ML20069L063

Forwards Response to NRC 820428 Request for Addl Info Re Organizational Changes.Draft Revised FSAR Chapter 14 Pages, Reflecting Changes,Encl

ML20069L063
Person / Time
Site:	Seabrook
Issue date:	11/10/1982
From:	Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE, YANKEE ATOMIC ELECTRIC CO.
To:	Knighton G Office of Nuclear Reactor Regulation
References
SB-360, NUDOCS 8211160406
Download: ML20069L063 (193)

Text

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SEASROM SMN IPUBLIC SERVICE -  :. 4 onk.: ,

Compar yof NewHempshire 1671 Worcester Road Framinoham, Massachusetts 01701 (617)-872 8100 Nove:nber 10,'1982 SB-360 -

T.F. B7.1.2 United States Nuclear Regulatory Conunission Washington, D. C. 20555 Attention: Mr. George W. Knighton, Chief Licensing Branch 3 Division of Licensing i~

Re fe rences : (a) Construction Permits CPPR-135 aci CPPR-136, Docket Nos. 50-443 and 50-444 (b) USNRC Letter, dated April 28, 1982, " Request for Additional Information - Procedures and Test Review Branch," F. J. Miraglia to W. C. Tallman s

Subject:

Response to 640 Series RAIs; (Procedures and Test Review Branch)

Dear,

_ Sir: .

We have enclosed responses to the subject Requests for Additional Information (RAIs) which were forwarded in Reference (b).

Responses to the. following RAIs are not included with this letter but will be forwarded in the near future:

640.4, 640.5, 640.8, 640.29, 640.33, 640.36, 640.61 Also encloed are the revised FSAR Chapter 14 pages which support the RAI responses and addicional revised pages which reflect organizational changes.

The enclosed information will be included in OL Application Amendment 48.

Very tr uly yours, YANKEE ATCHIC ELECTRIC COMPANY

/

J. DeVincentis Project Manager ALL/ fsf cc with enclosure.

Mr. Walter A ppley QD Battelle Northwest Labs P.O. Box 999 Richland, Washington 99352 8211160406 821110 PDR A

ADOCK 05000443 PDR

640.6 The initial test program should verify the capability of.

the offsite power system to serve as a source of power to the emergency buses. ! Tests should demonstrate the capability of each starting transformer to supply ?ower (as the alternate supply) to its unit's emergency buses-while carrying its maximum load of plant auxiliaries and the other unit's emergency buses (as preferred supply).

Tests should also demonstrate the transfer capabilities of the unit's emergency bus feeders upon loss of one source of offsite power. These tests should be per-formed as early in the test program as the availability of necessary components allows. Provide descriptions of the tests that will demonstrate these capabilities.

RESPONSE: The initial test program will verify the capability of the offsite power system to serve as a source of power to the emergency buses. The test program will demonstrate the capability of each transformer to supply power to the emergency buses while carrying its maximum load of plant auxiliaries.

Seabrook design does not include interconnections between units, therefore, no testing will be pre-formed in conjunction with the other unit's emergency buses. The test program will demonstrate the transfer capabilities of the unit's emergency bus feeders upon loss of one source of offsite power.

Table 14.2-3 item 30 will be revised to include this testing.

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640.7 Testing in conformance with Regulatory Guide 1.41 must

. incorporate the following:

1) Provide assurance that all sources of power supply to vitc1 buses are capable of carrying full acci-dent loads. If some portions of the power supplies cannot be full-load tested, provide justification.

2) Verify that testing is conducted with only one power source at a time.

3) Verify that buses not under test are monitored to verif,y absence of vol.tage.

RESPONSE: 1) Testing will demonstrate the safety related inverters are capable of carrying full accident loads while being supplied by all sorces of power (Table 14.2-3 item 32).

2) During the loss of offsite power tests (Table 14.2-3 item 39) testing will be conducted with both diesel generators started simultaneously and with each diesel generator started separately and operated independently. The test abstract will be revised to state thi.s. .

3).During the loss of offsite power tests (Table 14.2-3 item 39) the buses not under test will be

. monitored to verify the absence of voltage. The test abstract will revised to state this.

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640.9 Verify that safety and relief valves are checked atopen and reclosure setpoint temperature.

RESPONSE

Verification safety valveoflift pressurizer and main steam settings (as defined by ivchnical Specifications) during Intergrated Hot will be conducted 14.2-3 item 40). Functional. Tests (Table ducted at hot conditions.This testing will be con-O 1

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640.10 Rsvicw cf licenssa svent reports disclossd that seco instrunsntation drift problocs are dus, in part, to extremes of local temperature and humidity. Provide a description of the inspections or tests that will be performed to minimize setpoint drift'due to local tem-perature and humidity extremes.

RESPONSE: The location of instrumentation is determined with consideration of the environment (local temperature and humidity). During preopera-tional testing adequate ventilation and/or cooling is demonstrated to maintain system or building design requirements. These tests are described in Table 14.2-3 items 22, 28 and 29, Table 14.2-4 items 23, 24, 25, and Table 14.2-5 item 46. It is not expected that local temperature

. and humidity extremes will cause instrument drift problems; however, should instrument drift problems reoccur for a specific instrument, the local environment for that instrument will be inspected fqg temperature and humidity extremes.

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640.11 Identify any of the post-fuel Loading tests described in Section 14.2.12, Table 14.2-5 which are not essential towards the demonstration of conformance with design requirements for structures, systems, components. Plant features that meet any of the following criteria should be tested:

, 1) Will be relied upon for safe shutdown and cooldown of the reactor under normal plant conditions and for maintaining the reactor in a safe condition for an extended shutdown period.

2) Will be relied upon for safe shutdown and co'oldown of the reactor under transient (infrequent or moderately frequent events) conditions and postu-lated accident conditions, and for maintaining the reactor in a safe condition for an extended shut-down period following such conditions.

3) Will be relied upon for establishing conformance with safety limits or limiting conditions for operation that will be included in the facility technical specifications.

4) Are classified as engineered safety features or

' will be relied upon"to support or assure the opera-tion of engineered safety features within design ,

limits.

5) Are assumed to function or for which credit is taken in the accident analysis for the facilit described in the Final Safety Analysis Report)y (as

6) Will be utilized to process, store, control or limit the release of radioactive materials.

RESPONSE: The following three tests are not considered to be essential in demonstrating conformance with the requirements shown in Regulatory Guide 1.68 REV. 2, C.1.a through C.1.f:

A. ST-40, NSSS Acceptance Test.

B. ST-48, Turbine Generator Startup Test.

C. ST-49, Circulating Water System Thermal-Hydraulic Test.

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640.12 Our rovicw of licensas sysnt rcports hns disclosed that many events have occurred because of dirt, condensed moisture, or other foreign objects inside instruments and electrical components (e.g., relays, switches, breakers). Describe any tests or inspections that will be performed or any administrative contrpls that will be inplemented during your initial test pr, gram to prevent component failures such as these at your facility.

RESPONSE: The conduct of the test program (Section 14.2.4) is described in the Preonerational Test Program Description. The administrative controls of this program require construction to be essentially complete on a system and individual components to be tested and/or inspected prior to the performance of the preoperational or acceptance test being per-formed. It is expected that this testing program should demonstrate such component failures iden-tified in RAI 640.12 do not exist.

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640.13 Containment Combustible Gas Control System Test (PT 25).

Demonstrate the following:

(1) the capability of the Combustible Gas Control System to operate in response to post-LOCA requirements, (2) that post-LOCA hydrogen monitors function properly, (3) the operability of the vacuum breakers.

RESPONSE: The three compcnents of the Cocbustible Gas Control System, (Hydrogen Recombiners, Hydrogen Analyser, and Backup Purge System) will be tested during the performance of PT-25. During the performance of PT-25, the hydrogen recombiner'will be opera-tionally checked to demonstrate proper operation of its control and mon'itoring functions. The air flow through the recombiner will be demonstrated to be at least 100 sofm. The heatup portion of the test will demonstrate that the recombiner has sufficient power to achieve recombination temperature (12250 F). During the performance of PT-25, the Hydrogen Analyser will be operationally checked to demonstrate proper operation of its control, moni-toring and alarm functions. Proper flow paths will

'be checked. The Hydrogen Analyser calibration will be confirmed by introduction of Reagent and Calibration gases. There are no vacuum breakers on the containment to be operationally checked.

During the performance of PT-25, that portion of the Backup Purge System not previously demonstrated operable by PT-23 (Containment Enclosure Exhaust System Test) will be operationally checked.

Compressed air flow to the containment will also be demonstrated operable.

Components of the CGCS located within the contain-ment are protected against damage from internally generated missiles or jet impingement in the post-LOCA environment. Moreover, such components have been subjected to qualification tests,to demonstrate their capability to remain operable in the LOCA environment for as long as may be required.

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640,14 Solid Radwaste System Test tance criterion to require that(AT 17). Modify the accep-fication for notin the solidfication sample v or pro idthere be no fre including this criteria.e technical justi-

RESPONSE

Thebeen yet waste solidfication system for Seabrook as not h

written. this request at purchased time. nor has a specification s

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640.15 Our review of recent Licensee event reports disclosed that a significant number of reported events concerned the operability of hydraulic and mechanical snubbers.

Provide a description of the inspections or tests that will be performed following system operation to ensure that snubber operation is adequate. These inspections or tests should be performed preoperationally or, if the system for which the snubbers are being inspected will not be subjected to significant transients prior to fuel

. loading, the startup then inspections transient tests.should be conducted following RESPONSE: Snubber installation and operability verification is discussed in section 3.9(B).3.4.d (Amendment 44).

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640.16 Review of licensee event reports disclosed that a number of sensing lines were rendered inoperable due to being frozen and/or blocked with crud, dirt and entrapped gas.

Provide a description of the inspections or tests that will be performed to ensure that the sensing lines are clear prior to utilization.

RESPONSE: During the flushing program instrument sensing lines will be flow tested to verify correct installation, continuity, and freedom from obstruction. Instrument performance is further verified by cross channel checks of similar instru-ments reading the same parameter.

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640.17 Containment Spray System Test (PT-12). Verify that paths for the air flow test of containment spray no::les overlap the water-flow test paths of the pumps to demonstrate that there is no blockage in the flow path.

RESPONSE: The Startup Test Department will develop and perform flushing procedures to verify Containment Building Spray system piping cleanliness. The air flow test of the containment spray nozzles will overlap the water flow path of the flushing program.

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640.18 Containment Air Recirculating System Test (PT 26).

Verify that the containment recirculation fan motor current is within its design value at conditions representative of accident conditions. Address such issues as air density, temperature, humidity, fan speed, and blade angle.

RESPONSE: The containment structure recirculation filter

. system (CSRFS) which is described in Subsection 9.4.5 is the only portion of the containment air recirculating system that is designed to operate in a post - LOCA environment.

Following a LOCA, the fans take suction from the apex of the dome and discharge below the operating

, floor. The fans, the dampers, and the suction and discharge ductwork are capable of withstanding the physical, chemical and radiological environment to which they will be subjected in the event of a LOCA. These components have been subjected to qualification tests to demonstrate their capability to remain operable in the LOCA environment for as long as may be required.

(Reference FSAR Subsection 6.2.5.1 - e) i

640.19 Verify that tests of sampling systems are adequate to verify flow paths, holdup times, and procedures.

RESPONSE: Flow paths from each sample source per Table 9.3-1 will be verified during the performance of AT-10 (Table 14.2-4, item 10). Holdup times for the sample lines from Reactor Coolant Loops 1.5 3 will be verified during the performance of AT-10 and a change to Test Abstract AT-10 will be incorporated to reflect the required verification of holdup times. AT-10 will incorporate the plant operating

• procedure to the extent necessary to verify that the operating procedure is adequate.

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640.20

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Provide a preoperational test description to test con-tainment penetration coolers. On those penetrations where coolers are not used, provide a startup test description that will demonstrate that concrete tem-peratures surrounding hot penetrations do not exceed design limits.

RESPONSE: Containment penetration coolers are not used at Seabrook. During the startup test program, temper-a

- ture data will be collected from the concrete surrounding the hot penetrations. This data will be compared to expected values to verify that design limits are not exceeded.

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640.21 Provide a commitment to include in your test program any design features to prevent or mitigate anticipated tran-sients without scram (ATWS) that may now, or in the future, be incorporated into your plant design.

RESPONSE: Any design features to prevent or mitigate ATWS will be tested at such time as they are incorp-orated into the Seabrook Station design.

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640.22 Describe the status of the power supplies to the "other" unit to ensure independence during power distribution testing. The descriptions should address both normal and' emergency A.C. and D.C. power distribution systems.

Provide assurance that crossties will not exist which could cause loss of emergency bus power to one unit due-to testing of the other unit.

RESPONSE: There are no crossties or interconnections in the electrical distribution system between units at Seabrook, therefore, the status of the power supplies of one unit will not be affected by the

, other unit.

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640.23 ECCS Parforcence Test (PT 8). Includo tha following for ths low end high pressuro sofoty injcetion, cold con-dition, flow tests:

1) Demonstrate that adequate margins exist between pump motor trip points and maximum operating con-ditions for all pump moters.

2) Demonstrate the adequacy of the electrical power supply by testing under maximum startup loading conditions.

RESPONSE: 1) During the ECCS performance testing (Table 14.2-3 item 8) current readings from the centrifugal charging pumps, safety injection pumps, and residual heat removal pumps will be obtained during full design flow conditions and compared with actual pump motor trip points to demonstrate that adequate margins exist.

2) Demonstration of the alequacy of the electri-cal power supply under maximum startup loading conditions will be conducted during loss-of-offsite power testing (Table 14.2-3 item 39) and AC electrical distribution testing (Table 14.2-3 item 30).

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640.24 ECCS Hat Functional Test (PT9) includa tho following:

1) Expand the test prerequisites to include those listed in re ulatory Guide 1.79, regulatory posi-tion C.I.c. 2).

2) In the exception to position C.1.a (2) (Page 14.2-8) reference "Other Tests" which will demonstrate the integrated system response to an actuation signal.

RESPONSE: The ECCS Hot Functional Test, PT9, in and of itself does not provide complete ECCS Testing. Several.

tests are combined to provide comprehensive ECCS operational testing. The ECCS performance test, PT8, (Table 14.2-3 item 8), the safety injection -

Accumulator Blowdown Test, PTIO, (Table 14.2-3 item 10), the containment recirculation sump operability demonstration, PT11, (Table 14.2-3 item 11), and the ESF Integrated Actuation Test, PT38, (Table 14.2-3 item 38), are supplemental tests which when combined with the ECCS Hot Functional Test PT9 pro-vide comprehensive ECCS testing. All prerequisi-tes, as identified in Regulatory Guide 1.79 with the exceptions as described in section 14.2, are verified during the performance of the previously identified tests.

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l 640.25 In Section 14.2.3 verify that the completion of the i

required preoperational testing that is required prior to fuel loading includes review and approval of test results. If portions of any preoperational tests are intended to after fuel loading: be conducted, or their results approved,

1) List each test.

2) State what portions of each test will be delayed until after fuel loading.

. 3) Provide technical justification for delaying these protions.

4) State when each test will be completed (key to test conditions defined in Chapter 14).

Note that any test that you do not intend to begin prior to fuel loading should be included in your startup test phase instead of the preoperational test phase.

RESPONSE

Completion of the required preoperational testing that is required prior to fuel loading includes review and approval of test results. Section 13.5.1.2 will be revised to include that approval of test results is required for all preoperational

. tests (except AT-17) prior to fuel loading.

Waste Solidification System Test, AT-17, ( Table 14.2-4 item 17) may be performed after fuel loading. This may be required if a Waste Solidfication System is not installed in Seabrook at the time of fuel loading. The system will be tested subsequent to installation independent of the startup test program. If during t:1e course of the Preoperational Test Program it becomes necessary to delay a portion of a preoperational test until after core load, such tests will be incorporated into the Startup Test Program. The justification for such a delay will be provided at that time.

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640.26 Safety Injection Accumulator Blowdown Test (PT 10).

Modify the existing abstract or provide additional tests that will demonstrate the operability of the accumulator check valves at higher-than-ambient temperatures in accordance with Regulatory Guide 1.79, Position C.1.c(3).

RESPONSE: The operability of the accumulator check valves at higher than ambient temperature will be demonstrated during the ECCS Hot Functional Test, PT-9, (Table 14.2-3 item 9) when the plant con-ditions satisfy the test requirment.

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• 640.27 Include a description of the test (s) (Table 14.2-3) that

, . will be performed to ensure conformance to Regulatory Guide 1.95 Protection of Nuclear Power Plant Control Room Operators Against1an Accidental Chlorine Release.

-(NOTE: for a Type 1 control room, refer to Positions C.1, C.2, C.3a and C.4-6.)

RESPONSE: As explained in section 1.8 the plant design does not include the storage of chlorine within 100

, meters of the control room, excluding small labora-tory quantities, nor is th re chlorine stored in excess of the maximum allowable chlorine inventory; therefore, no additional testing is required to be performed to ensure conformance to Regulatory Guide 1.95.

Control room ventilation testing will be performed (Table 14.2-3 item 28). Included in this testing will bc the " Control room envelope" boun-dary seals to maintain the required positive pressure. This test will meet Regulatory Guide 1.95, Regulatory Position C.5 for measuring gross leakage characteristic of the control room.

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640.28 . Diesel Generators Test (PT 33). The test is presented in insufficient detail to assure the staff that Positions C.2a and C.2b of Regulatory Guide 1.108 will be satisfied. Modify Table'14.2-3 (test abstracts) and Section 1.8, accordingly.

RESPONSE: The positions of C.2a and C.2b of Regulatory Guide 1.108 will be. satisfied with the exception of posi-tion C.2a(5) as dis. cussed in section 1.8.

Diesel generator testing (Table 14.2-3 item 33) and

, loss of offsite power testing (Table 14.2-3 item

39) will be revised to provide sufficient detail to assure the positions will be satisfied.

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Pago 1 of 2 640.30 Instrumsnt the following: end Sarvice Air System Test (PT 12). Perform 1)

Expand the test prerequisites to encompass those cited in Regulatory Guide 1.80, Preoperational Testing of Instrument Air Systems.

2)

Include testing of the components and systems C.2-C.7. to in Regulatory Guide 1.80, Sections referred

3) Identify the systems that are dependent on service air andtoare going be to be tested and those that are not tested.

To ensure conformance with Regulatory Guide 1.80, provide the following:

a) Sufficiently detailed test abstracts for those systems, tested.

dependent on air, that are to be b)

Sufficiently for not detailed technical justifications on air.

testing any systems that are dependent RESPONSE: 1) AT-12, Instrument and Service Air Systems Test i will satisfyGuide Regulatory the prerequisites 1.80. required by -

2) AT-12 will comply with Regulatory Guide 1.80 sections C.2-C.7.

3a) No systems supplied by service air will be tested by AT-12.

3b)

Service systems: air provides air for the following Auxiliary Steam: Air is supplied to atomize fuel for the auxiliary boilers during startup of the boilers from cold conditions and to prevent furnace gases from escaping when the viewports are opened. The auxiliary steam system does not provide any safety related functions and will not be tested by AT-12.

Hot Water Supply: Air is supplied to pressurize the compression tot water heating systems. tanks in building the HWS system is not not will a consumer mean of air soloss immediate lossofofpressure service in air .

the compression tanks. The HWS system equip-ment is adequately plotected from loss of compression tank pressure by interlocks and alarms testing.

which will be tested during HVAC AT-12. This system will not be tested by

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Pago 2 of 2 G40.30 Combustible Gas Control:

Service air provides makeup air to containment during operation:of the Backup Purge System.

This capability will be demonstrated by PT-25 Containment Combustible Gas Control System Test and will not be tested by AT-12.

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640.31 Shutdown from Outside the Control Room Test (ST 33).

Modify the test prerequisites to include those set forth in Regulatory Guide 1.68.2, Initial Startup Test Program to demonstrate remote shutdown capability for Water-Cooled Nuclear Power Plants.

RESPONSE

FSAR Section 14.2.7, "Conformance of Test Programs with Regulatory Guides", Regulatory Guide 1.68.2 rev.1 states that "The remote shutdown capability of Seabrook Station will be demonstrated in accor-dance with the intent of Regulatory Guide 1.68.2".

The prerequites listed in the Regulatory Guide will be included in test procedure ST 33.

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640.32 Conformance of Test Programs with Regulatory Guides, Regulatory (14.2.7) Guide 1.128 (page 14.2-9).

Reference is made to FSAR Subsections 8.3.2 and 8.3.3 for a detailed discussion of the utility's position on Regulatory Guide 1.128, Installation Design and Installation of Large Lead Storage Batteries for Nuclear Power Plants. Indicate the degree of compliance with General Criteria 1 and 17 of Appendix A and Criteria III of Appendix B in Subsection 8.3.2.2a and the degree of compliance to IEEE Std. 484-1975 in Subsection 8 3.2.2c.

RESPONSE

The response to RAI 430.31 (Attached) states that the design of

• the Seabrook de system is in conformance with IEEE 484-1975 and Regulatory Guide 1.128 (Revision 1).

The latest issue of the Standard Review Plan for Section 8.3.2 of the FSAR does not indicate that General Design Criterion I of Appendix A is applicable to Section 8.3.2; therefore ,

Section 8.3.2 does not address GDC 1. However, Section 3.1.1.1 of the FSAR describes how the overall design of the Seabrook plant complies with CDC 1 of Appendix A.

Compliance with General Design Criterion 17 of Appendix A is discussed in Section 8.3.2.2.a.2 of the FSAR.

Chapter 17 of the FSAR addresses the Seabrook QA Program and compliance with 10CFR50 Appendix B. Since the QA Program covers all aspects of the plant construction and design, no specific statements on 10CFR50 Appendix B are needed in Section 8.3.2.

Fur'thermore, the latest SRP does not include Criteria III of Appendix B in the acceptance criteria and guidelines for FSAR Section 8.3.2.

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RESPONSE

The design of the Seabrook de system is in confomance with IEEE Standard 484-1975 and Regulatory Guide 1.128 (Rev. 1).

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640.34 Conforcanco of tost progrens with Regulatory Guidos, Regulatory Guido 1.5,2,_Rev. 2 (page 14.2-5). Either upgrade the technical specifications and appropriate test descriptions involving the control room air cleaning system from non-ESF to ESF or provide addi-tional technical justificationLfor considering this a 7 non-ESF test..

RESPONSE: In the evaluation of the control room air con-ditioning and ventilation' systems, the NRC (AEC) ,

staff, on pages 9-12 and 9-13 of the Seabrook  !

Station, Units 1 6 2, Safety, Evaluation Report for '

the PSAR dated August 14, 1974, makes the following >

statement:

" Based on our evaluation and failure analysis,

'. we have determingd that the design of the air , ,

conditioning and ventilation system contains sufficient component redundancy and physical separation to meet the single failure criteria -

so that air conditioning and ventilation will be assured during all assumed operating '

conditions."

1 The staff then concludes with the following:

On the basis of our review of the design cri-teria and bases, we conclude (that the control room ventilation system functional performance vill meet the habitability requirements of AEC

, General Design Criterion 19 during and following postulated accidents, and is

\ acceptable."

We are revising Section 14.2.7, in Imendment 45, to add Regulatory Guide 1.140, Rev. 1, " Design, Testing and Maintenance Criteria for Normal Ventilation Exhaust System' Air Filtration and Absorption Units!of Light-Water-Cooled Nuclear Power Pumps."

f For a discussion on conformance of Seabrook Station to '

Regulatory Guide 1.140, refer to FSAR Section 1.8. '

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640.35 Confornanco to Regulatory Guido 1.68 (Revision 2), Itca (2). It is the staff position that the requirements for

, systems relied on to prevent, limit or mitigate the con-sequences of postulated accidents be completed prior to exceeding 25% power. Modify Sections 14.2.7, 14.2.11 and the appropriate test abstracts accordingly.

RESPONSE: As stated in FSAR Section 14.2.7 "Conformance of Test Programs with Regulatory Guide", Regulatory Guide 1.68 REV.2, Westinghouse plants have tradi-tionally conducted testing at 30% power.

Conducting testing at 30% power allows use of this generic data base for comparison purposes.

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640.37 State that copies of approved test procedures will.be available for axamination by NRC regional personnel approximately 60 days prior to the scheduled performance of preoperational tests, and not less than 60 days prior to scheduled fuel loading date for startup tests (NRC possession of the procedures should not impede the revision, review or refinement of the procedures), or describe the conditions that could be allowed to occur such that the procedures would not be available as planned.

RESPONSE: It is anticipated that copies of approved test pro-cedures will be available for examination by NRC regional pers.onnel approximately 60 days, prior to the scheduled performance of preoperational tests, and not less than 60 days prior to scheduled fuel loading date for startup tests. The only antici-pated exceptions to the 60 dagg examination period would be if system design was incomplete or if the scheduled performance of the test changed such that the test had to be performed during the 60 day exa-mination period.

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640.38 Review of your precritical control rod tests indicates

' there is no testing of decelerating devices. Include this in your test description.

RESPONSE

In the Westinghouse design of the control rod, deceleration is performed in the " dashpot" region of the rod thimble. This is not an active device as such. Entry of the control rod into the dashpot region and subsequent deceleration is seen in the rod drop timing traces and will be monitored during the performance of ST 7 (Table 14.2-5, item 7). .

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640.39 Scycrol itcas rcquired by Rogulctory Guido 1.68 for o roccter coolcnt systeo flow test hevo not bosn addressed. In addition to verifying that flow measure-ments are conservative with respect to the safety ,

analysis, verify that piping reactions to transients and flows are as predicted for all modes of pump operation.

If a prototype plant design is not referenced, differen-tial pressures across the fullt loaded core and major components must be measured. Confirmation that vibration levels are acceptable is also necessary.

RESPONSE: FSAR Section 14.2.7, "Conformance of Test Program to Regulatory Guides", Regulatory Guide 1.68, REV.

2, will have an exception added. The exception

, will read:

" Vibration levels of the reactor coolant system and piping reaction to transient conditions are measured during hot functional testing. (Appendix A, 2.f)".

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640.40 Initial Criticality Test (ST 16). State that the signal-to-noise ratio of source range instrumentation (or temporarily installed detectors) will be greater than two prior to startup or provide technical justifi-cation for excluding this requirements.

RESPONSE

As stated in the FSAR, Seabrook Station will comply with Regulatory Guide 1.68 rev.2, with exceptions as noted. The signal to noise ratio of source 4

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range instrumentation will be greater than two prior to startup.

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640.41 Ccamit to verifying that adequate shutdown margin exists

, with the greatest worth rod-cluster control assembly i (RCCA) stuck out of the core while performing control rod worth measurements (ST 20).

1 RESPONSE: The definition of shutdown margin shown in the Technical SJecifications explicity assumes that the RCCA with the greatest worth is stuck out of the core. Seabrook Station will comply with the Technical Specificiation requirements for shutdown margin during the performance of control rod worth measurements.

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640.42 The wetor chsaistry control test edstreet (ST 42) is incomplete. Include both chemical and radiochemicel tests. Verify that both installed analyzers and alarm systems operate properly.

RESPONSE: The test abstract objective will be changed to read: "To demonstrate that chemical and radiochemi-cal control and analysis systems function as described in the FSAR, and to verify that water chemistry requirements can be maintained at various plant conditions."

The acceptance criteria will be changed to read:

" Control and alarm systems function as described FSAR Section 9.3.4 and water chemistry is main- .

tained within limits established by Westinghouse SIP 5-4 and Technical Specifications 3.4.8 and 3.7.1.4. Analyzer responses agree with analyzer results."

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640.43 Ccc. cit to parforcing your pssudo-rod-ojection tost (ST

21) et grantor than 10% powar or provide justification for performing the test at a lower power level.

RESPONSE: Seabrook Station will perform this test at greater than 10% power in compliance with Regulatory Guide 1.68 Rev. 2. Table 14.2-5 item 21 will be revised to include this additional testing.

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640.44 Incero cnd oxcoro instruz9ntation sansitivity to a control rod nisslignnont cust b3 demonstrated at both 50% and 100% power (ST 31).

RESPONSE: FSAR Section 14.2.7, "Conformance of Test Porgrams with~ Regulatory Guides", Regulatory Guide 1.68 Rev.

2 provides justification for not demonstration incore 5 excore sensitivity to control rod misa-lignment at 100% power. A letter from Westinghouse to the NRC (SS-CE1462, June, 1977) provides further justification for not performing this test it 100%

power.

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640.46 Modify the acceptance criteria of the process computer test abstract (ST 43) to include verification of perfor-mance calculations and correct process variable inputs separately rather than comparing final results.

RESPONSE: The acceptance criteria will be changed to read:

"The process computer inputs and process instrumen-tation agree and the related calculations are being performed correctly.

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640.47 Brench stosn lina isolation valves must be verified as to operability and response times. Include this commit-ment in your main steam isolation valve closure test (ST 47).

RESPONSE: The MSIV, including the small bypass around the valve, operability and response time is demonstrated during preoperational testing. (Table 14.2-3, item 13). Response time and operability of these valves is also demonstrated in compliance with the Technical Specifications.

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l 640.48 Specifically include primary containment and steam line tunnels in your ventilation and air conditioning test l (ST 46). This test should not simply verify proser t operation, but.must be designed to ensure that t.tese spaces can be maintained within design limits.

RESPONSE: As stated in the FSAR, Seabrook Station will comply with Regulatory Guide 1.68 REV.2, with exceptions as noted. The primary containment and steam line tunnels will be included in ST-46. The accestance '

criteria in the ST-46 abstract states t. hat tLie ven- -

tilation systems are capable of maintaining equip-ment space environmental conditions within the design specifications.

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. 640.49 The exception taken to Regulatory Guide 1.68, Appendix ,

A, Section 5.m.m., in subsection 14.2.7, part (9), is '

not acceptable. Either provide technical justification for the deletion of this startup test including how the proper plant response will be demonstrated during other specified transient tests, or perform the MSIV closure test at 100% power. Modify (ST 47) accordingly.

RESPONSE: FSAR Subsection 14.2.7, "Conformance of Test Programs with Regulatory Guides", Reg. Guide 1.68 rev. 2, exception 9, pg. 14.2-6, will be changed to read:

• "9. As shown in FSAR subsections 15.2.3 and 15.2.4, dynamic response o~f the plant to a

. MSIV closure is bounded by the response of the plant to the turbine trip event. Plant response to a turbine trip will be demonstrated during performance of ST-38, Unit Trip from 100 Percent Power. The ability of the MSIVs to close under steam flow will be demonstrated by automatic closure of all main steam line isolation valves at 30 percent power during the performance of ST-47.

(Appendix A. Section 5. m. m.) "

Tne abstract for ST-47 will be changed accordingly.

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. ,640.50 Pags 1 of 10 Review of the preoperational and acceptance test phase descriptions disclosed that the operability of several of the systems and components listed in Regulatory Guide 1.68 (Re' vision 2), Appendix A, may not be demonstrated by tests described in Tables 14.2-3 and 14.2-4. Expand your test descriptions to address the following items:

(1) Preoperational testing 1.a(2)(h) Reactor vessel and internals; including vent valves.

. 1.a(2)(1) Reactor coolant system safety valves.

1.b(1) Control Rod System Test. As a minimum address the following: control rod drive o,cration; operation of functions such as wit:1drawal inhibiting features, runback features, rod worth minimizers, withdrawal sequences; .

interaction of the control rod drive system and design features; failure mode on loss of power.

1.d(2) Steam line atmospheric dump valves.

1.d(3) Relief valves associated with residual or decay heat removal.

1.d(4) Safety valves associated with residual or ,

decay heat removal.

1.d(8) Assure the absense of flow instabilities in the emergency feedwater system components, piping, or inside seam generators during normal system startup and operations.

1.d(9) Condensate storage system.

1.d(10) Emergency cooling tower. ,

i.e(6) Turbine stop, control, bypass, and intercept.

valves.

1.h(5) Cold water interlocks.

1.h'.(7) Ventilation, recirculation, and filter systems to minimize radioactive release associated with postulated accidents.

1.h(8) ECCS water sources.

640.50-Pags 2 of 10 1.h(10)

~

Ultimate heat sink. Verify that sources of water used for long-term core cooling are i- tested to demonstrate adequate NPSH (net posi-

' tive suction head) and the absence of vor-texing over range of basin level from maximum to the minimum calculated 30 days following LOCA. ,

1.i(3) Containment isolation valve leak rate tests.

i 1.i(4) Containment penetration leakage tests.

, . 1.i(5) Containment airlock leak rate tests.

1.i(8) Primary and secondary containment isolation initiation logic tests.

1.i(10) Containment and containment annulus vacuum-

. breaker tests.

1.i(11) . Containment supplementary leak collection and exhaust system.

1.i(12) Containment air purification and cleanup 1 systems.

1.i(13) Containment inerting system.

1.i(15) Containment penetration pressurization system.

1.i(17) Secondary containment system ventilation.

1.i(18) Containment annulus and cleanup system.

1.j(7) Leak detection system for ECCS and concainment recirculating spray systems located outside containment.

1.j(9) Pressure control system to contain fission product leakage.

1.j(12) Failed fuel detection systim or functional equivalent.

1.j(13) Incore instrumentation.

1.j(14) Water transfer instrumentation and control.

1.j(15) Automatic dispatcher control system.

Feedwater heater ~ temperature, level and bypass 1.j(17) control system.

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640.50 Page 3 of 10 1.j(18) Auxiliary startup instrument tests.

1.j(20) External and internal flooding detection instrumentation.

1.j(22) Postulated accident tracking instrumentation.

1.j(23) Post-accident hydrogen monitors and analyzers.

, 1.j(24) Reactor control and ESF annunciators.

1.k(1) Personnel and criticality radiation monitor tests.

1.k(2) Personnel monitors and radiation survey instruments.

1.k(3) Radiation level and radioactivity con-centration laboratory equipment.

1.1(6) Isolation features for ventilation systems.

1.1(7) Isolation features for liquid radwaste effluent systems.

1.m(l') Spent fuel pool cooling. As a minimum address the following: antisiphon devices, high radiation alarms, and low water level alarms.

1.m(2) Refueling equipment tests. List the equiption involved or cite system description in the FSAR. The equipment must include as a minimum: hand tools, power equipment, bridge and overhead cranes and grapples.

1.m(3), Operability and leak tests of sectonalizing devices and drains. Leak tests of gaskets or bellows in the refueling canal and fuel storage pool.

1.m(4) Dynasmic and static load testing of cranes, hoists, and associated lifting and rigging equipment.

1.m(5) Fuel transfer devicas.

1.n(8) Seal water system.

1.n(10) Reactor coolant system purification and cleanup system.

640.50 Pago 4 of 10 1.n(14) Heating, cooling and ventilation systems for:

(a) spaces housing engineered safety features.

(b) primary containment (d) diesel generator buildings (e) reactor building (f) control room habitability systems.

, Testing or verification of operation of the following: space temperature control; duct leakage rate; toxic chemi-cal and smoke detection.

1.n(15) Shield cooling system.

1.n(16) Refueling water storage tank cooling and .

heating systems.

1.n(18) Heat tracing and freeze protection systems.

, 1.o(1) Reactor components handling systems dynamic and static load tests.

1.o(2)

' Reactor components handling systems protective devices and interlock operability tests. .

1.o(3)

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Reactor components handling system safety

, device operability tests.

RESPONSE

1.a(2)(h) Operability of the reactor vessel and inter-nals will be demonstrated during reactor post-hot functional inspection (Table 1".2-3 item

43) and as described in Section 3.9(N).2.4.

There are no reactor internals vent valves in the Sfabrook design.

1.a(2)(i) Operability of the reactor coolant system safety valves will be demonstrated during integrated het functional testing (Table 14.2-3 item 40 section h).

1.b(1) Operability of the control rod drive system will be demonstrated during control rod drive mechanism operational testing (Table 14.2-5 item 5), rod control system testing (Table-14.2-5 item 6), rod drop time measurement l

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640.50 -

Page 5 of 10 testing-(Table 14.2-5 item 7), rod position indication testing (*able 14.2-5 item 8), and automatic reactor control testing (Table 14.2-5 item 24-).

1.d(2) The operability of the steam line atmospheric dump valves will be demonstrated during heat up to hot functional testing (Table 14.2-3 item 41).

• . 1.d(3) Operability of the relief valves associated with the residual heat removal system will be demonstrated prior to system operation during Phase 1 t'esting. (Table 14.2-3 item 7). \

1.d(4) 3eabrook design does not include safety valves associatedwiththeresidyglheatremoval system.

1.d(8) Flow instability testing will be conducted during PT 14 (Table 14.2-3 iten 14).

1.d(9) The operability of condensate storage system with regards to the emergency feedwater system will be demonstrated during the emergency feedwater system test (Table 4.2-3 item 14).

1.d(10) The operability of emergency cooling towers will be demonstrated during the service water system test, PT-15, (Table 14.2-3 item 15).

1.e(6) The operability of the turbine stop, reheat and intercept valves will be demonstrated during the initial turbine roll, (Table 14.2-3 item 40.g.) The operability of the turbine bypass valves will be demonstrated during hot functional testing (Table 14.2-3 item 40 Section 1).

1.h(5) Seabrook does not'have any cold sater interlocks. Power operation mode requires all four RCP's to be operating, therefore, cold water interlocks are not required nor tested.

1.b(7) Ventilation, recirculation, and filter systems to mimimize radioactive releases as a result of postulated accidents will be verified during the containment enclosure exhaust system t'est (Table 14.2-3 item 23) and the fuel storage building ventilation system test (Table 14.2-3 item 27).

1.h(d) The operability of ECCS water sources will be demonstrated during the ECCS performance test (Table 14.2-3 item 8).

640.50 .

Pcgo 6 of 10 1.h(10) Cooling Tower performance will be verified during the service water system test (Table 14.2-3 item 15). The ability to provide tower makeup water as discussed in subsection 9.2.5.3c will also be verified.

1.i(3) Containment isolation valve leak rate testing will be conducted during the primary contain-ment leak rate tests (Table 14.2-3 item 37).

1.i(4) Containment penetration leakage tests will be conducted during the primary containment leak

, rate tests (Table 14.2-3 item 37).

1.i(5) Containment airlock leak rate tests will be conducted during the primary containment leak rate tests (Table 14.2-3 item 37).

'1.i(8) Primary containment isolation initation logic tests will be conducted during primary con-tainment isolation valve testing (Table 14.2-3 item 21).

The Containment Enclosure Building (secondary containment) does not include an isolation feature as such, however, the containment enclosure exhaust equipment will initiate upon

'. recei This'pt of an is feature ESF actuation tested duringfeature signal.

the containment enclosure exhaust system testing-(Table 14.2-3 item 23).

1.i(10) Containment vacuum - breakers are not used at Seabrook.

1.i(11) Containment supplementary leak collection system will be tesced during liquid waste system testing (Table 14.2-4 item 15) by verifying the operation of the containment sump pumps and their ability to transfer water to the liquid waste system.

The containment exhaust system will be tested during containment purge system testing (Table 14.2-4 item 22).

1 l 1.i(12) Containment air recirculation system (described in subsection 9.4.5) will be tested i during the containment air recirculation system tests (Table 14,2-3 item 26).

1.i(13) Containment inerting system is not used at Seabrook.

1.i(15) Containment penetration pressurization system is not used at Seabrook.

1.i(17) The containment enclosure ventilation system (described in subsection 9.4.6) will be tested during the containment enclosure ventilation test (Table 14.2-3 item 22).

. . . . - . . . - .. -. -. ~

640.50

. Page 7 of 10 1.i(18) Containment annulus and cleanup system is not used at Seabrook. The containment air recir-culation system (described in subsection 9.4.5) will be tested during the containment '

air recirculation system test (Table 14.2-3 item 26).

1.j(7) Leak detection systems used to detect failures in ECCS and containment recirculating spray systems located outside the containmert are not used at Seabrook.

1.j(9) Pressure control systems used to maintain design differential pressures to prevent leakage across boundaries provided to contain fission products are not used at Seabrook 1.j(12) Systems that provide indication of failed fuel, as specified in FSAR section 11.5.2.1.g, will be tested by AT-30 (Table 14.2-4 item 30).

1.j(13) Incore and excore neutron instrumentation will

' be tested during the movable incore detector system test (Table 14.2-5 item 50) and the excore nuclear instrumentation test (Table 14.2-3 item 18).

1. j (14-) Instrumentation and controls that effect transfers of water supplies to emergency feed-water pumps, ECCS pumps, and containment spray pumps will be demonstrated operable during the systems tests (Table 14.2-3 items 14, 8 and 12 respectively).

1.j(15) Automatic dispatcher control systems are not used at Seabrook.

1.j(17) Feedwater heater temperature, level and bypass control systems will tested during extraction steam and heater drain system test (Table 14.2-4 item 2).

1.j(18) Auxiliary startup instrument systems will be tested prior to initial core loading.

Completion of this testing will be identified in the test requisites (procedureTable 14.2-5for initial item 3). core pre-1.j(20) Containment rump level monitoring system is used to detect flooding conditions that could result from such sources as fluid system piping failures, the containment sump level monitoring system will be demonstrated opera-tional by performance of a channel calibration in accordance with technical specifications.

. n. _ _ .

640.50 Page 8 of 10 1.j(22) Accident monitoring instrumentation (as described in RG 1.68 Rev. 2, 1.j(22)) will be demonstrated operable in accordance with tech-nical specification 4.3.4.6.

1.j(23) Post accident hydrogen monitors and analyzers used in the combustible gas control system will be demonstrated operable during contain-ment. combustible gas control system test (Table 14.2-3 item 25).

i 1.j(24) Annunciators for reactor control and engineered safety features will be demonstrated operable during computer testing (Table 14.2-4 item 28).

1.k(1) Process, criticality effluent and area radiation monitors will be demonstrated operable during radiation monitoring system j testing (Table 14.2-4 item 30).

1.k(2) Personnel monitors and radiation survey instruments will be demonstrated operable in accordance with section 12.5. The procedures described in section 12.5 will be implemented

. prior to core loading. ,

1.k(3) Laboratory equipment dsed to analyze or measure radiation levels and radioactivity concentrations will be demonstrated operable in accordance with section 12.5. The procedures described in section 12.5 will be implemented prior to core loading.

1.1(6) Isolation features for radioactive waste handling and storage area ventilation systems are not used at Seabrook.

1.1(7) Isolation features for liquid radwaste effluent systems will be demonstrated operable during liquid waste system test (Table 14.2-4 item 15).

1.m(1) Spent fuel pit cooling features will be demonstrated operable during spent fuel pool cooling system test (Table 14.2-3 item 17).

1.m(2) Refueling equipment will be demonstrated operable during fuel handling and transfer equipment system tests (Table 14.2-3 item 34).

640.50 -

Page 9 pf 10 1.m(3) Operability and leak tests of sectionalizing devices in the refueling canal and fuel storage pool will be demonstrated operable during spent fuel pool cooling system test (Table 14.2-3 item 17).

1.m(4) The test abstract for fuel handling and transfer equipment (Table 14.2-3 item 34) will be revised to require dynamic and static load testing, as a prerequisite to performing

• PT-34.

1.m(5) Fuel transfer devices will be tested during fuel handling and transfer equipment system test (Table 14.2-3 item 34).

1.n(8) Reactor coolant pump seal water system will be demonstrated operable during chemical and volume control system (charging and letdown) test (Table 14.2-3 item 5).

1.n(10) Purification and clean-up systems for the reactor coolant system will be demonstrated operable during chemical and volume control system (charging and letdown) test (Table 14.2-3 item 5).

1.n(14)(a) Heating, cooling, and ventilation systems -

will be demonstrated operable for spaces housing engineered safety features during the performance of the engineered safety features system or during the performance of a speci-fic ventilation test (e.g., emergency feed-water system test (Table 14.2-3 item 14),

service water system test (Table 14.2-3 item 15), Containment enclosure ventilation system (Table 14.2-3 item 22), emergency switchgear ventilation (Table 14.2-3 item 29), primary auxiliary building ventilation system (Table 14.2-4 item 23) and electrical penetration area air conditioning system (Table 14.2-4 item 24)).

1.n(14)(b) Primary containment cooling will be demonstrated operable during the containment cooling system test (Table 14.2-4 item 21).

1.n(14)(d) Diesel generator building ventilation will be demonstrated during the' diesel generator test (Table 14.2-3 item 33).

640.50 Page 10 of 10 1.n(14)(e) Reactor building (containment) cooling will be demonstrated operable during the contain-ment cooling system test (Table 14.2-4 i' tem 21).

1.n(14)(f) Control room habitability system is described in section 6.4. Operability of the control room habitability system will be demonstrated during control room HVAC system test (Table

14. 2-3 iter 28 ) .

1.n(15) Shield cooling system is not used at Seabrook.

1.n(16) Refueling water storage tank (RWST) cooling system is not used at Seabrook. RWST heating system will be demonstrated operable during ECCS performance test (Table 14.2-3 item 8).

1.n(18) Heat tracing for the boron injection tank subsystem will be demonstrated operable during ECCS performance test (Table 14.2-3 item 8). Freeze protection will be

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demonstrated operable during the test of the

' systems that utilize freeze protection.

l.o(1) The test abstract for the polar crane (Table 14.2-4 item 35) will be revised to require dynamic and static load testing as a prerequisite to performing AT-35.

1.o(2) Operability of protection devices and interlock of the containment polar crane will be demonstrated during the polar crane test (table 14.2-4 item 35).

l.o(3) Operability of safety devices on the contain-ment polar crane will be demonstrated during the polar crane test (Table 14.2-4 item 35).

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640.51 Page 1 of 6 We could not conclude from our review that you have addressed all of the startup tests. required by Regulatory Guide 1.68, Rev.2. Exp'and your startup test abstracts or provide additional test abstracts to include the following tests shown in Appendix A.

2) . Initial Fuel Loading and Precritical Tests.

2.a Shutdown margin verification. -

2.c Reactor protection system final functional testing'.

l 4) Low-Power Testing.

4.a Boron and moderator temperature

, reactivity coefficients.

4.j Primary containment ventilation system. -

4.k Steam-driven engineered safety features Performance of natural circulation tests of 4.t the reactor coolant system to determine that design heat removal capability exists. Your  !

natural circulation test should comply sith our letter to you dated June 12, 1981. We sdggest you contact Westinghouse in reference to the Westinghouse letter to the NRC dated July 8, 1981, on the subject of Special Low Power Test Program which complies with the staff position on TMI-2 Action Item I.G.1 requirement. To comply with this requirement new PWR applicants have committed to a series of natural circulation tests. To date, such tests have been performed at the Sequoyah 1, North Anna 2, and Salem 2 facilities. Based on the success of the programs at these plants, the staff has concluded that augmented natural circulation training should be per-formed for all future PWR operating Licenses.

Include description of natural circulation tests that fulfill the following objectives:

Testing The tests should demonstrate the following plant characteristics: Length of time required to stabilize natural circulation, core flew distribution, ability to establish and maintain natural circulation with or .

without onsite and offsite power, the ability to uniformly borate and cool down to hot shut-down conditions using natural circulacion, and subcooling monitor performance. -

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640.51

.Page 2 of 6~ l Training Each licensed reactor operator (R0 or SRO who ,

performs RO or SRO duties, respectively) l should participate in the initiation, l

maintenance, and recovery from natural cir- '

culation mode. Operators should be able to recognize when natural recirculation has stabilized, and should be able to control saturation margin, RCS pressure; and heat removal rate without exceeding specified operating limits. If these tests have been performed at a comparable prototype plant, they need be repeated 'only to the extent necessary to accomplish the above training objectives and to obtain data for " fine tuning" your simulator.(as stated in FSAR Subsection 13.2.1.1.b.5) for natural cir-

$g culation operation.

5) Power Ascension Tests 5.d Xenon transients controls.

5.1 Residual or decay heat removal system and components.

'5 . o Reactor coolant leak detection systems.

5.s Principal plant control systems.

5.v Main steam and feedwater systems.

5.x Auxiliary systems required to support the operation of engineered safety features.

5.c.c Gaseous and Liquid radioactive waste systems verification. ,

5.e.e Primary containment inerting and purge systems.

5.k.k Dynamic response due to loss of a feedwater heater.

5.o.o Vibrations and expansions of ASME Class 1, 2 and 3 systems.

RESPONSE: 2.a FSAR section 14.2.7, "Conformance of Test Programs with Regulatory Guides", Regulatory Guide 1.68 REV.2, exception 3 states that shutdown margin will be verified throughout core loading and precritical testing.

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640.51 '

Pago 3 of 6 '

2.c Reactor Protection System (RPS) functional testing is p~erformed as part of Technical Specifications surveillance testing. .

Verification of final RPS functional testing will be included as part of ST 3 (Table 14.2-5 item 3).

4.a The boron worth coefficient is-defermir.ed as part of ST 17, Boron Endpoinc Mea'ssrements .,

ITable 14.2-5 item"17). The moderator tem- '

perature coefficient is determined as part of .

. ST-18, Isothermal Temperature Coefficient Measurements (Table 14.2-5 item 18). -

. r-4.j The performance of Primary containment ven- '

tilation systems will be demopstrated during s.

preoperational hot functional testing. (Table .

14.2-3 item 26 and Table 14.2.4 item 21. ..

4.k The only steam'3 riven engineered safety feature at Seabrook is one of the emergency .

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feed pumps. Operability of this system is *

• demonstrated during hot functional testing (Table 14.2-3. item 14) and is, maintained in

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accordance with Technical Specifications. "

4.t For the response to this item, see YAEC ,

1etter, dated November 27, 1981, " Response to Acceptance Review RAI's", J. DeVincentis to D.

Eisenhut, SE.N 193.

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64G 51 PageJ5 of 6 37 5.1 FSAR section 14.2.7, "Conformance of test' i Programs with Regulatory Guides", Regulatory N Guide 1.68 Rev.2, exception 5 states that the residual or decay 3 heat removal systems capabi-bility will be demonstreted during hot f unctional ' tes ting.' F < .

t 5.o The response of the reactor coolant leak detection system will .be demonstrated during preoperational testing (Table 14.2-3 item 40)

• and will be in operati,on in accordance with Technical Specifications during the power ascension program. y 5.s '

FSAR'sectioW 14.2.7, "Conformance of Test Programs with Regulatory Guides", Regulatory Guide 1.68 Rev.2, exception 7 specifies,some of the systems that can not be testing during power ascension. Listed below are the proce-dure numbers that demonstrate control system performance.

ST-24;-T-average control and automatic reactor control. '

4 PT-5.1; Chirging and Letdown control.

PT-5.3; Baron Addition System.

PT-(I)-40.1 and ST-9; Pressurizer Pressure Control.' '

ST-25 and'5T-26, Main Feedwater Control -

5.v The objective of ST-26 will be changed to .

.v read:

"To obtain various primary and secondary plant s temperatures, pressures, and flows in order to i perform a calorimetric determination of reac-tor power and verify that the main steam and /-

I feed water systems perform as described in 1 the FSAR.

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The acceptance criteria of ST 26 will be chenged to read:

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." The data specified in the procedure has been collected and the calorimetric performed.

Main Steam and Feedwater Systems operate as described in FSAR Section 10.4.7".

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640.51  ;

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'i 1 5.x Ventilation systems are tested during ST-46.

9 Performance of support systems such as com-ponent cooling and service water is demonstrated during hot functional testing

, (Table 14.2-3 items 15 and 16).

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L 5.c.c The operation of these systems is demonstrated during preoperational testing (Table 14.2-4 items 14 and 15).

5.e.e There is na inerting of primary containment

, at Seabrook. The Containment Purge system g is tested during the preoperational testing. .

phase (Table 14.2-4 item 22).

~

5.k.k FSAR Section 14.2.7, "Conformance of Test Programs with Regulatory Guides", Reg. Guide 1.68 rev. 2, exception 8, pg. 14.2-6 will be

, changed to read:

"8. A demonstation of the dynamic vesponse of the plant to a loss of or bypassing of a feedwater heater (s) will not be performed. As shown in FSAR section

. 15.1.1, the transient resulting from the.

most severe case of feedwater tem-

) [' perature reduction initiated by a single y  ; failure or operator error is similar to, but of a lesser magnitude than-the excessive load increase (load swing).

. The-load swing test will be performed at several major plateaus. (Appendix A, Section 5.k.k.) "

5.o.o Vibration and expansion testing will be per-formed during hot functional testing (Table 14.2-3 items 3 and 4).

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640.52 List the specific FSAR sections describing Acceptance Tests No. 25, 28, and 35, " Turbine Building Ventilation," " Computer", and " Polar Crane."

RESPONSE: These are non-safety related systems for which an acceptance test will be developed and performed.

There is no s:secific FSAR section describing these tests other t: tan Table 14.2-4, items 25 , 28, and 35.

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, 640.53 Change the table of contents title for PT 36 from

" Primary Containment Structural Integrity Test" to Primary Containment Structural Acceptance Test" in accordance with Regulatory Guide 1.18.

RESPONSE: Regulatory Guide 1.18 was withdrawn on July 8, 1981, and superseded by Regulatory Guide 1.136, Rev.2, 6/81. Regulatory Guide 1.136 endorses ASME Code for Concrete Reactor Vesels and Containments.

Article CC-6000 of the Code is titled " Structural Integrity Test of Concrete Containment Structures".

The present title for PT 36 is used throughout the FSAR, therefore, to reduce confusion and to be con-sistant with the ASME Code, the title for PT 36 will remain " Primary Containment Structural

. Integrity Test". Table 14.2-3 item 36 will be revised to reflect this change.

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l 640.54 It is our position that your description of the reactor protection system test (PT 19) does not provide assurance that the total reactor protection system response time is consistent with your accident analysis assumptions. Expand the test abstract.

RESPONSE: The test abstract has been expanded to include the technical specification definition of reactor trip system response time, e

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640.'55 The loss of turbine-generator and offsite power test I should be initiated from a sufficient power level and should be maintained for a period of time sufficient'to demonstrate that the necessary equipment,. controls, and instrumentation are available following station blackout to remove decay heat from the core using only emergency power supplies. It is our position that you initiate this test from at least 100% generator output and. main-tain the loss of offsite power for at least 30 minutes in order to demonstrate this.

RESPONSE: Regulatory Guide 1.68 Rev. 2 (item 5.j.j.) shows the approximate range for the loss of turbine-generator coincident with loss of offsite power to be 10 to 20%. At Seabrook, this test will be done at approximately this range during the return to power following the unit trip from 100% power. The loss of offsite power will be maintained for 30 minutes.

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640.56 Paginate all pages (sheet numbers are acceptable) including for tables. pages with tables, figures, and definitions RESPONSE: Table 14.2-1, Initial Test Program Responsibility /

Authority Matrix will be revised to include she<3t numbers.

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i 640.57 Provide a corresponding page number with each test listed on the startup test abstracts page.

RESPONSE: Table 14.2-5, Startu? Test Abstracts, will be revised to include t:1e corresponding sheet number with each test listed on the index pages.

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i 640.58 Provide a corresponding page number with each test listed on the acceptance test abstracts page.

RESPONSE: Table 14.2-4, Acceptance Test Abstracts, will be revised to include the corresponding sheet number with each test listed on the index pages.

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640.59 Provide a corresponding page number with each test listed on the Preoperational Test Abstracts page.

RESPONSE: Table 14.2-3, Preoperational Test Abstracts, will be revised to include the corresponding sheet number with each test listed-on the index pages.

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640.60 Recently, questions have arisen concerming the operabi-lity and dependability of certain ESF pumps. Upon investigation, the staff found that some completed preoperational test procedures did not describe the test conditions in sufficient detail. Provide assurance that the preoperational test procedures for ECCS and contain-ment cooling pumps will require recording the status of the pumped fluid, (eg., pressure, temperature, che-mistry, amount of debris) and the duration of testing for each pump.

RESPONSE: During the Preoperational Test Program, all safety related pumps will be tested in accordance with ASME Section XI, Subsection IWP. This will sa'tisfy the requirement of recording the status of the pumped fluid, except for chemistry. During the Preoperational Test Program, flushing of systems 9b will be performed, as stated in Section 14.2.11 of the FSAR, to establish System Design Cleanliness Conditions. Once System Cleanliness has been established, it will be maintained in accordance with the system design. Additionally, during testing in accordance with ASME Section XI, Subsection IWP, the pumps will be run until staba-lized conditions are obtained and pump run times

.are recorded for the Station IWP. Program.

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640.62 Our review of Licensee event reports has disclosed several instances of emergency feedwater pumps failing to start on demand, It appears that many of these failures could have been avoided if more thorough testing had been conducted during the plant's initial test programs. In order to discover any problems affecting pump startup and to demonstrate the reliabi-lity of your emergency cooling system, state your plans to demonstrate at least five consecutive, succesful, cold, quick pump starts during your initial test program.

i -RESPONSE: The test abstract for the emergency feedwater pumps (Table 14.2-3, item 14) will be revised to include a demonstration of at least five consecutive, successful, cold pump starts.

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640.63 125 VDC Distribution System Tact (PT 31). State your plans to verify that individual ce?.1 limits are not exceeded during the design discharge test and to demonstrate that the DC loads will tunction as nec-cessary to assure plant safety at a battery terminal voltage equal to the acceptance criterion that has been e established for minimum battery cerminal voltage for the discharge load test. Assure that each battery charger is capable of ficating the battery within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while supplying the largest combined demands of the various steady-state loads under all plant operating conditions.

RESPONSE: Battery testing will be performed to verify that individual cell limits are not exceeded during the

• design discharge tests per IEEE Std 450-1975 in accordance with RG 1.129. PT 31 will demonstrate battery capability to meet design requirements.

Individual cell voltages will be monitored by a data logger. The safety related UPS has shown sta-tic inverter operation with rated regulated ac out-put during factory tests with minimum battery terminal voltage (105 vde) input. The size of the battery charger is based on restoring the battery back to fully charged state following a service discharge test while supplying the largest combined demands ahd hence rated at 150 amperes. 150 ampere rating was verified for each charger during factory performance testing in accordance with NEMA-PV5.

In addition, each safety related permanent battery charger will be tested to demonstrate it is capable of floating the battery within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while supplying the largest combined demands of the various steady state loads under all plant operating conditions.

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l 640.64 Integrated Plant Cooldown from Hot. Functional Tests (PT 42). Expand the cooldown test to assure that adequate  !

control and monitoring is exersised such that an over-cooling transient (I.E., thermal shock) will not occur l during normal or emergency cooldown modes.

RESPONSE: Test abstract for PT 42 (Table 14.2-3, item 42) will be revised to include monitoring and controlling cooldown rates. The cooldown limita-tion of the Technical Specifications will not be exceeded.

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640.65 Certain terminology used in the individual test descrip-tion does not clearly indicate the source of the accep-tance criteria to be used in determining test adequacy.

An acceptance format for providing acceptance criteria for test results includes any of the following:

- Referencing technical specifications (Chapter 16),

- Referencing accident analysis (Chapter 15)

~

- Referencing other specific sections of the FSAR (eg. 7.4.1.2),

- Referencing vendor technical manuals,

- Providing specific quantitative bounds (only if the information cannot be provided in any of the

, above ways).

RESPONSE: Individual test description abstracts will be modified to meet the requirements of RAI 640.65.

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I 640.66 Several of the acceptance criteria do not reflect complete accomplishment of the test objectives.

Modification should be made so that when the acceptance l criteria has been met, the test objective will have been aschieved. Modify the individual test description abstracts presented below to provide consistency between the test objective'and the acceptance criteria.

(1) PT 40. Acceptance criteria implies that all systems and all instrumentation would have to be demonstrited or operated. Objective and Test Method state a limited number.

(2) AT 31. The objective indicates a test must be per-formed. The acceptance criteria implies that the test has already been completed. The acceptance criteria needs to be changed to " Demonstration of the..."

(3) ST 1. Acceptance criteria needs to include the completion of a schedule or proposed test sequence.

(4) ST 3. Need to change " procedure" in the acceptance criteria to " test objective" or reference a procedure that provides a detailed list of plant conditions, systems, and equipment necessary for a safe and

+

controlled core loading.

(5) ST 4. Objective is to develop detailed instruc-tions for loading whereas the acceptance criteria is aimed at completion of loading and its documentati.on.

(6) ST 10. Acceptance criteria does not assure that the calculations outlined in the test objective were performed.

RESPONSE: (1) The Ace tance Criteria of PT 40 (Table 14.2-3, item 40 will be revised.

(2) The Acceptance Criteria of AT 31 (Table 14.2-4,-

item 31) will be revised.

, (3) The Acceptance Criteria of ST 1 (Table 14.2-5, j item 1) will be revised.

(4) ST 3 is the procedure that is referenced in the acceptance criteria. .ST 3 provides the de-

-tailed list of conditions, components, systems, ect.

(5) The Acceptance criteria of ST 4 (Table 14.2-5, item 4) will be revised.

(6) The Acceptance Criteria of ST 10 (Table 14.2-5, item 10) will be revised.

SB 1 & 2 '

FSAR 14.2 SPECIFIC INFORMATION TO BE INCLUDED IN FSAR 14.2.1 Summary of Test Program and Objectives A comprehensive initial test program will be conducted at the Seabrook Station to demonstrate that plant systems, structures, and components will perform in, a manner that will not endanger the health and safety of the public.

The' principle objectives of this program are to provide, to the extent prac-

'tical, assurance of the following:

a. The plant has been properly designed and constructed and is espable of operating safely at performance levels specified in the FSAR, and

b. The plant operating an'd emergency procedures have been verified ib by trial use to be adequate, and

c. The plant operating and technical personnel are knowledgeable about the plant equipment and procedures and are prepared to operate the facility in a safe manner.

The initial test program will include a preoperational test phase and an initial startup test phase. Preoperational testing will consist of individual

,_, system and integrated system tests performed prior to (and in some cases after) initial core load on essentially completed systems and structures.

These tests will demonstrate, to the extent practicable, the capability of systems, structu'res, and components to meet performance requirements.

Initial startup testing will consist of those single and multi-system activi-ties scheduled to be performed during and following fuel loading. This will include precritical tests, initial criticality, low-power tests, and power ascension tests. This testing will demonstrate that the plant will operate in accordance with design and the ability 'of the plant to respond properly to anticipated transients.

l 14.2.2 Orga;nization and Staffing ap.anwnT The Yankee Atomic Electric Company Startup Test Group will manage and provide overall direction for the initial test program. The Startup Test Group 6-r 6'a#

will consist of personnel assigned to the plant site with specialties in areas such as primary systems, secondary systems, electrical systems *, and plant operations. These individuals will be assigned overall responsibility for various aspects of the test program within their areas of expertise.

During the performance of system preoperational tests and initial startup tests, the Startup Test'dskuy'Eersonnel will direct plant operations personnel during test activities and will be responsible for ch'e acqui.sition, review and evaluation of relevant data.

Table 14.2-1 is a responsihili:y/ authority matrix showing the various organi-zations involved with each porcion of the Seabrook initial test program.

,, , A definition of each of the major responsibilities is provided to clarify

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. j its specific intent This table also presents tne organizations responsible for the preparation, review and approval of Preoperational,

~ ~N.r ~ Acceptance, Starttip and Special Test procedures. The r

. responsible design organizations or vendors will provide tech- ;M@;

nical support, as requested by their respective on-site

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' organizations,'and will either review or specify the acceptance @ k criteria used in these test procedures.  ?;, .-  :

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! . The interrelationship of the various organizations during testing activities is discussed in Sections 14.2.4 and 14.2.5.

In order to insure a comprehensive overview of the preoperational test program by the appropriate organizations, a Join .

consisting of site representatives of th_ __. gGy (J ) gli by f g.

upas _ _mup, b, an , ag,g,4 the Seabrook Station operating staff. The representative from the St2rtup Waku A7en N'<

Coy,ayTe t Cay shall act as chairman of the Joint Test Group. When necessary, personnel from other organizstions shall be invited to attend the meetings of the JTG for the purpose of information, coordination, or technical advice.

The Nuclear Steam Supply System vendor (Westinghouse), the Architect-Engineer and Construction Manager (UE&C), and Yankee Nuclear Service Division will provide technical, assistance in their areas of specialty as required through-out the test program. .

The JTC will be responsible for the following activities:

a.

Review and approval of preoperatioital test procedures, b.

Review and approval of changes to preoperational test procedures, --- - --

c. ~

Review and approval of the results of preoperational_ testi.

At the time of the start of initial fuel loading, the JTG will be dissolved and the Station Operations Review Commi'ttee (SORC) will assume the respon- 's sibilities stated above during initial startup testing. ) _

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't All personnel authorized to direct testing during the test program and to approve the procedures used in these tests will be appropriately qualified in accordance with the requirements of Regulatory Guide 1.58 (Revision 1, 9/80) as further clarifie:

in Section 1.8. Personnel authorized to direct preoperational and startup tests (Phases 2 through 6) shall also meet the additional requirements of a Bachelor Degree in Eghineering or related science with a minimum of one year experience acquired in testing, operation, and maintenance of power generating facilities for the direction of preoperational tes.es and a .

minimum of two years experience for the direction #startup tests.

Fcr personnel who do not possess the formal education, this requirement may be waived where upon other factors provide sufficient demqpstration.pf ability. Personnel assigned to the Startup Test GF8J) N 6a'TT also receive additional training in the administration and requirements of the test program. The qualifications of the station operating and technical staff are discussed in Section 13,1, 14.2.3 Test Procedures The initial test program will be conducted using written procedures for each individual. test. Tests of systems and equipment performed prior to (or in some cases after) initial core load are designated as either Preopera-tional Tests (PT) or Acceptance Tests ( AT) . Preoperational Tests will be subdivided into either of the following categories:

a. Individual Systems Tests - tests which demonstrate the proper operation of plant systems and equipment which perform a safety-related function.

h. Integrated Systems Tests - tests which involve the integrated operation of plant systems and equipment to demonstrate or verify a safety- related function.

Acceptance Tests will demonstrate the proper operation of non-safety-related _

plant systems and equipment.

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SB 1 & 2 4

FSAR L

a-Tests performed as part of or subsequent to loading of fuel into the reactor core are designated as Startup Tests (ST). In addition, Special Test Proce-dures (STP) will be used for situations which require the performance of a test for investigative or data collection purposes which are not in the original scope of the test program.

.Each test specified above will contain as a minimum, the following sections:

, s. Test Objectives

b. Prerequisites

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c. Special Precautions

d. Initial Conditions (including environmental)

e. Test Instructions

f. Final Conditions

g. Acceptance Criteria The Test Instructions section of the test will provide data blanks or reference data sheets which specifically identify the data to be recorded in each test. Means will be provided to identify the individuals who witness or record data during each test and the instrumentation used for data collection.

Administrative procedures will be provided .to specify proper methods for collection and retention of test data. .

Table 14.2-1 shows the organizations responsible for the preparation, review O and approval of Preoperational, Acceptance, Startup and Special Test proce-

"dures. The responsible design organizations or vendors will provide technical support, as requested by their respective on-site organizations, and will either review or specify the acceptance criteria used in these test procedures.

{ 14.2.4 Conduct of the Test Program The preoperational test program will be administered in accordance with the Preope Program Description which is prepared Test ~Geeup, rat,ional Testand approved by the Je4et-Test-Group participating,"gy the organizations.

Where necessary, due to certain unique activities associated with. tepting, administrative procedures will be prepared by the Startup Test 'G4 esp and reviewed by the Joint Test Group; otherwise, station administrative procedures will be used as applicable during the initial test program.

The initial startup program will be administere in. ecordance with a.startup procedure which is prepared by the Startup Test ah$ approved by the Station Operations Review Committee. Normal station administrative procedures will be used during the initial startup program.

• l Prior to the performance of a system preoperational or acceptanc.e test, a test engineer (or engineers) will be assigned b tge Sgaptup Test 'G' es'p' to direc t t

the test. For startup tests, Startup Test engineers or appropriately qualified station staff technical personnel will be assigned test director responsibility. These individuals will be responsible for insuring that prerequisites are complete, precautions are complied with and initial con-i ditions are established. They will then direct the station operating per-l 14.2-3

SB 1 & 2 Amendment 44 FSAR February 1982 m

sonnel in the performance of the test and assure all applicable data is recorded. Station op'erating personnel will be responsible for the safe end proper operation of the plant and its associated equipment throughout the test program. The Shift Supervisor shall take whatever action is neces-sary including, but not limited to, stopping any tott and placing plant equipment in a safe condition.

Once a preoperational or acceptance test procedure has been approved by the Joint Test Group, all procedure changes which change or may change the intent of the test must be approved by the Joint Test Group prior to the performance of the test. Any changes which clearly do not change the intent of the test (e.g. , substitute data recording instrument which provides equivalent .

data as the specified instrument) will be properly documented and reviewed by the Joint Test Group subsequent to test performanc.e. All changes to startup test procedures will be approved in accordance with technical specification requirements.

Al1 plant modifications which are initiated as a result of system preopera-tional or acceptance tests shall be controlled in accordance with the procedure for modifications during plant construction. Any such modifications or repairs will be retest'ed to the requirements of the test procedure. Sub-sequent to the completion of the system preoperational test, all modifications or repair activities shall be performed and retested in accordance with the normal station administrative procedures for modifications or maintenance; as applicable.

• 14.2.5 Review, Evaluation and Approval of Test Results Upon completion of each preoperational, acceptance, or startup test, the re-sponsible test engineers shall review the test data for completeness, perform any evaluations or calculations required, and compare the results to the stated acceptance criteria. Any unresolved or incomplete items, including acceptance criteria, shall be described on a summary list of test exceptions.

The test results shall then be submitted to the Joint Test Group or Station Operations Review Committee, as'applichble for completion review and approval.

Upon satisfactory review and approval by the Joint Test Oroup or Station Operations Review Conunittee, the test will be considered complete pending tesolution or completion of any outstanding exceptions by the responsible ions.

Prior to the start of each major phase of the initial startup program identi-fied in Taele 14.2-2, the Station Operations Review Conunittee shall perform a preliminary review of all prerequisite testing to insure that it is satis-factorily completed to the extent necessary to perform the next phase of the startup program. This is assisted by a prerequisite list which shall be approved prior to the start of any test in the following phase of testing.

14.2.6 Test Records A copy of all Preoperational Tests, Acceptance Tests, Startup Tests, Special Test Procedares, and all relevant data recorded during the conduct of the '

tests will be maintained for the life of the station in accordance with station procedures for record retention.

14.2-4 e

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SB 1 & 2 Amendment 44 FSAR February 1982 14.2.7 Conformance of Test Programs. with Regulatory Guides l

The below listed Regulatory Guides will be followed, to the degree indicated, during the conduct

• of the Seabrook Station initial test program.

Regulatory Guide 1.8, Rev. 1-R Personnel Selection and Training The personnel selection and training program meets the requirements of Regulatory Guide 1.8 (1977 edition). For discussion, see Sections 13.1 and 13.2'.

Regula tory Guide 1.20, Rev. 2 Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing 1 The Westinghouse position on Regulatory Guide 1.20, Rev. 2, is discussed in Subsection 3.9(N).2.4.

Regulatory Guide 1.33, Rev. gf)

Quality Assurance Program Requirements (Operation) -

.\ The quality assurance program for operation complies with the r'equirements Ndh of this Regulatory , Guide. For further discussion, see Section 17.2.

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, Regul,atory Guide 1.41, JRev. 0 -

Preoperational Testing of Redundant Electric Power Systems to Verify Proper Load Grou,g Assessments Seabrook Station conforms with the recommendations of Regulatory Guide 1.41.

Regulatory Guide 1.52, Rev. 2 Design, Testing ant Maintenance Criteria for Engineered Safety Feature Atmosphere Cleanup System Air Filtration and Absorption Units of Light Water Cooled Nuclear Power Plants .

A detailed discussion on the degree of conformance to Regulatory Guide 1.52 is found in Section 6.5.1.

Regu latory _Gu.'de 1.68, Rev. 2 Initial Test Programs for Water-Cooled Nuclear Power Plants The initial test program for the Seabrook Station will be conducted in ac- ,

cordance fied below:

with the intent of Regulatory Guide 1.68 except for the items speci- '

1. During the preoperational test program, no practical method exists to vary system voltage to obtain maximum and minimum design voltages.

The intent of the requirement to demonstrate that the emergency loads can start and operate with the maximum and minimum design voltage available will be met by testing the eeergency loads under plant light load conditions s te simulate the maximum practically obtainable voltage and under plant heavy load conditions to simulate the minimum practically obtainable voltage. The results of this testing will be compared to the station 14.2-5

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SB 1 & 2 Am:ndment 45 FSAR Jun2 1982 ,,,

1 voltage study to verify the adequacy of the analytical model.

(Appendix A, Section 1.g.2).

2. During power escalation, testing will be performed at approximately 30 rather than the 25% power plateau. Westinghouse-supplied plants have historically conducted tests at 30% and, therefore, generic data is available for review. (Section C.8; Appendix A, Section 5.)

3. Throughout core loading and precritical tests, the shutdown margin wil'1 be verified by periodic sampling of core coolant and verification that boron concentration is maintained at or above the Technical Speci-

'fication concentration limit for refueling conditions. (Appendix A, Section 2.a) .

4. Control rod runback and partial scram features are not used in the '

Seabrook Station design and, therefore", will not be tested during power escalation. (Appendix A, Section 5.j.)

5. A demonstration of the capability of systems and components to remove residual heat or decay heat from the Reactor Coolant System will be performed during power ascension testing only if not performed during hot functional or low power tests. (Appendix A, Section 5.1.)

6. The failed fuel detection systeni is not appli able to the Seabrook design and, theref ore, will not be tested during power escalation.

(Appendix A, Section 5.q.).

7. The integrated control system and the r or coolant flow control system are not applicable to the Seabrook Station design and therefore, will not be tested during power escalation. The Startup and Emergency Feedwater Control Systems and the Steam Pressure Control Systems are only used in the hot shutdown, hot standby or low power operating modes.

These systems can not be tested during power ascension. (Appendix A, Section 5.s.)

t. k m.s y &n,sg. . ,,

O. h w u w fkuta.w A J k %Q eu .A& wtL.-e44 to a Jooe.

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. SB 1 & 2 Amendment 44 h FSAR February 1982 W- -

t sq, , e sul btai , ,

fr u teg oe t

, ,) 1 o 9e gIV' will b,e'dem9 tra ts ranste e n t spee t Pcoper j

n du 'ng ho '

b 'pyr es tig/.ag Ap ,endgx A Secti funet'ionaf p

5.m.$d.

A v

10. The ability of the incore and excore neutron flux instrumentation to detect control rod misalignment.s equal to or less than technical

, specification limits will be demonstrated at 50% power only. The design of the nuclear instrumentation is not intended to specifically detect a misaligned control rod but rather an anomolous core condition. The individual rod position indication system is the primary means for determining control rod misalignments. Since at 100% power the control rods are essentially fully withdrawn, individual rod worth is such that the ability of the nuclear instrumentation to detect a control rod misalignment is limited. Therefore, data on the nuclear instru-

- mentation characteristics over a wide -ange'of control rod insertions will be obtained during the static rod drop test at 50% power.

(Appendix A, Section 5.i.)

11. Since Units 1 & 2 are essentially identical, the -below listed tests, which will be performed on Unit 1 solely to verify the adequacy of calculational models,. will either not be performed or reduced in scope during the Unit 2 initial startup program.

1" Q.\ a. The low power psuedo-rod-ejection test will be deleted for Unit 2.

(Appendix A, Section 4.c.)

b. The power coef ficient measurement for Unit 2 will consist of a

. single measurement at approximately 75% power. (Appendix A, Section 5.a.) * '

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7, m a e ,,, . u , , j c.s,,,,,,,, s. r .s..,t.e-s../ rn r. .".',y Regulatorv Guide 1.68.2. Rev. 1 '

Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants The remote shutdown capability of Seabrook Station will be demonstrated in accordance with the intent of Regulatory Guide 1.68.2.

Regulatory Guide 1.79. Rev. 1 Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors The initial test program for the Seabrook Station will be conducted in accor-dance with the intent of Regulatory Guide 1.79 except for the following:

1. Section C.l.c.(2) specifies that an opening test of the accumulator isolation valves be performed at the maximum dif ferential pressure I that the valve will experience using both nermal and emergency power suoplies. Since the valve operational capability is independent of the source of power and the valve motors are a small fraction of the

%..?

14.2-7

. . . . , . 7_-_-- __ _ _ _

- -~ ~

SB 1 & 2 Amendment 44

'FSAR February 1982

- ~

Regula tory Guide 1.108, Rev. 1

• Periodic Testing of Diesel Generators Used as Onsite Electric Power Systems at Nuclear Power Plants .

Seabrook Station is generally in conformance with Regulatory Cuide 1.108. *

• The detailed discussion on this guide is found in Section 1.8.* I y Replatory Guide 1.128, Rev. 1 ,C - s ' '-

3 Installation Design and Installation of Large Storage Betteries for Nuclear s ,-

Power Plants _ _

3

,+* ,

Seabrook Station is generally in'conformance with Regulatory Guide 1.128. / ,

The detailed discussion on this guide is found in Subsections 8.3.2 and 8.3.3. ,

p .e is 14.2.8 Utilization of Reactor Operating and Testing Experiences in

~ _

Development of the Test Program 44 .,

n - DepATiM ,

The y Startup Test (Gessp;will perform a survey of PWR operating fxperiences, encoinpassing approximately samtlar power plants over at least the two prektous -

4 years. The survey will identify operating problem areas or categories of ,

abnormal occurrences tha6 are repeatedly being experienced by other facilities.  ;(

. This information will be appropriately incorporated into the Seabrook Startup * .

Program.

t' 14.2.9 Trial Use of Plant Operating and Emergency Procedures 44 The procedures used in the conduct of the preoperational test program' wi.11 reference the station operating, emergency and surveillance procedures inhenever possible. During initial startup, plant operating and emergency procedures [

will be used almost exclusively to operate the plant andidtj systems. 'Jh eneve r.

corrections to station procedures sJe identified during gesting, the corra'ctions -

~ '

will be evaluated and the procedures revised accordingly. ,

A description of station procedures is providsd in Section 13.5.

I 14.2.10 Initial Fuel Loading and Initial Criticality \ l

+- -

4

~

The following describes the general approach used to prepare for and perforp ,

initial fuel loading and initial criticality. Deta? led procedures prepared; and approved in accordance with Table 14.2-1 will govern the actual work . ,

activities.

14.2.10.1 I_nitial Fuel _ Loah f A4 Initial . fuel loading will not begin until all prerequisite system tests ,

and operations are completed to the satisfaction of the Station Operations ,,

Review Committee. "

Fuel handling tools and equipment will have been ch -cked out and dry runs conducted in the use and operation of the tools.and equipnent. -

w' s ,

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[ht f $3) 1_t.ITIAL TEST IROGRAN RESPONSIBILITY /AUTNQRMT MATRII 7

Preoperational Test Program' ,

Initial Startup Progre:p N

Activity Individual System Integraded Systems ~ C Cota Load e Cri hality Power Escaleilon Tests Testa Ji- & Physics Teste Tests ,

=-

Test Program Management - 4-STSP STGP ~ STEP , STgv ' 178n 3

s .

TeJt Procedure Preparatio STjh or -AE STSB ST EMS ~ ST or SS #

St or SS Test Procedure Approval AE,-STC, SS P f d AE rST0;-SS Y STS, SORC STp, SORC STS, SORC

.I.19 <

TT&

-Test Coordination &

Direction '

[ /

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Systems & Equipmen't ~

,T j  ? Maintenance AE or SS SS SS

• SS

• SS s1& Stc p Test Completion Approval AE, STC, SS AE. STC, SS

..) p STW, SORC STS, SORC STS, SORC .

Technical Support NSD, NSS, AE, TC NSD, NSS, AE, TC NSD, NSS, AE NSD, NSS, AE NSD, NSS, AE, TG i.

I i

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FSAR t

Definitions for

, TABLE 14.2-1

^,'

, i Vst& Y 2 3) ,.

Test _ Program Management

" Test Program Management" defines the organization responsible for

' coordinating and sequencing of the initial test, program activities.

Test Procedura Preparation

" Test Procedure Preparation" defines the organization responsible for preparation of the test procedure initial draft,'oordinationc of the procedure review, and resolution of comments.

. Test Procedure Approval >

" Test Procedure Approval" defines the organization that will review and approve test procedures prior to their performance. ,

Test Coordination and Direction .

" Test Coordination and Direction" defines the organization that will

coordinate the activities prior to, during and af ter each test. A Test director will insure that the test is properly conducted and all relevant data is properly recorded. Upon completion of the test, the data will be analyzed for completion review and approval.

Systems and Equipment Operations

" Systems and Equipment Operations" defines the organization responsible for the operation of the plant equipment during 'each phase of the test program. .

System and Equipment Maintenance l

" System and Equipment Maintenance" defines the organization responsible for the maintenance of plant equipment during each phase of the test l program.

Test _ C ,omgl_e t_i,on gr, oval,

" Test Completion Approval" defines the organizations that will review and approve the results of completed test procedures.

l i

i s'

1 SB 1 & 2 FSAR TABLE 14.2-3 (Sheet 1 of 46) -

PREOPERATIONAL TEST ABSTRACTS Index

^

+ .

1. Reactor Coolant Pumps '

g-

2. ,Pressuriser Relief Tank 4 -

3. Reactor Coolant and Associated Systems

. Piping Vibration Test .

4. Reactor Coolant and Associated Systems Thermal Expansion and Restraint Test b .

5. CVCS - Charging and Letdown 7

6. CVCS - Boron Thermal Regeneration System C

. 7. Residual Heat' Removal System - /

8. ECCS Performance Test IO '

9. ECCS Hot Functional Test

10. Safety Injection Accumulator 31owdown Test ,

11. Containment Recirculation Sump Operability Demonstration !3

12. Containment Spray System IM

13. Main Steam Line Isolation valves

14. Bsergency Feedwater System ,

Ib

15. Service Water System 17

16. Primary Component Cooling Water System .

13

17. Spent Fuel Pool Cooling System I9

18. Excore Nuclear Instrumentation 20

19. Reactor Protection System

~

7[

20. Engin'eered Safety Features 2g - *

- - j. f., ,

' S & n 2 g W q e

~

- - - - - - - '~

SB 1 & 2 FSAR r

Defini.t ns for TABLE 14.2-1 (Cont'd)

.$.tt'.* 3rl Technical Support

+

" Technical Support" defines the off-site organizations that will be used to provide technical input for the initial test program, as required.

Legend:

,, p., . a. %<,,?

ST,G y 1c.

Startup Test Group - Yankee Atomic Electric Company J.. . 1 Te ,r c<r. w NSS Nuclear Steam Supply Vendor - Westinghouse Electric Corporation AE ArcF'_cet-Engineer and Construction Manager - United Engineers

& Constructors SS itation Staff - Public Servica Company of New Hampshire NSD' Nuclear Services Division - Yankee Atomic Electric Company TG Turbine Generator Vendor - General Electric Company SORC . Station Operations Review Conunittee l

i.

l

y)

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• ~' TABLE 14.2-3 (Sheet 2 of 46) st.k TJJr Primary Containment Isolation Valves

~,

21. .

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22. Containment Enclosure Ventilation System $4-@;N,7ygd 6 '.

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23. -Containment Enclosure Exhaust System

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,;24. . Containment Enc osureW& 4.Q%?,WiAMf,UfS;Q:yfj?Q@fvXhkl% . .. 13 % . ~ " ' ,

25.'-Containment Combustible Gas control System

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26 .

..- . ,, , ~, . , ,, .p . r :. System ~. . . .. ;;. 7 ; .

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27. Fuel Storage Building Ventilation System h

28. Control Room HVAC 3/

29. Emergency Switchgear Ventilation a .:..

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30. " - 7 g AC Electrical Distribution . g".::~.L,z.

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31.  %':,'[eM ~ ~ ,(

• l c- ~

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32. 120 VAC Vital Instrument Power Supply k 3F'

33. Diesel Cenerators .

34.

Fuel Handling and Transfer Equipment 37 - -

35. Reactor Coolant System Hydrostatic Test ~# 5

36. Primary Containment Structural Integrity Test tG

1. I

37. Primary Containment Leak Rate Tests 40

38. ESF Integrated Actuation Test At

39. Loss of Of f site Power Tests 47-

40. Integrated Hot Functional Tests

d. d Functional Tests

41. Integrated Plant Heacup for Hot

42. Integrated Plant Cooldown from Hot Functional Tests a 4b

43. Reactor Post-Hot Functional Inspection o

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• W/[ M 'a$.3fl5f W A

TABI.E 14.2-3 (Sheet 3 of 46)

1. REACTOR COOI. ANT PUMPS ,. ... ..,

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• • f-W: A'* .

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gTo verify proper _ operation;of 'the, rasetor coolant

pumps ,. and. to establish-

,- basefi'ne data for pump operations. .

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..,~.r. s m. A . MPH $N 4;' % ;-jLj l % i Q ,, g /.. W ' \' [ ~- Y , ), . . O Prior to and during hot functional testing. '

. Wyu. i.-) s. A:;, c  ; *yg.fMr %? \ ;-: : ll. ?. , '<;  ; '

Test Method '

Instructions will be given specifying the required operations for the initial run of the reactor coolant pumps. Interlocks and controls will be tested. Pump operating data vill be recorded. Additional operating data will be obtained during hot functional testing.

.o .- w. e ,<. , c.

c, . ,-w.....  :. , - .:- a^ ~- -

i Acceptance Criteria

, . . . m ns . :. . u. . e r?.

All re_setor coolan pcontrolaginterlocks andalapsshunctioeper desi ,anjall ufa'eturer' ar' data is.ve ified to be accu'rade.

seline p p ndmotokataiscolacted< '

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TABLE 14.2-3 (Sheet 4 of 46)

2. PRESSURIZER RELIEF TANK :ija: y ' -k,_'

~

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Obicctiven $ ~

~N 9.u tw,Vi-lW$.l$(-ik$;i$W[f $$$$$, ?y?W.N$ ' '

To verify that- the pressurizer- relief' tank provides adequate. .' 5.* @control Q of ',the-

-i g k i_ .h f.f,*' .WTib?N%N,5AI.%;l'f

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disch:rges from the pressurizer relief valves.WY:$

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P1rnt Conditions / Prerequisites _f'

, n 'k;4% .z af

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- -9 . x Prict to and during hot functional testing. .a : *

.- y , .-: , q :- y .

Tast Method Th2 operation of the pressurizer relief tank will be demonstrated by d p2rfcrming operability checksfunctional of the tank tests,andthe associated ability of the instrumentation system an cuxiliary equipment. During hot lief valves to rcceive and cooldown a discharge from the power operated re ,

e

)

cill be verified.

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Acc ptance Criteria _~'  %~ m ,_ ,,

a pressurizer r - ief tank acceots discharge from the primary plant in NM stem'esi cr rnanin-aatJ and the heat dissipatio

/ cccorda$ce wit the are3FrffEeE Wsg of the pressurij,e'r ( relie. tank c-# '

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TABLE 14.2-3

(Sheet 5 of 46)

3. REACTOR COOLANT AND ASSOCIATED SYSTEMS PIPING VIBRATION TEST

l. ,

T demonstrate thatvibration. levels in.: selected. ASME' Code Class.14,2.and. 3'  :-4 Nl#systenspSeismicCategoryI.

Iocated in Seismic Category Isystema,andotherhighenergypipingsystema structures are acceptable.

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Plant' Conditions / Prerequisites .

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Prior 'to and during hot functional testing. He specific conditions required for each system will be specified by the test procedure.

Test Method ~

Selected' lines will be instrumented and the misp.litude of the vibrations measured for various operational modes. Non-instrumented piping will be w inspected during system operation to ensure vibration levels are within acceptable limits. .

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ibratio is a with (speci h rocedn'- Si=i W and test resul satis AR Subsec 3.9(N).2.1.. -

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• SB1&2 Amendment 44 FSAR February 1982 i

'd :' .

TABLE 14.2-3 (Sheet 6 of 46) 4: Df. ACTOR C001 ANT AND ASSOCIATED SYSTEMS THERMAL EXPANSION AND kESTRAINT TEST Objective -

To verify that the reactor coolant and other selected plant systems are free  !'

to expand during plant heatup and contract during plant cooldown.

Plant Conditions / Prerequisites - -  !

During heatup and cooldown for hot functional testing. Preservice inspection has been completed for hydraulic snubbers.

Test Method "

Bcseline position data will be taken at selected points on components and piping at cold plant, conditions. During heacup to normal operating temperatures, expansion data will be taken at specified temperature plateaue cc these selected points. An inspection will be performed to detect any points of interference which will be corrected prior to continuing the m hoccup. Hydraulic snubbers wil,1 also be visually inspected during hestup and cooldowti to demonstrate operability. Following the cooldown, a final ch ck. of piping and component baseline positions will be obtained.

~ "

Accentance Criteria

• v v V V v The reac rc c an sei plant syst ..Ir to e and centrac w' out obst on durin and coold e sy -

movene does noe (r e_rr-__ .._;we as determined b inspection. pes,-Pipe A > --

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• v, TABLE 14.2-3 (Sheet 8 of 46)

.6... CVCS - BORON THERMAL RECENERATION SYSTEM ...;... m

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To: demonstrate the operational; capabil'ity-of',the boron- thermal regeneration.

cyntem (hTRS).,

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Plant Conditions / Prerequisites '

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.; u . m; Prior to and during hot functional testing. .

'N." ' ' '

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T se Method  ?. _y

~

J" '

Prior to hot functional testing, system components will be operationally ch:cked to the extent practical. During hot functional testing, the system reill be operated in its various operational modes and relevent pressure temperature and flow data recorded. . .(nP.. - -

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J c W '<*' Q,g e n..Qg: ?g. r . f.,y g.4 %n.m'% '.' - ) V n't FSAR e ' .9l'%'p M. ,. ..

.- m-: v.,m. .

n nn -

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. TABLE I4.2-3 (Sheet 9 of 46)

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. . c . . 9:: 9 Ts'/. i.M a %L2c. D.'l . ~- ~

-i.

~~  :

E i .%:

2'~W; 47 .~ 7'. RESIDUAL 4 4 s BEAT p .p REMOVAL

• f m edk.W. ,j l g SYSTEMb.W'Qli.mp.,Qpn,.

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Nd n r%it N TN d2d h 5 N.,. Nk g.:

.: ,,: C b3 e etive~.s.y

.$N}i f::Q.@k N b N h'.ht.- [#,,'- y '

.'im f.E.% feeM W 9stE.b 4.nTo demonstrate the operational capability of the residual heat bh .

removal'9R / yOf:'M2#6 44; O -

j @'7.cystem," and'to estahtish. b.M'*%y baseline pd.'.t;.WM.%;;?PDf data:for pump Pf.5 1% operati

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'*-*? l* .

Plaat Conditions / Prerequisites o o d a Lw t& R-: 'm

• 2 R 'E -

>> . & .;.e?.: -*m ,2  :- i ~

v -

Prior to hot' functional t.x m testing. u p . m & f &~ik'f}

' ' . . " ' % g! M M F;"...m$d

- t.

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. : .'s &

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k.W, &, ' --

> mt1%

                                                                                              .n ' ' . . OI . . V +3.

Teet Methode- -

                                                                                                                                                                           ..             .p                                              .

p The residual heat reanoval (RER) system will be tested to Additional verify controls and interlocks and to determine systest operating characteristice. ldown from hot " M' '

                                                                                                                                                                                                                                                                                                                                                 ^
              ; testing will be performed during the integrated p ant coo W 3)y'n.4 STch*"F l

functional testa t 4.V;u:: -sys spriyng4:.1=h pojrgt.h,o .

                                                                                                                             <setiMsuk;mht$MHsn                                                                                  ipokaMS M.*'.&M."'r                                                                                  .w:t.7..UC
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             .,".Accept
                    . .: .n. i s5ce' Criteria                  Aw."&M.Vi;2)SN.M8:@~.                                                                         :

S.m.I.$ -:sqY84~Li 90 tT!'f'

                                                                                                                                                                                                                                                        ..D. .Y$.&.t.$A                                   ,                   %,k"c.T p                            : c A.;@2 ed:rg.: 7.4 M rin s3( h ed D. R                                                                                                                                                                                                                             h N ;                        ,

The residual heat removal system operates in accordance with the L M4 requirements of FSAR Section 5.4.7. m; 2 u Wih.':6'..w.d,md M*u. -W e:Od4

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                               ;'q            D                                       CW'                                                      W. C P3 *.. - @ g/j.                                                   ndment 44 91.@/,      g.J,.36,3FSAR  , ' .Bil rp                                                                          y@                        .d. .*r '

• February 1982 qJ&hk

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TABLE 14.2-3 (Sheet 10 of 46) ( - \ - -1 .o, m;.;;;sy s;,-[ mqg ; _. 9:. , ,_ . : q , , , _ u M; lfMCGA OC79 D3 '2/N<..: C.7 8.:.f ECCS PERFORMANCE TEST ,,; .r f0,$,. 6 .c,4 ~ ? ^ '  ??  ? i dW

         . Is'd?Xl'tUNYkY' .
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                                                                                                                                                                                                    $W                                       .
        '"                                                                                                                                          . _.                                    : **                .%.*     N ' ;&.hhQ:.: ~. .

i

      . , To ~demonstrn:e' the capability of. the emergency core cooling-systems to pump                                                                                                                                                                   -
                                                                                                                                                                                                                                                                                             .a
            'w' ater from the refueling water. storage. tank into the reactor vessel through
             /various ccabinations of pumps and injection ^ lines.                                                                                                          . +GM        -
                                                                                                                                                                                                                                    ,-V M 4 . M 'y Y O-D'fMRN 6.G5h@EWJ$Y.(U$ fig [>c . . '" D6.%'Qf$2}+ir',1
           . Plant Conditiona/Prerequieiter N M E N E N N k.%                                                i' h Nr rSh5E #N
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                                                                              ~                                                                                                                                                                                                            . - -
          - Prior to initial core 1oading with the r#hetor vessel open.
                                                                  ^
                                                      . ,,. g u.. .%.. n     . ,-. 2.
                                                                                   .a- ;- :. ,.,,; ,.                                                      " ,
                                                                                                        ... y ,pc.; J..y . , ~. -.              m, 1.,
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? .':'.'= W X ~-

T2st Method ~~^ . c.: r. i.vinn&)iifAMNsbE$I!$$$,S&WM W~c"b 1=> ' M N b"O - A series of. flow tests will be run using the centrifugal charging pumps ~, 5' safety injection pumps,. and EHR pumps to verify proper flow rates and to -

                                                                                                                                                                                                                                               *'4=-'                   ~ ~

perform any required flow balancing during pumping from the RWST to.the M , reactor vessel. . The draw-down characteristics of the RWST and SAT will be . , :c. demonstrated during thace operations. ~ Appropriate data will be obtained to . :. du '

   ?           d;termine pump headflow characteristics. The ability of the RHR pumps to                                                                                                                                                                        ..,~^'

cepply water to the SI and the centrifugal. charging pumps will be " - ' - ^+G };' demonstrated. The operation of'the baron injection tank recirculation '7 ' ' ' c stem and heat tracing ystem will be verified. . fle a 2$b' e N$1*od& SAT' 2d,5 waZu -** send.)m2fbeon.jwA m l A ceptance Critria ~3-

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                                                                      ^___---..               - -

SD 1 & 2 Amendment 44 FSAR February 1982

)  ;

TABLE 14.2-3 (Sheet 11 of 46)

9. ECCS HDT FUNCTIONAL TEST .

Objective - To demonstrate the capability of the emergency core cooling systems to pump into the reactor coolant system at operating conditions, and to verify.that the accumulator check valves operate properly at higher temperaturcs. Plant Conditior.s/Frerequisites i During hot functional testing and during cooldown from hot functional l testing. u Test Metho'd Water from the RWST will be injected into the reactor coolant system utilising the centrifugal CYCS pumps to the extent necessa'ry to verify check valve operation and to obtain rated pump flow. The duration of injection will be limir.ed to minimise thermal shock effects. During'the cooldown from hot functional te'sts, th'is test will be performed using the safety injection j pues and the accumulators. Following each injection, the ability of;the check valves to resene will be verified. Acceptance Criteria Emergency core cooling water is injected into the primary system by each g at_ics d_es g limi_t in_accordance with FSAR Section 6.3j.7.,/ W --i

                - 152. & %9                                    cA n de & a w k ['el f F sa-aAsp M o.s.
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n ., .,-e us. 4- 7+, TABLE 14. 2-3

                                                                                                                                                                                                                                ~

c. (Sheet 12 of 46)

10. SAFETY INJECTION ACCUMULATOR BLOWDOWN TEST

                                                                                                                                             .c.

[$

• y.}gh2 h. 4 .

f,< c*.N.'b e h r d d h.h f k, b Tdi Mdh $3. NbbkNN5N Tb demonstrate proper system actuation and, f1"ow rata. f6r. the test conditions,, M N b 7'O 2 . ,] and< tu demonserate. iisolation valve' operability. ' s "~"~%Ia?.P M g ~s- ;.4 'i $

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Plcne Conditions /Prerequisitee

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r .:y v w w.-e;-e w.,y-uymret%gL :e .. a .a-,;z .

ne w s

Prior to initial core loading with the reactor vessel open. m

                 -                                                                                                                                                                            ~

f. Tant Method mot 9,'Mifdddf'*[eM~ ' -- - c..n W.J.l M N y $ffy: M -5;M73v;

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                                                                                          ,              u c...        ,

s .

     '1h2 accumulators will be filled to their normal operating level and pressurized to a specified pressure. The accumulators will be discharge one et a time into the vessel and data will be collected to determine the rate of discharge. The accumulators will again be filled and pressurized to the mari== expected accumulator precharge pressure. The accumulator isolation valves will be opened under the, maximum differential pressure condition.

w. = ,. - -

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Acceocance

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cirn-r 9 * .0 J. , - - e Safety injection accumulator response is in accordance with FSAR Section 6.3 dssign requirements, and the isolation valves are capable of opening with 44 i maximum o thipressure/ A$ 5 ( M~jy[ug. d 3,5, f,

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TABLE 14.2-3 .

                                     -                                                                                   (Sh,eet 13 of 46)

11. CONTAINMElfr RECIRCULATION SUMP OPERABILITY DEMONSTRATION y.:mo'r- rwy*.. . ./ . x., n. :l .v.g e g;u: _j, "- g .ing,,.. . > -o n -,. , . a ;

                                                                  - vos v;.                 -.                                                                                                                                                        .               1.

y Obj.-'y.~, ective G.-- 'dQ. m. .;., p;e 4 . 4 $WeWAM.,' . ;a,.g- gg,M'fk,;,gg., f g.t4 4'~~7.. b'Y~ ~'Y$'  : ' 1*F -'

                                                                                                                                                                                                                                                     '~~'
            ',7*                                                                                                  ..        ~                                '7'                                                                             .

1f d@1*E ?*

• J' I - J/ "

To verify the operability of the ECCS s' ump. f.."/h~8

       'M AMThd.WTM W M #4diiQg(6 7. 1                                                                                                                                                                                                       .      v,MI                    I- ' .

3. yPlane Condit1ons/ Prerequisites '

P %fa

                                                                                                                                   . u.         ' ~ "$                     Tk.,a.[4-9/47EtAMME
                                                                                                                                                                               ..                   gs.q d.N.'jey.Qt. 86i'f k,7.,' N M.,$.

AT Frior$tf,tnWWW,2939t#xM to initial' core loading. . .Wy jfT* T.MY a:fS #. 3di: W ~*, ' :'

                                                                                                                                                ~
                                                                                                                                                                                                                                                           ~

eY $XA 0 .

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                                                                        .        .                   v. sfp       Mq     . Y.:. p; e s yg..t. , L -. Q t.'?.i                       .

s The ECCS sump will be filled to its anticipated post-LOCA level. ' An RHR and a containment spray pump will be operated at post-LOCA recirculation flow rates and recirculated back to the sump. Appropriate pressure and flow data

• will be recorded to verify net positive auction head characteristics.

                                                                                    ^
                    ~~ AcceptanceK                                                                                                   "f                        r. ,e..
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Criterta - -

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i - _ _m _ . m_ m _ .,..m. SB 1 & 2 Amendment 44 FSAR l February 1982

     }    .

TABLE I4.2-3 (Shset 15 of 46)

13. MAIN STEAM LINE ISOLATION VALVES Objective To vyrify proper operation of the main steam line isolation valves.

1 Plant conditions / Prerequisites Prior to and during hot functional testing. Test Method Operation of the main stesa line isolation and bypass valves will be demonstrated at cold plant conditions including the response to a main steam line isolation signal. During hot functional tests, valve operation will be demonstrated and the closure time measured. # l Acceptance Criteria P [G _ . , A rumentation, controls, al d interloc'ks operata @ I ssociated desibe3 inval sponse o normal or

• 1 aced in t si mals.

 ,v o

Valve e sure times a m h cal snedifip4 tion requ M eh under(dynamic hot functional condit' ns. V -

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oE'46) .

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14. EMERGENCY .. .d t FEEDWATER%: ;w 4. (. SYSTEM .. - ... ..,

                                                                                                                                                            . ~ >    -   ~

7D **"' %"G.en%f IO , 0;) 4 &IG '.v dsKQof9pi.

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9; q.Wi'b5 n:m, :m. feedwater. h.ob,ective; l;M. W Q ,k h3 ' g y"N,@%5%Fb$Y$d

 /?',g.To.emmmnstrate proper operation of" the: emerg ncy, Pjj e
                                                                                                                                                  !hj,g.Q.

a'.' Li;. W'>~ab -<: F W?{.g g

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M Plant' Conditions /Prerecuwwhmbi$thtrx+~x

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mux 4uy:wv. whot funcitonal testing.p, v,:r .L  ;,

                                                                                                                                                                                      /
          - - xg;;to+rduring.

Pr ior g:,ppy p g y~y.$$': ' + .r/ Q^ q'-

                                                                                                  .(

Tast Method- ency feedwater pump and ability checks will Prior to hot functional tests, emergl feedwater isolation valve control and  : .L oper be performed to the extent q practica

                        ,4 w g':i:l% ;Q-ir w . igfry.7:,=.h emergency feedwater pump will                         .

During hot- functional tests, eac h racteristics and to be operated to verify pump head-flowteam c a generators whilels, including demonstrate the capability isolation to feed the sSystem response to 1

                                                                                                                    +

at pressure.the operation ._ , . ,,, , .y of .:thewfeedwater,

                                                                                                                       ,               , w(z.                                             :

strated. . ,2 nt restart will be performed i A 48-hour endurance run and subsequeto demonstrate long ter on each emergency feedwater pump bility. starts.for consecutive, successful, cold, pump ll be demonstrated. At least five (5)each emergency feedwater pump wi ing the emergency feedwater Heat removal of the primary system usffsite and onsite ac power system under a simulated loss of o condition will be demonstrated. cy feedwater flow-restricting The proper operation of the emergen venturis will be demonstrated. formed to demonstrate a "watere A flow instability test will be per hammer" will not occur in system componstartup operation. fied steam generators during normal systemtilation system will be veri The operation of the associated ven d during this test. age system will be demonstrate . The operation of the condensate stor l l - r . A g

                                                        '"E+-

s y ' s E S . 2

                                                                                                  '"n

h;p -- - - 4:~,Q .;; Hw&'yli ~ Q:yb ! ,+' V-7&YA c.kW -8A.-S - % .~W*. 5c 5. e + ~~W

                                                                                                                                                    ~

WNk q+.9My%*.h}p.R ~ - XX.2:. 2.Qh3: fat Ma d - A,) . .

                                                                                                                                                                    ~                  '             * ^

• Acceptance Criteria The emergency feedwater system operates in accordance with the requirements of FSAR Section 6.8.

                        '. r;. . m . v*:               , . . ..               :.y; 2 :, .;.rf m, ni;: f;Q i.o -

s.A,;,..The .emer9encY_'feedwater.9 ump can operate for the.48-hour.

     -~-

d . endurance.run erational'. Iimitations with assubsequent; l'isted in.thevelant restart without exceeding operating. the:- procedures. p N M d M M @ $ M i$ N k M N M M M N I M W U" 9 9 ~; " t"" ' . " ~ *WM 7.5- . , 3.F'eedwater Isolation valva closure times meet Technical Specif1-nic,-aN w+;g C.JV;M e

   ?.;%p%~ cation ~ : Table 3. 6-1:'r'equirements
 .'N@Q?$?$$$$$W$$$$$Sh%$.                                                                                                                                 N?kW. ,
                                                                                                                                                                                                              ' D '.Mha;;;.                 fjpy=? %
       "yHeat removal of the primary system under a simulated loss of
        '. offsite. and onsite. ac power condition is demonstrated.
              - : w.w..:.m; cn, em m,.m ;%c.:
                                  .                                                                                           y.+ w . . :9. : . <, ,

Emergency feedwater flow-restricting venturis limit flows in accordance with FSAR Subsection 6.8.2.

                                                                                                 ;+ i . ' ' .       ,      ;        ai. -              . .                     ..
                                              ~ $4'."

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l . TABI.E 14.2-3

                                                                                               ,        (Sheet 17 of 46)

15. SERVICE WATER SYSTEM -

                            'r      .'                                                             ,
                                                                                                                                                                                         ,y      .-N' 4       :f idemonstratether proper operation. of the, service. water system                                                                                                . . - 
            .I'                            ~' % f M k. &,                                                                                     '
               .s         PIant Conditions / Prerequisites - /. n                                                                                                        ifa.E' V$ .5fd.l   k A jQ p,Ah,.k ; 5lW h M.J
           ' c'.$Priort%%4&!1961aDMioKa4Q'to and during hot functional MW                                          k                      !TtW.+.N?$A.Y testing. ' Cooling tower performanc N5.
                  ~
                     be demonstrated when adequate' heat loads are present on the system.

MTese 'NSM$}/Mid'ty'$$$hg%jgV7.$Q2,% Method ~ '

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                                                                                 ;2t%jpf3                                                                           . -

,. m . -. .n, e4t?- ; ,g. d .s

                                                                                                                           ~

Prior to hot functional tests, control system functional tests will be performeds Pump and overall system performance data will be obtained using  ! both the ocean and the cooling tower as the source of cooling water. During j hot functional testing, the ability to maintain required componen: l temperatures will be verified. When adequate heat loads are available, a ,

              ..        cooling tower performance test will be. performed. The operation of the                                                                                                                      I associated ventilation systems for the service water pumphouse and cooling I'-

tower will be demonstrated. . -r. . % U 9'A 9s.n w c -- - -

                                                                                                                                                                                                               ~

T &

                                  . e n. w .$ ,- 9;yg.g,p g f;*.
                                                                                                                    ,ty                            WM -                     '

Acceptance Criteria .- The s M e water stem pua t or cee esi.gn flow and pressure jettui/remenVh3 -

                                                                                                 .s               -                -

y s Instrumenta ton, cont o , interloc s and alas s oper ((sdesigned)in ( s' ~ response to normal or tuulated input signals. f Each system flow train sup. plies @ : 62 2 cooling to both safety and non-J L safety related loops in the normal plant configuration and to safety-related loops in the accident configuration utilising either the ocean or cooling CO** . The_ coolint tower performance tese resultf~x-s--- w" *~-- N--'------Dhe dissipation 'of the heat loads specifiN .2-13 M . l doolingtowermakeupwaterequipmentmeetsFSARSection9.2.5.3c crtteria. l

                    ' Y ,9 v>5tA. W                                                                                    S&                                              k        &g
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s u e. m 4.z.to 46 _

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• _ _ _ _ . _m 1.m.- m- - W n SB 1 & 2 Amendment 44 FSAR February 1982

                                                                                                                                          .c

• 7-a TABLE 14.2-3 *

(Sheet 18 of 46) l

16. PRIMARY COMPONENT COOLING MATER SYSTEM Objective. ,,

Ta demonstrate the- proper operation of. the- PCCW System..

                                                                                                                                     ~

Pirnt Conditions / Prerequisites ! Prior to and during hot functional testing. Test Method Prior to hot functional testing, system component operability checks and esntrol system functional tests will be performed. During hot functional tcsts, data vill be taken to verify that adequate cooling is being provided to PCCW components. #

                                                   ~

Acceptance Criteria p.Q -- A f- - Th3 primary component cooling w er s test pumps meet or excee t an F1 ~ s d

          ,gadfjressure                 Ermagrteegnes) Ins rument ion, cont cpera pea cenamed in\respons to no
                                                                                               , alarms and or si late input signal terlocks The j

cyst em su plies cool

• g to both the s ety an non safety-r sted

     / loop in t e n real plan co iguration a                                     e 'the safe -related loop M ,n.              k

,t 7 tha teciden onfigurati .

                                                                                                                               ~
                                                                 ~..#--                          .~           ' . A     m 9 l

sent,tra, Sw # b /f - A aL.quq . s u a. w w e. z .2.. nua & _atL. M p g ans4 4 -asa % L L & n ' - o O s

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• h ['*, S, 6, e * **

S.

                                                                                   't abw                                          . ... . -
                                                                                                                                                         ~~
                                                                                                                                                                . tFebruary                1982 u.Y:.k':>r                  /-

i 5.g.-nuyy ,s:,.y r c. fjj . 1. l19.JSAR.. , , ,. .

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p .. ^'

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                                                                                       <    f, TABI.E 14.2-3                                                                                                                                          -

(Sheet 19 of 46)

                     . 17. SPENT FUEL POOL COOLING
                                                                                    'WSYSTEM                                                                                                                                       .
                                                                                                                                                                          . < . .r, K >.lY.hG&                           irs.W.          vc<ca.'y?                      " * ' -Qj                   w.D       ov4 .?!"5lN-S
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K - .-:. ' 1: w- .

m. s. ..

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                                                                                                                                                                                                                      '.            l g BM0!gzg        - 1% >                    .

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     & m a% % @ 6 & M dtiJo, demo 6 strata

• the: proper J

                                                                                                                                                           ';.Lf,f:g operati~orr             *c-      ,   J of?the if'  '       S spen j

A'"' QA;g/nf J'd;A m,;f

     .it$A Q W ,@f 4 6 7 4 h % i 7 f 9,$3fffdyy                                                                                 F 72p:9.'C/j'q S';. : .                  -       .}'

3 Plane Conditions / Prerequisites ' ict

          .Trior
               .:, uw..r.7,+-u,.me; to initial core loading.
                                                                          .wewqyr$&.          .. .. 4 e. ,. Ks.    .

J- , n.,tj

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• J. c V ; ;,.%w.qc ; Q4,g;-ggj q.g?.j.y '7,.e.; ,; '-

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            ~
                                                                    ',d' ',, .~ ' !' '                    ?. D > 3 Test Method Spent fuel pool cooling and cleanup system equipment operabilty checks, flow                                                                                                         in verification tests and control system functional tests will be perfor=edg Sc Mi the various system operational modes to demonstrate proper system                                                                                                                                                         '

A & hMoo, , A ceptance Criteria ' *; ,,.j[;fr,;[ y 7

                                                                                                                              '."tj,'> .. jr                       -~                  ---

n . ---

• Tpe spepe--fuel poo co ing s tem umps meet near ton, e tro

[ls, alatceedh, and interiflow ks anp ' press e @ re. ment.3) Ins s nse to rorma or simul ted 'aput igna . Nirmal ,5 l e ,as des gnej in ed. i F ],cQr an alternate system design flow

                                  ~

pat re demonstr

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TABI.E 14.2-3 (Sheet 20 of 46)

18. EXCORE NUCLEAR INSTRUMENTATION .

yQ. i .,-y;;,:3... ,-; . q . g e.. .

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         ~.4%yMNd'iRN;.

7 . g%y < 4. ,p,.;z, ;.,.p;u,g.a g ,(3',pg,.g;3., t ,..;

                                                                                                                                        . A1 Taaverifyrther calibraaia' n, of' thes escore nuel' ear instrumentationt L                                 .s Q gg[i. -~~.%{jf.'jW,%,G:.
                                                                                                                                                                   $%':S #4.1:::                   .
                                                                                                                                                                                                                  ~

pp.t:

                                                                                                                                                                                                                                     .#W[4
      'hNNkh k[,;hkh               fg, hh.

I.;7 PIrne Conditions / Prerequisites ~

                                                                                                                                                 'x                     c#       - e-ay;M.,Qf4p;. qi;
          .45)Cd *** M. W.'#W9/MdiffiMM'                                  d Q                       ,,

w., . ' k . ;.r.UI [*'-  ;.- ~~ I,- - 1

                                                                                                                                 -s                                             .,o.          7             -

Prior to initial core loading. G dV,%  %-W.e,g,, k.W,.,4:; ,jih.k,. 7 . ';~ ), ". ~ 'f.

                                                                                                                                                                            ,q. 4                                                          r.t 7,q$q                                                                                              .A 2                          .

A A. W H,, . ' "2 k T se & "B 'tNWSf" Method =Tl.>#2..Js:%mi 'tf+k%iN:EOt*%Q.1

                                 ' c.g.:k:NM.

• 4.^ " '

0-8 Tha excore nuclear instrument channels will be calibrated and functionally ch:cked to verify alarm and trip setpoints and the operation of auxiliary cquipment. The response of the source range detectors to a neutron source will be verified. . --  %,y-4 9.. c.- n . .- ' i

               ./ s M y t;;e2 R $ { % h " w; . N *p'I Q {h h d ],g.)fk :q 5                         ,
                                                                                                                                                                                                    }.'s-     'i [ : -        ,

Acceptance Criteria -- ' - '

                                                                                                        %( 0&$h
                               .M.~:'iK'iAQ:Mh$$$,Y:mr.w h gy& N, pk Y .,k ^?.

s  :- n-a Th3 reactor. trip sec~ points and interlocka generated by the nuclear ' 1 instrumentation system have been verified at the values specified in the- y Tcchnical Specifications.7e~2d/d 2.Z-/.-

                                                                                                                                                               ~
                              .q,;::p .v                                         .%',~ ; . M.S;&k '* 0.

Tha control and indication functioca of the nuclear instrumentation system have been demonstrated to be in accordance with the FSARS The overall time-racponse of the nuclear instrumentation channels has beenNemonstrated at tha values specified in the Technical Specifications ,

                                                                                                                                                                                                        %                         N l
                                                                                                                                                                             &a& 22.)

tem .r. e-z.

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                             " :/M. G.S@, ,, .,:rf.1,*MN TABLE 14.2-3                  '
                                     'h'J'..N$(.,'f.D,NN/.iI(Sheet                                                                            21 of 46)
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                                               ],f. REACTOR PRO.                                    >~.,

TECTI,ON SYSTEM , h;.nn :, . .. . e:'in:rd3h$$//f.' .,M

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     ' M;7fQ$$7*f                                                                 ..         . . .
                                                                                                                    ?                       .-            5.                  .. . b$ ,# W Y8?-P M N ,T E*3 2 D ;b' M- Tor verify!, proper operation and' response , time- of                                                                                                                                       the reactor: protection W * *J-d Di
                                                                                                                                                                                                            <7n es-Jp           3ygw      n w co       %,r
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Plant- Conditions / Prerequisites

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               . ,9 Prior to initial core loading.. . . . -

( ..t T.,3.f.4[p&p *Wi * ' . /;d6'

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• J'P ~-, .,';C (

The operation of the reactor protection system will be verified for all ^ conditions of logie using ' outputs or simulated outputs from each of the RPS s-

            . ;. sensors through to tripping of the reactor trip breakers.' Individual W                                                                                                                                                                                       N ' M '. d 7'.' protection channels will be tested to check design redundancy and to
                                                                                                                                                                                                                                                                   ' ' - k"2" - [';
                  ... demonstrate safe failure                                                                     on loss of power. The :::pn                                                                   : ti n ;f cr "- ??S . - --- -...- -e- -.. < ' x

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                                               .s.

4,~:>s}%*&~ .{,]&y.g!.d.Q,ygg$...139.%.%b$7@tgMndt.S..,5.W.55..' We st .s b . v ~ .. t M.53 '

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'z . Acceptance criteria rup.4.%jst-mq.,4,jdTMMdh,%,9,M,E4..Ny.c :*3?4T 1*= h M U a'U M u " '.

                       . 4 ';.9                                                                                                                                                                                                                                            ' O
                    ~ The reactor protection system has been verified to operate in accordance with the design requirements dictated by the FSAR Gection 7.2.                                                                                                                                                   .

1 W . p ,",;,1.,,,4 ,.,,,,c.:. g y ; r v.g W p..%.7 .

                                                                                                                                                                                               .   . a.  ,   f-c P :.w                                                    1          ,

The reactor protection time response has been verified to meet the ~ requirements specified in t,he. Technical Specifications All react 6r protection system trip setpoints and interlocks have bee demonstrated at I the values specified in the Technical Specifications c ..

                                                             . aj. ,                           .....,,..':.4'c.
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                                                                                                                                    ~

February 1982 TABI.E 14. 2-3 *

 *                                                                        (Sheet 22 of 46)

20. ENGINEERED SAFETY FEATURES z,s.. -? ,,IT,h ,e - .;

ObVctive W.; $.. , . ,%= ' .i'N l,c . $C A P.W ,7 :: - ut ..%'..fMIMS9Ih5h$.IY$Ns# N'S\i':N2/h #h556).D' T.3 verify-proper operation and response tism of'the-engineered. safety- ,[ f;ctures- (ESF) actuation logic. M' sF -

                                                                                                                                                      /.-

O W ,.Ww"M '.* .D O'.DM ' ' . ' ~ ~

          ..'. Conditions Plant      aid !l:.%*           / PrerequisitestM18.%.     --

m. .?)}:ft%'.;O.

1.F,; t. /V7.l:y .' s ANi. ~

                                                                                                                                             '   3f';..&cw$$,_ q,,,q.;M. R y~~?wwg un ~cy.W::;.Q,~gj 'f' e bl'*S , ' f'
                                                                                                                                                                 ~
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          .m..         y .e,                                                                                                           ~

Prict to ESF integrated actuation test.

• T

                            .. . . , y .y.
                             "                 J     :N .,           v.           ,            *t'
                                                               ~                                  ' ' '

Tnot Mehtod Tha operation of the ESF logic will be verified for all modes of operation using outputs or simulated outputs from each of the sensors through to the output of the slave relays. Individual ESF channels will be tested to verify dssign redundancy. The response time of required ESF signals will be daccrained from the sensor output to equipment actuation.

                                                                                        -.-             ~ ' -.r.                                               ~

Acenptance Criteria 1- - :$~f

                                                       . .: 4_ _ >                      .>< i .v        y o                              -                                        ..
       'Ih3 engineered safety features have been demonstrated to operate in ceccedance with the design requirements of FSAR Section 7.3. The engineered safcty features time response has been verified to meet the requirements specified by the-Technical Specifications 7 M~ .S. 9 - g
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25. ColfrAIlOElff COMBUSTIBLE CAS CONTROL SYSTEM .

QThe demonstrate-the proper-operation of" the containment combustib1'e' gas ' ~ [ 'l. v.-k'f.@.

         .E,. con' trol'syatem.'~ ' 1' Vj$pe ".EstampJm.p. t , H.Q*AAAM
                -W$N.'W.NM                                                                                                                                        II.,.
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        ,,; 4. Plant,Condtetons/Prerequisttes
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Prior to initial core loadtag. -,

                                                                                                                                                           ' ,lh . , ' ~ '                     .-
                   '.1,%%.ty:n,:y,QQ;ij)                                                           Gj.'j'l'.}f ;k i{yg9;j.-      .,     .;- l..'llc. ., u '::e Tese Method                                                       - 

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                                                                                                                   ~

Containment combustible gas control system operability checks, flow t verification tests, and control system functional tests will be performed to ! demonstrate proper system performance. .

                % c.;L .Y n s >h*.

Acceptance ces,tarta

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__ the al ydrog recom iners , or exce , s N w s1  : freduipfements) Th hydroge ana zers a e ca rated <ind acti,) 1[.a_ture- -

 -/'          desyned) T                      e        ckup purge                                    tem funcrio                               hes-igi                            I
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j _ _ _ _ __ __._ ____ _ .._. _ .;;- q TABLE 14.2-3 (Shcet 32 of 46)

30. AC ELECTRICAL DISTP.IBUTION Objective.  ;-

To.6,emonstrate-the capability of'the.offsite. power system to.i . serve- as a source of power to the e.mergency buses. .

                                            ~                          .

Plant Conditions /Prerecuisites During hot functicnal testing. Test Method Tests will be performed to demonstrate the capability of the UAT's and the RAT's to supply power to the emergency buses while under a full load Hot Functional conditions from the plant auxiliaries and the emergency buses.

            . Tests will also be performed to demoristrate the transfer
             " capabilities between the UAT's and the RAT's.

Acceptance Criteria l The AC electrical distribution system operates in accordance with the requirements of FSAR Section 8.3. e 6 1 l l l l

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      .                                 _ . , . 7 . _ . n g.                      ,.r TABI.E 14.2-3 (Sheet 33 of 46)
                                                                                                                                                                                                                   ~

31. 125 VDC DISTRIBUTION SYSTEM

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              ." %&N;*MA.'NMh                                                   ;
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                                                                                                                                                                                                                            ^
           - Ti!r demonstrate the proper operati'on. off the.125'vde diistributiotr systeur.
                                                                                                                                                                                                  . u' .. .' ',' -1N i ~;'
           'ff6W        U     W       h?b      MNijj/      Yh15&[dn  Prerequisites                . , , ,                              '&bQf?}}{dj,rft MEWN2W,'                           7     -% y:&

tiffJ". f;4. Plant Conditions :J - - (N,6$[f.((fY N." ~ W4%" NT 4Fri .W,T WsN3*:Mt'E735 ' ' d ." * . "

                  ' Prior- to loss of offsite power tests., " i J ~                                                                                          ',~.;<',
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Test Methods Tests will be performed to demonstrate operation of instrumentation and alarms, and that actual total system amperage loads are in agreement with design loads. A discharge test of each battery bank will be conducted. System interlocks will be verified to demonstrate proper operation under accident conditions. The independence of redundant power supplies and load groups will be verified.  ; . .- c ,, . - ,..,,m c . ~. Q' Qs-

                                                                                                                                            -c                                  ~

eu :;Criteria . Mi.c::,k@i;.  ::.%?q " .,5x%.,.$i&.g ,:p..  ;,.~.;n'\p'k :,.D .I' 7

                                                  .         ., -- - ~                                .

. u. -

 .                  Acceptance                                                                                                    ,%                               -        .

M d Jnse tion, neral , alarms d ih_terlocks jrpera :e th de/fded in , respo se to no 1 or si laced nput s Lguals. ull-load a design _ / attery bank oltage h mum

                                                                                                                                     ~

l

                ;'durdiondie                    rge          tests                                         trate        that        th

( llimit)and in ividual cellt ;mits are noi e eeded. GM % -

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SB 1 & 2 knendment 44 FSAR February 1982

                                                                                                                                                           .6 TABI.E 14.2-3                                                                                        '

(Sheet 34 of 66) 32.- 120 VAC VITAL INSTRUMENT POWER SUPPLY Objective '

  . TJ demonstrate the proper- operation of the 120 vac vital instrumentation '

power supply. Plant Conditions / Prerequisites <* Prior to loss of offsite power tests. ' Tcst Methods - 4 Full-load tests fir the uninterruptible power supplies to the vital buses will be conducted using normal and emergency sources of power supplies to

• tha bus. System interlocks will be verified to demonstrate proper operation.

Tho independence of the redundant . power supplies' and load groups will be . verified. -*

                                                 ~

Acceptance Criteria 7 - -

                                                                                                                                               .a
                                                                                                                                                             .~

LN - Instrumenta n, co ro s, a ra d in riocks rate e in

                                                                                                                                      ~           '
                                                                                                                                                         .V r::s a      to ormal o simul ted in                             gnals. Fu -load ests demonstrate q a

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• cyp of the

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s to meet itsQpign rec,h _ n.e. . s m m. n J --~ #- - n tiu rZov.u.wM C & M(4 Th7%'  ! L w h m d, r-sg su,4.uira 9.3.1.l.of. g p

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l'34a :e,.>,.y.4.;.%. w L ..&.i .

                                                             , x'..ixpg y, H %<;(Sheet.35'.of 46) i .

2 - , W. .,'.:.r ' .c~~ J ,> y:;  % u.. h.;. 31, , ,. F.. . .. , , -

                              -v'              :: a%:"

33. DIESEL GENERATORS Objective- .

          ..To demonstrate reliability,and extended. full-load carrying                                                                                                      .
     "M'Weapability$,

P-r5nta Condition /Prerequis'ites ' of. t.he ~ emergency , Y IY f diesel'_ '

                                                                                                                                                                          -k generato 3        -2 3
  . ktJW,3W$MLM-Ud &%*WIpM4uSf5M!dMM2,                                              Whore possible, diesel generator                                                                    .
    <kPrior,tocoreloading.                                                                                    l          d prior to loss of                                    ,

j*g. offsitereliability testing will be', j f%i@ comp Q ete 9yJ.jbf.Q. %pf e, j - 1s +3..  :,w.,. power, test.

                                       ~14,%yygpfg",q_Of~#dM?/.P'"J"?y              . q {fQ';:::g.                         :            f c

Test Method , 3. --In' p..':: q g>- System and cotaponent operability checks will be performed ot the diesel engine support and ventilation systems. . . Prot 9ctive features and , g u':interlocks cs . will

                                                                                                                                      .. . be        /
                                                                                                                                                          ~  demonstrated

• operable.

                                   - q;p y -a-M y.....,,

ga. p.my&c. :.. w.up ~y 5% Full-load-cal.:::f i ng capability for an interval of not lessth , - .. j with RG 1.108 position 2.a(3)...s . s 1.

                                                   .-    ...,,                                 -)

Diesel generator load shedding will be demonstrated operable in accordance with RG 1.108 - .- position 2.a(4). Diesel generator functional cacability at full-load temperature will be demonstrated operable in accordance with RG 1.108wit position 2.a (5) Diesel generator reliability will be demonstrated by per-fo accordance with RG 1.108 position 2.a(9). Accentance Criteria. The diesel generators operate in accordance with the require- l ments of FSAT. subsection 8.3.1.1.e and complete the testing l speci.fied above. l l

l. .

l l l l l , 1 ' l . . i ' 1 -

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TABLE 14.2-3 i (Sheet 36 of 46)

                                   .              ,,                      s: ,, . .H.L~ ' e. .i'ia.                                                                                   .
                                                                                                                                                           .:$ ::.9 .. ,,;                        ,
                     'p 343 FUEL HANDLING AND. TRANSFER EQUIPMENT                                                                                                                     ..
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T.) demonatrate- the proper. operation. of fuel' handling equipment. " ~ C '

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         ' Plant INNConditions     #dDDNNM.                                                               4$Mk8                                                                                                                                                                         -
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N*f'A~P$[N88.h'.Yi.?.sNYl'qj.

                                                              / Prerequisites                                             ~ ' . :? m                 -
         ~

G;7,+4%A Mc:1 % .+ M 4"+ G is C W 6. $ . _wWn? SM'"> s'*'**XL^ .& *

                                       ~

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                --W to         .'.5   storage
                                            - Owd5Gbd.ibs;115    of new fuel 7and                                 Qu2/,;)   initial4 core loading, .as applicable.

cabin.ftelfkyw;?ign- . > u+ :. ^*'if : ' v.-:

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f T.tst Method D.s.5 .'.T?rirai

                                                                          ,.       .           .           4; 5 N; ;rd.Y,W           'V' M '. . '"-rf ?=114.h v.ST- c2 - r.ns M.*d Jr. :                     -

Tests will be performed prior to core loading to demonstrate the functional operability, controls and protective interlocks of the fuel handling and transfer equipment. used for handling spent fuel. Components required for new . fuel storage will be checked prior to the receipt of new fuel. ' * . - * .... ,~-

• I. :Wi.M r2 !Sithu~'c3u:5W:pr1*rf521ti?.d.N.co.1nn4Q:s.;o 15x s19 r :: - +; ;-:  : = 2 -

Acceptance Criterie

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el. l'h d 'ng equi _ provide for. torage ra er d handl o ..- . hcs iesGo depigTed) _

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g TABLE 14.2-3 i (Sheet 38 of 46) . i

36. .. PRIMARY CONTINHENT STRUCTUREAL.ACCEPTX1 ICE TEST .. , ,  !

                , N:Wih':$ &i&jQ% Q W Q M Q 'y.*I"WE627.](',.z.m.., .d5?h$5:h,;;.p.
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                                      .tTh. O                               E                                                                                                                                I                                                         .

T& F- fi an structural' aceeptance veriff' cation of; them containment. ". ' J h. " C '. ' M .

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Plent Conditions / Prerequisites'

                                             ~
                                                                                                                     ~ '~~' .*~'                                                                                             I
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gi $ lb .

                                                                                                                                           -+ .. e,en, 9a- - * ' . [.              1e t~                  ?.  ':'I*'                  --
                                                                                                                                                                                                          '9. ;. -

Prior to inittal core loading. -,

                                                                                                                                                                                                         ~    i.4Q          / '--

<::X;g .;~' n, %. e,.;Y.pt,y :'suf Mf ? -* .T

                                                                                                                                                     .?:R.*.

Test Method

                                                                                                                     'u'                                                                                  "

l A structural acceptance test will be performed in accordance with Regulatory Guide 1.18. . . . .g .._... .- . ., .

                                            ,.,e,* 93-i<. Q fl*.}l:l1 :..;* -S M a ~

Th3 containment will be pressurized to 115% (60 psig) of the design pressure (52 psig), with inside and cucside temperatures monitored and controlled.

                       , c ec...W' % ;yr-:=,t9yyne}.eMp-,;. :y.:n 4,. . :.;, . e -
                                                                          ~

Structural responses to test conditions will be measured and compared to m pr:dicted responses, to verify that structural behavior is as analytically ] caticipated. .. . . ,y.. . , . .. ',.

                                                               ,      ?.'               5 - ,- Q ta p ,;i.".                                                                                            x
                                                                                      ' '                                                        ' ~
                                                 .                .                                                  %                   .. .                                                ,                                                                                               44 Acceptance Criteria                                                                                                     .>v :                               <& ,                                            '
                                                                                               .,.....;..s...v.....                                                                        .
                                                                                                                                                                                                    , -        ~ . . .           ,.           -

Tha reactor containment structure meets structural integrity design requirements, as defined by regulato'yr guides and codes described in FSAR . Subsections 3.1, 3.8 and 6.2. 44 i e

• 0 *

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SB 1 & 2 Amendment 44 j PSAR February 1982 'l TABLE 14.2-3 (Sheet 39 of 46)

              '37. PRIMARY CONTAINMENT LEAK RATE TESTS Objective To perforar the- initial pri .ary containment leak rate' tests.

Plant Conditions / Prerequisites Prior to initial core loading. Test Method Type A, B and C primary containment leak rate tests will be performed in accordance with the requirements of 10 CFR 50, Appendix J. Prior to the Type A test, Type C (containment isolation valve leakage rate ' test) tests will be performed at a pressure not less than-Pa (46.1 psig). valve leakage rates will be recorded and verified within allowable design limits. , o r' - Prior to the Type A test and concurrent with Type C tests, Type B (cuntain-  ; s ment penetration leakage rate test) tests will be performed on containment airlocks, hatches, electrical penetration and fuel transfer tube, at a pressure not less than Pa. - l Type C and B leakage rate results will be tota' led and verified within

allowable design limits. -

On completion of all prerequisite testing, the containment will be pressurized to Pa; while pressure, temperature and dew point will be controlled, recorded and allowed to stabilize. Test conditions will be maintained for a minhunn 8 hour period and, utilizing the perfect gas law, leakage race in percent per day will be computed from the changes in containment air mass. i At the end of the prescribed test period, an instrument accuracy verification test will be performed on the containment to verify test instrumentation and test results accuracy. 44 Acceptance Criteria B and C leak rates 5 and instrumentation tU.-*,nlilovable~ N sign limits as set forth in a aau s, l w. F.fA d Se.e b /s.Z,

                                                                                                   ++

H.N #rsyAFg $ g e70F4WE@$$ iD Nit 2 M N: dNN b 0ff b-

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TABLE 1442-3... y W  ;,,$ 7d f W

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T ' ;:# N ' J 41 G. ~~W..W*"' ' .2 * . '4 A . .. f. e- (Sheetr41Tof 46) , j%:#'.G 5}

                 %("$,2,.110}4,;ty)9%j;e$'W.gC.Sti.?E-W6-:?;:;m?

i @W.'; k. ,. . H y.S ( W !? '** *' '

39. LOSS OF OFFSITE POWER TESTS Objective

                                                .c.M im:.,U h/

N Y' '

     .%%.. . , ~ _ sTo' demonstrate the proper response of plant systems'to a loss...,.                                                                                                    a    'i .

Qs& Bf'oEfsite ouer. ' i Q( "'~ b.LO f' 2 c...,rg"o ;44 < ny.i.N,..:,.F, .. .

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h- ' E M'ft-W li q,a!' h.9'vMt%%,%%sl*J% Q .g.'. ,1 ; Plant Conditions / Prerequisites 'iff} {p,tpf M,t? .,.,J  %.4M GrA.F.g 7 Q .,, Y.

                                                          ~
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3 I_

                                                                                                                                                                                        ' . , ' u. '

Prio%4HIRfK'i*1J kitkikf> .kb.hhloading k. h. .h,- , b. , $$T*Ed

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[ ' Y. r oinitial,9

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                                                                                                                                      ,'M %

7 n " e ',-Test' Method SE

              ' %.( ,... x.p.mmg.y.NQ,'.4.+;%, p{g,?)s&%[2 n.;-a u-           ':         ' -
                   -Startup' operation of the diesel generator units will be demonstrated by simulating loss of all a.c. voltage in accordance with RG 1.108. position 2.a (1) .
                                 '                       4            ..

Proper operation for design-accident-loading-sequence to design-load recuirements will be demonstratedwill in accordance

           .*     Uwith RG 1.108 position 2.a(2). This testingThe                                                                            be conducted bus not being
                    .with one diesel generator unit at a time.

i $ tested will be monitored to verify absence of voltage. Load

            ..        testing of the batteries will..also                                                 be demonstrated.

T,n.'. .;.Q.~n g.pv~.c ., o, *Qn g .v . . . _ The ability to (a) synchronize with offsite power, (b) transfer load to offsite power, (c) isolate the diesel generator unit, and (d) restore it to standby status will be demonstrated in accordance with RG 1.108 position 2.a(6). . . , , .

               - - . , , . . .     . _    s. . . . -.. p.,. . e , . w .. . .                   . , , . . . , , . ~ . , ~ . . .

The capability of the diesel generator unit to supply emergency power within the recuired time is not impa2. red during periodic testing will be demonstrated in accordance with RG 1.108 position 2.a(8). Testing will be conducted in which both diesel generator units will be started simultaneously to help identify certain common failure modes undetected in single diesel generator unit tests in accordance with RG 1.108 position 2.b.

                                                                 .. ! 5                -                             .
                    . Acceptance Criteria                                                               '

Diesel generator operation and circuit breaker sequencing are in accordance with FSAR design requirements of Section 8.3. l w e

                        ~

:.~ > -

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                             .                  :-   ~ .           .,

e~ e l

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f. -

w

. ac . M p g~  ; ;4.p< t: <n

u. . .

     ~
              ..    ~p.. mw - . 4.

m );: :g.::- au;,.y

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7 .cy.p, c.q lcq .. TABLE 14.2-3 - (Sheet 42 of 46)

                                                                                                                   ~c    ..        .
                                                                                                                                                                                    -e

40. . INTEGRATED HOT FUNCTIONAL TESTS f%

                                                                                                                       '.f.]l , ' ,f.[j. a '& .'.                    -                :.

f' 54?,:kQf&l'E  ;.

                                              *j " J CTh' " **'lg2                              [ &p4 g.yyyg< FN'W g:/[8RS$Noi,"         ,                        ;; i,;'; y$ye:~,4)    -
                                                                                                                                                                           -        1.'

Obicetivee . 4

                                                                                      ,;-.,    Wf                                                                                   ~[           E
    .yrr+m-e#5:5 8                         .,,[:. % .                      ,

pri' mary and secondary instrumen-ratures and pres- ', M-Tbr. verif'y-- theiproper. operationi of variouar ~ i O tction,Icontrols and components at normal'operat ng tempe functional , Y curso and to, provide general guidance for the conduct of hotWdi 47"~7^ - -

                                                                                                                                                                  "("'

7 W ~ ~ . tu ting. . .N9':Qt i&gMW.%/%N$g%gl}{,#Y'a@& ['. .

      - .::ft:M? -                               q h W k.q6s!-. g ",~ ~.?fz?N; ' ~ '" ? .

Pirnt Conditions / Prerequisites. . ; ;. 3 ,*' , "'

                                                                                                   ' i-Prior to initial criticality.

Tact Method

                                                                               . . .                                                           m will G:nsral guidelines for the conduct of the hot functional test progratemperature and                                                                                     ~

ba provided. Following plant heatup, the reactor coolantA series of tests, i prassure will be maintained at normal operating values. eration. k m which are listed below, will be performed to verify system op Q

                              'GP-Qh.k.               T : " ' ':q:iM. ~ ..:M;p . n                                                                 ility a.

Dentnatration of the pressurizer pressure control system ab to ez.intain RCS pressure. ~"<.~c . .. %

                                            .    ,a          _..

Demonstration of the pressurizer leiel control system ability

b. i r level.

_ to maintain pressur ze . c. Demonstration of the RCS leak. detectica capability.  ! bility. I 1 d. Verification of steam generator level instrianentation opera A instrumen-e. Verification of selected primary and secondary plant cation operability. l t f Demonstration of the Remote Shutdown Panel to maintain the p an in e. bot shutdown condition. ding g. Initial roll of the turbine generator with main steam, lve operation.inclu verification of turbine stop, reheat and intercept va i ts. h. Verification of pressurizer and main steam safety valve setpo n

                                                                                                   &                              ,0A                                    ,

N ' mdanw> afi .g f.D

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                 , u ,.,      ,. aaqwqy, hwy}Q&N.Wh!'                                            '

_ r--

                                                                                                                                                                                                                                               ,~
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                                                                                                                                                                              ..                      me .c;n.                                          ,

ff CY. *

                                                                                                                                        .} u Ja'f*.*ltW.a. February 1982 a -~ ;

O W

                    -0 '.:        ,-+<                                    .qR.p,                                   r.      s:      .t;J}.E}22:                         -
                                 ' ::.-M:Q.c,4.5.'                       f*>'v      'jQ    . pl p W:45 < -{J'M:'p ' '
                                                                                                                                                      ~ ~ ' '

4 n , w; M.t.;r.3.,.,w m . TABLE 14.2-3 (Sheet 43 of 46)

40. - INTEGRATED HUT FUNCTIONAL TESTS (Cont'd) nW;7,:h'A%"EiNnfy,'%1;Q.*h* ,q$%$M}qlQ'Q.*1{Q'4tQ:EC'dW.*T7IQ5.$, Y~

                                                                                                                                                                                                                                    ;.. + .

gin.additiontothe-above,othertests.specifiedinTables.14.2-3.and14.2-4 "QasTheing, performed.during hot. functional testinge will be: performed at- this-

                                                                                                                                                                                                                                           ' f.},
            ;,.fitime.,{,Af ter.,ther, completion of at' temperature- testing,. the plant:wi1L be-                                                                                                                                ,         .
                                                                                                                                                                                                                               ..,.',         .;g n                                                               2 tisfac                        demonstStiqn of sy

_ _%inst _ tior op a or nee w A ^ Sa reou ^frwene F es.; l

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g "E O D '. ~. f- t , f *C.**/ 183 0 ., 4 , . 1 _ ' ' 1."'

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h ~ w w.w m..g.ex$.. Y

g. , .

wt

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                       .                 ..     ._._...._,+~,,s..,....~.~

t W Q.#sul . A AU 14s-i n - . . _ . . ~

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                                                                     * * . *          '.s      e,E     --===w---.-.....                     ,,           "_,

plu,,. M $ u~lr x. Z E T T I t-

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FSAfl. N 77I

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                                                                                          , Q. M                   %r .jf m:n          A       acn t 44 d

February 1982- j

                                                          .[        SBf1        4    2;    g'?      x ;,;.?r q $f*h C hdMh
                   $mjp'                                                FSARp.

ft! f4.; ?Jh fy# . =._::r g57%j:k

                                             . u,-e      sc L,.9( : .2;. W:               3:, d.     .L?

a.x. >:.<p  ;.< i.e. .;' ' ':~. + . ;p ?L ,c,,C~",- w

          . .,. ~
                 ;g          ,_
                                                         ..3
                                                                   . .        3.    .

TABLE 14.2-_3 - (Sheet 45 of 46)

                                                                                                                                                                 ~.

42. . INTEGRATED PLANT C00LDOWN . . . FROM . . C . .. T HOT FUNCTION WRFW:Dj - .

w- ' P.m" ?!.', 5.n. n

   --: ?'$.% N $'y7p'j 5,' Q Nfi f {s? '?':

J - m-  % ', .

  .S :.?D&%ut'th$?'}5&;N:M)vy.y@5)N{< Ap             M v.                        r
                      ' -        ' ? ni-                            .?gn       $1 &E.Gbw?8 5%                                                                                     ;     "'4           g

• Obiretive- - - 9 ipisv f

                                                                                                                                                                                           ,,f.
                                                'h2              r:ingsthecplant:froe normal operating, ;?,,d f,4'Tif'                                                    ,
  ;;;Tr     demonstrate.                         the.        ability,          to.       ld    shutdown h,40,5 l50&.. :$.lu is+>

conditions.j'l$.flhk&5'h%$h,

   ,ltemperature and pressure to co                                                                                                              m<               e         c' -+

ffMW '

  \N%

Plant W2 Conditions& T.$ N $b 5 hN$$N?b$.

                                 / Prerequisites n4W4                            & Y &hf?$f${'4p,p$30.0' completion of 6,Ar,f"
         -r..   -    1;. . - :, ... . : . H.m :. e v?mW5W iV X'N.                                                  i Tha plant is at normal temperature                                        >: - and            + pressure follow ng t e hst    functional testing.                  ,.

Test Method _ i g steam dumps and Tha plant will be brought to cold shutdown id conditions us nDuring operation of the its-heat the residual heat removal system, as requ re . d to .

           = W at heat          removal systeg data will be collected to verifyAt speci removal capability.                                                         functional                tests.                                                          -

allow the performance of specified hot a n~

                                                             ~ :.         ww                .
                                                                                                                                                              ~

q :.w wi ~,1.:- . :, . f i Acceptance Criteria # x

                                                     .                                                                   in accordance with                                                 .

P

         ~The plant has been brought to cold shutdown conditions                             -

44  ! l nsrmal plant operating procedure:. ,

                                                                                                                ~
                                                     ~ m. e.

3..<-.,--

                 -. , m..g - , . . . . .                                                                                                           --           --
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addant a and k &

           ?;g'e & s n. W                                                                             f S'A0 M/0.f                         g /ud k .m saAd.                                                                                -

D , f

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f . . _ ,, ~ A,, N  %~

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• m

_ ~~' T M ~~ D M*:dk:%l5 r Y {,i/{&$$ f }J5 W #-( 'j b '

                                                         %     - . . - . .   ...--._m     .- h - .- hh h d ash.asm             s rd K w . as              16 h i

SB 1 & 2 FSAR C TABLE 14.'2-3 (Sheet 46 of 46) 43.. REACTOR POST-HOT FUNCTIONAL INSPECTION Objective .

                     +

To provide a sequence of operations to be followed af ter hot functional tacts to disassemble, clean, and inspect the reactor vessel and internals. Picnt Conditions / Prerequisites Af ter completion of hot functional testing and prior to initial core loading. Tast Method Instructions will be given describing the required steps to disassemble, in;cpect, and clean the reactor vessel and its internals. l Acceptance Criteria \ n : ;;ee a. .;_.u cia.oing.ana I. .rou.ons aredI SfaEcrily - h % <> v k (Wtdi.vt". 6 N (242++'M db D ( t rm a a LntnM mw>rm ~ kin.Wx JL BM &ak. J.961).E.4. -

• l 9

G t

 %   a

• 9 * -

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~

g 3 ':7.,g, g

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                                                                                                                                                                                                                ,3 xe'n, ?.R W.,9 ; ,,-e o:tms,4% QW q ,1wsan-

w. .

                                                                                                                                       ..e y g.m.s; w.;y,w':w <y9':                           ~

w =e. c '" ; ' '. f;f.

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~. .,y,y.L:W;ya.m:s;.si,%t'R::; 8

p. c, ; c+;; , , . , . i g a .

p j f- ff <, , d  :: .Ym.:h.W%::;:?,

                                                                                                                                     .s 2 v.f TABLE 14.2-4                                                                                                                                .

(Sheet 1 of 37)

                                                                                                        ~
                                                                       ; .'                  .        ACCEPTANCE TEST ABSTRACTS                                                                          *
                    . -,. .                              .- -.                      6... .s                                                                                                                             -
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1.55~E6#K63.Jntudex .4W:%. . .w

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                                                                                                                                                                                                                                      'L         i:           -5
            * [%   e d^9Iihjk- W .!L.;,. g$ 'J                            _

E.5F~eedwater-System-' 'jI '~.

                                                                                                                                                          ? eg'k@, r.95i'. Qf~
                                                                                                                                                                                                    -                                            i/         :Q
            /               I.-

i 'fa;[ $1h[, pip h. Uj?shYU.'.$'?. l;l,7. ',$ h 5&5&N5$5$ . .

                                                                                                                         .. ?

l$$'h'4 h0 + 7 6A ' C: ' '; - ' ' '? . N. M-po . 2.- Extraction Steam and Heater Drain  : System 'l .Ybig:.

                                                                                                                                                                                                                                                       ~. ,.)

hf

                                                                                                                                                                                  .F h ' 3.;b$?$hkE{Wkah$f.ff #h,&m.e Condensate System . .- '
                                                                                                                         -4
                                                                                                                                 ~
                                                                                                                                                                                            'b r, i,%>.%, y A.
                                                                                                                                                                                                       +

4. Condenser. Air Removal Systems u e.;,c, . ,.,-  !

Chemical Addition System

                                                                                                                                                                                                 )

5. 8

6. Circulating Water System -

                                                                                                                                             ---t
                                                      .. .         m                       .
                                                                                                .,a , ,              :p

7. Secondary Component Cooling Water System i ., -

                       < p -w, p,,gp .:p z,7.,.,g.y, ,;/g,c,,g . g . . , ., ,,. , 9 , ; ,                                                                                                                                                                         -

10

                                                                                                                                                          , h . t!." . '                                                                  ,

8. , CVCS .1,;e - Letdown Degasifier'

                                                                                  . . y.. . ._ ;. e,a
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g_ .:r:. ., _..  ?,,, c-

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9. Reactor Makeup Water System >

P ., . Q % r* 10 . Sampling System

                                                                                                            .                 .:       c           -
                                                                                                                                                                                                      ,3

11. Reactor Coolant Drain System -

                                          . . . ,                 - n.            . . n .. . w. r:
                                                                                                                         . -.         v..        .    . . . . . .                                  ..g

12. Instrument and Service Air System .

Ib

13. Fire Protection System Ile

14. Radioactive Caseous Waste System

                                                                                                                                                                                                       \1

15. Liquid Waste System ik

16. Spent Resin Sluice System N

17. Waste Solidification System Zo

18. Boron Recovery System b

                    -       19. Steam Generator Blowdown System

20. Waste Processing Building Ventilation System f2.

21. Containment Cooling Systems 2y i 22. Containment Purge System '( t(

I , N' # s

                                                                                                                                                                                -*K"".
                                                                                                                                                                                             .,               e  '"  M' ' 'Y'  e"

• fT4'.; ."

e %'~]' L n p uw -. . , --S er" T "I '

                                                                                                                                                                       ': V+    5 * ~ 
         ) 'R.       *ff$~h**'N$$$Q&b}.h,'&&hf0.[-T*l?Y, iM.b*N'-                                                                                             o

TABLE 14.2-4

                                                      ~

(Sheet 2 of 37)

                 ,c                ,-        .
                                                     ,t..
                                                                              ..._,.n 4,'* Index (Cont'd)
              .: rim:j.t .:y M.z.t i FO W:.-%M :, m r y y v. Q ,.-                                                                                  .*;. 4      .. g., g .                  ..~.                      .

23 ? Primary Auxiliary Building Ventilation: Sys*.em- .

                                                                                                                                                                                                 ~ ; Y+

QW[.WMN'a%iYUN80%$$kk$%%%t*;'NEtWU..hEYb5$hiSh;A 24.; ;

                                                                                                                                                                                           '                      W -N* Y.' . '.

i . V.;-

                                                                                                                                                                                                                                               ~'"

Th, Electrical

                 $ l@MEEfW-f,UDN    Penetration-.Ares: Aiz: Conditioning; System 25 t Turbine Building ventilation. , ...                                                                                                               v   .'

• 7 I.,.

2 $

                                                                                                                                                                              .$,p>[."A        ., h!.

[ " 2d~7 k / .f 4 [y$ 7 iNJ i5$

.9 M% . E.; .P Q]f@u,,

g- f5 t26$'.5h550A$3"[6Y$?$%? " Rod Control System ' _. yyMhg{8.y$p$f$hh 4 *p b.% g e. . _. . jf.r. -'Y.YN!$'f' f*f. ' . -

' '- K t.':.4dCM%n@%5?. N$" p] 75,:l}_f ~g'

                                                                                                                                                                                                                                       ~

rlt~-

                                                                                                                                                                   , .7?A. ' . - . f^4

27. Individual Rod Position Indication

                                                                                                                                                                        ~- '
                  . a.       .: w .           ..z y .u. 9. m...w. w ;+ M. ,,,.:. w .'.. .d. :. % .'                                                                                                 .
                                                                                 .. o
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                                                                                                   ' -- .<                      s             .

A

28. Computer y-v

29. Primary Plant Instrtamentation II l 30.

Radiation Monitoring System

                                                                                                            ,.;.o     s..;
                                                                                                                                              -J
                                                                                                                                                      ..'. e.,

WJ 6 L '-.

R

                                            .w,    .na                . ,.: ,. ~m,. , . u, iv..ge, kVe'd. "%,.,.a?%. n ;34..' .;Y                                                                                    ."i
        ...- ,. s.   . . . ,e .;. . . . ,
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33

31. Seismic Monitoring System r ^4.N 4*. e . :Eq - 3 " ., "'

         ..~ y x . :. 9 y 3.; n ; m .g..ygy.q4fr$BQsik'M,T~i.fe?.apy.L;',^ , '}
                                                                                                                                                                                                             .'*            ~ ,                     -

l _

32. ' isC Elecuical~uis u ibuciour - . . 3 y

e.i. y .~. .y . . .:g;; , ,_.. 9.u

                                                                                                                                                      ~

3b

33. Communi, cations System .

                                                                                                                           .':.~;:         '.'           . . .        '
                                                                   ,,            :> :.[':7         . . .
                                                                                                                , li%. t 1-             *
                                                                                                                                                                                                  -3g

34. Emergency Lighting l

                                                                                                                       ',.?(                      --         ~."-
               .          .. 4-          . '-           .

m4. , e.- '>..w;.s . .. ~ . . , . ~ - ~ ~ n

35. Polar Crane s ;>. t . .'< */ . /

B e er. 6, -

• h e

i

                                                                             =

g a .,s 4

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[

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 -                                  Qi n 4                         [q&%Q 9 *1              .SB 'E& f 2J..S"$,.y#                b,fL.;k.!Amendmtnt
                                                                                                                               #- ' " ' February           1982 44 "th'a .wMC r-         ;','6M.                      , ..., ?Nf M .FSAL ] .i-                                                    -      '
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w, : 4-7;p , _s., 9 9: g _ . . , 3 . TABI.E 14. 2-4 ' e (Sheet 3 of 37)

1. FEEDWATER SYSTEM

: NF;::, ,y;'iQfMLnM &&~Q?,.bfb. . ' R.

Nh{fhi&:a.Q;.

• wbN$fNbb['2 ..

N. N b eteNb Nk'k ja Tv demonstrate- the properc operation.of~ the .feedwater system f

                                                                                     '                                                                                    3.
                                                                                                                                                                         ~ ~ - ,

%$ ' ?.

I j ,

hPlantConditions/ Prerequisites'?$5,ii$Rb.*f*  ; f, .g-hq.; .g.y ,g..:;. ,kWL%iehsSQi,$;Q,

                                                                                                                                                            . f.s
                                                                                                                                                                               .-. .J. .
        $g WA-;e,M*c ~n nwid va<. iss?QYI f%#G ??W-f: WP<%Q.                                                                           '?"~.       Wf

• Prior to and during hot functional testing. . ._'

M.Gif : ig%J .jd, J.q'af?' ,.f7f..[.Mf.s U. ~ Test Method

                                                      ~
                                                              *-t,C :T.',u;Jy v.f:/M { '                                             .

Prior to hot functional testing, the operability of the startup feedwater The control and performance characteristics of pump will be demonstrated.the turbine-driven feedwater pumps will During be hotoperationally chec extent practical using the auxiliary boiler as a source of steam. functional tests, the operation of the turbine-driven feedwater pumps will , A. be demonstrated using main steam. , . , . _ j

9. 6ryg.g. : ; t.w,>~.s u .4 . ,,&.f.. ir "" '3..pg. ,6, 4_'#, .6..:

W' ..a. a,<....,0,.~-

                                                                                                                                                        /
                                                                                                                      / '

Acceptance Criteria > W l J e,startu feedwater pump meets o ceeds(desisr6'hlow / and or1Insus[ M ments i

                                                                                                           ~/

['  %'

                                                                                                                                        /               /
                                                                                                                                                          /       ;

l , The\ turbineydriven feedwater , pumps evelentmeep dur1A or , exceed hot funct.ional (dggsi t{n ting._ flow andaresgure

          - ("requiremen.cs) at opera' ting co'nditions N     /                                                                 l entrols, alarms and inter ocks operate (as'designedj "j Systemjnstrumentation, in response to normal or simulated input signals.                                                                                                                       44,
                      %N M                                            N-x.

h 6-A. & F $ 4 W to N.7 m /6.y'it enthas pumbJ doy ho-t ~-ckhd

                    *ba f>v .                                                                                                                                                                 .

J O 3 j

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                                                                                                                         *                -1 E        4        V* ". [5lh

                                                    ~ ~~

7 SB 1 & 2 Amendment 44 FSAR February 1982

                                                                                                                                                         .C
                                                                                                                                                           ,.g TABLE 14.2-4 (Sheet 4 of 37)                                       .

2. EXTRACTION STEAM AND HEATER DRAIN SYSTEMS i

objective To demonstrate the proper operation of' the extraction: steam and he'ater. drain-sy: tem e(uipment. Plant Conditions / Prerequisites Prior to hot functional testing. Tx t Method  : Functional tests will be performed to verify, to the extent practical, the proper operation of equipment associated with the extraction steam and heater drain systems. , Acceptance Criteria [i The extraction steaur and heater dr_ain systems performance, to the extent .. m pecctical, is in accordance- with -j ?:;w -.. mm in response to-simulated .g input signals. i - - 44

                                                            ', (TJAk e$ secTa>n /d.2.2.3 & /O. M '

k -_._ # e i a 6 e t i e g

• e sA g A fr

                                                                 -F *                         '

_ _ _ , _ _ . _ _ . - - . . . ~ _ -- SB 1 & 2 Amendment 44 FSAR February 1982 J TABLE 14.2-4 (Sheet 5 of 37)

                      -3.                CONDENSATE SYSTEM                                                  .

Objective l

     ,           To 'damonstrate- the proper > operation of the. condensate system.

Plant Conditions / Prerequisite 1 t. Prior to and during hot functional testing. _ Test Method - Tests will be performed to demonstrate the operational perfor==aae characteristics of the condensate pumps, the hotwell level control system, and the condensate makeup water system. Acceptance Criteria > - - - e Conde e pumps meet coed est /s o rat' s condlitiins evalent 'up to su __ nc flowdingand hot pressure 6eouirementl at ction testing. !J (.S em inst ation, coner

                                                                                                    /terlocks a                   s               -

_desirnej

                                                                                                                                                                             ~

alarms o rat <

              / in response to normal or sinu                                                 d input signals.                                                            I
                , _ --         .s-              /nn,p                                                                   -
                                                                                                                              ~S.-                  . - .
                                                                                                                                                            -            ~

p Ww

• g* Q ffAlf W lO.W.Y &

l l M af'* N M M "% e 9 S e W W

O

                               ~~ ~

T ;, . ',~ k {}.Q. Y }T -l iQ-*... . p.+( : > .4 i ' -

                                                                     .y       p_.,-                    . . , .-

TABI.E 14.2-4 * (Sheet 7 of 37)

                                     \
                              -.-5                    CHEMICAL ADDITION SYSTEM                                                                              .
                 .f$ &Y&&?'f:.Q3&
                ',0b3ect1ve.                                            ,s IM&&fW h x. Y S ' f.fhl                                                                  .k' n [ .. _
                                                                                                                                                     ,f k. hg:gxk..-x 5 y:e{. ::.:' . w. ?              '

r%W$~7ts v bd%'kN .. ihs !$5.W$Q%%$h$.Nl*Y,"'?? ' .

               $Ttr demonstrate- the. proper operatiotr oF ther secondary p1'                                                                                            a nt chemical' addition
         .    'Tsystema..s.,- D P ,'i ~ 577
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                   . , ,         ,                           .    % a-                    -         L.                                             t           , . . .

i. ., ..~.,'y:.s.4, '. ":; .fp*Q 41h , k _.:, . _ RQh,y' gag.'y ;} 'h 9 ' ' ~~L ,'

• Plant Conditions / Prerequisites - '

5 i w, . r :.= a..a a~,s-

                                                                                                            ..                  t:e*4.06%
                                                                                                                                         .~m' : ? .                                                                                                                                                                            ,
                                                                                                        .vik. . +., w*.
                                                                                                                                   ~y;,
                                                                                                                                       ~ ' p.: * -

Prior to hot functional ... . testing. - . ..u r Test Method Functional tests will be performed on the chemical addition pumps and > associated instrumentation and controls to demonstrate proper operation. pk Acceptance Criteria' Czh -

                                                                                                                                                                                        - [.- -
                                                                                                                                                                                                           ^
               ,_p.                                                  _.- -- . - ' ~ - ~                                          ~ . .' " - *~'-                                                             w 3 The chemical addition system pumps can deliver cal' a_ted chemical volumes

• to the associate % eus normal
• Jec_.

on poi at@signcoAtion). d System i t entation, o ois, inter 1 s and ala a erst , t n the course of sampling associated system fluids. -

                                                                                                                                                                                                           '       ^-

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                                                                                                                                                                                                                                                                                                                 .,v TABLE 14.2-4 (Sheet 8 of 37)
                                                                            -                        - * -g                                                 , , ,.-    .                                                                       ,
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6~.

                  -:AV'JCIRCULATING                                             WATER SYSTEM                                                                h .w .% . GM. M. 4 .1                                                                        Y
           .QyJ.L ng 3:'                        9*ws
                                                   '.y                            ;qg, ~ tj %yA                                                                                                                                            i e:ww          %        ;r&y ', -   '
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e Cy'tf.% %gg< SCI

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           #46&*h5'$54$k.3.                               kni.4                       .' s b h k , . .v 4'                                                                                                                            '$Y$yp$5bN.'~h
                                                                                                                                                                                                                                             ?                             h h iN ".  .-

To dominatrate-th'ee proper operation of the- circu1~atibgrwater syntesa. ~ ~ ~ . '.i. l%p 7 ?..f:

         Q82i&&WNWh?$2l%$&

Plant Conditions / Prerequisites ^ ^' &%Qiskr[gl$?i?${

                                                                                                                                                                                                                                                                                             .$l%.  ?.~,          :.hY'&
                                                                                                                                           -;y                 .
                                                                                                                                                                                                                                        ;i WSAt'fM% yW                                  .
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                                                                                                                                                                                                                                                                                     , n - : ~,~          ~~< O
                                                                                                                                                                                                                                                                'i 1, .M;.      -

Prior to initial core loading. f ;Q. ,. . g. f S;, d:#,k $ i mW , W.

                                                                                                                                                                                                                                                                                         ; %  y'*        ' e;; M   . .F"..
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                                                                                                                                                                                                         'h.'

p,e eo h [ *

                                                  . ,           ... .       ,:. m d ; + .
                                                                                                                                                                                                      ?-

Functional testing of system components, instrumentation and controls will ba performed to demonstrate operability. An overall system hy E-- = '

• parfornance test will be run to determine specific system operating p:rameters and response during steady state, transient, and backflush cperational modes Proper operation of the pumphouse ventilation system will C.RTiy#r-@,hf-

                                                                                  r 9.e.,.w.:..

h angppp. m..,h Acceptance .. yjJ h,h,h' n .'.$'N\ .hc[ Criteria ' ~ r- , ,,

                                                                                                                                                ~
       -tisfacto system per rua e during various                                                                                                                Ass of operation, e. M 1H:sttreatmegt, start and sh tdown, shall ed A.

nstrated.. ,- 5

                                 .g.       ,
                                                    , / . . . .. ,                    .                                                      --
                                                                                                                                                                       .-                                                          4.
  , System instrumentat' n, controls, alarm and interlo so tir-response to no                                   1 or simulated ate @ signedl ,

t signals.

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SB 1 fr 2 Amendment 44 PShR Pebruary 1982 < . J TABLE 14.2-4 (Sheet 9 of 37) 1

                    -7.           SECONDARY COMPONENT COOLING WATER SYSTEM I

Objective To- demonstrate- the proper ~ operation of the seco'ndary component cooling water (SCCW) system. ' Plant Conditions / Prerequisites Prior to and during hot functional testing. Test Method Prior to hot functional testing, system component operability checks and control system functional tests will be performed. During hot functional testing, data will be taken to the extent practical to verify that adequate cooling is being provided to SCCW components. ' ~ Acceptance Criteria i ~

                                                                                                                       .   (
      -                                      ?

j e secondary component a meet or exces flow and pr.ssereme=1remene2.) g System ins entat' , ontrols,'a andQaterloc ratefa~s desig g l}' in response to no 1 or mulate input signal ,

                                                                                                                                                             \

The system supplies cool'ing water to all associated heat exchangers,.

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g

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1 s w J L VSAA  % k to A.No.

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1 l SB 1 & 2 An.endment 44 FSAR February 1982.

                                                                                                                                                                    .~

i.*C. kQ TABLE 14.2-4 i (Sheet 10 of 37)

8. CVCS - LETDOWN DEGASIFIER Objective To demonstrate- the proper. operation of- ther letdown degasifier portion of- the-CVCS.

                                                                      ~

Plant Conditions / Prerequisites ' Prior to hot functional testing. Test Method Functional tests will be performed to demonstrate the operational characteristics and performance of the CVCS letdown degasifier. 4 Acceptance Criteria - The let own egasifier system rat in acco ancekt sys

   ,   All pumps a_

ves in accor ce th(manafaVeur ' m -m p scatto -

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w 44 U' 1 1k. M <~ ws%W

         %% F5A2_ S*>>4ech 4. 3. 4. 7. e . n .

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3 "~~

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3l*fca-oD[k'M)%..~.. kY'NdfY_-

TABLE 14.2-4 (Sheet i 11 of 37)

                                                                   .s.        -        t a' - -              .v, . ;:

3, p.i 942 : REACTOR HAKEUP-WATER SYSTEM .. y.Q- ,J j! >& -x.f * < m.<,

                                                                                                 * ^- *                            *                                                                                                     .

qOb3octivey $hjjfy' - g,f. 'N{h' ' *ffj"h$h:h. .

                                                                                                                                                                                                                                                    ; g-?? ;.
                                                                                                                                                                                     %Af l             ,  ,c;,.,;.y s

5..rij: 3 M S 9d$/5d M N N N < P. WY'N S$$ g <ND gg. ' ZWTut demonstrats- ther proper,' operatton of'the-reactor makeup water. system.. WN [5 . CC-.i hjs,3

        .hY,%WIWWO%Wii8$*'$(kWbh$                                                                                                                   -                      "

fri! Plant- Conditions / Prerequisites ' - ' t ': E ;, ,. ~2 2.&g .*.&ik h l$D

       "'*%*i9%p Q "JE6 G ~% SN W 69riffR.g

a. Y.

gx Q. .x ., v.: ' .JT.e?f.,;. %f~'& . t<

                                                                                                                                                                                                       .*      tss:W+vph           c   .W  <W   M    ~&c   ' n
             .Prtor to hot functional testing.

t;t r p  ;:. -;r,- ' .

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re '. - 2 '

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              'hl'NSkbONN.$$h$f'hili{[)Pe                                                                                                                :: ;^.'L:.?}f '{l . h ?; Y ,. g . /.. u.

Test Method '-

                                                                                                    , ,,. :.,                                     -         1^                         '
                                                                                                       .l 9 . .-                                  - . ). ,*

Functional testing of system components, instrumentation, and controls will be performed to demonstrace the ability of this system to transfer water to other plant' systems. . . . . ,...s, ,, , Acceptance Cr;iteria

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                                                                                                                           .. ... g~.,se,2,v                                      <<

The reactor _ makeup water pumps an rCm a . ~ _- -h = % srinns) and th Ives syst func 'on in accordance with ope dance with Gyatem g '

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, w L ,cr 7; .g.y g:, qw; M_ <5L=r. ' . D,Q't.'-k_L Q';>f-X*"Mj'DQMfrKTHDE S!$sNJ                                                                                                        'r- ? i
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TABLE 14.2-4 ~

                                                              .                                       (Sheet 12 of 37) 10        SAMPLING SYSTEM                                                                      4.M                                  'b g ' ' MY n.x ' A - C '6 . .- .

[ if-,F'.the.propeer

                                                                               ~
                                                                                    . ~ :,. of'           yy.g cuaI.ys1s         equ1puent ., operation.

that plant . ':sampliny systems, and, instal.Ied. *-

                                                                                                              ~--ua                        :r                                                                                            _          ,;

yg,g,f. q q xg4 Ze,f yl?c ;.;c ,:g.y' ;: '.

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         '%t'fLW.'?NGtt i                                                                                                                 "
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a fg & &  ;.;kS?:)l'; I Plant'~ Conditions / Prerequisites 4, q %: ' . c.lh?;:$, :D;,$

                                                                                                                   '. . n                                                                                                           '
          . re-;. , .-r n..wes-). : -s.+ %%F-:M N 4 S**'                                                                                                     ,
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                                                                                                                                                                                                      'p g <' -                       .c This        test will be performed during operation                                                                                                                    $$.j'*     '"'                                                   ,
                                                                                                                                                                 N ' '                -                                          '                      '

of the systems whtch are served . by the sample system. The major po tion of this test will be performed during hot functional testing. _ , , T:st Method 4 !. _- , Samnples will be drawn from each of the primary and secondary sample points to verify proper piping arrangement and function. The installed chemical analysis equipment will be operationally checked to the extent practical. _.

           . - =.    ,

np.q::6i,*gy;1gpy t..g.%..Qg  % -).y ?., .(pcz,p: .;:....~..:.t9 L -.. . . -

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Acceptance cette ta -- ...

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m 5: .e 9n.k'4W ?%q lw;&M*ys.v,'P;r.f'.  ?,*: * . .. .L. G** y .-;;- :; Sample point identification and piping arrangement has been verified. .V

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   -.m     vus                       at                                                n:p.;pq : .;;t.:
                                                                                                                                                                             .Q                  , %,j The sampling system operates N1 accordance with the design requirements of FSAR Section 9.3.2.                                                                                                                                                                                     -                              -

44. l -

• a ,.

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TABLE 14.2-4 ' (Sheet 13 of 37)

                           ~

11. REACTOR COOLANT DRAIN SYSTEM . . . .

                                                                                                                                                                                                     ^

r~ -..' 7,;gTogdemon,stratac ther proper .operatiour.oE ther reactor coolant- draizr;syscem . ~

                                                                                                                                                                                                                                                                      -@4

[iY

             ?PIant-  N MConditions      N k M/ ^Y                              M kd, Prerequisites                                                              a           -

h,h. $)h$$$f.w [,$,7.rlTdp?),h$j'CIE.h$$. - . n

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q_. f-smg4 - s .. ;%'MQ?i

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y.n x a . 4 s. 4u ~291-.. n:%

           ;,NS 46'WW%9+%%:i4Gk%MM440u%i?-                                                                                                                                                  . ~ Y.                      M&. " ~~*'^T      : ^ O" %: ?M
               Prior to hot funetional teating.'                                                                                        .
                                                                                                                                                     -1+cd 1 i T. ,~ % .' ';c~# - JO . -                                         ~' '          

5

              / Test N Method    N N N N f[8'$                                         , v .g, y g h$ %.n qimar',                               ,fh, g D /d kar Wh$hhh:;D
                                                                                                                                                                                - ; 1-5   -
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9. c,. . ,,-

                                                                                             . .          .- p.s.
                                                                                                              .        g , ,e.

c . . .::..--:, - The reactor coolant drain tank, pumps and associated components will be functionally tested to verify proper performance in the various system operating modes. . ., .

                                                                                                                                                         ,_                   ,                                                 J_,,
                      ~.-        -,n~.                                                                                                                                                            *
                         ~

v .,; d c -.+?M S., m?:M wa -s 'em,.-  ; w ;) g:r: S > .,:.'..'. 6 s . ~ ~ -- we- n;a w A~ -~:*.- Acceptance Criteria '

                                                                                                                                                                                                       /                                                  -

Instrum/n' tion, controls,' alarms and interlocks operate @ esigne in response t norma

4. .

                                                                             - sism:1sted,,ib c signals.

2;; u .n . ~

                                                                                                                                                                                                            \A (.                                             , ,
   --           The              e abiN.Vr)of the re cor coolan                                                                                                n system has been demonstrated.
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Amendment 44

                                                                                                                                                                                                                                                                                                                                       ~

m. 4 , ...

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4..' .F. eat e:U .. ..n.%u

                                                                                                                                                                                               .t.

p . M: a. Februa77 1982 t . . a@mM 'tM: .1.,

                       ~
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. - m ,.x.  % V; 7.. r i: .6 ,y

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                                                    .-             ,                                                 n-                                                                   .                                                                                                                                              4, TABLE 14.2-4
                                                                                                                     ;(Sheet 14 of 37)                                                                                                             ~
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• s-; . :s .. p.s ;s , ,.-.mes ,p. .

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                  . . 12 f g . INSTRUMENT                                   :--                  AND- .

SERVICE .p. AIR SYSTEMS:#' ~G.d $. Q M , jg, M <& g- gyy, 2.1.'.,~. . g 3 , .j, - Objective c - $ m g ' y;gM'g{ggjpgicM $

      ,, M %*W % T 5 N,                                                            _. ..                            . .                                                   E 1 ..,,.I y ,Mc                                       g egr q, M 8 M idEit?$.F.'N
     ' To demonstratecthe proptr operatione of the instrument and ' service' air ' O' ? *T O*7h t'syatems~{&ym 4                      Wp.@jWM'$f6M5[$g.                                                 .                .

y'l i h

       %'&&ve.%f Plant Conditions / Prerequisites e                   .
                                                                                                                                                                                , Wg{$*7@hMW@!@';.W^=*

C'a WN%p T %f. 7.. . , ,MpK W .V,$ t M . @ W Q ..9,

                  ' .pwrJW,4 #.Md w*me .M,4#

n F'74 ', ,, '7f[ g % @ b) M r. 4 N 9.h . $ . U W5 Prior to hot functional testing.'hM!.[O

                                                                                                                              ~

F ..f%-f.%.7 Kh'GM1

• W OQN .r:eM..;A'd..Ds.~ N '". 2 "A -....IF  % N't*y 'S mC,r.:@' Y M J,2.dt$'.if.td.Q-:.L?;qh" m. y. - / .  :: sv&7Me.g@;lThve.

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s

     %' Teat Methoda                                                             ^               -
                                                                                                        "**"',?g' - m ec. E r- -tT 3.;Y " W r.
                                                         .m..i 6 3xi-:w:9rd'.'R*FgRii*.A^'15                                                                                                            'ndsn;. M & rHS: . :v~.*                                              -:

g

                                                                                                                                                                                                                                                                                                              *V                            .

Functional testing of system components, instruments, and controls for the plant and containment building air system will be performed to demonstrate cperability. Testing of components which perform a ' safety-related function '. will be performed during the respective system preoperational test..

             . .' '; J. Gy+2.iC$~%hQg~.%ff                                                                                                                                                                                                                    ....;.:_.E?WN,,')c
                                                                                                                                                                                                                                                                               .. ,. . .n                                                   $r Acceptanee                                                                                                                                                         C                                                      $ Q : :.F % i .y:*.. I'A. W.                                                         c. . -': +v. 4.W m; . - yW6.'+ i Crieeria .D 'i'.oc.                                                                                                                                        5.:d..&'"'.IO$>&d%#91t&@.
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M;/ M-%. .9..W.s.M.... M,

                                                                                                                                                                                                                           ~E,            4.,,M; .                     . . . ,                           .
     ' Instrumentation,controls,                                     ?M i'A,WJj?                   alarmshy$                  and%~~-       interlocks         % operate as required              B                            J T .M:...N'M     -

in M W-B.5+P ' . - cecordance with FSAR Section 9.LI .in response co normal or simulated input ' f cignals. .j g .y.[X{:j @ y % Cg.g yd yg/..pj, g y p . g, y .{

                                                                                -. _-                    --__                                                  __                                                                                                                             .         .*( ' :. ..w},W

l. 0 y.s k ..Of N.4 sh wumpf.casors meeL O. r ..exscud(d..

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TABI.E 14.2-4 (Sheet 15 of 37)

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jl$h. f 13. FIRF. PROTECTION SYSTEM h b N ,9 Vdk . '

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                                                                                                   .1                                                                    a.        <
              ?s To!.demonstrata:                                              the. proper operati' m o *'

o thatfire protection:systest., . ~

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             % . Plant Conditions / Prerequisites :. ' --e                                                                                                                                                                                                          -
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                  --Prior to inttial core loading._ . . ,.g.,1                                                                                                                                    5:. .k?e,x- Ih e,_

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Tests will be performed to demonstrate proper operation of fire protection subsystem equipment and controls as follows: A

                                                           .-          r.:                                  .: . , a .-. ?.a m;                                        ..                                             ,
                       ,.,            a.',. Capacity tests of the fire pumps                                                                                                                                        '

l 2.fh .1:~ . ;SEI-7pMM9dQfJ<h&hf NOCd.03/dipl@AO AWJ bu iActuation tests of the water and halon systems

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(Proper-operation of the smoke and fire detection syntems

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                                   - d. .           Fire pump house heating and ventilation                                                                                                                                           '
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                                   ' e.             Fire protection interlocks with other (i.e. HVAC) plant systems
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Acceptance Criteria - ' E ~ " ' * ' ' ~ * *

44. .

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Demonstration of fire protection system performance satisfies codes and - l regulations per design, as stated in FSAR Subsection 9.5.1 and ehe-Technical

                    ' Specification // 3. 7. f./                            .
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14. RADIOACTIVE CASECUS WASTE SYSTEM . ...

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To de'monstrate:ther proper operatica. oCradibactive. gaseous. waste system- ..- components.$: M " ^ "* *

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N"yd@Mb ~3g T h i.f;.l N f M 3:1 3.. F~.h,-%[b,4@A. Plant- Condition.s / Prerequisites -

                                                                                                                                                                                                                                            ,O- J. ... N ' T ~.Esf.7          -

s

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4.uo:e Prior towinitial v.W.ikOcore W Wloading.- W+Mitg .

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Operability tests will be performed on system components, instrumentation end controls to the extent practical to verify proper operation. ' g

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Acceptance Criteria ~ , m,

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alarms and inte ._eks ope e as d ~ igh@ in Instrumentationi contro l (i t rcspons to 1o simu ted;in si .31s. .. y 3

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                                                             . L-          ,..;. M;-y                        ;:.y.y.j Jg.,g g 'a;@ g.                                                                                                                 ,

gV - ygg,w .% f ,[;. fy ' ,, The[operMlitj of the' radio t' e gaseous' waste sys' tem'has l been

 ;     demon trated. f                                                                      x-
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low paths to all system components have been demonstrated.

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TABLE 14.2-4 (Sheet 17 of 37)

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                  . < g 15. LIQUID WASTE SYSTEM                                                                                            . -* - h =* ~r W e
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demonstrate the proper-operati~on obliquid1 waste system h ' ents. c'innpon.QW%TN

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, . M Plant Conditions / Prerequisites ~ rtM(L;N')N, M WW S. :.ihn .;

           ~%                                                                                                                          "- P lf '4m *2 Syr%$4m                                                                 * .'#

h t._"i  % s- . : V . M 'v di

               ~Prior.to M,t*V'IWpti!!y>l                                                       core                 loadingft.*SWe4,k/MM.                           %      j     t';     ?   p     y     V     R      '  [.*   p  Y M[.,Y,,f$h'                yc .t
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Tests will be performed to the extent practical to verify the proper ) operation of sy , stem components, instrumentation, and controls. 1 ! & f 9 Acceptance'Cri eria /*'and /veNbl4&trernd2Tet.22 e f.

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Ins trpneentati trols,-aTasins and interlocks o ae as ,degign, respons s__ normel or at t . . _ ---j in 3

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Flow paths to system components have been demonstrated.

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_ _ _ _ .. _ . .._,-.~,1 SB 1 & 2 heendment 44 FSAR February 1982 m tm v.;, TABLE 14.2-4 (Sheet 18 of 37)

16. SPENT RESIN SLUICE SYSTEM '

O, bigellve

• T6 demonstrate the proper operation of the. resin sluice system equipment.

Plant Conditions /Prerequi' sites . Prior to initial core loading. '

 'Thst Method                                                                                                                               ,

Functional tests or' system components, instrumentation, and controls will be l performed to verify, to the extent practical, the proper operation of resin sluice system equipment. C b Acceptance Criteria . T .c-nat tent n,jont is, a and in ocks e s . 6. gin a se o no 1 o'r s 1 ted i e gnals. - m low paths to system components have been demonstrated. \ u (%~  %% m_ . %7

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TABLE 14.2-4 (Sheet 19 of 37)

                       -17.. WASTE SOLIDIFICATION SYSTEM                                                                                                                    ..       .         -            ,..

fa~' qts 2 Objectiire&gQ" * "1), * ~ 's .c~c  :> r

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           '71h- Am=aaecratee the-proport opoca tion,: of'was tas solidificacion- systesk w ...-, ,                         ...h. WD                      .o                ' bk3h - '~ ' - k.)
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• fPlant- Conditions / Prerequisites ." ,-[., - " -

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Prior to initial core loading.'% # # es~Wxv.6L.nsk PDWN.;->a ,g w?.Y. .s'Q, u .r,d.r'n$ H5! W,. o.r

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g:w ~ ci ' ' s. .v{. n.~..t., '"/ .- Tests will be performed to the extent practical to verify proper operation of system components, instrumentation and controls. Solidification of test setsples, representative of the expected wastes, will be performed to verify proper .; operation of the waste solidification system. .

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Acceptance Criteria

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                                                                                                                                                                                                                ,.                      s strumentation, controls, alarms                                                                             interlocksoperate(asdesigne,"in s

• espo e to I or ated put igual ,

Solidt tion o test sampi meets gesign s reqs g. treme.nt;s.

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                                                                                                   ' TABLE 14.2-4 (Sheet 26 of 37)

, 24.' ELECTRICAL PENETRATION AREA AIR CONDITIONING SYSTEM Ta-demonstrate, proper, operation of the electri' cal penetration: area, air 1 l

                                                                                                                                                                                                               ~^j
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             NhIMM[ IN PIane' Condit[ ions /Prerequisitesc:nditioning t                                        IN/                  ' '
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• systeur. t '.,Q[j"
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              , 2? 6 Mr.M iiW'fWVM)Mt4-2.TfM4@Mk                                                                                                ,p,                   g.g,(5)[h.         -h, Mk.R ?.U ' 47 '.: #.R ;;s f.
                                                                                                                                                                                                                             .Y ; '

q Prior to and during hot functional testing.  ; ff4'4p' T.!.., Y. 9%

                                                                                                                                                                                                                                                   ~

s . ~%$ J.g,rgiG. .@s.ie-n$.-yi.el,7.l' la4.-cd e..p;W. ,y .'to c.'XJ < J '.6' , 'f-T^st Method y..+.,pf e.e'::terd a.31..d.!*... q E, je m 4,. r,' 'y v ,{.v ~. <d

                                                                                                                    ..:<            4 ;-

t e. v - Tcsts will be performed to verify the proper operation of system components cud controls for the electrical penetration area air conditioning system. During hot' functional testing, data will be recorded to verify satisfactory cres temperatures.

                    .. -      n..

v .4.-J.:.,$.EsCw,;n*gQ,q,#,gpg&c w, aM- #$'g. vgbty3pM5.Qt + v :-"? s.-z. ,

                                                                                                                                                                                                      '         g Acceptance Criteria N                    :
                                                                                                                                  ~

f,[' h$khkhynUM' ~ i I trument n,contrTo an inter 1 so rate as de_signe in.' response to 1 or simu , inp t sign 's, a d area ratures are main'tained_ j V tricht sign 1, ts _ p

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_ _ . . _ _ .____.__....,._--w.~_ SB 1 & 2 Amendment 44 FSAR February 1982

   ..                                                                                                                             l TABLE 14.2-4 (Sheet 27 of 37) 1

25. TURBINE BUILDING VENTILATION Objective .

To demonstrate- proper operation of- the turbine- building ventilation system.. Plant Conditions / Prerequisites Prior to initial core loading. Test Method Turbine building ventilation system functional tests will be performed to verify equipment operation and air flows. Acceptance Criteria ' I se entat* co is and *nterloc s oper e(aPdeai in re g odsy.s ne 1 mula e in ta na . A a.ert h w.t.d L AJ7 t b@ A. , sy s D 4 D q u pt re B' '

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SB 1 & 2 Amendment 44 FSAR  ! February 1982

                                                                                                                                   .C TABLE 14.2-4 (Sheet 30 of 37)

28. COMPUTER Objective ,

To demonstrate- the operation of the- plant computer and the associated coftware. Plant Conditions / Prerequisites Prior to initial criticality. Test Method T sts will be performed to demonstrate computer interface with plant parameters and computer response to changing variables. A & MWM W # ss Acceptance Criteria MMW Computer interface with plant parameters and the computer response,.co changing parameters'are in accordance with dc Isu dow u -=i. - -s [ _ jff d y S t., DW4 -M - 51000 'l. 1 , .

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TABLE 14.2-4 (Sheet 31 of 37)

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(.vkkh .atPRIMARY.: PLANI"INSTRUMENTATIONY

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plant instrumentation. V.!

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              *g1To!                 verify                                the- initial calibration                                                        ' 75CT4 ~                      of the&rprimary                                        $e5%

Plant Conditions / Prerequisites - Z -~mc '/k7' f

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              Prior to hot functional testing for specified instruments, otherwise prior to initial core loading.                                                                                              -
                                            ,                              .                                                       . .            .y. . ,

e Test Method .s-

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The calibration and alignment of various primary plant instrumentation (temper-ature, pressure, level, flow) will be performed to verify the operation . . of each instrument and associated setpoints. Plant calibration procedures will be utilized to the maxima extent practical. , O ,;-Q-N j f' 'ibp;.g g' ghg Acceptance Criterta '

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1 n:- . < , .. 5 . J - .+ , , - The primary plant instrumentation has 'been calibrated to within the setpoint accuracies required byc y :-ccc =

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TABI.E 14.2-4 (Sheet 33 of 37)

31. SEISMIC MONITORING SYSTEM .

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               - . Toe veriffr tha* proper' operati'on. o.f the: seismic- monitoring -instrumentation.
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Prior to initial core loading.

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The seismic monitoring instrumentation will be calibrated and functionally tested. .

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It has been demonstrated that the seismic monitoring system and its) associated indication is operable and meets the requirements of tJes.

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TABLE 14.2-4 (Sheet 35 of 37) ,

33. COMMUNICATIONS SYSTEM .. .s,. c ., . . J. .-

           --J 'Dz:ver,ifyz proper operation. of* the.p.lant; page.andi. sound: powered. phone;-                                                                                                               . 34:.yy ;.j
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         .f~ systems.), To' verify operability of other plant- communications
               -utilized. in the facility emergency plan.-                                                                              DC?- W ff'

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Prior to initial core loe.itas.

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Consrunications will be verified between stations, and the outputs of speakers and amplifiers will be adjusted as required. . . l

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j to consumficate st a alarm thr ghout th p1 hav be den strated.

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TABIE 14.2-4 (Sheet 36'of 37) '

                                                        +
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34. EhTRCENCY LIGHTING .

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 ' ;Tb demonstrace- ther-operation of the emergency-lightiny systew.. '                                                                                                                                   . h E v'C.9 M.P3+'." 9.
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Prior en' , to': my loss of,gd

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Tasts will be performed to demonstrate the operation of the emergency lighting systems during partial and total loss of ac power. Acceptance Critert'a

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TABI.E 14.2-4 (Sheet 37 of 37) -

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                                                                                                                                                                                                      ' QT.g.polar                     f,fi crane. . 
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4. Q'Flane Conditions /FrerequisItes

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Prior to hot functional tests. ~~V' .1 l 's &C.R  % .&:.;'WQ: t.-f.. @l.g N%t. . m?,,f:.[f . ' ' .W.  ?

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Functional tests will be performed to demonstrate proper operation of the crane and its controls. The operation of interloc's s and safety devices will be verified . ~. ,. .-

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AcceptanceCriteria'R;yk.Qgsy.ag@tw.f.gpyy.1~;...o.si.....,p.>. g a.y.:.. O + .9 9

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l'Its polar crane operates in'accordance with t;:u .:2.2g rq 1;;_e ;p

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                                                                                                             ' TABLE 14.2-5

_ (Sheet 1 of 53)

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N' s g .T:r 4, .g t.'.*y n.N 3* 'C## STARTUP TEST ABSTRACTS

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2. ^ Primary Source Installation . .

3.isl? p:ikgbAW*GtyQ9$QQ&&f,{?l&p4WF."1 ' 9:# 2-'l.'-f f -Q: -. '~ '~~ ~ Core Loading Prerequisites .c m.~, pfs.n.-: *

4. Initial Core Loading

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5. Control Rod Drive Mechanism Operational Test b

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6. ~ Rod control . ,

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             . 7. #. Rod   1 4t-9       Drop 6,44MSW8,,

Tune Measurement m ,. @ %w. w w .a . .s.jdl$;fg:7.'. 7 .g

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8. Rod Position Indication * -

J- -

                                                              - -                    - wp. .;e.w; h,                               j gp~,4..  -

9. Pressurizer Spray and Hester Capability' Test u,- . :, ..s+-n um. .. w n y .f . - -

T -

10. Resistance Temperature Detector Bypass Loop Flow Verification l'3

11. Reactor Coolant! System Flow Measurement N .

12. Reactor Coolant Flow Coastdown ' b 16

13. Operational Alignment of Nuclear Inserts:entation

14. Operational Alignment bf Process Temperature Insertsmentation l9

15. ReactorPlantShtensSetpointVerification -

f8 2 . . p l7

16. Initial Criticality'

17. Baron Endpoint Measurement N

18. Isothermal Temperature Coefficient Measurement " b

19. Flux Distribution Measurements at Low Power I2

20. Control Rod Worth Measurement N ,

21. Psuedo Rod Ejection Test M 4

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                                                                                                                                ;-< TABLE 14.2-5 (Sheet 2 of 53)
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                                                ., Thermal Power Measurement and Statepoint                                                                                                                                                                 &
                                                                                                                                                              =t;3; , #'Data Collection                                Q'
              - %%!i@E2;?>Ft*t$6nMtZ?t.@2Mr,if*N.fi2;&W                                                                                                                                  "

tA 27.~ Startup Adjustments of Reactor Control System 30

28. Calibration of Steam and Feedwater Flow Insertamentation. 3i p ,-:v..-M.s:3 =: n r- ; -..? ;; -

                       .:5,. 29.. Core Performance Evaluation 'g _..;p R,                            1        :.: 4%                     ;                       - ,- , ,             -
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                           . t 32. Negative Race Trip Test Ey .
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                                           '   Shutdown        .

from Outside u-- the Control- Room -

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                 ,.,w'34.-.                                           .                                   .:,n, Load Swing Test .                                                      s me..swv,a

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                               -35.              Large Load Reduction Test                                                                                                                                   .$                        *

36. Axial Flux Difference Instrtamentation Calibration

                                                                                                                                                                                                            )f

37. Steam Generator Moisture Carryover Measurement M

38. Unit Trip from 100 Percent Power '

                                                                                                                                           - ., , ~ . .

k/

39. Station Blackout Test ., c- - 4'l

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L ' 40. NSSS Acceptance Test 3

41. Radiation Survey . Af,

42. Water Chemistry Control 47

43. Process Computer

• 6

44. Vibration and Loose Parts Monitor 47

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45. Process and Effluent Radiation Monitoring, System A3 .

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49._ circulating Water System Thermal-Hydraulic Test U e . s _ e.  : s..~ ,

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50. . Movable Incore Detector System

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SB 1 & 2 - FSAR v TABLE 14.2-5 (Sheet 4 of $3)

1. STARTUP PROGRAM ADMINISTRATIQN

     .          Obj ec tive-
               'To prov*.de general guidance for the administration of'the initial startup test program and a recommended sequence for the conduct of startup testing.

Plant Conditions / Prerequisites A list of general precautions for the overall test program are presented. General plant conditions are specified in the test sequerc% with specific requirements dal'ineated in individual tests. Test Method General guidelines for conduct of the program are presented with specific instructions given in individual tests. The test program hold points are included in this procedure. " g Acc..t _ e cruari.

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TABLE 14.2-5 (Sheet 5 of 53)

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d. To'provideIdatatIedt Instructions for the-handling and installation of the

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        - q Primary sources into the required fuel assemblies.                                                                                                                                                                                                r.               ~ < . -
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y.Prant Conditions / Prerequisites ~

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Prior to initial core loading. , . 5.' .MI? $!,M.40 t Tp'/ps n:s .. ~~~

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Test Method - -

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                                                                                                              .                      3 .              'D Instructions include a sequence of steps for unloading the shipping cask and installation of the sources into the respective fuel assemblies.
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The primary scurees are g'L -_ loaded in the requir'ed fuel assemblies.

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p/f3d{CORELOADING'.REREQUISITES .

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M T y:W;; S . Plant C'onditions/Prerequiisites ~ (q% g# g n w;.{p w@ w.s

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M.d. . ,.F.4.. ,s,Ghfr..%mim-w-e,mu,n i.r,m 'M t.mingWWiy' . r %.%:&. M*u.:v.d.1

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                                                                                                                                                                                                           .c.                       -          *  . '  +.-:    - ' . - -

Plant"cenditions

                     .';'f[MT ,W s%?,are
                                               .                    ~~.    .,
                                                                                          ;;g'   established
                                                                                                         .8 .,'y' ' 'g:;; as                         , ,-:p      require.1 x . _, y ..by                , , ;test instructions.

Test Method '2* ' ~#

                                                                                                                                                                                                    'T
                                                                                                                                                        ~ ? '- ~

A detailed list will sumanarize plant system and equipnent status required prior to the start of core loading. In addition, sampling of reactor cool-sat and associated auxiliary systems will be performed to verify uniform

• v boron concentration and the alignment, calibration, and response of the

1. . temporary cope loading insertamentation will be verified. IM' '

                  ?:Q'1As.fm'ng W . E n an. FA*b etbn, S p" r' wtZ/ 4.s
         ',           e..'- Accep6dn e Criteria M                                                                                                                                                             '

n 's M a-

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                                                                                                                                                                     '.N.      E~W           A -e 'r~ y.'

r ~ , . "- J . - ..-pn - All requirements specified in the procedure l$ ave been tfqvghicom-Pi eted. _

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                                                                                                                          ' I TABLE 14.2-5 (Sheet 7 of 53)
                                                                                                            -~ w' p'^..;; ,,                  .

e ag .?.h.;) NS bppq INITIAL CORE LOADIlC

                                                                   .. n-       ~. ,, . ,                              -

T I-h ?' h-J.M.N$YM.'j'T il iftr%g&e:. ;c<. y . , .

                                                                                                                                                                                                                               ,g%p ,p ;,qqyy;pg ,c gy. g.

i.g 063ective-  ; ,.s p., v p  %.gwge.g*gg~,;1~ed instructione-fbe the conduct of# initial' core Ioad m ~.a; + .. . '. . . n ?-

                                                                                                                 . .                                                       n.                                                                                     -: .

deta1 . . ipr,ovi ~

    . pyg,is ,ai,s. afe 2,                                  controlled manner.~.                                                                        " %."
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Fr.- 2.c.m. ,: p ,.g.'."

Xt$s'0kg# dig,$ s

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     9 Plant Conditions / Prerequisites                                                                                                                                                                               .hfy j aIT5.D#:C SyriU.$ ' *
                                                                                                                                                             .'p %                           ..
          ?-- 3-:m.w .;-.cm y.,,,                                                                   . . yy ;sgyy.ff:fQ                                                                                                           5 J ;L :: . : ,. . . ' : - u
                                                                                                                                                                                                                                                        ^

Required preoperational testing is complete and plant systems are opera-tional as required by the core loading prerequisites.

                                                          ~                      p                                . . , -                                      .

Test Method

                                                                                                                                  ~

F ,.

                                                      ,                          , . _.                        .s a                 ;,1 'M A detailed loading sequence giving specific fuel assembly identification
           .ntsabers and core locations will be provided with appropriate data taking requirements. Specific administrative control and core monitoring proce-dures to be applied during initial fuel loeding will be provided.                                                                                                                                                                             ,
         ~' @.MG~<.%@$?$3pjjg@ggr{2d4'Cy'                                                                                                                          gRyp;./rSgg jp: f,.(.wg                                                       .n" . /.cr
                                                                                                           " * -. ,..w' -

Acceptance Criteria .- ' *w- 1 O,.M. fw: *.;j:.. u . ,g . g .4, E.y. s: c..:. - . .3 f . ..

                                                                     , - w,
                                                                                                                                                                                                                                                                         \a )' ,
                                                                                                                                                                                            -           -- w e core                          be                                                          loaded as defined b                                                                    he core loadin a                 ent                     ord                 o operig(final the . %                                        as-loaddT                                    cor config6ra'ti_o/ h}g plan ands been sla A             %

G ' s.

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                                                                                                                   - - -   -=m,        - -

SB 1 & 2 . PSAR' l

      )

J TABLE 14.2-5 (Sheet 8 of 53)

5. CONTROL ROD DRIVE MECHANISM OPERATIONAL TEST Objective

                     'To ' demonstrate the proper operation of the full length control rod drive mechanisms (CRDM) and provide verification of proper slave cycler timing.                                        .

Plant Conditions / Prerequisites Prior to initial criticality, during cold shutdown or hot standby condi-tions as required by the test instructions. i Test Method During cold shutdown, the ability of the slave cycler devices to supply the proper operating eigoals to the CRDM stepping magnet coils will be con-firmed. The proper operation of each CRDM during both cold sad hot plant conditions will be verified by recording CRDM magnet coil currents and e audio signals. , a h Acceptance Criteria - CRDM cperation 2:onforms to the "- ' requirements

                                                                           ' ~

of proper mechanism operation as dea cribed. L ;'.. .je r in Cup +ce4 d-+L+ u *.4i <v *M

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e e I e l. O E 9 - e S l ' . , pe y_,

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I - ?' MM&&%$ W^  %. fat 9%i In:TM %% E%'MfalJlli84%u M @* N

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_ -- TABLE 14.2-5 \ i (Sheet 9 of 53) ,

                                                                                  '                                                                                                                                                                          l 1

f. y . , . .

           . ... ? 67 ROD CONTROL SYSTEM                                                                                                              . , -*.., W h,                 ,        .

Sy ,'/' [ h g 7 M . & Jt.f

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 ,': m, Obj.ectiveg Thy                                                                                                                                                         .r.*;

a ,.

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   - #'49G4#44f/riEM .                                                                                                                 ..             . . .            .          pW Vf -/'Rdd9.#,M. .iE                                             M
 .;hTCd,emonstrate- that .the. full'.* length rod' control' sys tem- perforias the- required-
    <N control land ~ indication functions just prior to initial criticality.                                                                                                                                                      C ' 'N   .
   . +hM'@.YM.'hMINd$I64MD                                                                                                                                                   MMN                                 f ,n.'.'%- - M'

• 0 T

                                                                                                                                          *                 ~~I Plane Conditions / Prerequisites '

l:. & : W u,N W '. hts + wa m A M W22.n

                                                                                                                                    +                           +

n-d g.y . .WN.Kfh+n*AbI'Nh;h.U.k M.TV:sw.NZh,ili!N . in . . . .N. : . . .@. m.c .

                                                                                                                                                                                         .v                                                      --

p.?' c,%

                                                                                                                                                            .                                        %  :.                   ~^                   -

Prior to initial criticality at no load operating temperature and pressure. '

                 .J~.S.4'h'sMtfrb^:WU Yf44}y,y_f,-                                                                          & Q Q:f.)z{% .q:i+ s:

Test Method d'

                                                                                                       +c~+               W .7'~'s.(

g. Testing of control rod withdrawal and insertion speeds and sequences, con-trol functions, protective interlocks, status lights, alarms, and indica-tion will be performed to verify proper operation. -

        .. x 2^k.%~;?.M,M.GWQL,:.J.+pys@, %a.s.ru2%y,gv.+g.M.                                                 n .my                                                                                          y : ., .

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                                                                                                                                                                                                                                - . 2 Acceptance Criteria                               .                                .
                                                                                                       -; ..                            M, ~, -.                           -           --
       -" %.:royvs.y.ssc:,;%9 Ws4:& (F ; . thk$$N. hk'?cYS . f.NS $h~:'

• The rod controlPsystem performs the required control'and indication fune- '

psinAcordancewith 1= - r M _; - a l- .a n in M c.y w r nC d tJe.W k 2.a caa s1s6 Lu.U.d wow i ..I.x.'M.~ .E. _, ~ s"..$' . [$ oa . n . . w n : ,a.w ~~.,- .n n ~ -. . - ~. . e c rgi. 7- .t. ~.-; -. *p

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_ .M. sc.s w;rr.n, trq. .?. g. : w:" (. -~';~ r TABLE 14.2-5 (Sheet 10 of 53)

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            - }n F g*3y ..:pROD                           r.'NDROP      3%-TIME MEASUREMENT                                                                                      ;-

W

      ~

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k. y1L-.%* w 7-~U.x 5$p '. % .~.j m a -

C, p*,gTti?determinef%; . _ - ~ J,@ R' p,.

thef drop- tiine o . eac!Pfhl1~ 1ength control rod under vari'ous* '

4  ;,,plantf.conditi~ons.-E. 5 l! J Vi$' % g M p n,3ty s o g e W M i M rA % in.>.9 4 4*i n f/3. + 6

  ~ 'k                5              Mhi.                                                                                                        h                              h A;./.v;.; Plan t Condi tions/Prerequisi te s N*.
                                                                                                                                                         . - 53pgs-:wSqjh. p- ;j : : :y,7.;4.a'.; . w^
         *"Rif-s:s.Lere Y-k: #                                      % % W+yu:.M r.g.9,4Kd:?YW.N! $ Y W=k# #, ~' ' '                                                                                                                                     ~ 1.4 :

T

                    , Prior to initial criticality, during cold shutdown and hot standby condi-tions with full flow and no flow conditions in the reactor coolant system as required by the test instructions.

w . Test Method --

                                                                                                                             ' W. .f. . %. ., .
                                     . . ; , , m:,y. 9. - ' .,e . n' '5;m. % -y. ' - .
            ._1 During each of the applicable plant conditions, the drop time for each rod fcontrol cluster assembly will be determined. Those control rods whose                                                                                                                                                                      ',
       "4: ~ ~ " drop times fall outside the two-sigma limit determined from the data for

" JJ all control _ rods ' ' will be ratested at least three times to ensure proper

           ..'3       performance'.                                                               :

p-bel - 3:21 ? ~;, *'a ~ --- m Q

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Acceptance Criteria ..J- . s

                                                                                                                                                                                                                                      ~
                                                                                                               .. . . % s .?A , ,i                                             ' 4 gg g [.g.

_The rod drop times meet the requirements given 1,7 i.LW = * *g= ^ M1

          .~ .m ec i E ' : - d ~' = .
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                                                                                                                                                                                                                                                             %=.

TABLE 14.2-5 (Sheet 11 of 53)

                                                                                                                                                -      v.;.      . % ,.. .                                                   .

E.'8.stROD POSITION INDICATION i l W 's--- - .4..i i.5:3. 7- - s. j?'*?$W b5)$ & & f N W W

                 $ 0biective~,~' ~. ,-                                           ,
                                                                                                 $                               ?h  pt;.,, :

hh5' hbk?bfl

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e. . .;.$

/

                                                                                                                                                                                                 %%s3
                     ' k?<

fTaf.v$&Z.WMhW?$$erify': that the. rod 6L " posit 2.or .

                                                                                                                                                                                   .- ' ~ 5?YE i'ndication        Wsystem #'.*G'-performs      W~ 's?p.t
                 'qindication and alarm functions for each individual rod and'to demonstrate
                                  ^                                                                                                                                                                                                                        .
                                                                                                                                                                                                                                                               'b   -
                ~ h that each control rod . operates satisfactorily over its entire range of                                                                                                                                                        .          99 r               -

i i Plant Condition / Prerequisites . t -MP 't i ' '"

                                                                                                        ?,+.r.-1.)
                                                                               . , .        . ,                                           -C W M ?.%'Wi D - >

Prior to i tial criticality during hot standby conditions. Test Method . 3,

                                                                            . _        7..     'c.3,y* . % 'N N. j                                                                                  Q Each control rod bank will.be fully withdrawn and inserted in % step in-crements where individual rod position indication and group step indication data is recorded. The actuation of various alarms will be verified.                                                                                                                                                                    '*
                          <;s, # ' M :

F'&*;&th';Kr.pgQi%f"?1- f,y p,QRyp.glg.g3. ;.p,: ~' ' ' 'p ' : , - .

f. . . .

Acceptance Criteiia - 'y i45y ?@;.h , f,@';;*f' AASSM-t'~ - -

                                                                                                                                                                                                                                                    ' '  ~h 9 %mte                                %hbic.d Tpe.c.lhe.d.*oo s ase4C.41$                                                                                                                                                                 O' The rod position system M ,u                                                               . i.,
                                                                                                                                   % 5-->

indi * '~.:-

                      ,m ."'w=v .-::.;     ..

cr- # r- - - as ~ 1 .,;;;.;

                                                                                                                                          ,im L ;                             q:: s:-a hv the 'techn: 21 r-                                -                                .       < w = m* '
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                                                                                                                                                                                                                       . $                    eQ    . s.w                           .,,..,~-pf..h; 719.--

my% L y %'.,;s[p,.-?g% . h. . n nth K .9e:u - *' yt#m&?,,, 314  %'-s-& .h3 m'~ -*.i*@ ~ ?' - ~ qq $pny.

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TABLE 14.2-5 (Sheet 12 of 53)

                                                                                     ..c .. p. , . q..
                                                                                                                                             --          s
                                                                                                                    .. .a                          L ..:. .: . . ...c, - ' W                                 .-

st 3 -@. W%a:: y?.~v:~, _e~y m, :-~r

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                                                                                                                                                                                                                    ~ . + ~ > ^ ; ,. :
                  . . Oj.-                                                                                                                                                     v                                                       .
             * .M# M.g9 d a PRESSURIZER SPRAY AND HEATER CAPABILITY. TEST..
                                                                                                                                                                                                                                                                                ~ '             -~                 '
                   "i dQ$ .* p fDQ:gp;n a%v r 'gg yg,, . g
                                                                                                                                                                                                                                               ,                                            pe P.4-$
      .l
       .A y W n.

hk Tor establi~sh the continuous spray. frow rata and ~ to verify pressurizer spray

                                                  ~

N $ w.eKC.%Y N Y and heater- effectiveness l Q%%g ' l-hdh - ' Mp'5 0M.e.8.5in +1t -@ A, -gPl.ant h.Conditions M.1iBMWKN. :in. .dN.. ,gad49.$. .u.%gf,y g. ..%.<p$..'p.,g m .~ ...

                                                                                             / Prerequisites                                                                                                                                                                ._.                                     ,
                ,W.f.A :                  W*ii.WmW:t,dW %'M &4'&NIV."&WWWN'g                                                                                                                                                                  M ~-_ . -
                                                                                                                                                                                                                                                                 . );' , ; ;: y 4.,: p
                                                                                                                                                                                                                                                                                        " W'
                  /

V3., Prior to initial criticality during hot standby conditions. . -

                                                             . m% ;. 7,.~. ...
                                                                                                . . .,m. .: w,.,,.      -
                                                                                                                              , m3         . ;pg..1.e.t. -         ,
                                                                                                                                                                               .._.,y
                                                                                                                                                                          . .., r% , s , . .                    .

Test Method

                                                                                                                                               ,r             ,;
                                                                                                                      -=-   .
                                                                                                                                                                                           ,J The spray bypass valves are adjusted for the minimum continuous spray flow.
                      . -Both spray valves are opened to initiate a pressure transient which is re-(Ml '."   [ corded                         andtocompared                                             to the expected                                                         pressure                                             All heaters are energized                                            initiate a pressure                                                   transient                             which isresponse.            recorded and compared
                                                                                                                                                                                       ~
                 - W .to. expected pressure response..>. '                                                                                             .

s

                                                                                                                                                                                                                                          ~
                                                                                                                                                                                                                                                                           /.           +N-                      ~
              . 5%,       <
                                     . .K.,Vi'WN.WL"-H. teria&.

Acceptance Cri

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                            .The continuous spray flow has been set, and the spray and heater effective-ness is' in accordance with 7-*r E d;;- -@run .
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                                .                                                                                        TABLE 14.2-5 (Sheet'13 of 53)
                          , ,'-                             3. '. ::..D ..0                  M /:@ G :                           ,

10.. RESISTANCE TEMPERATURE DETECTOR BYPASS I40P FLOW VERIFICATION . l

         't -Ttkcorcul' ate-the Hoc and#cordTIEg bypass li'ns: flow                                                                                                                   'I'                                           I                   'i
                                                                                          ~                                                                                                  rates. necessary to pro --                             f ,; { i      <

vide" adequate transport times, to determine the actual flow rates, and to .i..'

         .I5 verify,the                    low flow alarm set nts ..                                                                                                    " ':4$ >' p jp. Q G gffg                                                   hff.R

m. . .  %

                   . w w*w
              Plant Conditions / Prerequisites
                              't -      .-         .N-A.w;"           *rew /<:.T4              wm              4 @a            .iM'.4      h"EW      NM P,                  .

hY ~

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d.'f;8CiQ N -

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                                                                                                                                                                                                                                                # W {-     ~'

Prior to initial criticality during hot standby conditions. ~

                                                                                          . .; n : . .n
                                                                                             ~ -

Test Method .  ?- '

                                             .,.                 . .; u . m .l';.:e Q ; Q : - i . &. . . ,                                                                                   '

The required bypass loop flows will be calculated from measurements taken on the installed RTD pipitig and compared to the measured bypass loop flow

              . rates. The hot leg bypass loop isolation valves will be throttled to ver-ify the low flow alarm setpoints.
                                                                                                                                               ...-          y if 6,~      h . . man.. :              .n. 4 . , -:
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                                                           ---                                          e                                                                                                                                      ,a Criteriad.%. ;s .< 7,N.,>.g/qo,                                      s                                                                                                                                          .

g.g.L-.: m Acceptance -

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ow a ope {Q

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TABLE 14.2-5 (Sheet 14 of 53)

                             .  ...+g...
                                                          . . , , ~
                                                                               - - . .               ~:r.~
                                                                                                      .a r.
                                                                                                                                          -:                    ; ~ . .: ; .

r -

               .ap+.$5M,(..;:z.,.II..                           .       REACTOR COOLANT SYSTEM FIDW MEASURE}iENT.                                                                                                                         ...,-R                                     i.
               ;$(.*EQM$fd0$t($h?Wh}                                                                       "* *A %&&. f W %.{*L                                                                                       /            g s .~x. m;t . iff$
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e. p.u Ob3ectiver , e e. n. y W- + me@.-:w^i.y<&::m,

                                                                                                                                                                                                                      .~                                 ~ ux.~; w:ns           :.->.      .,..

P NYi%5't&4 mw if%gTty measure actuar. reactor coolant system flow.J ~ <2d&E.I,hr & h yfr.vM...

                                                                                            .r.+                                               *<           .                    .e &                                   .

f

l

             E p.
                             $b#WNWSbM$&N$.WN$iNTfff}]\&}'

Plant'Condi~tions/ Prerequisites ' fW. [W.?.

                                                                                                                                                                                                                               $       ?E$5f*m$h*k  % psp &%&

[g)l'lT3,.g:$;I'&f'?

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h 4 ,, . ' '

                                                                                                                                                                                                                                                                                          ' %.i
                                                                                                                                                                                                                                                                                          1 yMs, <w.v;.t t.% van >n-tn- 'svtWAY]$kt-MD:; * **

67 Prior to initial criticality during hot standby conditions. -

                      . < .-    ~. ,. u:. , g.-n* e.          % .% A$v.,. - .ny v ,~          .-
                                                                                           ';p q , y.g 4.y,- . .,ty -]C{%; ., . ,4.
                                                                                                                                                                                                         - ;4..

Tese Method 4- - -

                                                                                                                                           . ; T v1. . y ;- '-

Measurements will be made of elbow tap differential pressure and pump input power for each loop under various pump combinations. This data will be

                                   'used in conjunction with the reactor coolant pump performance curves to
                                -obtain a measurement of actual reactor cociant system flow.
                ' ' ' . y;, %4.% .ww ymg.g y: p:.w ;,.q M.,a.s.:.:.
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p.c ' f.yg.g p;4.q.y:n~

                        -, Acceptance Cetterna
                                                                                                                                                                                                                           .?.
                                   - . m w w *: r.-. % :. W % & $ 6* N '$ % h ? 6 5-S M '                                                                                                                                 c ,,t      ab'.3~ W ^

g

                                'The'
                                   .e calculated reactor coolant system flow rate is ::;^:::.. ;~,ua Ru %e b r.                                                                                                                                                         -
                                            -cne vas usm_ .uuu
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s JA, c.u -n % -rL n e

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                            --2 . : y m
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2.9.j TABLE 14.2-5 (Sheet 15 of 53)

                                               - .                  2.c . ,                    -. .w . . . , ,w . ,w -                         .                    ,
              .cQ.)M12.~REACTORCOOLANTSYSTEM.FLOWCOASTDOWN                                                                                                                        , . , k. ,wgJ. ,b
                                                                                                                                                                                                                                         -W.         .

dsNSD Objective ' h h h hi'Nk$1

                                                                        '~
                                                                                  ~

dh'$[

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      ,lNTo'adasure Y$2*k$%%WM-Wk ~the: rate                                                           .
                                                                                                        . i.sh a,t"which                                        .$ reactor coolant.k'hh.

flow chan o.p - -. . - 2 ,- areactor coolanc. pump trips and to. determine ~ delay times associated with .

                                                                                                                                                                                                                                                                         ;s
                                                                                                                                                                                                                                                                 ..,M.6
                                                                                                                                                       ~

Y%-

      ' D.f.'.Y' d M R $ T M NMis.                                                           T#s'.t M.*4$the loss                                                 '%    'of Q      flow  ,D'6?    accident.IkN]SsAg!

g@ . '.'b,i

                                                                                                                                                                                                                               . . (d b I' M
                                                                                                                                                                                                                                         ' %.fI.MIST r.[. k. /; U         f2 "2k Plant Conditions / Prerequisites
                                                                                                                                                           .%. m      , D4N.

w.u t..N$.

                                                                                                                                                                                          -               $. m,                                                 .
                                                                                                                                                                                                    ..A~ .,.e                      - , -

c_

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             *                                                                                         . u .- . WJL *?9n,W.ns^ n =m * ;:w
                                                                                                                                                                                           .m.,.a...:er.
                                                                                                                                                                                                             . .-               .e -

m:. ..c.+%. .

• Prior to initial criticality dur ng hot standby conditions.

                                                                                                  ^               

Tcat Method '

                                                               ..:..;.J. m:                              
                                                                                                     . :. '%. '                                    . &.?

The reactor coolant pumps will be simultaneously tripped from various opera-ting configurations. Data vill be recorded for coolant loop differential pressure, coolant ptsap breaker position, low flow trip relay output, reactor trip breaker position, and rod position indication as required by the test Procedure. . . , i f.a ' .

                 .e. : . ..n.rm. ..g'                                               y.g?,'f     . .W.                     .                                                              yg ,,,3., ,, . ; : , e
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                                                                                                                                                                                                                                                                           .m.

e. . . ,y.m. . . . ..k. .p. .

Acceptance Criteria . .

                                                                                                                                                   .g,;        ,i .. . ,                                 .                                                           .d
                                     ,.                                   . ;,                . , , .- cu .                     -e. w g '

The reactor coolant system flow coastdownr..and measured time delays are conservative with respect to those. ,,. m W ehe saf e r:1 3cir. 2. g g ggfE t 5 , T f 'tk.a. 5 4 if .

                   .      ~w><geg y. 7, m.;yg.-

i . A m

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Y q .

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t

                                                                                       , g'                      TABLE 14.2-5 (Sheet 16 of 53)
              .. 013.. OPERATIONAL ALIGNMENT OF NUCLEAR INSTRUMENTATION
                                                                                                                                                                                                                                 ?           .' -

N.Wdetar=ina voltage:.settingsw tri'p setti'nga,.operati'onaL settinga.,. al' rme. a ' l.i , ,' J' M#se'ttings,'"and/ ~ overlap *-for thelsourcei. intermediate, and power rangewpm 428%WW-l'y "'  ;.-2%E. instrumentation 'E. . 5? d vw ca y g'vs'MiQR,

                                                                                                                                                                                                         .~                %'OW$~~;             Q-W.s
    ~ ~as                                                                                                                                                                                                                      rn.r e '.5 5 m
          ~ Plant Conditions / Prerequisites                                                                    -' -
                                                                                                                                   . e-                                                                 k.:n g%.v. u., - -:      E     V'-
                                                                                                                                                                 '...; r4+ ,h.q. ,                          JL. :: .1                               3.
          ~   . ? 9i -#%f nlsap.:4v.:v%'%Ng@,T(W$h r siW?.M$W 5"? *'                                                                                                                                                       -

I, ' '

                                                                                                                                                                                                                                                       ~
         - Portions of this test will be performed prior to core loading, prior to initial criticality, at hot zero power conditions, and during each of the major power plateaus (30%, 50%, 75%, 100%) as required by the test instructions.                                                                                4 .                             .

1 h, ' Test Method 4,c #.::phd;W@hW[C2h  % *X d.a. pdY.5iN

                                                                                                  .,                                      nJD-n -

P ~. ~.- i

                      .pwf;i:,W:;-Wib..~f4#,    .

t m$m:,:,U2MW$n-

A.*Br'e>iP W 9 W.:w . %- -

fJ:. . .I The nuclear instrumentation will be calibrated and functionally tested utilizing permanently installed control and adjustment mechanisms. The u operational settings for the various ranges will be adjusted for their ' proper function during the applicable portions of the startup program. ~-

 )          Acceptance Criteria 4 ; - % . & , 4 7 ; y/ 7 ,b. ,y ', 9 ; ; f. y,g ; g y           '

7

                                                                                                                                                                                                                       ~                     ~
                                                                                           . .-           , nm.' e,P..;-Q,W 4: W iO..4 'W.                                        ,
                                                                                                                                                                                     - .. ,., g&
                                                                                                                                                                                                  -- e..'ner..

Sr

                                                           -j ,,, - % . .          .      * .e* . f,,                                                          - -

• Th's plear instrumentarinn"Funheions b eccxd:::: rid 2:  :; :t- i .sn and\ safety analysis requirements, and meet _s Te'chnical -

specification a operabt12.ty requrrements., ,

                                                                                                                                         .. , ,- r
                                                                                                                                                                          ~

Yh & 3 y& > O% W s

            %                                              km W ktusud ~4 m ~ % " =F                                       -

ML - r g, A. Wu m c A w h h Q4-

               $d M .H A J .- M sm'                                            _ . ._.

3. t. t ..

c . . . ~, 4 #

• e e- 3 W *, .k a, e hb- # * . ' ,,

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                                     , '

• N..' '.f * , ' } ,.' *";

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                                                                                                                                                                        \

e e Ss - 9% 4 .

                                                               ,y           .         4                -e                                                             -
                                                                                                                                                                               ~                          .

• 7 y . y 3t% ;-p - .  : ,

.. o : . , .. + .2 ; M;.~.W **

                                                                                                                                                           ~
                                                                                                                                                                               ~
                        . -                                                                                        ~
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tc o. 1, .u:,~; ., t ,,.

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                                          ,   ms, yW __

( ;,::r:. n3gq -it 4, yM,5"%'W.3-t n-+ -+ ,

                                                                                                                                                            =, , .                                                                                               _
                                                                                           .. TABLE 14.2-5 (Sheet 17 of 53)
                                                                            # $ ",". 8 .$ ' :;j .. .
                            , ,r       ...     ~ J t"D
         .,f.14.- : OPERATIONAL ALIGNMENT OF PROCESS TEMPERATURE INSTRUMENTATION                                                                                                                                                                               ,
       \$;l.f%$

• 6 1; & :g,;; ,gl.p.y;,'gx;.z, 4 ;.g.: _. ,.. g .. ,

sf' # f '" ObjectiveftQ' - *~ ~

                                                                                        ~

g'W9"!!4.?d@.,WFl-A 9 ~

        .'.#+y@IMI                              3 To' aligir the 6,TTand Tavg process institsnefstati n.5 9

p,c;

   #l$W16fj~$
         ~        . . .. .'                                          . .
                                                                                                                                        ~ ~

o

                                                                                                                                                       ,m.

a,;Yg -$ :QG1

                                                                                                                                                                                    .'% - a;; "

h,i Mi.i, . V.W_is.

6. ', c :N,.&, 9..g. 5

                                                                                                                                                                                                                               - :'*t:r-/              -4 s Plant Condittons/ Prerequisites                                                                                                       . i                                                      4   ca-                          ;f

_ < %up. v " ~r- .~. ~<'

                                                                                                                                                                                     ~ b%         ..an
                                                                                                                                                                                                     . - &%e ^- m. .m'"

t. 4, .;* '.N Cw 'Lt.3%}yj' ,WW,;*k.wkQMy%g%-s4

                                     ~
                                                                                                           .-c                                 h..g s.J - .                            - -       ':.o A*                     '

As required by the test instructions, portions of this aligtunent will be ~ perfomed prior to initial criticality and at the 75% and 100% power

                                                             ;f.7                                                                                            -

5-plateaus. "Is

                                             ,p. ..,,+ : 0 ;.%[g',7                      . n.    % :~a.-      :- C d . , ' ,' ' ' .
                                                                   ~

Test Method '.' a c e: r . .: u- - During plant hestup, an isothemal calibration of the RTDs and incore themo-couples will be perfomed.  ;.g ,.$0.;ii,Wq . . y:.

                 , 'i-* ;c ',- ~ >i.9 %;,uh',p?A;WliQ'. : NWNM%5hn.Q:;.
                                                                                                                                                                     . ' '.? .              .

The A T and Tavg instrumentation will be aligned at isothermal conditions prior to criticality and at approrimately 75% power. An extrapolation of the 75% power data'will be made for the 100% power values of A T and Tavg. ' At or near full power an alignment check will be performed and' any necessary v readjustments will be made. '

                                                                                                                                                                                   ~
                                                                  -: M, ? Q.'s)O: ?&'e. . , ' ' '                           .             ,                              :     ~      -

Acceptance Criteria ' w... s .,. w : . m ~ + k - ~ r b m ? , 7 7M *** " A= - The A T and Tsvg process instrunentation .fuMkn ui"#- N Gne4Esf requiu ' ',f-th,. ..fc , . 217 "c;rrr. , . r e

                                                                                                             .-4 e
             ,                                                    -                                   .                             .c.-
                                         ,.         , ,,.              's            n'.. ,. -% ,                                                !                     -
                                                                                -          .'- ',' 'V ;
                                                   ,3        ,-                 ,2

• x . ;s - . .

                                        '[        e            "

• ls' fl _-

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                                             .-             ,- , , . - y 4'

b - h ' * ~ *

                   -w            :-
,                                         -yi;;gy.      .
                                                                            ,,,        ,wgge.x,.g, q , ~;.y.. ,. . t.

TABLE 14.2-5 (Sheet 18 of 53)

a. ?:: . ;.y s.

r - .

          ... / n h g15'.:_ REACTOR PLANT SYSTEMS SETPOINT VERIFICATION                                                                                                                                                    ;

Y$ N h.Y N D aD,2k i 53 ' ' ' i Mh %d% O ." ^'t; 5 dl

       ?' Tb3veriff u -f.,                  $%$wh%w                    that-idicial'bL%w644'                                                                                               k$&h,j$5W ~ Odi-l                           \

setpoint adjustments. have been made prior to plant-

     #h{.?        ~d stsetup' and to' maintain a record of setpoints which required readjustment
       %'       %W29'    uring, initial startup testing. . :: g y Q Q pp g ~ q q;y p f, .. . !g' jF;. ' gg. 'O:.                                                                          ,
         ~17[M!PlantConditions/ Prerequisites 9]/Sk W J $^*6 M N O.i! D .n,*4. wig ,
            *'kkT.n v-: 9. <::n n:93%.-ir:

Pl '-:E????

                  ~ Prior to initial criticality and following full power testing.
                                                                    .                   - - n-              ,; ;                              y Test Method                                                                                                                         '
                                                                                          . . . , . .                        *,.          ...e                   _

Verify and record initial setpoint values and any changes performed during initial startup testing. . .: - E .

          --l~fNyCMT1.%6fp;?:M"~.$xw&34p?plfiej.-4[$h$?                                                                                                             &$^**"'~                   * *'       ~
           .;.f,JAcceptance Criteria                                                                 ,'                  ' ? T@g@&f;.s..
                                                                                                                     ...g,5                                 dMpn ?;i :f.: t ..                      ,       ' '  ..
                                                                                                                                                                                                                      ~

D[J y _ , . .S-4if;S4A ?fkh rM' , 4 O'.:The4setpointaareverifiedtobeinagreem$yiE*.. ent with the settings and tolerances O specified by the4= ~ *--- T _ . m. p n c-- y I 'I - -

• 4 ~3-if.iT M & & % - 3 5 & & J %$ O(

y -h-c Q gA,'s & /5hsd.d., W

           ~7"@ sQ -ta%g &' h '                                      .                      .                                                         .
                                                   =

e h+ ,

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a- f

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9 6 I e e a

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( =r 4 g , m 5

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r ' ..;., .':py.y.'.xw@. e

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                                                                                                                                                                                                                         ~
                                                                                                                                                                                                                           .~
                                                                                                         ~<                            . . .; . . . . y . ---                                                                          ,

y .. TABLE 14.2-5 (Sheet 20 of 53)

                                                                                                                                        ~
                        , , ,                                                         ,,.               _-     ~.g       .- .: v .,              -                                                                          -
             ..t. 3  M r$.17.- cBORON ENDPOINT MEASUREMENTS                                                                       ~                                                                                    .
                                                                                                                                                                                                                                ,   ...i.;

7 d i, c. ; - 4MEAY.bS$$&' W~S?, ' 1 4 W M obiective. f'*% f*A!'* bS 'b'E?:M%

&WW$5?~!"'M T ' 1l "l05k'* C + ,. -

          $$h%&an?"%S$9"h$./Y ~ ~ .kv . Ar                                                                                                                                                                                    . h$5bhNU 5U5 ' ~ -

• 1* '

          -9] N I     Tb'determi'ne the critical' reactor coolant system boron concentration appro-N.> .:r/ priate for a specific control rod endpoint configuration.                                                                                                                                                                                                                  -
         . $ b M E = S B $ $ U W - N i k : % ?'^T~~' 5 ,V W I O 5 W & Q i & h k k . % S W c & ' ^$ .                                                                                                                                                                                                    ' '

1 Plant-Conditions / Prerequisites 5 % ,, - g.

                                      . ,. . .+ - . 3 .                                                            .       ._ . m 0,.?:v.S? '. .' '                                                                                  ,

The plant is critical at hot zero power conditions and at the control rod configuration specified by the startup sequence.' Test Method -

                     - The boron endpoints will be determined by measuring the boron concentration of the reactor coolant system at or near the desired control rod configura-tion. Iferequired the rods are quickly moved to the desired configuration
                      . with no boron adjustment. The change in reactivity is measured and conver-ted to an equivalent maount of boron to yield the endpoint at that' rod con-O                        figuration. The data obtained will be utilized to determine the boron worth.

Q ..- } Acceptance Criteria The _ calculated boren worth 1 -:=- -- bu with the value contained in the 7 - %=-= = 4 = -reportd r , ~

                                                                                                                   # /* OQ                                                                O                                       g s

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                                                                         -- ' *                          $ , 4..                                                                                                                           .

_N_&&Q& Joe %t5[5.$ -Yh W$T&l,'N.YsN

                                                                                                                                                                                              ~

oi ** L-:f :; w'r i , .m yW;l1.% eT}sG ss.Kf;,.Q*1l.fiQG y).RKS)*k* .-[f~'g.~~Q+f}g~ E~ N" ' * - '*~~ ~

99 2c '

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      ,+                                                                                                                                                                                2'                                                                           .                            ...

e p.Q

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                                                                                                                                                                                                                                                       <,  S.Y,',*k'    ft ,. .fY'/

t. T $4 '" Y * ! ' r'

             # 't ~,k..Sh u Wm                                                                                                                                                    4h r W,X4                                Y - ^. b Y -                                                  m.'

ec ; 74's .g .m +, .Mw ;%.e~- c ' t~ ,~ - 1 s,. x n

                              - i';y,p*[;A.[mnA;Qggr${n                                                                                                                                                                                                                                                               '6' Q ' x..,. ,.yzIR                                                                   N'574,G. %.
                                                                                                                                                                                                                                                       - '        5*
                                                                                                                  .                             ' TABLE 14.2-5 (Sheet 21,of 53)
                                                                                                                                 ?                      .     ,          ,

l l ISOTHERMAL TEMPERATURE COEFFICIENT MEASUREMENT

                    ,-gg.18.gg
                          .     .a
                                                                                                                                                                                                                                       ; .;;g
                                                                                                                                                                                                                                                                                        , . .                   ,               a   J fabiseeivef^+g                                                                                                                                                                                                                                       fjg
              \ b W G rat                       Nd- $dk.

y ; Qj[ggg,A fM EM U, IFjy E ' W M9 D i(;f Tb then isothermar. temperature;coeffi'cientt . l ',. .. 1 3 5 .

                                                                                                                                                                                                                                                     %    Q.*#                             P                             +.%
             'i.' . Plant Conditions /PrerequisttesWW&mWAnWW4l;ic.                                                                                                                             .                    *      .,e.# , .            Ib#Jb.

PO'.-d.i ..-mb.h. A. :- ~' h

                    ;The plant is critical at hot sero power conditions and at the control rod

configuration specified by the startup sequence. '

                                                                                                                                                                                                                                                         .,/   .                             r        ,                       i ^
                          %;s% ": . :~&cM.QQtgf:                                                                                                                                                                                          . ,
                                                                                                                                                                                                                                                            ,9 -

Q Q -f, Q.e xEM. . Q.WQ-ag*Qll:k.

                                                                                                                                                                             ..$ p. ,,..;.3.

Teee Methad yN.:u

                                                                                           .                   .       ~. -                                         ,

The isothermal temperature coefficient will be determined by alternately heating up and cooling down the reactor coolant system at constant rates while data on reactivity and reactor coolant temperatures are obtained. A ce t - n m v e.w m argws9?oadia8f5MW. u M C :'.

                                                                                                                                                                                                                                                                                                                                  ~

The measured values of the isothermal temperature coefficient ar w h ~

                       ^^^.                                     .             .                                  . .                         .
                                                                                                                                                                                                                                                           = -^ ^

• P_ach_

                              .          w, 7**a T C t10n m aZ.-auww An F.D4 seauwy                                                                                                                  =+y=As 's u yusy.

k. .a" ,y.a: J '~ -~~ % =nts.

s . . . . . -

                                                                                                                                                   - s f .* .*yge _s',% ,Ip*IW*i' - * ** '.*;* * **' ' / 1 ' * "y f 2~'                                                     ' ' * " ' '
                                                                                                                                                                                                                                                                                                        * " l'         ~ * ' ' '

g . J ** .

                                                                       .;. Q                               _ . , 6 c '.'"??V;._*5y *.i "' iq:,W~,-*' *' ~
                                                                                               ,4~.                  ,
                                                                                                                                                                                                                     '                                             e                           *
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                                                                                               ,y,                 -se . - -
                                                                                *               \                       3     , i,'
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                                                                                                ,.           ,4# a . '*. '             %.. f ~. . _ - . ' , -                                       , ,, .
                                                             ,..p"l                      - ?$.,}A
                                                                                                       ,   -&           J = 5 g.s^ ~ 'r f. . 's T.
                                                                                                                 .;.....t                            .

c '2. f-;, -) ,tOl[- :: 2 - ., i l .- i' : ',.

                                                                   .                 ? qa,y' ) Q ' l&Ij N lfs *f                                               ' '
                                                                                                                                                                        ].*.*

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• d, **
• l J7*' . =, * - ?. ', .l'$' * !9. ., -l ,

                                                                 .+ *,<

y .: >.*<- ** ~) * - I

                                             .J --
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                                                                                                                                 , .".f.J g . y --    ,
                                                                                                                                                    *r ( .s,-m.,.   -;                            ,                    ,

F

                                                                                                                                                      ~
                                                ., . *         ,            .                   ^'~,                    ,.

r;' a- * -l .  ; y.

                                                                                                                                                              < : ; . .~                             >.2+1                 2'.                                         -
                                       .e.c . w t,. &, . i.                                                                         p 5; . ..             y.'u '.                             '.e
                                                              . > i. , I~ ':,.                       p5 . 1.. .gE.r.
                            , . , . , .-                                                                                                                                       ,+                                   s
                                                                                  . . a e>

• f . .g , .1
• 4 On O.~ G - . - ) s w- _. *

                     .        "[ '.a@,M i..i S ~ -h' N.r', , .'f/. +*Td*j
                                                                                                                            ..,,.r 2;-(( n. *** . h, [* . . [*rg . ' k..

[..;. ,..

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                                                                                                       ...-.     !; pu,, ;;. .m . y , + ;;- -                                       -

TABLE 14.2-5 (Sheet 22 of 53)

                                        +1 N ..FLUK DISTRIBUTION MEASUREMENTS AT LOW POWER
            **T.c
             .g          .'id'hNKK

~QnM E '

A -

z. ,., y. , .. .:

                                                                 . w'-

pg,, [0bj.... ~,~ w%M&f&y' ' a

                                                                                                                        -Y~'.s       M m s: ynvy n,w                   d4          3 y,,.)1 W-p c';.4, wLr$.,                        a..;,%

y ,'v~.m , ,. , . ective: p gN*:* ;.3pgmj.,g$*g m s .c

         'M44 NsWW/G
                           - Ttr measure 5bm
                                                                                           %t/ .
                                                                 .the-reactor core fl,u,rdistributiotr at low power.

L

                                                                                                                                          'd Q                           k/NkfbM. y- 7...;u nec.gy -         k p 3iI.h    .wh@      ;w:h h*ceM g/

h rg.p.W,84my:M

     . . ,. 9 gg
       ,             - e.

g M W4 g% %e%@ Plant Conditions / Prerequisites W.w e?p4*M M&M$ ,, ; - $ $ 9 % r. b g' y.

                                                                                                                                                                                    . W. imp.
                                                                                                                                                                                    +
                                                                                                                                                                                               .k. -

• g-r."&.

g Q. ).*

                                                                                                                                                                                                 +gkk.%.,'-.-#.pg;,;;q;,:0   -'
                                                                                                                                                                                                                                . ." w ?

h.Q,

                                                                                                                                                                                                                                         ,g   w..
         . ~.-@9:f;5b The plant is at 'a low power level (less than 5%) at the control rod configu Q"~.ftionspecifiedbythestartupsequence.                                                                                                                                 ~-                         , -
                          *' 6 %fll;Qhyn.'.g.y.q.yg.;jgf g*g g_y: . .' , L         .                         .
                           ^ Test Method                                                          ~

q'y$.,; jf; The flux distribution will be obtained by analysis of data acquired by means of the incore movable detector system. . i [7;Q yi . s.

                        . *Acceptance
                                ..:, 5.s % Criteria               ~ E.,$.h.1_                              5 k l.e}lsj                      % f*E y ;'J:h                          k's.v i.~~$[:.. %

c._--

              ~~~

p EJ:1 +'z,92'

                                                                                                                                                                                 ~
                                          ..        ,1 :,m: ~. : : Q                                                                T

• N j Flur map 'results 'ere- e~

                                                                                                           - :: = with the predicted distributions contained _

n - -z- ir. the c s;. , = r.,s13. Q '

u. ,

                                                                                                            . c t ' n ~y -
                                                                                                                                 . = 2:3                .~.cm- se -

F -

                                                                                                                                                                                       .1                          1

q .

                                                  ,                                                                                                                                    T -' l   ...                ;L.

L ( c.l& :.y.. .n -

                                                                                                                              % g:.2l. ?                  y.
                                ~a ; ..;: y ~2?.";c,)5:g.                                  , x. m-y-gg']\

Q.Q'Q ; j C , i; % .'J, . .

                                                                           - g s*-                                                                                         ;.

s. . . .c. s +v..:w. ~ ,; . 7s a. , .m...n:

e ;. .: y y .w .--7.e ' . * * .

                                                                                                            . m.m
               . s .. ,          -:.u+
                                              .y,.,.wa s; ~.,w& 4p=e+ *+w - i.w Wa o.^a ~ 4 ^ " ^ - -  ' ' ~ "' ^' "                                                                                                ' '        ' ' ' ~ ~ ' '
                                         '* ' :' ? .R                                                                               .s .- ,*%' , . 'Y ' ' -e '
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a

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                                       ....,,..s.    ;                    .y.       -

- , ,. ; y .y

                                     .  ..),:~.>..,..". ', ': ,y'. .
                                                                                ,"..     .,'.f.'
                                                                                                 , ,             'y
                                                              -,                                                    ,          .e    '
                                                               *             **"r 6

o 3 . g , a -

                               ' .         a , } , 'Ly                     .. ; . . ' ' _'. ~' l .' ' I L ' ~
                                   ;.;l^$.        U.         >-$                                                                                                   a?                          '

m di',%.-l- . , . .1~-i:."K<. 'W

                                       .m 5Y2MWe .%=wph:v"Ri&M&W.CQf.twFpisWYMMW#:VMWMWWiWMWDM?L

                         * b.(Ul5d'k'&',*R ~2 (~0= Y~WMUN (.WW'* - ~ '
                           ~
                                                                       . . . .                                       TABLE 14.2-5
                                                                                                         '(Sheet 23 of 53)
                                                                                                                                    -~

a -

                                                                                                                                      - ~ . ...                   p,                                .
                       ; 20. CONTROL ROD ii0RTH MEASUREMENT                                                                                                       i    .

d . . . W.- d. '

     .            .                   .'                                                                                                                                                                           i      -
     .4 control rod bad 'and to ensure- proper shutdown margin.ruine                                                                                                                                          TMW.5-l'f~
                                                                                                                                                                                                                       ;:" Jcthe..diff~erencia            94'7,f
                                                                                                                                                                                                                ,,2
      ".'.                                             ~. 4                                                                                                                                                                                            .
        . The plant is critical at zero power at, the control rod configura.: ion speci-
         'fied by the startup sequence.
                                                                                                               ~                                                    .

t

                                                                                                      .. .                      'i .'uc .f                                           .  -f.                      ,
                                                          ' ~ fr.1m:f.?g%N ${'$0$pk.e <w.-]T ? '
                                                                                                                                                                                         ~

Test Method "'~/,,.,,'. Control rod worths will be obtained by maintaining a constant boron addi-tion or dilution and compensating for the reactivity change by rod move-ment. These changes in. reactivity are recorded by a reactivity computer - and analyzed to obtain the control rod worths. Analysis of the collected data will be performed to confirm adequate shutdown margin. ~ !< ~; <' 'l[ et.n;!$1%W-%QQ.f&ggy'Q~-;yt Acceptance Criteria - fr %'; QQyjfp$g'f;.;5plyi w .4 c n" ky-f, -

f *Si[]l 3 . , , .

n , jw.W.7 Me

                                                                                                                                                                                .uf$.k.,wpa.c +. k The measured control rod worths                                                                              . o #=*-                           '
                                                                                                                                                                # 9 t he . J ,.. . c ou w d d -
          ' ;ie saf:t- -- ' d s . '                                                                                              . ec .. -                                                                                                                     -

8 '-

                                                                                                                                                                                                                                            ^

r .---W-

                '- '-                                                                                                                                                                                 ^
                                              +' ',' Q. .{lT.i*g?
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T

                                                           ~n.f.),;[y,'C.^~                                        s';-     ef'       .a     .           -    .                                               *                           -

s f - M g b  ; p , 4 g 1, *' .w . a i

                                                          .0,kO'5b e . .. < 5 r ... A :. ; .c(.                      :.$.].&mg!~ 7
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w :<,

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5- T . ;d. .v .h..fh!N.'.Y b,.'8-[ i'.' #~.~ *' <

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                                                                                                                                                                 - ~-
                                                     ., , m k.

r. u' h i- .

      ^
                                  . * -; :' '.T    C ..y;;;           '*;f i,,$       ,. T,. 'l.' ',' , ' ?'Y.                              . N "'~",  ., : "Y         ' ,? -
                                                                '. i.n        ~. ~q.:,                                     ..                                   c ...                                   '
                                                                                                                                                                                                                                                 ~
                   .. a:.        w ' %. 1N&.k. r.,:*.h 'v.. y ,.y.

. . fa. W D uy t . .. . : ' .> ' - .

m

• m *a "I 9-

__m Vf

        %. .,,4                                                                                                                                                                                                                                                          ,s                            '
     , %.9 .- .,
           ~"                                                                                                                                                           Z..                                                                                              jrg i          (..                                                                    ,              . . , p: .W ~U.*f
                  * $ty                                                                                                                                                               i ' {.                                                              +?<". " ' c m                                                                                                                                                          n                                                    M u@r..N                      4n"9'1
                                                                                                                                                                                                                                                   ~s J k .i  ' '
         )                 -wwgifd,'.%.,.?.~..qgjgr?r

%NgdMp,

                              '~
                                                                                                                                                   ^
                                                                                                                                                 .~ty:-v         ,;2.4N       Ml"kJL           '"            &.%          '%1.*

18,W'y.*(CY,%mf,Qhyv - . .

                                                                                                                                       . TABI.E 14.2-5 (Sheet 24 of $3)
                                ,          . a, . ~ ~ .                           ~                 ..<.-n,.                         ,.                      . , ;....,
                     .. f 21 '. PSEUDO ROD EJECTION TEST                                                                                                                         \ 9'                  . .'        u..c-               .
                                                                                                                                                                                                                                                                                        ^

1 i f onservatism.of*'the. ejected rodc. analysis at zero povert o a3. ct.geWJtA

              ,^
              #.K     $ .~ 40{.~. . % , . ' .Y **.$$ &                                                                                                                                                                                                                         ,,, c ,' W
              }[}PIant Conditions /Prerequisitss                                                                                .
                                                                                                                                         &~ e?         , e.<           ,
                                                                                                                                                                                                        *,.M'g,,QtMi'6{T)'y,'
                                                                                                                                                                                                             ) h Q i 9 h 'j U i$.pR                           . @I; f M ;,',.3Qi ,

h Q 4 Stf o owtr . ao a: . 3G.I t t/ nc# 10 9 - p W.{ ,

             T> lNt tth- wM1...a_-g--...-==]_w         . be.ged amod 4:m c                                                                                                 _          '
                                                                                                                                                                                     .                                 .         .. x            .

sp ' -

               * -14W4T.W@$pMJ(%;g)"'fl:tMaMJg-ps.g!!Eq.s                                                                                                                                         hp$gi'.{ 77 i, DJ

Test Method .' ,1% 8#p e MAN F'f2.495r." ' ' * -

                                                                            -         .e                    J..mw:.a p..,c~       ..

w:;s s,y_m.-

                                                                                                                                                                                                      ~

The selected RCCA will be fully withdrawn Ohile compensating for the reac-tivity change by boron additionsy A flux map will be taken to measure the resulting flux distribution. at h(Cc'5% . . .

                    .                     - , . : v w. u s..g;. .g:.g.y,;,.:
                                                                                                                                                                      .. .. : n > ... u. . .. ..., . _..,

Accepcance Criteria ..u..p,g:.d;.,eLns . m .,.'% q>Kty. -6.m'W :p .> ' ~ ~

                                                                                                                                                                                                                                + iC; e'.
                                                         , a. y. . . :n;,hq. .;.:                                            9p .a ,. r-m.,ql&M.l.?.~2       ; $ 2,..9.- ::;c;,,'- v'@hy;!.'; ~F %.*.
                                                                                                                                                                                            .; A : .
                                                                                                                                                                                                                         +     .
                "~ Analysis:of the data obt.a.ined yields rod worths and hot channel factors                r which are conser..vative with respect to the :_~ q                  .

1,.1. m..; ..

     , /                                .: QMlsj                                              *;Q.y:) g5                                             '
                                                                                                                                                                                                                             ,j g y                                 wA 9                                           .L. n ke..
                              .} < , ' ,      .w.n c.-<.
                                                                              ~
                                                                                  % y . (.Q.g.- K ,p. y ; ,.,. g                                                 u** , ,;,;.,,..
                                                                                                                                                                             -c',r ' .

a , 9 y . w <,; _ . ;. . * *- .

                             .?.s aq 'A p 4.-*c-                                                                         sN>p.%v.,.."e.tAv ,. g .,mp , , , ,a,                                                                                                                                     .y
                                ;.... . . . m.--*d.geris-g4
                  .                                              4 q:,.             .

3 p.y:yg;y.cy;. :'.g .;. ;,my; -s,;.

                                                                                                     > . .                            w,                                       . . . .
                                                         'y                            'r'

(* ' ^ 's .'. 1. .- ' * - . l I \ r , . ~~. .. l' . 4 ; .h .c.' . . . - ' , . , , . . . . id ' <

                                                 ,                       .             . g...         ,         .a n .             . , . , .                           .   .
                                                                                , , . . _ , , . y ~ R h i .e W                                                     ,-h
                                          ':a   .e s                                              ,                                                                                   . -                 -

as- , ~ . . , *-

                                                                           ~.g,,-          . .: nve...     , .. u  ~< f.c , ., . :                                   ,
                                                                                                                 .v.

r s

• e 5

n a . . f . *;.. - . ,

                               , .                                                               . .                                                                                        .s.-
                                  , ,.                           . o . . . .%. .3.<_=.
                                                                                       <                   . . s c s. .. . ,~                     . , . .                                          -
                                                                     , h.             **",         ? } l.' ' '               ). a.    , ,                      .

a'  ?* f . ' % ,).~,. .,\ ' 'l'$

• lEl, ' . 'b.e,0 ~

                                                                                                                                                          '.* ,                  'd.               ,,                .
                .          h                                                                                                                                                                                                                [                                .

                                                                                ., . TABLE 14.2-5 (Sheet 26 of 53) 23.. DYNAMIC AUTOMATIC STEAM DUMP CONTROL
                         *t ' a                                                                                                                  .
     . Ttriverify.-proper: operation ~of the*Ta'vg; ste.sse dump control. system, tot                                                                                           .W 4      . .u d}

2 demonstrate the dynamic characteristics of the controller, and to obtain the ' Tfinal settings' for steam pressure control of the condenser dump valves. .',; , ' ...' {:.W PlantNConditons/Prerequisi h $ W W W $ $ ltesN'h~kk  !%c c . l ;e Yf *$6.-

                                                                                                                                                 ;hW$h?;$5hAV5?,

C,H.. y : - Y?$K I -

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                                                                                                                                                         .2'.o-The plant     is critical at no load temperature and pressure. -

1.yy-g g6; -

                                                                         ;y, ; , cgg,gjy ;.           .

Test Method _

                                                                                            -,j ' g- f ,                       --         -

Reactor power will be increased k:o approximately 10% by rod withdrawal and steam dump with the turbine in both a tripped and reset condition to demonstrate proper operation and the setpoint adequacy of the Tavg-controllers. With the steam dump system in pressure control, power will be increased to demonstrate proper operation of the ' steam header pressure controller. Any gequired adjustments of controller gains or ,setpoints will

 ,l      be made sa necessary.                                                                : r:l y %.&:6[f W ;                                         ..
                          .,_.s; ,;.3. w ; % n'yt;;7. r'. .,f.J. s.                                                           . , .

y -

                                                                                             .w                                             .

Acceptance Criteria' V i- gF The steam dump control system operates in :::: d:::e 1.="i M W i~ 9MALUcu.73tf,, :L .g uem de s ipr cpin nte and is capable of maintaining the react r coolant systeur

       ' temperature at the .>-d.J                                           s ch. c. :: - ' " -                             w                                              .

44

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                                                                                                                                                                               ,a..   .   ,

g;; TABLE 14.2-5

                                                                                                              -(Sheet 27 of 53) 4
                                                                                                                                                         ^
                . 24. AUTOMATIC REACTOR CONTROL                                                                                                                       '

A*h Objeetive. $ c$ - .$p?- , . gt

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                                                                                                                                                                                                               '" *

• YG*I O A # ' '.

                                                                                                                                                                                                                                         ; Y~~                      #21':' "

To, verify. the capability of' the reactor controI" system to maintain. the. reactor.-' .~ * :Q,' G ', ' i ' coolantf average temperature within acceptable limits. . , , . . ,, ,,. s. 4; . 4 . 62.r j jiij .% i@8D'$PIPA$TD4MiINAVI'M-id'ddirdih%dNgd/pf Plant Conditions / Prerequisites

• 4M #ij3: - ; Y -

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M GWfft:. 3%. . ,,,~ ~7 " ' ~

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                                                                                                                                                                                                             ~
                                                                                                                                                                                                                                                             ~

The plant'is stable at the 30% power plateau.

                      . - %:- zl. '4;Qg: t%~4:.f. (e -                                                                                       .--

Test Method . - 'c.2 .' -

                                                                                                           - ~

Tavg will be varied from the Tref setpoint and the control system will be placed in automatic to verify its ability to return plant temperature to the reference value. . . . . e sp c ,

%'q.p(.*WeAkifhf, . . ?l.5,& , f ' j rf. .., f.2f.QL*?y{i? 5 " ' .

Acceptance Criteria . .. . c .g -.v

                                                     , n . r ip 44Ni&(([.,h' .                                                                                                                   6,.

E A- L d i 7 7.t.t .. tor control'" system functions L ms,. h--- *-i:L as g ;- E-L a =_ G 5

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TAELE 14.2-5 (Sheet 28 of 53)

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_ . 4;:1~ . .; ? M -.;p? h G ha : '*. <' . ,. dF=.u n . ?f . ' ..! : '" . Ap4 ,25 G AUTOMATIC STEAM CENERATOR LEVEL CONTROL s- ....,. ., 9 i -f t e 5To ~ if'y the stability of~the automatic steam generator level control-.

                   i .. b.. tvers'yst'em~ foIIowing . simulated transients at low power and to verify the opera-.

tion of the-main feed pump control systes. .f;;.fg".;,;4 lva t; & ,3.(A ,.* y

                  %,'@?DERh&R$WOMEP?.4,*M:

O Q'g..;.PlantConditions/Prerequis1tes49fE%RQ$Q' t&.

                .   .:                                                                                                                                                                                                                       {                            .
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• The plant is stable at the 30% power plateau.

Test Method , .

                                                                                            .               ,              ,     , . , % a,1 . , .                                           . ,                           .
                                        .Steamgheratorleveltransientswillbesimulatedtoverifyproperlevel 1
                                       . control response. The operability of the main feed pump control system
                                        .will be verified by manipulation of the controllers and by simulating se-
                               .       ;1.ected input signals.                                                                                                                                                         -$ .? t _ : . . ,. .. a . .< .                                                       " _..            .
                                                                                                                                                                   .w '-p!.r.*..ygp*h U$pli'. -iy .: .
                            . '. ,'O.ci                        P$ QOWi.L5Gi$$h!?,khW{QQ.4                                                                                               6 fatL1.h
                                                                                                                                                                                                  ?.

Acceptance Criteria

                                                                                                                                                                                                      .. -?:3                                                                                                4 7

w. .

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7.-;:-

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The e enerator levei.-d =M n feedwater pump control systems function apaaM A y u c:. #::t- aneef51Mnernh - -- -

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TABLE 14.2-5

                            ., , .               :;, e g .;' r.: C.*(Sheet 29 of 53)                                                                                                               .-

j> Y < ~

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                                                                                                                                                                                           ?%               ..%w      .
                                                                                                                                                                                                                                                     . .hb.

26h-THRMAL.POWERJ MEASUREMENT"ANE STATEPOINT'. DATA COLLECTION

                                                                                                       ~                                                                                                                              . O! -          1
         ~P   . ,, ./d:Yg-r Ob3eetive                    g%M.                                                                                                            ~W             y
                                                                                                                                                                                         ~j hN$.hi.h                     gha <
         $@@J.Wif 8W>M
     .'iMTor obtain various primary and secondary plant temperatures, pressures, and 4                                  .             -              Mb . 3. ..D N       ' @d g!yij'.4.;y:d p.4m x                        !4 N
       "8 flows'and' to perform a calorisatric determination of reactor powerf.
                                                                            ~
                                                                                                                                                                                                             -.4, w
             %%a%

Plant Conditions / Prerequisite % & ' u b. e4 J J .:. % . w ..

                                                                                                                                                    . E . J.
                                                                                                                                                                                                                                                   ~
                                                                                                                                                         - f             . -           . , . ..     .
                                                            ...y
                                                                                                                                              . . . .c This test will be performed at each of the major power plateaus (30%, 50%,

75%, 100%) as required by the startup test sequence.

                                                            .-~.s                    . .. . .                     :., 73: v , ..                                                     .

Test Method ~ if'7 9 em 2.aget5wn.j,Q.Q]l}h.'ZM;gg-:x%l5%#C.niq.a: L A :~ . S MJf.. '; . ,

                                                                                                                                                                                                   ?;     -
              .. ..                                                                                                                                                                                                     ~a With the plant stable at the required power level, data will be, collected to allow calculation of thermal power Additional statepoint data will be collected to grovide baseline plant operating temperatures and pressures.

Some of the data collected will be utilized by other tests to aligu various plant instruments. - .:. .vP . , .

                                                   - v ,:;;,.r, .;, t > e :.~s.** .c.2"-9 . . . ~
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Acceptance Criteria - The re; *. J dat h ee le f MM ' SW J n*A--%. s & a damalud n . EsMLu.c46to.9.'7, g b I* . 8 -' ' '

                               =
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• _w _ '-_ - --

                        .               A . . . , . ^ <....,....:.                                       .

u.. . TABLE 14.2-5 (Sheet 30 of 53)

                            .27. .STARTUP ADJUSTMENTS OF REACTOR CONTROL SYSTEM id.N;hM.                                                            '
                                                                                      ~ ~~*d
                                                                                                                              "'^

W L T TM@Nd. s',0bTective*%h$g'f7 ..Q : ., h ' S y ? )krNh. 'f - . , . . - - .$ M Q ,W l'46 @ # d M ,M M o :

                                                                                                                                                                                                                                .gj 10 e -. . . u. i.M:f.g.Qf ??y.
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i Ttri.determineithe

                                                                          ,Tavg program resulting:in' the+optimisplant efficiency- JI.44%@fC NM
           '                       #                                                                                                                                                                                                                       , f :'#.i withou't

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                       ,,            exceeding                            plant,                  wpressure                         and          temperature                          limitations                                        !              ?MWN v.<        . m.                                          y8 .-
                                                                        .m              n aa                                                                            . ..

ay~

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           " strane-conditions / Prerequisites ~. . . . , -                                                                                                                                              p,Ry yue                                          -
            %~ ww.wn?.muwwewsit&Mtkn .                                                                                                                                            .',likVWW$$w,W F ^ff~' w                                                2
                                                                                                                                                                                                                                                     *9y&y,p/        l 1
              " Portions of this test will be performed at hot zero power and various major power plateaus (50%, 75%, 100%) as required by the startup test sequence.

ne.

                                       '~~-T. v3.w.s-;ygjw.; .f.y.~;                                                            .                 .g .3.     ,       j y .                                                                                             -

Test Method f- y.6 ' s'. t Analysis of system temperature and pressure data obtained by this or other tests at the required plant conditions will be utilized to provide a basis for the adjustment of the,:ereactor control system. .y w , ..

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m. - -

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                                                                                                                                                                                                                                             - 'W~'
               'I'he reactor control system has been' adjusted to provide opti== plant performance without esceeding L ;. I 2 0,..1 lu. 2d: ;-i.g y53y mp.

wg ;@~ . . f MMg@r;.crm

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                                                                                           - ,-               TABLE 14.2-5
              . ; :, c. 4$ 1-Mkd'jhdjh2(Sheet 31 of $3)
                                                                                                                                                                             ..-s.c.."...#--                .

28;;,v CAT.TNBATTON.0Ec STN AND.: FEEDWATFE FLOF INSTRUMENTATION- ,. 2

    $$sifdEE55!$$$IE5@1:M'n$$,.

To. calibrate- the steam and feedwater flow ~1nstruments. ~ '..- f V

            -U NDN NNN2%7d2 TiPk%kN %Tjai}.9ddg%y pMS $ Y N'I'[;[" 7<'d ' . ..'                                                                                                                 -
                                                                                                                                                                                                                            ~ J1     $                "

Plant Conditions / Prerequisites - e <-*?". 9 ? % ?.Ylf C N e M - '

                                                                                                                             ,.m r
                                                    .  . . .e , , ? .. .yg  .
                                                                                                                     ,n,e..::n,.

f~.s n,c ~ a. ? n -

                                                                                                                                                         ~. .

Portions of this test will be performed at hot zero power conditions and at selected major power plateaus (75%, 100%) as required by the startup test sequence. - u .J :. :l: O. .,c..~4;*. -N-n v c.~ . ;Q- .'~a

                                             ?                           -
                                                                                                                                                                                  *             ~

Feedwater flow, as, determined by special test instrumentation, will be com- U. pared to steam'and _feedwater flow readings from plant instrumentation. Ad- . justments of plant ' instrumentation vill be made to obtain a best fit to _ ._ S the data from the special test instrumentation. - v U%.i - .....&ij..'->'4 A ~ Acceptance Criteria , , q U.S.p.1. . . -

                                                    . .           ...a.-.                  . n-..v 4,: ai?#t, : . ~                                            -:      ~ ~-             -                                -

The' b n steam and feedwater

                  . -- .~                                m               ,

flow instrumentation has been calibrated tr

                                                                                                                                                                                                              ' thin 1111 %. 4.A      u w w sa h            uwJjv*                                   I * '""                       - S

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V%. %' .?i&*,!;'s  ; ** 2 s%*.k.b M}l.u% * ' ~ . TABLE 14.2-5 (Sheet 32 of 53)

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                                                                       .t. .* 2- l.-.W- ' .yx . x.. 2                      .
                                                                                                                                   . M.;p. ,. . .4yq, 29.c CORE PERFORMANCE EVALUATION                                                                                            ^' 7.-W O_              ,7 '.;f                            ..              .:

[g T.E$MN " provide-Instruction $NMIkkhkk<k, $c.f .

       ..,        Tb
                   .-                                                                  s for obtaining incore movable detector flux and thermo-
        ?      Jcouple.mape'at power.and to' verify pro                                                                                                                                                                          . j' Q ff.W Ed0.$ 1 0 0 W W 'h*N N N.R & . &per.                                                                                                                  core hQ)s'&}Wy'$if.f E       performance                   margins.
                                                                                                                                                                                                      *bdi%O                  Yb, .. ,

h;%-Plant Conditions / Prerequisites =/w w r <;re. b. '7 M h"?G.aurpfc .w

                                                                                                                                                                                                      ~ s'
                                                                                                                                                                                                              ^    ~dy>'i
                                                                                                                                                                                                                       > - ~ .' - '.'
                                                                                                                                                                                                                      ...9-
             ,[ 'n%',. -;.n.~.9ym%w%7. .u:,w.TTC~d. h(Lg)h:
                                                                                                                                                        & -.4 :-J.L.r. n.                                                                '
             -- This' test will be performed at selected power plateaus (30%, 50%, 75%, 90%,

100%) as required by the startup test sequence. Test Method ,,

                                                       - . . .    ..y i .<-Y. th ; f& ? .: , .$:'i.h.s .

Flux distribution data will be obtained utilizing the movable detector system. 79..Incore thermocouple data will be obtained using the analog readout instrument or process computer. This data will be analyzed to indicate core performance. y.\yp:;.f3.  : fg-37.y y . ;;.; , -

            .: Acceptance f 4 ;j :t d sCriteria               n q .-s.h t n Q s, %gwp                                              Q Qgq y .j f f;j                            k,ao.
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                                                                                                                                          . TART.R 14.2-5 (Sheet 33 of 53) 3 -
                       .r, .30J.. POWER COEFFICIENT MEASURDENT cy ..'.t.."
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          ~ '.DPlant Conditions / Prerequisites? - - a ,- .
                                                                                                                                                                                                                                                     .      ebe 5.D' W#*:. STI}
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                                                                                                                                                      ~
                                                                                                                                             .:.p.                               s. %.m n l* , -                              .    '* k This test will be performed at selected power' plateaus (30%, 50%, 75%, 100%)                                                                                                                                                                                                ,

as specified.by the startup test sequence. ,.- . v, . ... . ,a, ; ; ,y'*f., .j,

                                     ..                                                                                                                                      e
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                                                                                                                                           ; NJ                                            mt C

p. ,, - _.;

Generator load will be varied and data will be collected for 4 T, Tavg, reactivity and reactor power. Analysis of the relative changes of these - parameters will be used to determine the power coefficient. From this the integral power defect and Doppler-only, power coefficient can be obtained. . s*~. 1 f ,qv

                  -Acceptance         . %hjoh3Y.piepMigg,.

Criteria - %  %? p. ~ .S.. ,g~'g.q?ifg;:M M./ - t 2. g'~.1"'g.m-p .-

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                                                                                                                                                          .                                         ,.~                     -               -                                          .
                           .                                                                                                                                  ;                        .P W@            .r. m+        4%:<'<costeeM                             -                                 .. -

The measured values of power coefficient of reagvity are Foeeeseeene with 3O0 ' the values contained in the ;;efer - 21 :#- *= ~ - W 7 J,'h: N. **d^'" '

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TABLE 14.2-5 (Sheet 34 of 53)

                                                                                                                            ,                       .,=.

4;;? ~f ' 31.. STATIC ROD DROP AND FLUI ASYMMETRY EVALUATION '

                                                                                "Thd?i                                        '*

IM.P NSy^;(6 0 @ ' M O k 5 L 2 ,4.a .' W . .4 N. ?OhIh$skT objective- - x - e.{ LWWWG'/ d@:h w 4

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         .             . '9 ~WE                                                                                                                                 .                     ,   v M,,e .      ..      .. . AS o!enz.spdu SWh.          'f.e. -. 2.gf c,r :q 4           TE demonstrate th,e-response.of' the i,ncore and'excore ihatrtamentation systems
                                                                                                                                                                                                                                                                     ;I
        ":',         to"alinisaligned RCCA and to demonstrate that core limits are not exceeded 1i
            't.f Plant Conditions / Prerequisites ~
                                                                                                                                                       ' * . 2'/di.q,d?Y-M5'M J -* '.
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                                                                                                                  *w                      ..
                                                                                                                                                                                                      .                             y.

The plant will be stable at the 50% power plateau. & p .- : . '; .:- ~ . Test Method '

                                                                                                                             . .h '
                                                                       . :, .                 - .. . W :. % L i V                                                                    .

A selected RCCA will be fully inserted into the core wt.ile a boron reactivity compensation adjustment is made.' Data will be taken periodically from the

              ,. excore and incore instrtsmentation to determine their response to the mis-
                  - aligned rod. . A flux map will be taken '*with the rod fully inserted .co allow ,
               " analysis of the core parameters.                                                                                                                                2                                          e              W.

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                                       ,             _.                .            . :o                   .s                                      .

The incore and excore instrumentation are capable of detecting a misaligned RCCA and the analysis of the. flux distribution due to a dropped rod is con-servative'with respect-to O.; :_f 4 . ;17 :i: ::;:rt - --~ -

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                                   . .s a . < .           . . ;. ; . s.~ . y.. . .. <- C , f..:m r .. -                                                       1
                                                                                                                                                                                        * [.         ..

SHUTDOWN FROM OUTSIDE THE CONTROL ROOM

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g ,...gAu .-.. s T. w/ U  %$@# I k M'kfkEI#k - $k.hib~p '4. . ,'I' demonstrate-the capabili~ty'to' shutdown'and ma,intain the reactor in a-

                                                                                                                                                                       ~                                                               .
           ?.'-                 bio'ticandby" condition from"outside the control room and to demonstrate the                                                                                                                                                                                              s
       " 1,                                                                                                                                                                                                                                                                                               'i pothtial; capability for~ placing the. plant 'in' a. ~ cold shutdown condition.

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                  . , .         Plant Conditions / Prerequisites                                                                                                                -
                                                                                                                                                                                                    .                                      Qm.

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                    ';- Thee plant                       .m is at a stable ~.:,...                                        power level of equal to or greater than 10% power.

a. i.. .*4  :. . .- Test Method ,,N

                                                                                                                                               ~

ng.. 7.m .- ~~r "- ': . - The plant will be tripped and maintained in the stable hot standby condi-tion for at least 30 minutes. The ability to cooldown from hot standby

                  'ly will also be demonstrated. The plant will be placed on the residual heat
               ,    g,. removal. system and a 500T cooldown will be. performed,                                                                                                                                                                                                            ,A                -
                                                                                                                                                                                                                                                                                's<
                                                                                                                                                                          ' M:ew                                       :,-f.~ K '
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' .Y The plant is e _ _ place.1 in hot standby, and the cooldown demon-stration is . ='  : .} performed

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                                                                             '.J DM"$0.                   9 h'Q @ &'T, 1/.-                                                      i              -
            . a 34. LOAD SWING TEST                                                                                                                                   ','                        '
                                                                                                                                                                                                       )

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                                                                                                                                                                                    ~           ]l,
      < To verify- proper plant response, i'aciuding automatic control system per-                                                                                                              ",
                                                                                                       . f;. ' . .- .;-cr.
        'formancs, to 10% step load changes.                                                                                                                             ~
      ',#YMJ.@??'iW,3 MOM 9??fM8.@IfhIfM_.$.dII[N;                                                                                k$ff.W$N. -         -

Plant Conditions / Prerequisites #

                                                                                  , > .,"'jf y/[-y ;pgjT '
                                                                                       .. .;. ,:.. y -                  .;..

This test will be initiated from steady state conditions at selected power plateaus (30%, 50%, 75%,100%) as required by the startup test sequence. Test Method Turbine generator output will be changed as rapidly as possible to achieve an approdmate 10 percent load decrease or increase, as required. Various plant parameters will be recorded or observed during the transient. i e

• s ;; < c .< A : j .n };:;*' .: Q 'Q:'}g,, .= -

                                                                                                                                ~

Acceptance Criteria

                                                                  +    . , , .

g;.b b ,4 p:. , '.~%.. - - The fo11'owing criteria will be used to determine successful test completion: O

1. Reactor or turbine must not trip.

                                                                                                                                               '~

2. Safety injection is not initiated.

3. Neither steam generator relief valves nor safety valves li-f t.

t

4. Neither pressurizer relief valves nor safety valves lif t.  !

5. No manual intervention should be o bring plant condi-tions to steady state.

I 6. Plant parameters should not incur sust'ained or diverging-oscillations. , , T. Nuclear power overshoot,(undershoot) must be less than 3 percent for load increase (decrease). Note}}