlocks, controls, and alarms.

Prereaufsites and Initial Conditions

1. C&IO testing is complete.
2. The plant chilled water system is available.

Test Procedure

1. Verify fan and damper controls, interlocks, permissives and alarms.
2. Verify fan and damper operation.
3. Verify trips from radiation monitors, reactor water level and

( drywell pressure.

4. Measure the differential pressure between various areas main-tained by the fuel building HVAC and the outside atmosphere.

Acceptance Criteria aS

1. Fan and damper controls, interlocks, and alarms function Adesigned. I
2. Dampers operate as designed.

a l 3. All radiation, reactorfwater level, and drywell pressure trips operate as designed.

4. Fuel building, containment gas contiol boundary, RWCU room, and ECCS pump rooms pressure is negative with respect to the outside atmosphere.

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CPS-FSAR 14.2.12.1.44 0FF-GAS VAULT HVAC SYSTEM g p p .g m . s ...m. , - . . , , , , , Test Objectives

1. To demonstrate operation of the off-gas vault HVAC equipment.
2. To confirm proper operation of system controls, interlocks, and alarms.

Prereauisites and Initial Conditions

1. C&IO testing is complete.
2. The plant chilled water system is available.

Test Procedure

1. Verify fan and damper controls, operation, interlocks, and alarms.
2. Verify the off-gas vault refrigeration equipment controls, operation, interlocks, and alarms.

( 3. Demonstrate that the system can maintain the required tempera-ture in the charcoal absorber vault and the fan coil unit room.

4. Demonstrate the system ability to elevate temperatures in the charcoal absorber vault to the maximum requirement.
5. Measure the differential pressure between the interior of the charcoal absorber vault and the adjacent areas.

Acceptance Criteria

1. Fans and dampers function as designed. 1 j

, 2. Refrigeration equipment operates as designed. l

3. Temperatures can be achieved and maintained per system design.
4. The charcoal absorber vault can be maintained at a negative pressure with respect to the adj acent areas .

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CPS-FSAR 14.2.12.1.45 FIRE PROTECTION SYSTEM g . F ' r T IC:l'MT j Test Objectives

1. To demonstrate operation of the fire protection systems and components.

Prerequisites and Initial Conditions

1. C&IO testing is complete.

Test Procedure

1. All controls, alarms, interlocks, and logic are checked for proper operation.
2. Remote operated valve operation will be tested.
3. The diesels and pumps will be functionally tested.
4. Deluge valve operation and associated alarms will be tested.
5. Smoke detectors and heat detectors will be tested.

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6. CO 2

system functions will be tested. Acceptance Criteria

1. Controls, alarms, and logic operate as designed.
2. Valves will operate as designed.
3. Diesels and pumps will perform per design.
4. Deluge valves will operate as designed.

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5. Detection devices will perform all functions as designed. l
6. The CO 2

system will function as designed. 'Q:1 ,

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CPS-FSAR ' 14.2.12.1.46 INSTRUMENT AND SERVICE AIR SYSTEM d_ -PREOPERATIONALxTEST f Test Objectives

1. To demonstrate the operation of air compressors, dryers, and filters.
2. To demonstrate that air of sufficient quantity and quality can '

be supplied to the instrument air system.

3. To. demonstrate, the effects that loss of instrument air pressure has on branch lines which serve safety related equipment. j Prerecuisites and Initial Conditions
1. C&IO testing is complete.
2. Valves, in other systems, that are required for the loss of instrument air pressure tests'are available.
3. Component cooling water is available.

Test Procedure -

l. Functionally demonstrate compressor, filter, and dryer operation.
2. Test capacity and quality of air'sdpplied to the instrument air system.
                                                                   .. s     .
3. Check interlocks, controls,'and alarms'for the air compressors, filters, dryers , and balance of system.

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4. Loss of instrument air testing will be performed on lines which serve safety related equipment.

Acceptance Criteria ' g

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1. Air compressors, filters, and dryers will perform as designed.
  ~ '          2.      The quantity and quality of the air supplied to the instrument
                 . air system will be within design limits.    ~

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3. Interlocks, controls,$ndalarmswill,performasdesigned.
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4. The instrument air system will perform'per design specifications during icss of air testing. ,

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CPS-FSAR so n , - 14.2.12.1.47 CONDENSATE PREOPERATIONAL TEST'.

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\~7 Test Objectives l

1. To demonstrate operation of the condensate and condensate booster systems.

Prerequisites and Initial Conditions

1. C&IO testing is complete.
2. The condensate polishing system is available.
3. The reactor feedwater system is available.
4. Turbine building closed cooling water is available.

Test Procedure ~,

1. -The condensate and condensate booster pumps will be performance tested.
2. Controls, interlocks, trips, and alarms will be verified.

2

   ./?          3. Hotwell level control will be tested.
4. Minimum flow rates and valve operation will be verified.
5. Heater controls will be tested.

Acceptance Criteria

1. Pump performances will be within design.
2. Controls, interlocks, trips , .and alarms will perform as designed.

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3. Minimum flow rates and valve performance will fall within desi 6n limits.

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CPS-FSAR 14.2.12.1.48 SEISMIC INSTRUMENTATION

         ]                                           cEREOPERATlONAkTEST_..

Test Objectives

1. To demonstrate the response of the seismic instrumentation system to testing.

Prerequisites and Initial Conditions

1. C&IO testing is complete.

Test Procedure

1. Seismic instrumentation will be tested according to manu-facturer's recommendations.

Acceptance Criteria

1. Alarm, indication, and recording equipment perform per design specifications.

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CPS-FSAR 14.2.12.1.49 CONDENSER CIRCULATING WATER SYSTEM

                                  -PREOPERATIONAlr-TEST-.

h]; Test Objectives

1. To demonstrate circulating water system capability for providing flow to the condenser.
2. To demonstrate integrated operation of the circulating water, traveling screens, screen wash, and chlorination systems.

Prerequisites ano Initial Conditions

1. C&IO testing is complete.
2. Vacuum priming is available.
3. The chlorination system is available.
4. Plant service water is available.
5. Filtered water is available.
6. The traveling screens are operational.

V(W Test Procedure

1. Controls, interlocks, and alarms will be verified.
2. System flow charac'teristics will be demonstrated for various pump. combinations.

l 3. Circulating water system valve operation will be demonstrated.

4. A demonstration of the integrated operation of the circulating water, traveling screens,-screen wash, and chlorination systems will be performed.

Acceptance Criteria l 1. Controls, interlocks and alarms will perform per design specifica-tions. l

2. Flow characteristics will be within design limits. Adequate NPSH is available ie. the circul~a ting water pumps exhibit no s'igns of j l

cavitation,.

3. Circulating water system valves perform per design specifications.

l ( -3 4. The circulating water, traveling screens, screen wash, and l My chlorination systems perform as an integrated unit.

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CPS-FSAR 14.2.12.1.50 COMMUNICATIONS SYSTEMS i ; JREOPERATIONAL -TEST. j kJ Test Objectives

1. To demonstrate the capabilities of the various inplant and off-site communication systems to be used for normal and abnormal operating conditions.
2. To demonstrate plant emergency alarms.

Prereauisites and Initial Conditions

1. Vendor installation and testing is complete.
2. C&IO testing is complete.

Test Procedure -

1. Plant emergency alarms will be tested.
2. The ability to establish communications required in the plant emergency plan will be demonstrated.

( 3. Operation of the public address system will be demonstrated.

4. Communications required for plant shutdown from within or outside the control room will be demonstrated.

Acceptafice Criteria

1. The emergency alarms will perform as required by design specifications.
2. Communications will be euccessful-17 established in each demon-stration. t i

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CPS-FSAR n 14.2.12.1.51 CRANES PREOPfRAT:IONAL TEST' (

           -                                            v                                i
,            Test Objectives
l. To demonstrate the operation of the containment building polar crane.
2. To demonstrate the operation of the fuel handling cranes.

Prereauisites and Initial Conditions i

l. C&IO testing is complete.

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2. Load testing is complete.

t Test Procedure

1. Test controls, interlocks,.and travel limits on the cranes.

Acceptance Criteria i 1. Controls, interlocks and travel limits perform per design specifications. i a f l l 3 i O

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l CPS-FSAR 14.2.12.1.52 DRYWELL LEAKAGE 1 .i . Test Objectives

1. To determine that.the leak rate is within design limits'for high pressure (30 psig) and low pressure (3.0 psig) leak rate tests.
2. To obtain base line data for subsequent drywell leakage tests.

Prerequisites and Initial Conditions i -1. C&IO testing iu complete. 4

2. The drywell structural integrity test is performed in conjunction with the 30 psig leak rate test and is completed prior to the 3.0 psig leak rate test.
3. The suppression pool is full.
4. All closures are in place.'

l 5. Pressurizing and test equipment is checked out and ready for t i the test. 4 Test Procedure i

1. The drywell will be pressurized to approximately 30 psig and the leak rate determined.
2. The drywell will be pressurized to approximately 3.0 psig and the-leak rate determine'd.

Acceptance Criteria I 1. The leak rate will be within design limits as specified in section 6.2.6. , I s w. , _ _ . m_. n. . ~. .w w .~.,._ w , n _. , wx .w= uwe

CPS-FSAR 14.2.12.1.53 PRIMARY CONTAINMENT LEAK RATE , g ye ng- - -

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Test Objectives

1. To verify that the integrated leakage rate does not exceed the containment design basis accident leakage rate.
2. To obtain base line data for use during subsequent leak rate tests.

Prerequisites and Initial Conditions

1. C&IO testing is complete.
2. Isolation valves are operable.
3. All hatches and closures are in place.
4. Containment ventilation is available.
5. Pressurizing and test equipment is checked out and ready for the test.
6. Containment isolation valves will be closed by normal means (s. -, and without preliminary exercising or adjustment.
7. Type "B" and "C" tests as defined by 10 CFR 50, Appendix J have becn performed.
8. Containment Structural Integrity Test is completed satisfactorily. l Test Procedure
1. A type "A" test as defined by 10 CFR 50, Appendix J will be performed.

Acceptance Criteria t

1. Containment leakage does not exceed design limits.

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CPS-FSAR 14.2.12.1.54 TURBINE 3UILDING HVAC SYSTEM l l

   ,.                                Pe DOS. N..N l
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Test Objectives l

1. To demonstrate operation of the turbine building HVAC equipment.
2. To confirm proper operation of system interlocks, controls, and alarms. '

Prerequisites and Initial Conditions

1. C&IO testing is complete.
2. The plant chilled water system is available.

Test Procedure

1. Verify fan and damper controls, interlocks, and alarms.
2. Verify fan and damper operation.
3. Verify air flow.
4. Measure the differential pressure between the turbine building and outside atmosphere.

Acceptance Criteria

1. Fan and damper controls, interlocks, and alarms function as designed. I i
2. Dampers operate as designed.

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3. Air flows are within design' limits.

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4. Differential pressure between the turbine building and outside atmosphere is maintained within design limits.

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CPS-FSAR 14.2.12.1.55 LOOSE PARTS MONITORING SYSTEM

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A Test Objectives

1. To demonstrate proper operation of the Loose Parts Monitoring Equipment.
2. To collect data to use as baseline information during subse-quent operation.
3. To establish alert levels for various operating modes.

Prerecuisites and Initial Conditions

1. C&IO testing is complete.
2. The reactor internals are in place and the systems connected to the reactor are operational.
3. The reactor will be operating at power for portions of this test.

Test Procedure

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1. Indication and alarm functions will be demonstrated.
2. Vibration and noise levels will be measured for various modes of f reactor operation, and corresponding alert and alarm setpoints ,

established by the design organizations. l Acceptance Criteria

1. Indication, alert, and alarm functions will perform within design tolerances.  :

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CPS-FSAR 14.2.12.1.56- ihYl//l\ $Wfl /li DRAIN SYSTEMS'J6GCEPTANCE TEST r Test Objectives C{}

1. To demonstrate the operation of the Containment, Auxiliary and Fuel Buildings Equipment and Floor Drain Systems and the Turbine,
 ;                      Radwaste, Off Gas and Diesel Generator Equipment and Ploor Drain
Systems.

Prerequisites and Initial Conditions

1. C&IO testing is complete.

l 2. Component Cooling Water is available for the Containment Equipment Drain test. ! 3. Cycled Condensate water is available. 1 i 4. Instrument air is available. 4 Test Procedure j 1. All system pumps will be performance tested. ] 2. Controls, interlocks, trips and alarms will be verified. ( 3. Valve operation will be verified. Acceptance Criteria

1. Pump performance will be within design CRITERIA.

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2. Controls, interlocks, trips and alarms will perform as designed.
 ,              3.      Valve performance will fall within design limits.

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Jf.w 6 ~;t CPS-FSAR 14.2.12.1.57 , EMERGENCY LIGHTING SYSTEM

                                                 <<PREOPERATIONAL TEST-(f t

Test Objectives

1. Demonstrate battery pack lighting system performance to simulated loss of AC battery charging / control power.
2. Demonstrate 125V DC emergency lighting system to simulated loss i of AC control power.

l Prerequisites and Initial Conditions

1. C&IO testing is complete on battery powered and 125V DC emer-gency lighting systems.

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2. 125V DC power to emergency lighting cabinets is available.
3. 120V AC power to reguldr and standby lighting cabinets is available.

Test Procedure

1. Battery pack emergency lighting system will be tested by simulating C '.

loss of AC battery charging / control power.

2. 125V DC emergency lighting system will be tested by simulating loss of AC control power to emergency lighting cabinets.

Acceptahce Criteria f r 1. The battery pack emergency lighting system willi ~opevde as Acshnc$ psovide-cdequate i ki-ghting during loss of AC control power. l ope r,i4c as $csSnc 1

2. The 125V DC lighting system will[ provide-adequate light 4ng-during loss of AC control power to emergency lighting cabinets. .

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CPS-FSAR 14.2.12.2 Startup Test Procedures The tests comprising the Startup Test Phase are described in this sub-section. For each test a description of the test purpose, test prere-quisites, test description and statement of test acceptance criteria, where applicable, is provided. Additions, deletions, and changes to these descriptions are expected to occur as the test program progresses. In describing the purpose of a test, an attempt is made to identify those operating and safety-oriented characteristics of the plant which are being explored. Where applicable, a definition of the relevant acceptance criteria for the test is given and is designated either Level 1 or Level 2. A Level 1 criterion normally relates to the value of a process variable assigned in the design of the plant, components systems or associated equipment. If a Level 1 criterion is not satisfied, the plant will be placed in a suitable hold condition until resolution is obtained. Tests compatible with this hold condition may be continued. Following resolution, appli-cable tests must be repeated to verify that the requirements of the Level 1 criterion are now satisfied. A Level 2 criterion is associated with expectations relating to the per-formance of systems. If a Level 2 criterion is not satisfied, operating and testing plans would not necessarily be altered. Investigations of the measurements and of the analytical techniques used for the predic-tions would be started. For transients involving oscillatory response, the criteria are specified in terms of decay ratio (defined as the ratio of successive maximum amp-litudes of the same polarity). The decay ratio must be less than unity to meet a Level l criterion and less than 0.25 to meet Level 2. l When phrases such as "per design, design specifications, consistent with I design intent, as designed, etc" are used in the acceptance criteria, that information is taken from the following sources: General Electric Design Specifications General Electric Design Specifications Data Sheets General Electric Test Specifications l General Electric Instrument Setpoint Data Sheet Sargent'& Lundy Design Criteria Sargent & Lundy Svsten Descriotions Sargent & Lundy 21ectrical Schematics Sargent & Lundy Instrument Data Sheets Sargent & Lundy P&ID's Vendor Manual Supplied by General Electric or Sargent & Lundy The PSAR Technical Specifications The specific documents used in the preparation of each tests are listed in the reference section of that test procedure. The tests will demon-strate that the installed equipment and systems perform within the limits of these specifications. Table 14.2-9 provides a listing of the startup tests. 3 i

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CONTROL ROD DRIVE SYSTEM TESTS Accum-Test ulator Preop Reactor Pressure with Core Loaded

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Insert / Withdraw

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4 Friction - all 4* Scram Normal all all 4* 4* all Scram Minimum 4* l Scram Zero 4* Scram (Scram Normal 4 Discharge (full Discharge core. High Level) scram) Scram - Normal

                    *Value refers to the four slowest CRDs as determined from the normal accumu-lator pressure scram test at ambient reactor pressure.                 Throughout the pro-cedure, '.'the four slowest CRDs" implies the four slowest compatible with                             -~

rod worth minimizer and CRD sequence requirements. lli ' -

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          ~ , . ' - ,. NOTE: Single CRD scrams should be performed with the charging valve closed (do not ride the chagging pump head). - ;.
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CPS-FSAR 14.2.12.2.8 ROD SEQUENCE EXCHANGE ,n s 14.2.12.2.8.1 Purpose The purpose of this test is to perform a representative sequence exchange of control rod patterns at a significant power level. 14.2.12.2.8.2 Prerequisites Required preoperational tests have been completed, the appropriate parties have reviewed and the Plant Manager has approved the test procedure and the initiation of testing. All system instrumenta-tion is installed and calibrated. All system controls and inter-locks have been checked. 14.2.12.2.8.3 Description Rod patterns will be periodically exchanged during plant operations to more nearly equalize fuel assembly exposures. This test is per-formed as an example of the exchanges which will be made throughout plant life, and is provided to. illustrate the principles involved. The control rod sequence exchange begins on the 100 percent load line by reducing core flow to minimum and reducing thermal power to between the low power set point of the rod worth minimizer (or the rod sequence control system) and the thermal power necessary to keep nodal powers below the PCIOMR threshold. Also, in reducing thermal power, care should be taken to avoid exceeding the design limits of i - the core total peaking factor. The exchange is performed a row or

 ' colunn at a time , starting at one side of the core and working row by row or column by column across the entire width of the core.

14.2.12.2.8.4 Acceptance Criteria Level 1-Completion of the exchange of one rod pattern for the compliment-ary pattern while continually maintaining all core paramaters within design limits constitutes satisfaction of the requirements of this pro-cedure. j Level 2 , All nodal powers remain below their fuel conditioning thermal limits  ! during this test. l 14.2-105 _.:- .. w =~ a c.~ > agx . ac , .. -

CPS-FSAR 14.2.12.2.9 IRM PERFORMANCE (~ 14.2.12.2.9.1 Purpose s The purpose of this test is to adjust the intermediate range monitor system to obtain an optimum overlap with the SRM and APRM systems. 14.2.12.2.9.2 Prerequisites Required Preoperational tests have been completed, the appropriate parties have reviewed and the Plant Manager has approved the test procedure and initiation of testing. All scurce range monitors and pulse preamplifiers, intermediate range monitors and voltage preamplifiers, and average power range monitors have been cali-brated in accordance with vendor instructions. 14.2.12.2.9.3 Description Initially the IRM system is set to maximum gain. After the APRM calib ration , the IRM gains will be adjusted to optimize the IRM overlap with the SRMs and APRMs. 14.2.12.2.9.4 Acceptance Criteria Level 1 ( Each IRM channel must be adjusted so that it overlaps with both I the SRMs and APRMs. The IRMs must produce a scram at 96% of 3 full scale. Level 2 - NA t W h d-[ ee 2 $L L Lb= Ae#t ^"*"^g --

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CPS-FSAR 1q a. I R.9.I 3 O 'e & d i ' ' ' " ' ' "' Level 1 (Cont.) , J With pump discharge at any pressure between 250 psig and 100 psi above rated pressure, the required flow is 800 gpm. (The 100 psi ! is a conservatively high value for line losses. The measured value , may be used.if available). ! The RCIC turbine must not trip off during startup. , If any Level 1 criteria are not met, the reactor will only be , allowed to operate up to a restricted power level defined by  : i Figure 14.2-5. Level 2

The turbine gland seal condenser system shall be capabic of
preventing steam leakage to the atmosphere.

The differential pressure switch for the RCIC steam supply line

,                            high flow isolation trip shall be adjusted to actuate at 300% of
the maximum required steady stgate flow.

For small speed or flow changes in either manual or automatic l mode, the decay ratio of each record,ed RCIC system variable must i be less than 0.25, in order to demonstrate acceptable stability. In order to provide an overspeed and isolation trip avoidance

            .                margin, the first and subsequent speed peaks associated with the
M transient quick start shall not exceed the rated RCIC turbine speed.

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2. Feedwater flow and water level control functions

(. 7,. 3. Safety functions

4. Safety functions The test will be done at rated temperatura and pressure and under steady-state conditions and will verify that the reference leg temperature of the instrument is the value assumed during initial calibration. If not, the instruments will be recalibrated using the measured value.

14.2.12.2.14.4 Acceptance Criteria Level 1 The reactor recirculation pumps shall not be operated unless the coolant temperatures between the upper and lower regions of the reactor vessel are within 1450 F (63R=C) of each other. f ICC The recirculation pump in an idle loop must not be started unless the loop temperature is within 50 F TTOO=C-7 of the core inlet temperature. f Level 2 The indicator readings on the Narrow Range Level System should g agree within plus or minus 1.5 inches of the average reading. The Wide Range Level System indicators should agree within plus or minus 6 inches of the average reading. i 1 (i .

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r CPS-FSAR /, 3 14.2.12.2.16 CORE POWER DISTRIBUTION e kl? 14.2.12.f.16.1 Purpose The purposes of this test are a) to confirm the reproducibility of the TIP system readings, b) to determine the core power distribution in three dimensions and c) to determine core power e-symmetry. e 14.2.12g16.2 Prerequisites , System installation completed and preoperational tests completed and verified. The TIP detector and dummy detector, ball valve f k time delay, core top and bottom limits, clutch, x-y recorder, and I purge system will have been shown to be operational. / Instrumentation has been eclibrated and installed. . Description 14.2.12 4 16.3 Core power distribution data will be obtained during the power f

                                                                                                              's ascension program using complete sets of axial poter traces taken with the Traversing In-Core Probe (TIP) System. At intermediate                             ,_

and higher power levels, several sets of TIP data will be [' 6 obtained to determine the overall TIE uncertainty. \

                                                                                                     \         P TIP data will be obtained with the reactor operating with a                        j             ,

symmetric rod pattern and at steady state conditions. The total TIP uncertainty for the test will be calculated by averaging the \ (. - total TIP uncertainty determined from each set of TIP data taken. ' j The total TIP uncertainty is made up of random noise and , geometric components. s Core power symmetry will also be calculated using the TIP data. 9 Any assymetry, as determined from this analysis, will be  % accounted for in the calculation for MCPR using the GETAB f . method.  ! 4 ' I ' 14.2.12.g 16.4 Acceptance Criteria Level 1 3 f[i V. S"

                                                                                                       \\

The total TIP uncertainty (including random noise and geometrical uncertainties) obtained by averaging the uncertainties for all data sets must be less than 7.87.. [ NOTE: A minimum of two and up to six data sets may be used to meet the above criteria. If the 7. 87. total TIP un-l certainty criteria cannot be met by the six sets of data, l, testing may continue pro.vided the MCPR limit is adjusted to reflect the TIP uncertainty. _ j 3, ., t 2 k,

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il MMNd;2h 14.2.12.2.23.3 Description (cont)  ;.c.2 and SRV actuations will be made to. confirm open/close setpoints (}'h and containment load mitigation through the prevention of sub-sequent simultaneous SRV actuations. 14.2.12.2.23.4 . Acceptance Criteria Level 1 There should be a positive. indication of steam discharge during the manual actuation of each valve. The low-low set pressure relief logic shall function to preclude subsequent s.imultaneous SRV actuations following the. initial SRV actuation due to original pressurization transient. Level 2 Pressure control system - related variables may contain oscil-latory modes of response. In these cases, the decay ratio for each controlled mode of resposse must be less than or equal to 0.25. , The temperature measured by thermoco'uples on the discharge side of the valves shall return to within 10'F of the temperature recorded before the valve was opened. . f During the.250 psig functional test the steam flow through each relief valve, as measured by.the initial and final bypass valve position, shall not be less than 10 percent of valve position under the average of all valve responses. During the rated pressure test,the steam flow through each relief. valve, as measured by electrical output shall not be less than 0.5 percent of rated MWe less than the average of all the valve responses. When the Jow-low pressure relief logic functions the open/close actions of the SRV's shall occur within +13 psi and +20 psi of their design points respectively. - The reclosure pressure setpoint of the SRV when operating in the power mode will be no more than 120 psig below the nerin:1 power I setpoint. I (jl ' " '

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  • 14.2.12.2.25 SHUTDOWN FROM OUTSIDE THE ,

MAIN CONTROL ROOM STARTUP. TEST

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                                                                                                's.                                              i C+m  4' 14.2.12.2.25.1                  Purpose The purpose of this test is to demonstrate that the reactor can
  ,                  be brought from a normal initial steady-state power level to the point where normal low pressure shutdown cooling is initiated and under control ~with reactor vessel pressure and water level controlled from outside the control room.

14.2.12.2.25.2 Prerecuisites nequired preoperational tests have been completed, the appropriate parties have reviewed and the Plant Manager has approved the test procedure and initiation of testing. All controls and interlocks are checked and instrumentation calibrated. 14.2.12.2.25.3 Description

                . The test will initiate from a power level of 10-25%.                                       The reactor will be scrammed and isolated ~from outside the control room after a simulated control room evacuation. Reactor pressure and water level will be controlled using SRV, RCIC, and RHR from outside the control room during the subseque'nt hot standby and cooldown.

The operating crew will be equal to the minimum shift operating

requirements.

m 2: 14.2.12.2.25.4 Acceptence Criteria Level 1 - NA Level 2 During a simulated control room evacuation, the reactor must be maintained in hot standby conditions for at least 30 minutes. l The test must demonstrate the reduction of reactor coolant pres-sure and temperature sufficient to put RHR shutdown cooling system in operation and cooldown of approximately 50*F using this decay heat removal system. 3 -

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_ __m_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . CPS-FSAR 14.2.12.2.27 RECIRCULATION SYSTEM i i 14.2.12.2.27.1 Purpose The purposes of this test are a) to determine transient responses and steady-state conditions following recirculation pump trips at selected reactor power levels, b) to obtain recirculation system performance j{' data, c) to verify that no recirculation system cavitation occurs on the operable region of the power / flow map, d) to verify that the feed-water control system can satisfactorily control water level without a resulting turbine trip scram following recirculation pump trips, and e) to verify the adequacy of the recirculation runback to mitigate a scram upon loss of one feedwater pumo. 14.2.12.2.27.2 Prerequisites i Required preoperational tests have been completed and the appropriate parties have reviewed and the Plant Manager has aporoved the test pro-cedure and initiation of testing. Instrumentation has been checked or calibrated as appropriate.

14.2.12.2.27.3 Description -

Single and two pump recurculation pumo trips will be made at designated power levels. Reactor operating parameters will be recorded during the transient and at steady-state conditions to experimentally determine the power and flow coastdown rates. Both the jet pumps and the recirculation pumps will cavitate at condi-tions of high flow and low power where NPSH demands are high and littic feedwater subcooling occurs. However, the recirculation flow will automatically runback upon sensing a decrease in feedwater flow, to lower the reactor power. The maximum recirculation flow is limited

by appropriate steps which will runback the recirculation flow from the possible cavitation region. It will be verified that there limits are sufficient to prevent operation where recirculation pump or jet pump cavitation occurs. While ooerating at near -rated recirculation flow simulate a loss of fcedwater pump. Study the transient and deter-l mine the adequacy of the system to prevent a scram.

14.2.12.2.27.4 Acceptance Criteria Level 1 l The two pump drive flow coastdown transient during the first 3 seconds , must be equal to or greater (faster) than the values specified in the

design. The predicted value will be determined upon measurement of the recirculation flow DP (pressure differential, transient time delay, and time constant).

! Level 2 During the one cump trip recovery, the heat flux margin to avoid scram will be at least 5%. I The reactor water level margin to avoid a high level turbine trip shall

be 2
3.0 inches during the one pump trip.

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m. CPS-FSAR 14.2.12.2.28 LOSS OF AUXILIARY POWER 14.2.12.2.28.1 Purpose

( .ci)e The purpose of this test is to demonstrate acceptable performance of the station electrical supply system during the loss of auxi-liary power. 14.2.12.2.28.2 Prereauisites Required preoperational tests have been completed, the appropriate parties have reviewed and the Plant Manager has approved the test procedure and initiation of testing. Instrumentation has been checked or calibrated: as appropriate. 14.2.12.2.28.3 Description The loss of auxiliary power test will be performd between10 and 20 percent of rated power, and the loss of power condition will be main-tained for at least thirty (30) minutes. The p, roper response of reactor , plant equipment, automatic switching equipment, and the proper sequencing of the diesel generator loads will be checked. 14.2.12.2.28.4 Acceptance Criteria Level 1 Reactor crossure and heat flux shall be tiithin the limits established

         .            for the beginnina-of-life conditions carameterized to alloti for vari-( . };           ations in the actual conditions of the test.                                                                       {

All safety systems, such as the Reactor Protection System, the diesel-generators, HPCS and/or RCIC syst~em action, if necessary, shall keep the reactor water level above the initiation level of Low Pressure Core Spray, LPCI and Automatic Depressurization Systems. r-Level 2 - NA  : I i i ti - i

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CPS-FSAR 14.2.12.2.30 RECIRCULATION SYSTEM FLOW CALIBRATION { 14.2.12.2.30.1 Purpose The purpose of this test is to perform complete calibration of the ins talled recirculation system flow instrumentation. 14.2.12.2.30.2 Prereaufsites Required preoperational tests have been completed, the appropriate parties have reviewed and the Plant Manager has approved the test procedure and initiation of testing. Instrumentation has been checked or calibrated as appropriate. 14.2.12.2.30.3 Description During the testing program at operating conditions which allow the recirculation system to be operated at rated flow at rated power, the jet pump flow instrumentation will be adjusted to provide cor-rect flow indication based on the jet pump flow. After the relation-ship between drive flow and core flow is established, the flow biased APRM rod block circuit will be adjusted to match this relationship. 14.2.12.2.30.4 Acceptance Criteria

-, Level 1 - NA Level 2 Jet pump flow instrumentation shall be adjusted such that the jet                  ,

pump total flow recorder will provide calibrated core flow indication i at operating conditions which allow the recirculation system to be operated as would be required to achieve full flow at full power. After the relationship between drive flow and core flow is established, the flow biased APRM/RBM system will be adiusted to match this relation-ship. i i 4 ,- ' 8 9 Sj.f.M.E f ,maam .a . . .n .2 maw.~.mm

h CPS-FSAR 14.2.12.2.31 REACTOR WATER CLEANUP SYSTEM ( W' - 14.2.12.2.31.1 Purpose The pu pose of this test is to demonstrate specific aspects of the mechanical operability of the reactor water cleanup system. (This test, perforced at rated reactor pressure and temperature, is act-ually the completion of the preoperational testing that could not be done without nuclear heating). 14.2.12.2.31.2 Prereauisites Required preoperational tests have been coupleted, the appropriate parties have reviewed and the Plant Manager has approved the test procedure and initiation of testing. Instrumentation has been checked or calibrated as appropriate. 14.2.12.2.31.3 Description With the reactor at rated temperature and pressure, process variables will be recorded during steady-state operation in all modes. 14.2.12.2.31.4 Acceptance Criteria Level 1 - NA m, Level 2 ( '~~ The temperature at the tube side outlet of the non-regenerative heat exchangers shall not exceed 1300 F. in any mode. The pump available NPSH will be 13 feet or greater during the hot standby mode. The cooling water supplied to the non-regenerative heat exchangers shall be within flow and outlet temperature limits indicated on the J process diagrams and system design specifications. l l t l l l

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CPS-FSAR 14.2.12.2.32 RESIDUAL HEAT REMOVAL SYSTEM ( 14.2.12.2.32.1 Purpose The purpose of this test is to demonstrate the ability of the residual heat removal (RHR) system to: 1) remove heat from the reactor system so that the refueling and nuclear system servic-ing can be performed and 2) condense steam while the reactor is isolated from the main condenser. 14.2.12.2.32.2 Prerequisites Required preoperational tests have been completed, the appro-priate parties have reviewed and the Plant Manager has approved the test procedure and initiation of testing. Instrumentation has been checked or calibrated as appropriate. 14.2.12.2.32.3 Description The suppression pool cooling mode will be used to measure the RHR heat exchanger capacity. Data will be obtained to determine the heat transfer rate with rated flow on both sides of the heat exchanger with the largest temperature differential possible between the service and suppression pool water. (Ideally this temperature differential can be established with auxiliary boil-ers or during extended RCIC or relief valve operations.) This heat transfer data can then be used as a benchmark by the appro- {, ' priate design personnel to check the heat exchanger capacity dur-ing other modes of operation. (An ideal demonstration of the RHR heat exchanger capacity would consist of measuring the heat rate in the shutdown cooling mode with the reactor at 50 psig or less. Unfortunately, the decay heat load is insignificant during the startup test period. Use of this model with low core exposure results-in exceeding the 1000 F/hr cooldown rate of the vessel. After accumulating significant core exposure, this demonstration would more adequately demonstrate the heat exchanger capacity.) The RHR system condensing mode is used to condense steam while the reactor is isolated from the main condenser and reactor vessel water level is being maintained by RCIC. This test will optimize the con-trols for this mode of operation. 14.2.12.2.32.4 Acceptance Criteria Level 1 - NA Level 2 The RHR system shall be capable of operating in the steam condensing mode (with both one and two heat exchangers) at the flow rates indi-cated on the process diagrams.

   .s    The RHR heat exchangers shall be capable of being placed in the L/     steam condensing mode and of achieving stable operation at design conditions within one-half hour or less.                                 ,

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CPS-FSAR 14.2.12.2.34 MSIV LEAKAGE CONTROL SYSTEM i y 14.2.12.2.34.1 Purocce The purpose of this test is to demonstrate the ability of the MSIV leakage control system (MSIV-LCS) to depressurize the piping between the MSIVs and outboard motor-operated isolation valve, maintain this I piping at a slight subatmospheric pressure, and direct allowable MSIV leakage into the secondary containment for treatment by the , standby gas treatment system. l 14.2.12.2.34.2 Prerequisites i Required preoperational tests have been completed, the appropriate parties have reviewed and the Plant Manager has approved the test procedure and the initiation of testing. All system instrumentation , is installed and calibrated. All system controls and interlocks have been checked. 14.2.12.2.34.3 Description The reactor will be scrammed or shut down from rated temperature and pressure, and the MSIVs will be subsequently closed. It will be l j demonstrated that after being manually placed in service, the MSIV-LCS l* inboard and outboard subsystems can be initiated provided reactor and main steam line pressure are below 20 psig permissived. The piping between the MSIVs will be depressurized, and the inboard and outboard (- blowers'will take suction there maintaining slightly subatmospheric pressure while discharging to secondary containment in the long term leakage control mode. L 14.2.12.2.34.4 Acceptance Criteria 1 Level 2 '" t i

1. Upon being manually placed in service, the inboard and outboard MSIV-LCS subsystems initiate automatically.

1 i 2. The inboard and outboard MSIV-LCS subsystems depressurize the piping within the-a14ewed- tirne' limits.7c.<t'M 47 de. r,j n . .

3. The inboard and outboard MSIV-LCS blowers maintain the piping between the MSIVs slightly subatmospheric by removing the existing MSIV leakage.

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 ;. ,;, , .      14.2.12.2.36                                       PENETRATION COOLING (j) 14.2.12.2.36.1                   Purpose The purpose of this test is to demonstrate the ability of-the penetration coolers to cool the concrete surrounding selected high temperature penetrat ions in the containment wall.

14.2.12.2.36.2 Prereauisites The required preoperational tests have been completed, the appropriate parties have reviewed and the Plant Manager has approved the test procedure and initiation of testing. Instrumentation has been installed and calibrated. 14.2.12.2.36.3 Dascription The penetration cooling tests consist of measuring concrete temperatures surrounding selected main steam and RWCU discharge piping penetrations in the containment and auxiliary buildings. Measurements from a series of temperature sensors, located on the concrete, will be taken at various steady-state operating power levels. The measurements will be compared to the analytically predicted temperatures and will be shown to be acceptable in relation ,to the results of the analysis and the design criteria. Readings will be taken during the initial reactor heatup and at each major power level during the power ascension test phase. (- 14.2.12.2.36.4 Acceptance Criteria Level 1 The temperature of the concrete adjacent to the selected containment 4 penetrations shall not exceed 200 7 - Level 2 The temperature of the concrete surrounding the selected containment penetrations shall not exceed the values predicted by enalysis, ' o ( d'- Q'A ,$jicci1i ca ,ulon : , I * {' h [ . 4 y g

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     <c      q!          14.2.12.3.1                                                                                     . EXTRACTION STEAM                                                                ,;
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    ...j Test Objectives
1. To demonstrate the ability of the extraction steam system
                                - to respond to process signals and interlocks.

Prerequisites and Initial Conditions

1. C&IO testing has been completed.
2. Instrument air is available.
3. Electrical power is available to extraction steam system components and controls.
4. Main turbine electrohydraulic control system shall be in the " tripped" condition.

Test Procedure

1. Valve operation shall be verified.
2. Operation of controls, interlocks and alarms will be verified.

(4,.O ._ Acccotance Criteria -

1. Valves, controls, interlocks and alarms shall function per design.

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14.2.12.3.2 TURBINE ELECTR0 HYDRAULIC CONTROL 7 ACCEPTANCE-TEST G l Test Objectives

1. To demonstrate the operation of the turbine electrohydraulic control system and its associated protective devices.

Prercouisites and Initial Conditions

1. C&IO testing has been completed.
2. T/G lube oil system is available to support turning gear operation.
3. Turbine building closed cooling water and plant service water are available.
4. Electrical power is available to turbine electrohydraulic control system components and controls.

Test Procedure

1. Pumps shall be performance tested C.p, Operation of controls, interlocks and alarms will be verified.

L .' ' 2. Acceptance Criteria . ; --

1. Pump performance shall meet design requirements
2. Controls, interlocks and alarms shall function per design.

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FEEDWATER HEATER DRAINS

                                                                                  --ACCEPTANCE - TEST f

Test Objectives

1. To demonstrate the ability of the feedwater heater drains system to respond to process signals and interlocks.

Prerecuisites and Initial Conditions

1. C&IO testing has been completed.
2. Instrument air is available
3. Electrical power is available to feedwater heater drains system components and controls.

Test Procedure

1. Valve operation shall be verified.
2. Operation of controls, interlocks and alarms will be verified.

Acceptance Criteria (. ~i

1. Valves, controls, interlocks and alarms shall function per design.

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14.2.12.3.4 MAKE-UP DEMINERALIZERI. ACCEPTANCE-TEST .! (..' I Test Objective

1. To demonstrate the ability of the make up demineralizer system to meet design requirements for flow and effluent water chemistry.
2. To demonstrate operation of associated controls, interlocks
                                    ~
                           - and alarms.

Prerequisites and Initial Conditions

1. C&IO testing has been completed.
2. Instrument air, service air, liquid chlorine and service water systems are available for operation.
3. Electrical power is available to make up demineralizer system components and controls.

Test Procedure

1. Pumps shall be performance tested
2. Operation of controls, interlocks and alarms will be verified.
                                                                                                                                                            ~
3. Effluent water quality shall be verified.

s. Acceptance Criteria . t .

1. Pump performance shall meet design requirements.
2. Controls, interlocks and alarms shall function per design.
3. Effluent shall meet the design requirements for flow and chemistry. .

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g,.r-:... CPS-FSAR , , 14.2.12.3.5 CYCLED CONDENSATE /MAKE-UP CONDENSATE

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                                                            -ACCEPTANCE-TEST O                                                                                                                                                       I Test Objective
1. To demonstrate the ability of the cycled condensate /make up condensate system to provide flow to components served.
2. To demonstrate operation of associated controls, interlocks and alarms.

Prerecuisites and Initial Conditions ! 1. C&IO testing has been completed.

2. Instrument air, make up water systems are available.
3. Electrical power is available to cycled condensate /make up 4

condensate system components, controls and heat tracing. Test Procedure g; 1. Pumps shall be performance tested.

2. Operation of controls, interlocks and alarms'shall be verified.
3. Operation of containment isolation valves shall be verified.

Acceptance Criteria

1. Pump performance shall meet design requirements.

! 2. Controls, interlocks dnd alarms shall function per design. -

3. Containment isolation valves shall operate per design.

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        ..              14.2.12.3.6                                        CONDENSER VACUUM

_. -ACCEPTANCE -TEST b Test Objectives

1. To demonstrate the ability of the condenser vacuum system to evacuate and maintain vacuum on components served.
2. To demonstrate operation of associated controls, interlocks and alarms.

Prerequisites and Initial Conditions

1. C&IO testing has been completed.
2. The following systems shall be available:

instrument air turbine building closed cooling water plant service water cycled condensate /make up condensate condensate system off gas main steam

3. Electrical power is available to condenser vacuum system

(. .?.. l' components and controls. Test Procedure

1. Pumps and ejectors will be, performance tested.
2. Operation of controls, interlocks and alarms shall be verified.

i-I l Acceptance Criteria i 1. Pump and ejector performance shall meet design requirements. . ! 2. Controls, interlocks and alarms shall function per design. E

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          .-                                                                                                                                      t Test Objective
1. To demonstrate the ability of the process sampling system to condition and analyze samples.

Prerecuisites and Initial Conditions

1. C&IO testing has been completed.

f

2. Turbine building closed cooling and component cooling water
  • shall be available. ,
3. Sampled systems shall be available as required.
4. Electrical power is available to process sample system components and controls.

Test Procedure

1. Sample panels shall be performance tested.

{gy 2. Instrumentation and control operation shall be verified. Acceptance Criteria -l

1. Sample panels shall condition samples per design requirements.
2. Instrumentation and controls shall function per design.

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C'**'"' 14.2.12.3.8 PLANT SERVICE WATER

    ,- s                                                                                                            - ACCEPTANCE-TEST f

O I Test Objectives

1. To demonstrate the ability of the plant service water system to supply water to the various components it serves.
2. To demonstrate operation of associated controls, interlocks and alarms.

Prerequisites and Initial Conditions

1. C&IO testing has been completed.
2. Components served by the plant service water system shall be available.
3. Electrical power shall be available for plant service water components and controls.

Test Procedure

1. Pumps will be performance tested.

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2. Operation of controls, interlocks and alarms shall be verified. ~
3. Flow to components served shall be verified.

Acceptance Criteria

1. Pump performance shall meet design requirements.
2. Controls, interlocks and alarms shall function per design.
3. Flow to components served shall meet design requirements. -

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p. ACCEPTANCE-TEST W j Test Objectives
1. To demonstrate the ability of the turbine building closed cooling water system to supply water to the various components it serves.
2. To demonstrate operation of associated controls, interlocks and alarms.

4 Prereauisites and Initial Conditions

1. C&IO testing has been completed.

l

2. Components served by turbine building closed cooling water shall be available.
3. Electrical power shall be available to turbine building closed cooling water system components and controls.

Test Procedure-hs. } 1. Pumps will be performance tested.

2. Operation of controls, interlocks and alarms shall be verified.
3. Flow to components served shall be verified.

Acceptance Criteria

1. Pump performance shall meet design requirements.
2. Controls, interlocks and alarms shall function per design.

Flow to components served shall meet design requirements. 3. i

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CPS-FSAR '"- 4.;,g:gf.Q"f,- 14.2.12.3.10 CONDENSATE POLISHING , ACCEPTANCE-TEST-

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Test Objectives

1. To demonstrate the ability of teh condensate polishing system to meet design requirements for flow and effluent water chemistry.
2. To demonstrate operation of associated controls, interlocks and alarms.

s Prerequisitas and Initial Conditions

1. C&IO testing has been completed.
2. The-following systems are available as required.

cycled condensate instrument air service air condensate condensate booster

  • reactor feedwater turbine building closed cooling water acid / caustic process sampling C:- C
3. Electrical power is available to condensate polishing system components and controls.

Test Procedure _..

1. Pumps will be performance tested
2. Operation of centrols, interlocks and alarms shall be verified.
3. Polisher effluent water quality shall be verified.

t , Acceptance Criteria

1. Pump performance shall meet design requirements.
2. Controls, interlocks and alarms shall function per design.
3. Polisher effluent water quality shall meet design requirements.

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_ 14.2.12.3.11 PLANT-BREATHING AIR ACCEPTANCE TEST ' I

      . ., s.<                                                                                                                                  l Test Objectives
1. .To demonstrate the ability of the plant breathing air system to provide breathing air to various locations throughout the plant.
2. To demonstrate the operation of associated controls, inter-locks and alarms.

Prereauisites and Initial Conditions

1. C&IO testing has been completed.
2. Electrical power is available to plant breathing air components and controls.

Test Procedure

1. Compressers and air dryers will be performance tested.
2. Operation of controls, interlocks and alarms will be verified.
      '?s                  3. Operation of containment isolation valves will be verified.

Acceptance Criteria

1. Compresser/ air dryer perfor,mance shall meet design requirements.
2. Controls, interlocks and alarms shall function per design.

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3. Containment isolation valves shall operate per design.

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(b A REGULATORY GUIDES USED

    %./                                           IN THE DEVELOPMENT OF THE INITIAL TEST PROGRAM 1.18               Structural Acceptance Test for Concrete Primary Reactor Containments 1.20               Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing 1.37               Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants 1.41               Preoperational Testing of Redundant On-Site Electric Power Systems to Verify Proper Load Group Assignments 1.52               Design, Testing, and Maintenance Criteria for Post Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants
  '    ;       1.68                Initial Test Programs for Water-Cooled Reactor Power Plants 1.68.1              Preoperational and Initial Startup Testing of Feedwater and Condensate Systems for Boiling Water Reactor Power Plants 1.68.2              Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants 1.80               Preoperational Testing of Instrument Air Systems

[ N 1.140 Design, Testing, and Maintenance Criteria for . Normal Ventilation Exhaust System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear f Power Plants

                 /,, /C[:/           PERIODIC TESTING OF DIESEL GENERATOR UNITS f USED AS ONSITE ELECTRIC POWER SYSTEMS AT NUCLEAR POWER PLANTS Note:       Exceptions taken to these Regulatory Guides are described in Section 1.8.
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m TABLE 14.2-2 i A . (p! PREOPERATIONAL TESTS Subsection Test Title Page 14.2.12.1.1 Feedwater System Preoperational-Test- 14.2-20 14.2.12.1.2 Reactor Water Cleanup System

                                            .Ereoperational-Test-                                                      14.2-22 14.2.12.1.3              Standby Liquid Control System Properariunni-Test                                                         14.2-23 14.2.12.1.4              Nuclear Boiler System Preoperationa                                            _Te s t-                                                                     14.2-25 14.2.12.1.5              Residual Heat Removal System Preoperational-Test-                                                       14.2-27 14.2.12.1.6              Reactor Core Isolation Cooling System Preoperational-Tese                                                        14.2-29 14.2.12.1.7              Reactor Recirculation System
                                           -Preoperational-Test                                                        14.2-31 14.2.12.1.8              Rod Control and Information System Preoperational-Test                                                        14.2-33 14.2.12.1.9              Control Rod Drive System Preoperational-Test- g                                                     14.2-34                 j 14.2.12.1.10             Fuel Handling and Veseel Servicing bJs                                         Equipment Preoperational-Test                                              14.2-36              )

( 14.2.12.1.11 Low Pressure Core Spray System Preoperational-Test- 14.2-38 14.2.12.1.12 High-Pressure Core Spray System

                                           --Preopernri'Onni Test                                                      14.2-40 14.2.12.1.13             Fuel Pool Cooling and Cleanup System
                                           ~Preoperationni Test;                                                       14.2-42 14.2.12.1.14 Liquid Radwaste P-reoperatrional-Test-                                                 14.2-44 14.2.12.1.15 Solid Radwaste EreoperationnT Test                                                     14.2-45 14.2.12.1.16             Reactor Protection System Preoperational-Tese                                                        14.2-46 14.2.12.1.17             Neutron Monitoring System Preoperational-Test ~ .                                                    14.2-48 14.2.12.1.18             Traversing Incord Probe System                                                           -
                                           -Prcopcr:rritnnl-Test                                                       14.2-49 14.2.12.1.19             Process Radiation Monitoring System
                                          --Preopera t-ionel-Tes t                                                     14.2-50 14.2.12.1.20             Area Radiation Monitoring System
                                      . Properational-Tes t                                                        14.2-52 14.2.12.1.21             Off-Gas Sys tem Preoperational-Test'                                       14.2-53 14.2.12.1.22             MSIV Leakage Control System
                                           .P-r-eoperatione-1-Test                                                    14.2-54 14.2.12.1.23             Suppression Pool Makeup System
                                           -P-r-eoperctionsi Tes t                                                     14.2-55 14.2.12.1.24 Containment Combustible Gas Control System Preoperativuum im                                                   14.2-56
3. ( . ' 14.2.12.1.25 Component cooling Water System .

Preopsationel Test 14.2.12.1.26 Shutdown Service Water T.re --' " 14.2-57..,h"M

                                                                                                                               ^M SI
                                           -Test-                                                                     14.2-58            ..
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[ Jh. /t.1.- 2. 4 M PREOPERATIONAL TESTS (Cont ' d. ) ny . Subsection Reference Test Title Page 14.h.12.1.27 Shutdown Service Water Ventilation a System Preoperational-Test 14.2-59 14.4.12.1.23 Essential Switchgear Heat Removal Preop erational--Te s t 14.2-60 14.2.12.1.29 Control Room HVAC System

                                       -Preoperational-Test                                           14.2-61 14.2.12.1.30            ECCS Equipment Cooling HVAC System
                                        -Preoperational-Test                                          14.2-63 14.2.12.1.31             Diesel Generator Room HVAC
                                        -Preoperational-5'es t                                        14.2-64 14.2.12.1.32             Dryuell Purge Ventilation System
                                         -Preoperational-Tes t                                        14.2-65 14.2.12.1.33             Drywell Cooling System Preoperational-
                                     - Tes t.                                                         14.2-66 14.2.12.1.34             Containment Building HVAC System Preoperational-Tes t-                                       14.2-67 14.2.12.1.35             Standby Gas Treatment System Preoperational-Test                                         14.2-68 14.2.12.1.36             Diesel Generator System -Preoperational-
                                         -Test                                                        14.2-70
        .i       14.2.12.1.37             Reactor Vessel Flow Induced Vibration
                                         -Preoperational-Tes t                                        14.2-72 14.2.12.1.38             125 VDC Systems Preoperationni Test                         14.2-73 14.2.12.1.39             Containment Monitoring System
                                       -Preoperat-ional-Test                                          14.2-74 14.2.12.1.40            Electrical Distribution Preoperational-
                                       -Tes t-                      '

14.2-75 < 14.2.12.1.41 Auxiliary Building HVAC Freoperational- ! -Te s t- 14.2-76 ! 14.2.12.1.42 Radwaste Building HVAC Preoperational-l Test- 14.2-77 14.2.12.1.43 Fuel Building HVAC System

                                       -P-reoperational-Tes t -                                       14.2-78          ,

14.2.12.1.44 Off-Gas Vault' HVAC Sys tem

                                       -Protiperat ibnal= Test                                        14.2-79 14.2.12.1.45             Fire Protection System Ercoperational-
                                        -Te s t                                                       14.2-80 14.2.12.1.46 Instrument and Service Air System Preoper-acional--Test                                       14.2-81 14.2.12.1.47             Condensate Preoperational-Test                              14.2-82 14.2.12.1.48             Seismic Instrumentation P-rcoperational-
                                     ---Test-                                                         14.2-83 14.2.12.1.49             Condenser Circulating Water System
                                       -.Precip eracirnri-Tese                                        14.2-84

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        ..                                                          PREOPERATIONALTESTS[C,f,/',6 Subsection Reference                                            Test Title                                                   Page 14.2.12.1.50                   Con:nunications Systems Preoperational-
                                                        -Test                                                                               14.2-85 14.2.12.1.51                   Cranes Preoperational-Test-                                                        14.2-86 14.2.12.1.52                   Drywell Leakage Preoperational-Test-                                               14.2-87 14.2.12.1.53                   Primary Containment Leak Rate Preoperational-Tes t-                                                              14.2-88 14.2.12.1.54 Turbine Building HVAC System
                                                        -Preoperational-Tes t                                                               14.2-89 14.2.12.1.55 Loose Parts Monitoring System P reopera tional.-Tes t                                                            14.2-90
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q.- TABLE 14.2-3 s-4 STARTUP TESTS Subsection Test Title Page

                                                                                                   %/f 14.2.12.2.1                 Chemical and Radiochemical                                14.2-92 14.2.12.2.2                 Radiation Measurements                                    14.2-94 14.2.12.2.3                 Fuel Loading _ /                                          14.2-95                ,

14.2.12.2.4 Feel-Nore Shutdown Margin 14.2-97 l 14.2.12.2.5 Control Rod Drive System 14.2-98 14.2.12.2.6- SRM Performance and Control Rod Sequence 14.2-102 14.2.12.2.7 Water Level Measurements 14.2-103 14.2.12.2.8 Rod Sequence Exchange 14.2-105 14.2.12.2.9 IRM Performance 14.2-106 14.2.12.2.10 LPRM Calibration 14.2-107 14.2.12.2.11 APRM Calibration 14.2-108 14.2.12.2.12 Process Computer 14.2-109

                                                                                                                                     ~

14.2.12.2.13 RCIC System 14.2-111 14.2.12.2.14 Selected Process. Temperatures and Water Level Referenca Leg Temperature 14.2-113 14.2.12.2.15 System Expansion 14.2-115 14.2.12.2.16 Core Power Distribution 14.2-117 14.2.12.2.17 Core Performance 14.2-119 14.2.12.2.18 Core Power-Void Mode 14.2-121 ( "?. 14.2.12.2.19 Pressure Regulator 14.2-122 14.2.12.2.20 Feedwater System 14.2-124 14.2-126 14.2.12.2.21 Turbine Valve Surveillance 14.2.12.2.22 Main Steam Isolation Valves 14.2-127 14.1.12.2.23 Relief Valves 14.2-129 J 14.;1,.12.2.24 Turbine' Trip and Generator;f Load i Rejection 14.2-131 14.2.12.-2.25 Shutdown From Outside the Main Control Room Startup Test 14.2-133 14.2.12.2.26 14.2-134 Recirculation Flow Control l 14.2.12.2.27 Recirculation System 14.2-137 14.2.12.2.28 Loss of Auxiliary Power 14.2-139 14.2.12.2.29 Piping Vibration 14.2-140 14.2.12.2.30 Recirculation Reactor Water;Sys, tem System Flow Calibration 14.2-141 . 14.2.12.2.31 Cle'anup 14.2-142 14.2.12.2.32 Residual Heat Removal System 14.2-143 l 14.2.12.2.33 Drywell Atmosphere Cooling System 14.2-144 f.), ;, J .,; . ;' . . * ; IV s awiv *: ~ ',,ha d, / wi' C y* dv ' d. W Y .

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