ML20091B126
| ML20091B126 | |
| Person / Time | |
|---|---|
| Site: | 05000605 |
| Issue date: | 05/20/1991 |
| From: | Recasha Mitchell GENERAL ELECTRIC CO. |
| To: | Chris Miller NRC, NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| EEN-9142, MFN-058-91, MFN-58-91, NUDOCS 9105290118 | |
| Download: ML20091B126 (54) | |
Text
,
l
GE Lcles vez i
hiay 20,1991 i
NiFN No. 058 91 Docket No. STN 50-605 EEN 9142
- l Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention:
Charles L. Miller, Director Standardization and Non Power Reactor Project Directorate J
l i
Sunject:
GE Responses to GE/NRC May 7,1991 Meeting on Performance &
Quality Evaluation liranch Open !! cms on AllWR SSAR Chapter 14 Enclosed are thirty-four (34) copics of the subject responses. Responses are provided for all the open items with the exception of open items numbered 2.1.4, 2.1.6, 2.1.7, 2.1.9 and the additional test abstracts that are required to address comments on positions 4.k,5.n,5.w and 5.c.c. requested l
under open item 2.1.8, pertaining to Regulatory Guide 1.68 Responses to these outstanding open items will be transmitted by the end of June.
It is intended that GE will amend the SSAR, as appropriate, with the enclosed responses in a future amendment.
l Sincerely, Q C T i hat k l
R.C. Mitchell, Acting Manager J
Regulatory and Analysis Services i
M/C 382, (408) 925-6948 l
cc: F. A. Ross (DOE)
D. C. Scaletti (NRC)
R.G. Ramirez (NRC)
D. R. Wilkins (GE)
J. F. Quirk (GE)
% () i ')ri 9105290118 010520
,a h l
FDR ADOCK 05000605 PDR a
ITEM BY ITEM RESPONSES TO RT$FF COMMENTS ON CHAPTER 14
~
PRESENTED IN 5/7/91 REVIEW MEETING
,A (Responses in Boldface)
O Based on a review of the ABWR ITP, the staff prepared a list of questions and comments to be responded to by the applicant, and errata information which should be used by the applicant in making corrections to it's ITP.
These are as follows:
2.1 Staff Questions and Comments Regarding Applicant's ITP.
2.1.1 Section 14.2.4,
" Conduct of Test Program," and Section 14.2.5,
" Review, Evaluation, and Approval of Test Results," should be modified to specify whose approval must be obtained before increasing power to the next higher test plateau.
Response-Such specifics will be a function of the plant owner / operator's unique organizational structure and detailed plant administrative procedures and ar'e thus lef t to the applicant referencing the ABWR design.
2.1.2 Section 14.2.7, "Conformance of Test Program With Regulatory Guides," should be modified to address the following items:
a.
Include Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an
(
Accidental Chlorine Release," in accordance with SRP Section 14.2.
Response-To be incorporated b.
Include Regulatory Guide 1.139, " Guidance for Residual Heat Removal," in accordance with SRP Section 14.2.
Response-To be incorporated c.
Either document the applicable revision number of each regulatory guide listed in Section 14.2.7 or reference Table 1.8-20 of the FSAR Response-Section 14.2.7 will be revised to reference Table 1.8-20 for the applicable revision numbers of the listed Reg Guides d.
Correct the reference to Regulatory Guide 1.68.3, "Preoperational Testing of Instrument and Control Air Systems," contained in Table 1.8-20 of the FSAR or Section 14.2.7, as appropriate, to Revision 0, issue date of April 1982.
Response-To be incorporated l
2.1.3 Section 14.2.10, " Initial Fuel Loading and Initial
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Criticality," should be a,odified to state that completion of preoperational testing (including the review and approval of the test results) is required prior to fuel loading.
If portions of any preoperational tests are intended to be conducted, or their results approved, after fuel loadings (1) list each test: (2) state which portions of each test will be delayed until after fuel loading; (3) provido technical justification for dolaying these portions; and (4) state when each test will be completed (koy to test conditions defined in Chaptor 14).
Response-It is intended that all preoperational tests shall be completed, and the results obtained approved, prior to commencement of fuel loading.
However, there may be unforeseen circumstances that arise that would provent this from occurring but that would not necessarily justify the delay of fuel loading.
section 14.2.10 of the SSAR
-will be revised accordingly to require that the above stated conditions be appropriately documented should the applicant referencing the ABWk design decide to request permission from the NRC to proceed with fuel loading under such circumstances.
2.1.4 Section 14.2.11, "1 c st program Schedulo," should be f-modified to include the following:
V)
- a. A figure which illustrates the power-flow operating map.
Response-see rigure 4.4-1
- b. A table which lists the startup tests and states at which test condition (s) each test is to be conducted.
Response-To be determined 2.1.5 Section 14.2.12.1, Preoperational Test Procedures," states that testing of systems outcide the scope of the ABWR Standard Plant are discussed in Subsection 14.2.12.3.
Either this subsection should be included in the ABWR FSAR or Section 14.2.12.1 should be modified accordingly.
Response-The material that was to be included in section 14.2.12.3 can be fo"n( in Section 14.2.13
-2
4 2.1.6 Section 14.2.12 test abstracts should be modified to
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address the following concerns:
- a. Several preoperational and startup test prerequisites include the requirement that interfacing support systems shall be available.
I wvity walch support systems are required for each tout and specify which individuals or groups are authorized to make this determination.
Respons3-Interfacing support system requirements will be specified in the detailed test procedures (and operating and maintenance procedures, if appropriate) which are required by Reg Guide 1.68 to bo made available to NRC I&E personnel at least 60 days prior to their intended use.
Additionally, the startup manual and app 1!. cable plant administrative procedures shall delineate how such determinations of operability and availability will be authorized.
Thus, these details are the responsibility of the applicant referencing the ADWR design.
- b. The use of the word "should" in most, if not all test abstracts is not a commitment by the applicant to perform certain tasks.
It should, thnrefore, be reevaluated and revised accordingly (i.e. "will",
"must").
O g,esponse-Buch a reevaluation shall be performed.
- c. Several preoperational and startup test abstracts include imprecise acceptance criteria (e.g.,
applicable intervals, applicable design specifications, specified amounts, specified tolerances, perform as specified, function properly).
Modify individual test abstracts to specify the bases for determining acceptable system and component performance.
Acceptable criteria includes specific references to regulatory guides, Technical Specifications, assumptions used in the safety analysis, other ABWR FSAR sections, and applicable codes and standards.
l l
Response-To be determined.
(Note chapter 14 of the j
SSAR was written primarily to document the appropriate j
testing commitments contained in Reg Guide 1.68.
It was anticipated that precise acceptance criteria would i
f be provided as part of the ITAAC effort)
L
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d.
Section 14.2.12.2 states that failure to satisfy come
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acceptance criteria (e.g., those related to values of process variables important to plant design) will result in the plant placed in a suitable hold position until resolution is obtained, while failure to satisfy other acceptanco criteria (e.g., expectations relating to system performance) may only result in the need for further data analysis.
The distinction between these types of acceptance criteria is unclear.
Modify Section 14.2.12.2 and individual startup test abstracts to differentiate between various types of acceptance criteria and the resultant actions for each type if uncatisfactory test results are obtained.
Response-As stated in Section 14.2.12.2, " Specific actions for dealing with criteria failures and otner testing exceptions or anomalies will be described in the startup administrative manual."
(To be supplied by the applicant referencing the ADWR design) 2.1.7 Startup test abstracts listed in Section-14.2.12.2 that are not essential to the demonstration of conformance with design requirements for structures, systems, components, Lnd design features which meet any of the following criteria should be provided:
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- a. Those that will be used for safe shutdown and cooldown of the reacte-under normal plant conditions and for maintaining t'.4e reactor in a safe condition for an extender' chutdown periods or
- o. Those that will be used for safe shutdown and cooldown of the reactor under transient (infrequent or moderately fraquent events) conditions and postulated accident conditions and for maintaining the reactor in a safe condition for an extended shutdown period following such conditions: or
- c. Those that will be used for establishing conformance with safety limits or limiting conditions for operation that will be included in the facility technical specifications; or
- d. Those that are classified as engineered safety features or will be used to support or ensure the operation of engineered safety features within design limits; or
- e. Those that are assumed to function or for which credit is taken in the accident analysis for the facility, as described in the FSAR; or
- f. Those that vill be used to process, store, control, or O
limit the release of radioactive materials.
-4
O Response-The tests abstracts contained in Section 14.2.12.2 of the ADWR SSAR are intended to meet the requirements of Reg Guide 1.68, updated and/or modified as necessary to reflect the actual ADWR design.
A screening will bo performed to identify and document a,.',' testing that is currently specified for systems that are not essential for demonstrating conformance with the aforementioned criteria.
2.1.8 Review of the preoperational and startup test phase descriptions disclosed that the operability of several of the systems and components listed in Regulatory Guide 1.68, " Initial Test Programs for Water-Cooled Nuclear Power plants," Revision 2, Appendix A, may not be demonstrated.
Either expand your test descriptions to address the following items, insert cross-references in Section 14.2.12 if complete test descriptions for the following items are provided elsewhere in the ABWR FSAR, or modify section 14.2.7 or Table 1.8-20 of the FSAR as appropriate to provide technical justification for any exception to Regulatory Guide 1.68 Rev.
2, for the following items:
2.1.8.1 Preoperational Testina O
1.a.(2)(d)
Supports and restraints for discharge piping of SRVs Response-A statement has been added to section 14.2.12.1.1 indicating that testing of SRV discharge piping supports and restraints is specifically covered by that testing described in 14.2.12.1.51.
Section 14.2.12.1.51 will be modified to specifically cross reference the applicable testing requirements given in sections 3.9.2.1 and 5.4.14.4.
1.a.(4)
Pressure boundary integrity tests.
1 i
Response-Integrity tests of the reactor coolant pressure boundary are specified in Section 5.2.4.6.2.
Section 14.2.12.1.1 has been revised accordingly to cross-reference the applicable testing requirements.
1.c
. Protection of facility for anticipated
. transients without a scram (ATWS).
1 l
Re.sponse-
)
ATWS protection functions are tested as part of the respective systems which perform such functions (i.e.
SLCS, RC&IS, FHCRD, RFCS).
However, for the purpose of more explicitly demonstrating compliance with Reg Guide 1.68, the appropriate subsections of Section 14.2.12.1 will be revised to more specifically indicate where ATWS related testing requirements are being fulfilled, particularly those related to the ARI function.
- 14. 2.12.1. 3 ( 3 ) ( a) Recirc Flow Control,
- 14. 2.12.1. 6 ( 3 ) (b) CRD System, 14.2.12.1.7(3)(b) RC&IS 1.h.(4)
Demonstration that containment hydrogen monitoring is functional without the operation of the hydrogen recombiner.
Response-In the ADWR design, containment hydrogen monitoring is accomplished separately from the hydrogen recombiners.
Therefore, the specific test described in Reg Guide 1.68 is not applicable.
Proper functioning of containment hydrogen monitors is verified by the testing described in Section 14.2.12.1.26.
l.h.(9)
Demonstration the containment recir-culation fans can operato in accordance
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with design requirements at the containment design peak accident pressure.
Response-The ADWR design does not utilize containment recirculation fans during normal operarI.on or accident conditions.
Therefore, the specific test described in Reg Guide 1.68 is not applicable.
1.1.(1)
Containment design over pressure structural tests (and vacuum tests).
Response-Containment structural integrity testing requirements are specified in Section 3.8.1.7.1.
Accordingly, Section 14.2.12.1.40.2 has been added to cross-reference the applicable testing requirements.
1.j.(12)
Failed fuel detection system.
Besponse-In the ADWR design the failed fuel detection function is performed by the leak detection and isolation system and the process radiation monitoring system.
In particular, gross fuel failure would be detected first by the main steam line radiation monitors and secondarily by the offgas pre-treatment O --
radiation monitors.
In addition, the normal reactor
(])
water sampling system will allow for identification of trends indicative of possible fuel failure.
Testing of the applicable features of the associated systems, as described in subsections 14.2.12.1.13 and 14.2.12.1.23, will assure proper operation of the failed fuel detection function.
1.j.(15)
Automatic dispatcher control systems.
Response-Automatic load following is performed by the Automatic Power Regulator whose testing is described in Dection 14.2.12.1.17.
This system will hava the capability, if enabled, to accept external demand signals (e.g. from the load dispatcher).
Should the applicant referencing the ADWR design-decide to seck approval for utilization of this capability, designation of the appropriate testing will have to be included in the application for such.
Section 14.2.13 will be revised accordingly to document this potential interface requirement.
1.k.(2) personnel monitors and radiation survey instruments.
O Response-Traditional HPreoperational testing" of personnel monitors and radiation survey instruments is not appropriate as these instruments are subject to very specific calibration programs.
It is the respoesibility of the plant operator to verify and maintain the proper calibration and operation of such devices.
Therefore, any required testing shall be the responsibility of the applicknt referencing the ADWR design.
Section 14.2.13 will be revised accordingly to document this as an interface requirement.
1.n. (14 ) ( f)
Control room habitability systems.
Demonstrate proper operation of smoke and toxic chemical detection systems and ventilation shutdown devices, including leaktightness of ducts and flow rates, proper direction of air flows, and proper control of space temperatures.
Response-The test description in Section 14.2.12.1.34 has been revised to make it clear that the control room habitability function is to be included in the testing specified for the dedicated HVAC system of the main O
control room.
Additionally, a specific requirement to
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demonstrate the system capability to detect smoke and/or toxic chemicals and to remove and/or prevent in-leakage of such has been added.
2.1.8.2 Jnitial Fuel _ Loading and Procritical Tests l
2.c rinal functional testing of the reactor protection system to demonstrato proper trip points, logic, and operability of scram breakers and valves.
Demonstrate the operability of manual scram functions.
Response-Buch testing will have been completed as part of the preoperational testing described in subsection 14.2.12.1.14.
Additionally, these tests are part of the plant Technical Specification surveillance program which is required to be instituted prior to commencement of fuel loading as specified in Section 14.2.10.1.
However, subsection 14.2.12.2.3 has been revisad to specifically require that the demonstrations resulted by position 2.c above be completed as J r.c <. tuisites to fuel loading.
2.G Final reactor coolant system leak rate test to verify that system leak rates are within specified limits.
O Response-Buch testing will have been completed as part of the preoperational testing described in revised Subsection 14.2.12.1.1, which references the required reactor coolant leak rate tests specified in 'ubsection 5.2.4.6.1.
However, subsection 14.2.12.2.3 has been revised to specifically require that the demonstrations required by position 2.d abo're be cotyleted as prerequisites to fuel loading.
2.1.8.3 Low Power Testina 4.k Steam driven plant auxiliaries and power conversion equipment.
Responso-Section 14.2.12.2 will be revised accordingly 4.1 Branch steamlino valves and bypass valves used for protec'tive isolation functions at rated temoerature and pressure conditions.
Response-For ABWR the only branch steamline valves used for protective isolation functions are those on the RCIC steamline and the common drainline from the main steamlines.
Accordingly, the description of RCIC O
system testing in subsection 14.2.12.2.22 has been
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reviond to include specific testing of the RCIC O-steamline isolation valves and Subsection 14.2.12.2.26 has been revised to include specific testing of the j
main steamline branch drain line isolation valves in addition to the HSIV testing already specified.
2.1.8.4 Power Anconglon Tests 5.j Plant performance is as expected for rod runback and partial scram.
Besponge-The ADWR design has no partial scram i
function.
Rod-runback is accomplished by the select control rod run-in (GCRRI) function.
Subsection 14.2.12.2.6 has been revised to assure that appropriate I
testing is performed to demonstrate proper functioning of SCRRI logic and hardware.
Also, subsection 14.2.12.2.30 has been revised to assure that proper plant response is demonstrated during the event that will result in initiation of SCHRI.
5.n Reactor coolant system loose parts monitoring-system.
Response-An appropriate test description will be added to Section 14.2.12.2.
O 5.o Reactor coolant leak detection systems.
gesponse-It is expected that testing of reactor coolant leak detection systems will be completed during the preoperational stage.
5.q Proper operation of failed fuel detection systems.
Response-In the ADWR design the failed fuel detection function in performed by the process radiation monitoring system, the testing of which is described in Subsection 14.2.12.2.1.
This test description has been revised-to require the appropriate demonstration of the related failed fuel detection function.
I Also see response to item 1.j.(12) above.
l 5.u Dranch steamline isolation valve operability and response times.
Response-The applicable test descriptions have been l
revised accordingly.
See response to item 4.1 above.
1
~_
5.w Demonstration that concrete temperatures
()
surrounding hot penetrations do not exceed design limits with the minimum design capability of cooling system components available.
Response-An appropriate test description will be added to Section 14.2.12.P.
5.x Auxiliary systems required to support operation of engineered safety features.
Response-Auxiliary syatoms required to support operation of engineered safety features includu the cooling water and HVAC systems whose testing is described in subsections 14.2.12.2.23 and 14.2.12.2.24, respectively.
These subsections have been revised to assure that the testing performed, and results obtained, will ultimately demonstrate the adequacy of a particular auxiliary system's performance under limiting accident conditions.
5.z Demonstration that process and effluent radiation monitoring systems are responding correctly by performing independent laborar.ory or other analyses.
()
Response-This testing is part of that described in Section 14.2.12.2.1(3), which has been revised to specifically address position 5.z above.
5.c.c Demonstration that gaseous and liquid radioactive waste prccessing, storage, and release systems operates in accordance with design.
Besponse-An appropriate test description will be added to Section 14.2.12.2.
5.g.g Demonstration of design features to prevent or mitigate anticipated transients without scram (ATWS), (if not previous 1v done).
E_esponse-ATW8 design features are comprised primarily of dedicated logic, and some hardware, which will be thoroughly checked out as part of the preoperational test program (see response to item 1(c) of 2.1.8.1 above).
Most hardware design features that perform ATW8 related functions do so in their normal mode, only initiated by dedicated ATWS logie.
Therefore, the O.
functioning of these features is adequately verified O
via the testing already conducted for such.
Thus, no dedicated testing of ATWS related features is planned during the power ascension test phase.
I 5.h.h Demonstration that the dynamic responso of the plant to load swings for the facility, including step and ramp changes, is in accordance with design.
Response-This testing is intended to be a part of that described in Section 14.2.12.2.16, which has been revised to specifically address position 5.h.h above.
2.1.9 Section IA 2.4 of the FSAR states that testing described in Chapter 14 is consistent with the BWR owner's Group response to Item I.G.1 of NUREG-0737 as documented in a letter of February 4, 1981 from D.
B. Waters to D.
G.
Eisenhut.
Section 14.2.12 test abstracts that describe testing outlined in Appendix E of this letter should be identified or modified accordingly.
Besponse-Testing outlined in Appendix E of the referenced document is specified in the following test abstracts:
- 14. 2.12.1.1 ( 3 ) ( a), 14. 2.12.1. 9 (3 ) ( j ) & 14. 2.12.1. 4 4 (3 ) (a).
A more detailed review and comparison will be performed of
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the requirements of Item I.G.1 of NUREG-0737 versus the response given in Section 1A 2.4 of the SSAR and the correspondence referenced therein, and the SSAR test abstracts listed above.
2'.1.10 Section 14.2.12.1.19, " Reactor Water Cleanup System Preoperational Test," Section 14.2.12.1.54, " Condensate cleanup System Prooperational Test," and Section 14.2.12.2.21, "Raactor Water Cleanup System Performance,"
should be modified to address the concerns of Regulatory Guide 1.56, " Maintenance of Water Purity in Boiling Water Reactors."-
I Response-Regulatory Guide 1.56 deals mainly with design related issues, specifically the equipment and l
l instrumentation needed to assure proper BWR reactor tfater chemistry.
Subsections 14.2.12.1.19, 14.2.12.1.54 and 14.2.12.2.21 describe.preoperational and-power ascension testing that is adequate to demonstrate proper performance of the reactor water clean-up system and the condensate filter /demineralizer-system in assuring-that acceptable reactor water chemistry is maintained.
Subsection 14.2.12.1.22 describes the preoperational testing intended to demonstrate the proper functioning of the (g g instrumentation required by Reg Guide 1.56.
However, this
,)
1 I
section has been revised to more spsoifically address
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functioning of conductivity meters, which are a major focus of Reg Guide 1.56.
Likewise, Subsection 14.2.12.2.1 verifies that a proper reactor water chemistry monitoring program is in place.
However, this subsection has also been revised to more specifically address the required demonstration of the proper functioning of related instrumentation (i.e. conductivity meters).
2.1.11 Section 14.2.12.2.14, "Feedwater Control," should be revised to address the following items in accordance with Regulatory Guide 1.68.1, "Preoperational and Initial Startup Testing of Feedwater and Condensate Systems for Boiling Water Reactor Power Plants!"
- a. Modify the test description to provide for demonstration of the operability of the feedwater system at low reactor power (15% reactor power)
(R.G.l.68.1.C.2.a).
Response-such testing is already specified in the current description.
A more specific commitment to the Reg Guide position will be evident in the test matrix to be supplied in response to comment 2.1.4.b.
- b. Modify or clarify the test acceptance criteria to
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provide assurance that vibration levels for system components and piping are within predetermined limits (R.G.1. 68.1.C.2. f) ; piping movement during heatup and steady state and tran31ent operation are within predetermined limits (R.G.1.68.1.C.2.g); and adequate margins exist between system variables and setpoints of instruments monitoring those variables to prevent spurious actuations or. loss of system pumps and motor-operated valves (R.G.1.68.1.C.2.h).
Response-The testing called for by positions C.2.f and C.2.g is included in the test abstracts of subsections l
14.2.12.1.51, 14. 2.12.1. 53 (b) & (k), 14.2.12.2.10, 14.2.12.2.11, and 14.2.12.2.18.
Subsection 14.2.12.2.18 has been. revised to more specifically address position c.2.h.
-2.1.12 Section 14.2.1:. 1.27, " Instrument-Air and Station Service Air System Preaperational Test," should be revised to address the following--items in accordance with Regulatory Guide _1,68.3, "Preoperational Testing of Instrument and Control Air Systems:"
1.- -.
- a. Determination that the total air demand at normal
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steady state conditions, including leakage for the system, is in accordance with design (R.G.I.68.3.C.5).
t Response-This determination is part of the testing specified in 14. 2.12.1. 2 7 (3 ) ( f) which has been revised to more directly address the issue of total demand, including leakage.
- b. Demonstration that the plant equipment designated by design to be supplied by the instrument and control air system is not being supplied by other compressed air supplies (such as service air) that may have less re-strictive air quality requirements (R.G.1.68.3.C.9).
Response-Although the service air system acts as a back-up to instrument air, it does-so upstream of the instrument air filters.
Furthermore, although totally separate (except for the manual back-up cross-tie) the design of the two systems is essentially identical.
Thus, the air supplied to the inlet of the instrument air filters is of the same-quality, whether it is sourced from the instrument or service air system; therefore, the cutlet air-will be of the same quality.
Since the design precludes occurrence of the conditions hypothesized, no specific test demonstration is needed beyond the construction verification and preoperational
()
testing already planned, c.
Demonstration that functional testing of instrument and control air systems important to safety is performed to ensure that credible failures resulting in an increase in the supply system pressure will not cause loss of operability (R.G.1.68.3.C.ll).
Response-The test description will be revised accordingly.
2.1.13 Section 14.2.12.1.34, " Heating, Ventilation, and Air conditioning Systems Preoperational Test," should be-l revised to address the concerns of Regulatory Guide 1.95,
" Protection of Nuclear Power Plant Control Room Operators i
Against an Accidental Chlorine Release."
i Response-See response to comment on position 1.n. (14) (f).
2.1.14 Section 14.2.12.1.8, " Residual Heat Removal System Preoperational Test," should be revised to address the following items in accordance with Regulatory Guide 1.139,
" Guidance for Residual Heat Renoval:"
O - - -
a.
RHR syatem isolation (R.G.1.139.C.2).
O Response-The applicable demonstrations were intended to be s part of the testing described in subsection
- 14. 2.12.1. 8 (3 ) (1).
However, the testing description has been revised to specifically address testing of features designed to assure isolation of low pressure portions of the RHR system from RCS at high pressure.
b.
RHR system pressute relief (R.G.1.139.C.3).
Fesponse-The design of the RHR system includes the relief capability and capacity required by the above referenced position, in accordance with the applicable ASME code.
The verification of the proper setting of relief valves is a vendor bench test required per the same ADME code, and thus no specific additional preoperational test is needed.
2.1.15 Section 14.2.12.1.34, " Heating, Ventilation, and Air Conditioning Systems Prooperational Test," or other appropriate preoperational tests, should be revised to address the concerns of Position C.5 of Regulatory Guide 1.140, " Design, Maintenance, and Testing Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power O
rieate."
Response-The testing requirements specified by Reg Guide 1.140, and by the industry standards referenced therein, will be reviewed for their potential applicability to potentially effected filtration and adsorption units.
Section 14.2.12.1.34 will then be revised accordingly.
2.2 Staff prepared ERRATA information which should be used by the applicant to correct the FSAR Chapter 14 submittal.
Section Pace Comment 14.2.12.1.1(1) 14.2-7 "and indication" should be "and indications" 14.2.12.1.28(3) 14.2-26 Title of the subsection on " General Test Methods and Acceptance criteria" is simply titled " Test Methods and Acceptance Criteria".
This should be consistent throughout the chapter.
O
- 14
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14.2.12.1.31(3) 14.2-28 Same comment as above.
i 14.2.12.1.32(3) 14.2-29 Same comment as above.
14.2.12.1.33(3) 14.2-30 Same comment as above.
14.2.12.1.44(3) 14.2-34 Same comment as above.
14.2,12.1.45(3) 14.2-3d Same comment as above.
14.2.12.22.76 14.2-44.15 The Offgas System Startup Test is misnumbered and listed in the preoperational test section.
Move this test to the appropriate coction.
- 14. 2.12.1. 4 ( 3 ) (a) 14.2-10
" Channel Trip" should be " Channel Trips" 14. 2.12.1. 4 ( 3 ) ( f )
14.2-10
" foe which" should be "for which" 14.2.12.1.34(1) 14.2-30
" nonessential equip-ment" should be
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" Nonessential equipment"
- 14. 2.1. 71. ( 3) ( f), (g), (h) 14.2-44.13 (f), (g), and (h)
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margins are out of alignment Section Pace Comment 14.2.12.2 14.2-44.16 Top of column B " equip-ment" should be
" equipment" 14.2.12.2.1.3 14.2-45 "perfor mance" should be " performance" 14.2.12.2.3.2 14.2-46 "lisconse" should be
" license" 14.2.12.2.8.2 14.2-49 "interation" should be
" iteration" 14.2.12.2.8.4 14.2-49 "liscense" should be
" license" 14.2.12.2.14.2 14.2-53 "interation" should be
" iteration" -
- _ _ _. _ _ -. ~. _ _. - _ _ _
i 14.2.12.2.17.2 14.2-55 "interation" should be h
"itoration" 14.2.12.2.18.2 14.2-55 Interation" should be
" iteration" 14.2.12.2.22.3 14.2-57 "direcly" should be "directly" 14.2.12.3 14.2.64 "Other Testing" section not included.
i 9
g e
16 -
l :'
c,
ABMTl
- m.,.
Standard Plant
,,,, 3 SECTION 14.2 CONTENTS (Continued)
Section lills pggg 14212.166 Steam Bypass and Pressur s Control Sptem Preoperational Test 14.2449 14.2.12.1.67 Feedwater Heater and ') rain Sptem Preoperational Test 14.2-44.9 14.2.12.1.68 Extraction Steam Sptem Preoperational Test 14 2 44.10 14 2.12.1.69 Moisture Separator /Rehester Sptem Preoperational Test 14.2 44.10 14.2.12.1.70 Main Turbine and Auxiliaries PreoperationalTest 14.2 44.11 14 2.12.1.71 Main Generator and Auxiliary Sptems Preoperational Test 14.2 44.12 14.2.12.1.72 Flammability Control Sprem Preoperational Test 1424eD 14.2.12.1.73 1.oose Parts Munitoring Splem Prcoperational Test 14.2 44.13 14.2.12.1.74 Seismic Monitoring System Preoperational Test 14.2 44 14 14.2.12.1.75 Liquid and Solid Radwaste Sptems Preoperational Test 14.2 44.14 14.2.12.1.76 nrreu c'-"- Picopctationel-Test-14.2 44.15
( beideO 14.2.12.1.77 Ultimate Heat Sink Preoperational Test 14.2 44.15 i
i 14.2 vii.1 l
O Amendment !!
ABWR mum Standard Plant PfV Tl SECTION 14.2 O
CONTENTS (Continued)
Section Illie Page 14.2.12.2.14 Feedwater Control 14.2 53 14.2.12.2.15 Pressure Control 14.253 14.2.12.2.16 Plant Automation ar.d Cctrol 14.2 54 14.2.12.2.17 Reactor Recirculation Sptem Performance 14.2 54 14.2.12.2.18 Feedwater Sptem Performance 14.2 55 14.2.12.2.19 Main Steam Sptem Performance 14.2 55 14.2.12.2.20 Residual Heat Removal Sptem Performance 14.2 56 14.2.12.2.21 Reactor Water Cleanup Splem Performance 14.2 56 14.2.12.2.22 RClC Sptem PcrIormance 14.2 57 14.2.12.2.23 Reactor Buildir.g Cooling Water Sptem Performance 14.2 58 14.2.12.2.24 HVAC Sptem Performance 14.2 58 14.2.12.2.25 Turl'ine Valve Performance 14.2 58 14.2.12.2.26 MS!Y Performance 14.2 59 14.2.12.2.27 SRV Performance 14.2 59 14.2.12.2.28 Loss of Feedwater Heating 14.2 60 14.2.12.2.29 Feedwater Pump Trip 14.240 14.2.12.2.30 Recirculation Pump Trip 14.241 14.2.12.2.31 Shutdown from Outside the Control Room 14.241 i4.2.12.232 Loss of Turbine Generator and Offsite Power 14.242 14.2.12.2.33 Turbine Trip and Generator Lead Rejection 14.2-63 14.2.12.234 Reactor FullIsolation 14.2 64 44-242-3 Other-Tesdr.g
!t.2 61 -
l 14.2.13 Interfaces 14.2-63 O
m2.eii Amendment 8
ABWR Standard Plant prv A O
review and approval of test results and for re.
that fer selected milestones or bold poir.ts b; I
solution of failures to meet acceptance crite-within the test phases.
)1 ria and of other operational problems or design
[,
deficiencies noted. It describes the various 14.2.6 Test Records 3
phases of the initial test program and establi-a sbes the requirements for progressing from one initial test program results are compiled and phase to the next as well as those for moving be-maintained according to the startup manual, j
yond selected hold points or milestones within a plant administrative procedures, and applicable t given phase. It also describes the controls in regulatory requirements. Test records that 2
place that will assure the as tested status of demonstrate the adequacy of safety related cach sysicin is known and that will track modi.
- omponents, systems and structures should be Y
fications, including retest requirements, deemed retained for the life of the plant. Retention l
necessary for systems undetgoing or already periods for other test records will be based on having completed specified testing. Additional-consideration of tbeir usef uloeas in ly, the startup manual delineates the qualifica.
documenting initial plant performance k
tiors and responsibilities of the different characteristics.
{_
positions within rbe startup group. The startup
'n administrative trocedures are intended to supple-14.2.7 Conformance of Test Program with 5d mat normal plant administrative procedures by Regulatory Guides 7(
addressing those concerns that are unique to the 1-startup program or that are best approached in a The NRC Regulatory Guides listed below were 4i different manner. To avoid confusion, the start-used in the development of the initial test ij up program will attempt to be consistent with program and the applicable tests comply with normal plant procedure where practical. The these guidesg plant staff will typically carry out their duties acarding to normal plant procedures. However, (1) R egulatory Guide 1.68. Initial Test in areas of potential conflict with tbc goals of Programs for Water Cooled Nuclear Power the startup program, the startup manual or the Planu.
ir.dividual test procedures will address the roquired interface.
(2) Regulatory Guide 1.68.1 Preoperational and initial Startup Testing of Fredwater and 14.2 5 Review, Evaluation, and Approval Condensate Systems for Boiling Water Reactor of Test Results Power Plants.
Individual test results are evaluated and (3) Regulatory Guide 1.68.2 Initial Startup reviewed by cognizant members of the stattup Test Program to Demonstrate Remote Shutdown group. Test exceptions or acceptance criteria Capability for Water Cooled Nuclear Power siolations are communicated to the affected and Planu.
responsible organizations who will help resolve the issues by suggesting corrective actions, (4) Regulatory Guide 1.68.3 Preoperational design modifications, and retests. GE and others Testing of Instrument and Control Air outside the plant staff organization, as Systems.
appropriate, will have the opportunity to review the results for conformance to predictions and (5) Regulatory Guide 1.20 Comprehensive expsctations. Test results, including final Vibration Assessment Program for Reactor resolutions, are then reviewed and approved by internals During Preoperation and initial designated startup group supervisory personnel.
Starrup Testing.
Fie:4-appsovaW5-obtained-from-the appropriate leve+-of platrt-management-es-defined rn-tire (6) Regulatory Guide 1.41 Preoperational t"p edaisistrative-maeuskPlasmasasgsassa Testing of Redundant Onsite Electric Power 7 w'itt stro have responsibility for final review Systems to Verify Proper Load Group and approval of overall test phase results and of Assigriments.
O Tinal apprmalis obtained from the SCO and the appropriate level of plant menagement as detined in the startup admmistrative manual. I}e SCO and the Amendaunt 2 desipated level of plant management mH a!K
M) nenumrv ouae 193. *Proicenon or suocar n n nonm,nina amm ABWR o "~a ^-= ^" * *a' en-x v
u4s m s Standard Plant /
RTV A (7) Regulatory Guide 1.52.. Design, Testing.
(1) prove the specific procedure or illustrate and Maintenance Criteria for Engsneered changes which may be requised;
. Safety. Feature Atmosphere Cleanup System Air Filtrollon and Adsorption Units of (2) pro %ide training of plant personnel in the Light Water Cooled Nuclear Pow er Plants use of these procedures; and (8) Regulatory Guide 1.$6.. Maintenance of Water (3) increase the level of knowledge of plant A
funty in Boshag Water Reactors.
personnel on the systems t<ing tested.
g o (/) Regulatory Guide 1.108.. Periodic Testing of A testing procedure utillring an operating, Diesel Generators Used as Onsite Electric emergency, ot abnormal procedure will reference Power Systems at Nuclear Power Plants.
the procedure directly, extract a setics of steps from the procedure, or both in a way that (J8) Regulatory Guide 1.140.. Design. Testing and is optimum to accomplishing the above goals (T
Maintenance Criteria for Normal Ventilation while eificiently petforming the specified Exhaust System Asr Filtration and Absorbtion testing.
Units of Light Water Cooled Nuclear Power Plants.
14.2.10 Initial Fuel leading and Initial a
Criticality
.]
14.2J Utilization of Reactor Operating j
and Testing Experience in the Developrnent Fuel loading and initial criticality are 3
of Test Program conducted in a very controlled manner in e
accordance with specific written procedures as 1
Since every reactor / plant in a GE BWR product part of the startup test phase (see Subsection line is an evolutionary development of the 14.2.12.2). Approval fo/ commencement of fuel previous plant in the product line (and each loading typically is granted by the NRC, via the product line is an evolutionary development from issuance of an operating license, after all Op<
'se e evio e ed ci iinc>. ii is evideni issi ere canisiie itsiin sas been saiisiseierii>
the ABWR plants have the benefits of experience completed. <
j acquired with the successful and safe startup of L
more than 30 previous BWR/1/2/3/4/5/6 plants.
14.2.10.1 Pre Fuellead Checks The operational experience and knowledge gained j
from these plants and other reserne tuaa* ku N aa the olant has been eclared ready to a
been factored into th-of specific checks fications of Gi? -
- ding. These O
that will be dr H "*"* 'here may be unforescen circumstancea that arae that wuund preve"'
perational
'h* * *P " "' *1' P P" "'I tins (includins the teview and approval or sy design O
tiooal aad sIa k
the tut nsulu) that wuld not neussanlyjushiy the delay of fuel kudmg that were reaC1or oper similar nuclea:
U "d' ' '"' h 'i" *'"" ' h' ' PP3k '"' "'"'"'*8 'h' ^I'*R di8" *'I ted during duide i nquut pn.nissi n from the NRC to prmced with fuelicadmg It Cifications Iicensee Event sDUTCes wiI porti ns f any pre perattanal tests are intended to be conducted,or their ig ggggggggg practicable in
'""'" "PP"* d ' #" "'*** "#' ** "' ""*' k'"d'nE. then the folkeming shall at this time be documented in such a request: (1)lat each test; (2) state which portions of sms tequited initial (cat p@
{
cach test mill be delayed until after fuelicoding;(3) proude lechnical the initialb g3 ypggg {
justification for delaying these portions; and (4) state when coch test mill be
.ggg,ggg,ggpgg
"'"'P '* d *"d ' h' "'"k' 'PP' d erifie d an d ibe k
Emergency P nuclear instruments fc To the extent p..
operational and initial startup test program, test procedures will utilize operating, emer.
14.2.10.2 laitial Feellanding gency, and abnormal procedures where applicable in the performance of tests. The use of these Fuel loading requires the movement of the procedures is intended to do the following: full core complement of assemblics from the fuci l
l Amendment 2 1425
. ~
- - - - - - = - - -.
- - - - - ~__
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- i_
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ABM m u nr<.nen oris.u,ni.,i. i..i nssi,,.na m,,.ii.ni,,n,,o,,s ?
2a4siants i
Standard Plant re.nor nui.ni p,,oor, s,,na.ry w. is, i,.t.c, r.,,.nafo, mo E
hydna,. w acsong u dca nt ed in beruon 5 2 4 6.1 and 5 2 4 6.2.
]
Specific testing to t.
respecuniy..no.
.slVs and main e
applicable acceptance
.alves, including veri.
preoperational test are in acco
.aation of closure time in the isola.
l detailed system specifications and equipment tion mode, and test mode,if applicable; Ig specifications for equipment in those systems.
t The tests demonstrate that ibe installed (d) verification of SRV and MSIV acumulator T
equipment and systems perform within the limits capacity; 1
of these specifications.
I I
(c) proper operation of SRV sir piston lf The preoperational tests anticipated for the actuators and discharge line vacuum ABWR Standard Plant are listed and described in breakers; mL l,i 4
the following paragraphs. Testing of systems
}
outside the scope of the ABWR Standard Plant, but p proper system instrumentation and l
that may have related design and therefore y equipment operation while powered from 4
i testing requirements, are discussed in +a primary and alternate sources, including 5
(
> 14M24 transfers, and in degraded modes for
!i
}
which the system and/or components are jj 14.2.12.1.1 Nuclear Boller Sptem expected to remain operations' jy Prvoperational Test 0,! [
Other checks should be performed, as appro.
(1) Purpose priate, to demonstrate that design requirements,
'A such as those for sizing or installatino. are To verify that all pumpt,-Vityt, ictuitors, inet vie is built calculations, visual inspec.
instrumentation, t /$ logic, afarms, annun. tions, review of qualification documentation or 5
clators, and indic fion associated with the other methods. For lastance, SRV setpoints and nuclear boiler sys em fu crfon as specified.
capacities should be verified from certification or bench tests to be consistent with applicable (2) Prerequisites requirements. <
o The construction tests have been success.
14.2.12.1.2 Reactor Rectreulation Sptem fully completed and the SCG has reviewed the Preoperatlanal Test 54 test procedure and has approved the initia.
35 t
tion of testing. All required interfacing (1) Purpose
{;
l systems shall be available, as needed, to E j; }l d-support the specified testing and the To verify the proper operation of appropriate system configurations, reactor recirculation system at condii ]j 1
approaching rated volumetric flow, inclu l
j (3) GeneralTest Methods and Acceptance Criteria the reactor laternal pumps (RIPS)
[:. p f motors, and the equipment associated 3g l
Performance should be observed and recorded the motor cooling, seal purge, 1T t
M.g a series of individual component and inflatable shaft seal subsystems jg 4tegsated system tests to demonstrate the l2 e
l fodowing:
(2) Prerequisitea
} $-
!E (a) verification that all sensing devices The construction tests have been sue J$
test procedure and has approved the i t j W respond to actual process variables and fully completed and the SCG has revir v l
provide alarms and trips at specified jj values; tion of testing. Cooling water from tl 7s actor building cooling watcr system ani
$[
(b) proper operation of system instrumen.
purge flow from the CRD hydraulic s j
L tation and any associated logic, inclu.
shall be available. The recirculation 3 $
ding that of the automatic depressuri.
control system should be sufficiently ti ij zation system (ADS);
5v I O
--, 11 l
l l
eGWR m sion e Standard Plant prv A teristics, from the testing described above, meet (d) proper operation of control systems in O
the applicable design specifications.
all design operating modes and all le-vels of controls; 14.2.12,1.3 Reeirrul4 tion Flow Control Sptera Preoperational Test (c) proper operation of the adjustable speed drives; (1) Purpose (f) ability of the control system to comm.
To verify that the operation of the recir.
unicate properly with equipment and culation flow control system, in:luding that controllers in other sptems; of the adjustable speed drives, RIP trip and runback logie, and the core flow meuurement (g) proper control of pump motor start subsptem, is as specified.
sequence; (2) Prerequisites (b) proper operation of interlocks and equipment protective devices; The construction tests have been success-fully completed and the SCG has reviewed the (i) proper operation of pctmissive, prohi.
lest procedure and has approved the initia.
bit ud bypais functions; and tion of testing. All tequired interfacing systems shall be available, as needed, to (j) proper system operation while powered support the specified testing and the from primary and alternate sources, corresponding sptem configurations.
including transfers, and in degraded modes for which the system is expected (3) GeneralTest Methods <nd Acceptance Criteria to remain operational.
Some portions of the recirculation flow con-System operation is considered acceptable g
trol system testing should be performed in when the observed / measured performance charac-conjunction with that of the recirculation teristics, from the testing described abuve, system, as described in Subsection meet the spplicable design specifications, 14.2.12.1.2. Close coordination of the testing specified for the two systems is 14.2.12.1.4 Feedwater Control Sptem required in order to demonstrate the proper Preoperational Test integrated sptem response and operation.
(1) Purpose
. Performance should be observed and recorded during a series of individual component and To verify proper operation of the feedwater integrated system tests to demonstrate the control system, including individual compo-following-nents such as controllers, indicatort, and controller software settings such as galos (a) propes operation of instrumentation and and function generator curws.
equipment in all combinations of logic and instrument channel trip including (2) Prerequisites recirculation pump trip (RPT) and runback circuitry (RPT' kg wat speib!!y The construction tests have been success-htk4e % rel.h4 kTtx5 Suc.py.
fully completed and the SCG has redewed the (b) proper functioning of instrumentadon test procedures and has approved the initi-and alarms used to monitor system stion of testing. Preoperational tests must operation and availability; be completed on lower level controllers that do not strictly belong to the feedwater con-(c) proper functioning of the core flow trol system but that may affect system re.
measurement subsprem; sponse. All feedwater control system com.
Amendtrent 2 1429
ABWR mame Standard Plant try a ponents should have an initial calibration in System operation is considered acceptable O'
accordance with vendor instructions.
All when the observed / measured performacce required interfacing systems should be avail.
characteristics, from the testing described able, as needed, to support the specified above, me e t the applicable design testing and the appropriate system configu.
specifications.
rations.
10.12.1J Standby Uquid Control Sptem (3) General Test Methods and Acceptance Criteria Preoperational Test Testing of the feedwater control system dur. (1) Purpose ing the preoperational phase may be limited by the absence of an acceptable feedwater To verify that the operation of the standby recirculation flow path. Comprehensive flow liquid control (SLC) system, includ.ing testing will be conducted during startup pum ps, t an ks, control, logic, and
- phase, instrumentation, is as specified.
Performance should be observed and recorded (2) Prerequisites during a series of individual coroponent and overall system response tests to demonstrate The construction tests have been success-the following:
fully completed and the SCG has renewed the y
test procedure and has approved the (a) propi.r operation of insJrumentation and initiation of testing. Valves should be controls in all compostions of logic previously bench tested and other pre.
and instrument chpnel trip [ including-cautions relative to positive displacement verification of set foints;
/
pumps taken. The reactor vessel should be
/
available for injecting Deminerallred (b) propet functioninqf instrymentation water. All required interfacing systems and alarms used to montronystem opera.
shall be available, as needed, to support j
tion and status; the specified testing and the appropriate system configurations.
(c) Proper operation of system valves, in.
ciuding timing and stroke, in response (3) GeneralTest Methods and Acceptance Criteria to control demands (including the reactor water cleanup system dump valve Performance should be observed and recorded response to the low flow controller);
during a series of individual component and integrated system tests to demonstrate the (d) proper operation of interlocks and following:
equipmest protective devices in pump and valve controls; (a) proper operation of instrumentation and equipmerit in all combinations of logic (c) proper operation of permissive, prohi.
and instrument channel trip; bit, and bypass functions; (b) proper functioning of instrumentation (f), pope.ra{ stem operation while powered and alarms used to monitor system opera-em prim and alternate sources, in.
tion and availability; cluding tran fers, and in degraded modes
- fo9 whichjhe system is expected to re.
(c) proper operation of system valves, in-main pef ational; and cluding timing, under crpected operating conditions; (g) proper communication and interface with l
other controf systems and related (d) proper operation of pumps and motors in l
equipment, all design operating modes; O
l Amendment 11 t G 10
r ABWR msimo Standard Plant uw n 1
(e) proper operation of the tank heaters and should be installed and ready to be stroked proper mining of the ocutron absorber and scrammed. Reactor building cooling
\\
solution; water, instrument alt, and other required interfacing systems shall be available, as (f) proper system flow paths and flow rates needed, to support the specified testing and including pump capacity and discharge the corresponding system configurations, head (with den ineralized water substi.
tuted for the neutron absorber mit.
Additionally, the rod control and ture);
information system shall be functional when needed, with the applicable portion of its (g) proper pump motor start sequence and specified preoperational test!ng complete.
margin to actuation of protective de.
vices; (3) GeneralTest Methods and Acceptance Criteria (h) proper operation of interlocks and equip.
Performance should be observed and recorded ment protective devices in pump and val.
during a series of individual component and te controls; integrated system tests to demonstrate the following:
(i) proper operation of permissive, pro.
hibit, and bypass functions; (a) proper functioning of instrumentation and alarms used to monitor systern opera-(j) proper system operation while powered tion and status; from primary and alternate sources, in.
cluding transfers, and in degrsJed modes (b) rroper communication with, and response for which the system is expected to re.
to demands from, the rod control and information system and the r.ct N
main operational; and ted with altertiste rod insertion,psad ATW tection system, including as (k) acceptability of pump / motor vibration alter. V O
i i
a >>'
viri a - v - ' d -
d i
<>e i
-).
d ie '
ing both transient and steady state controt rod run in functions; operation.
(c) proper functioning of system valves,in.
System operatior la considered acceptable when cluding purge water pressure controf the observed /mencured performance characteris.
valves, under expected operating condi.
tics, from the testh.g described above, meet the tions; applicable design specifications.
(d) proper operation of CRD hydraulic sub.
14.2.12.1.6 Control Rod Drive System system pumps and motors in all design Preoperational Test operating modes;-
(1) Purpose (e) acceptable pump NPSH under the most lim-iting design flow conditions; i
To verify that the control rod drive (CRD) system, including the CRD hydraulic and fine (f) proper pump motor start sequence and mar.
motion controf subsystems, functione as de.
gin to actuation of protecthe dedces; i
signed.
l (g) proper system flow paths and flow rates i
(2) Prerequisites including sufficient pump capacity and discharge head;-
The construction tests have been success.
fully completed and the SCG has reviewed the (h) proper operation of laterlocks and test procedure and has approved the equipment protective devices in pump, initiation of testing. The control blades motor, and valve controls; O
Amendment il 14211
ABWR mai.
Standard Plant m4 O
integrated system tests to demonstrate devices and acceptable nonleakage from the following:
pool drains, sectionalizing devices, and gaskets or bellows; (a) proper operation of instrumentation and equipment in all coa.binations of logic (m) proper functioning of the system in and instrumant chanael trip, including conjunction with the RHR system in the isolation ano bypass of the nonsafety supplemental fuel pool cooling mode; and related fuel pool cleanup filter / demi.
neralizers; (n) proper operation of filter /demineralizer units and their associated support (b) proper functioning of instrumentation facilities.
and alarms used to monitor sptem opera.
tion and availability, including those Integrated system testing with flow to and associated with pool water level; from the fuel por:1 cicanup subsystem will be perfor2ed in coajunction with the appropriate (c) proper operation of system valves, in.
portions of the sJppression pool cleanup system ciuding timing, under expected operat.
preop described it. Subsection 14.2.12 1.20.
ing conditions; System operation is considered acceptable (d) proper operation of pumps and motors in when the observed /meast red performance charac.
all design eperating modes; teristics, from the terling described above, meet the applicable desgn specifications.
(e) acceptable pump NPSH under the most limiting design flow conditions; 14.2.12.1.22 Plant Process Sampling Spter Preoperitional Test r acau had'"
'"' (('
[f (f) proper system flow paths and flow rates inci ding pump capacity and discharge (1) Purpose oElst M ". M' 9 '*
To verify t e proper operation and the l-(g) proper pump motor start sequence and accuracy of equipment and techniques t l
margin to actuation of protective used for +Wsampling and analysis of $lant devices; process streams, including the post accident L
sampling system (PASS).
l (b) proper operation of interlocks and equipment protective devices in pump, (2) Prerequisites motor, and valve controls; Construction tests have been successfully (i) proper operation of permissive, prohi.
completed and the SCO has reviewed the test bit, and bypass functions; procedure and has approved the initiation of testing. Adequate laboratory facilities and (j) proper system operation while powered appropriate analytical procedures shall be from primary and alternate sources, inplace.
l including transfers, and in degraded i
modes for which the system is espected (3) General Test Methods and Acceptance Criteria to remain operational; Performance should be obsemd and recorded (k) acceptability of pump / motor vibration during[eries of tests to demon trate the levels and system piping movements dur.
following:
ddW ing both transient and steady state operation; (a) proper operation of on line[ampling and monitoring equipment M-_!:; calibra.
f uda sr can%d;y var a..v tion,indicatiogand alarm 6tJ (1) proper functioning of pool antisipha
.O Amendstent 2 14222
ABWR m-Standard Plant prv 4 U
-fiedhelheqdad+penik =4u.#
bead; O
(2) Prerequisites (g) proper pump motor start sequence and margin to actuation of protective The construction tests have been successful.
desices; ly completed and the SCG has reviewed the test procedure and has approved the initia-(b) proper operation of interlocks and tion of testing. Tbc fuel pool and suppres-equipment protective devices in pump and sion pool shall be adequately filled and the valve controls; appropriate filter /demineralizer support fa-cilities and other system interfaces avail-(i) proper operation of permissive, able, as needed, to support the specified prohibit, and bypass functions; testing.
(j) proper system operation while providing (3) GeneralTest Method and Acceptance Criteria tbc speeified intersystem tefill capabilities; and Tbc suppression pool and fuel pool share com-mon water treatment facilities. The suppres-(k) acceptability of pump / motor vibration sion pool cleanup system has a dedicated pump levels and system piping movements for circulating, water to and from the suppres-during both transient and steady state sion pool and through the common filter / demi-operation.
neralizer. However, the shared filter / demi-neralizer f acilities are considered part of System operation is considered acceptable the fuel pool cooling and cleanup system. when the observed /msasured performant.c Therefore, this preoperational test should be characteristics, from the testing descrit'ed closely coordinated with that of Subsection above, meet the applicable design specifica-14.2.12.1.21.
tions.
g-t Performance should be observed and recorded 14.2.12.1.21 Fuel Pool Cooling and Cleanup during a series of individual component and System Prtoperational Test integrated system tests to demonstrate the following:
(1) Purpose (a) proper operation of instrumentation and To verify that the operation of the fuel equipment in all combinations of logic pool cooling and cleanup (FPC) syst:m, and instrutnent channel trip; including the pumps, heat exchangers, controls, valves, and instrumentation, is as (b) proper functioning of instrumentation specified.
and alarms used to monitor system operation and availability; (2) Prerequisites (c) proper operation of system valves, in.
The construction tests have been eluding timing, under expected cperating successfully completed and the SCG has conditions; reviewed the test procedure and has approved the initiation of testing. The required (d) proper operation of pump and motor in interfacing systems shall be available, as all design operation modes; needed, to support the specified testing and the appropriate system conf gurations.
(c) acceptable pump NPSH under the most limiting design flow conditions; (3) GeneralTest Methods and Acceptance Criteria (f) proper system flow paths and flow rates Performance should be observed and recorded
(
including pump capacity and discharge during a series of individual component and Amendmem 2 14 2 T.
____- # M (b) proper o[<rahon of control rod runon k$ic ind idmg that ammiated with Ald (NtWS). SCRR1 and nonnel mmt SCI'AM rolhm.in.
DA6100AN i
Standard Plant arv A (1)- proper operation of perminive, prohi-cisted alarms and annunciators in all bit, and b)pau functions; combinations of logic and instiument channel trip locluding all positions of (j) proper system operation while powered the reactor mode switch; from primary and alternate sources, including transfers, and in degraded (p) proper functioning of instrumentation modes for which the system is expected g used to monitor CRD system status such to temain operational; as rod position indication instrumenta.
tion and that used to monitor continuous (k) acceptability of pump / motor vibtation full in and rod / drive separation status; levels and system piping movements during both transient and steady state (f) proper operation of RCalS software in.
operation; j cluding verification of gang and group assignments and predictor.comparator, (I) proper operation of fine motion motors rod worth limiter, and banked position and drives and associated control units, withdrawal sequence functions; and including verification of acceptable e
normalinsert and withdraw timing; (f) proper communication with interfacing systems such as the power generation con.
(m) proper operation of hydraulle control trol system, the automatic power regula.
units and associated valves including tor, and the automatic rod block CRD scram timing demonstrations against
- monitor, atmospheric pressure.
System operation is considered acceptable System' operation is considered acceptable when when the observed / measured performance charac.
ine observed / measured performance characteris-teristics, from the testing described above, tics, from the testing described above, meet the meet the applicable design specifications.
O 99'><>6' d i r <i'>c 'i 142.12.1.g Residual Heat Removal System 1 (2.12.1.7 Rod Control and leformatlos System Preoperational Test Preoperational Test (1) Purpose (1) Purpose To verify the proper operation of the resi.
To verify that the rod control and informa.
dual beat removal (RHR) system under its tion system (RCalS) functions as designed.
various modes of operation: core cooling, shutdown cooling, wetwell and drywell spray, (2) Prerequisites suppression pool cooling, and supplemental fuel pool cooling.
The construction tests, including initial check out of RCalS software, have been suc. (2) Prerequisites cessfully completed and the SCO has reviewed the test procedure and has approved the ini.
The construction tests have been successful, tiation of testing.
ly completed and the SCG has reviewed the test procedure and has approved the initia.
(3) General Test Methods and Acceptance Criteria tion of testing. The reactor vessel shall be intact and capable of receiving injection Performance should be obserwd and recorded flow from the various modes of RHR. The -
during a series of tests to demonstrate the reactor building cooling water system and following-other required interfacing systems shall be l
available, as needed, to support the speci.
(a) proper operation of rod blocks and asso-fled testing and the appropriate system configurr; ions.
Amendment 2 14112 i
m.
m
ABWR aw m Standard Plant nrv s (a) proper calibtation of detector assem.
(3) GeneralTest Methods and Acceptance Criteria O
blies and associated equipment using a standard source or portable calibration The instrument air system and the service unit; air system are specified as separate sys-tems. However, since they are so closely (b) proper functioning of indicators, recor-related the preop test requirements are ders, annunciators, and alarms including essentially the same.
those monitoring system availability; Performance should be observed and recorded (c) proper system trips in response to high during a series of individual component and setpoint and downscale/ inoperative integrated system tests to demonstrate the conditions; following:
(d) proper operation of permissive, pro-(a) proper operation of instrumentation and hibit, interlock, and bypass functions; equipment in all combinations of logic and instrument channel trip; (e) proper initiation and operation of detec.
tion and sampling functions including (b) proper functioning of instrumentation pump start and valve sequencing, if ap-and alarms used to monitor system opera.
propriate, in response to a LOCA signal; tion and availability; and (c) proper operation of system valves, in-(f) proper operation of calibration gas sup-ciuding timing, under expected operating piv systems and self calibration conditions; functions.
(d) proper operation of compressors and System operation is considered acceptable when motors in all design operating modes; the observed / measured performance characteris.
O
'i
'< - '6 ' 'i = d
>>6 d 6
- " 6-( > 6iii'r '
-r
< > ' - i ' i-applicable design specifications.
receiver at specified pressure (s) and to recharge within specified time under de.
14.2.12.1.27 Instrument Air and Station sign loading conditions; Service Air Systems Preoperational Tests (f) proper system flow paths and acceptable (1) Purpose flow rates to individual loads at spec-ified temperatures and pressures under To verify the ability of the instrument air design loading :: fd:::;%
l and service air systems (IA and SA) to provide the design quantities of clean dry (g) proper compressor start sequence compressed air to user systems and (including load and unload) and margin -
componenis, to actuation of protective devices; (2) Prerequisites (b) proper operation of interlocks and equipment protective devices in The construction tests have been successful, compressor and valve controls; ly completed and the SCG has reviewed the test procedure and has approved the.ini ia.
(i)' proper operation of permissive, t
tion of testing. Primary and backup elec.
prohibit, and bypass functions; trical power, the supplied system and compo.
nents loads, and other required system in.
(j) proper system operation while powered terfaces are available, as needed, to support from primary and alternate sources, the specified testing, including transfers, and in degrade O
- conditions includme a determmation that the total air demand at steady state Amendment tt Innditions. includmrieskare tot the miem. is in accordance with design;'
4 r
a
.-,,...nn
.,.,-,--+.. -
n,m
ABWR ms-Standard Plant prv 9 modes for which the system is expected to integrated system tests to demonstrate the remain operational; following:
g (k) acceptability of compressor / motor vibra-(a) proper operation of instrumentatica and 2
tion lesels and system piping mosements equipment in all combinations of logic 3
during both transient and steady state and instrument channel trip; operation;
},
(b) proper functioning o!' instrumentation
'jp (l) the ability of the air to meet end use and alarms used to monitor system l$c. b oil, water, and particulate matter con.
cleanliness requirements with respect to operation and availability; E.f.
tent; (c) proper operation of system valves, i
including timing, under expected j{e (pd) proper ' failure' (open, close, or as is) operating cohditions; 7
n of supplied components to both instanta-3 g!
neous (pipe break) and slow (plug;;ing or (d) ability to maintain receiver (s) at spe-gE freezing) simulated air losses (per Reg-cified pressure (s) under design loading 5 %
t 'E "
ulatory Guide 1.68.3): And conditions;
>i (f) the ability of the service air system to (e) proper system flow paths and acceptable E.s act as backup to the instrument air sys-flow rates to individual loads at speci.
j "g
- tem, fied temperatures and pressures under st design loading conditions;
[j System operation is considered acceptable when 7
(
the observed / measured performance characteris.
(f) proper operation of interlocks and tics, from the testing described above, meet the equipment protective devices; applicable design specifications.
102.12.1.28 liigh Pressure Nitrogen Gas Supply hibit, and bypass functions; System Preoperatic nal Test (h) proper system operation while powered (1) Purpose from primary and alternate sources, in-t cluding transfers, and in degraded modes To verify the ability of the high pressure for which the system is expected to l
nitrogen gas supply system (HPlf1) to furnish remain operational; compressed nitrogen gas to user systems at design quantity and quality.
(i) acceptability of vibration levels and l
system piping movements during both (2) Prerequisites transient and steady state operation; The construction tests have been successfully (j) the ability of the nitrogen gas to meet completed and the SCO has reviewed the test end use cleanliness requirements with l
procedure and has approved the initiation of respect to oil, water, and particulate I
t e sting. User system loads and other re-matter content; and uituLay tem interfaces shall be available, as needed, support the specified system (k) proper " failure * (open, close, or as is)
- testing, of supplied components to both instanta.
C.
I neoui (pipe break) and e (plugging or
~
(3)3 Test Methods and Acceptance Criteria frecting) simulated ni"6en gas supply losses (per Regulatory Guide 1.68.3).
l Per ance should be observed and recorded l
during a series of individual component and System operation is considered acceptable Amendment 11 14226 l
l l
l l
ABWR m s.
Sigf ard Plant prv A
/^
To verify the ability of the plant make up Systern operation is considered acceptable if
(
water system (s) to resupply the designated the observed / measured performance characteris-plant systems with water of tbc design tics meet the applicable design specifications.
quantity and qualiry for each such system.
14.2.12.1.31 Hot Water lleating System (2) Prerequisites Preoperational Test The construction tests have been success- (1) Purpose fully completed and the SCG has reviewed the test procedure and has approved the initia.
Verify the ability of the bot water beatinit tion of testing. Final interconnection with system to provide hot water to the appropri-the suppl:ed systems is complete and those ate HVAC sptems in order to maintain the systems are ready to accept transfer of de.
specifiad design temperatures within the sign quantitiet of makeup water.
Vrfious building roots and areas.
(3) GeneralTest Methods and Acceptance Criteria (2) Prerequir.ites System performance should be obrerved and The construction tests have been completed recorded c'uring a series of incidual com-and tbc SCG has reviewed the test procedure potent and integrated system t. to demon-and has approved the initiation of testing.
strate the folhwing:
Electrical power, the appropriate beating source (s), the various HVAC systems heating (a) proper opervion of instrumentation and coils, ar.d other reqrired interf acing equipment in all combinations of logia gsfiihball be available, as needed, to suppon the ipecified testing.
(b) proper functioning of instrumenta on 6.el
)
p and alarms used to monitor system o (3) Test Methods and Acceptance Criteria ra.
i J
sion and status; er rmance should be observed and recorded
'c) peoper operation of p.aps, motors, and during a series of inoividual component ard l
vahes under expected operating condi-integrated systern tests to demonerate the tions; following-(4 proper functioning of icterlocks and (a) proper operation of instrumentation and equipment protective devices in pump, equipment in all combination: of logic motor, and vuve controls; and lastrument channel trip; i
(c) the adequacy of system flow paths and (b) proper functioning of instrumentation flow rates including pump and tank and alarms used to moritor sptem opera-l capacities; tion; (f) proper functioning of chemical addition (c) proper operation of system valves under and water treatment facilities and upecsed operating conditions; enipment; (d) proper operation of pumps and motors in (g) proper funetioning of freeze proteetion all design operating modes; l
devices,if applicable;and l
(c) acceptable pump NPSH under the mest (b) acceptability of pump and motor limiting design flow conditions; vibration levels and system piping movements during both transient and (f) proper system flow paths and flow rates stesdy state operations.
including pump capacity and discharge l
head; Amendment 2 14248
ABWR 2WlMAN Slandard Plant pn n (g) proper pump motor start sequence and during a series of individual component and p
rnargin to actuation of protective de-integrated system tests to demonstrate the U
vices; following:
(b) proper operation of inteilocks and (a) proper operation of instrumentation and equipment protective devices in pump, equipment in all combinations of logic motor and valve controls; and instrument channel trip, (i) proper operation of permissive, pro-(b) proper functioning of instrumentation hibit, and bypass functiorr and and alarms used to monitor system operation and availability; (j) acceptability of pump / motor vibration levels and system piping movements (c) proper operation of system valves, during both transient and steady state including isolation functions, under operation.
expected operating conditions; System operation is considered acceptable when (d) p.oper operation of pumps and reors in the observed / measured performance characteris-all design operating modes; tics, from the testing described above, meet the applicable design specifications. It may not be (c) acceptable pump !JPSH under the most possible to fully evaluate heat exchanger and limiting design flow conditiont; heating coil performance during the preoperation-al test phase because of process temperature (f) proper system flow paths and flow rates limitations.
to all supplied loads including pump capacity and discharge head; 14.2.12.1.32 HVAC Emergency Chilled Water System Preoperational Test (g) proper pump motor start sequence and margin to actuation of protective (1) Purpose devices; To verify the ability of the HVAC emergency (h) proper operation of interlocks and l
chilled water system (HECW) to supply the de-equipment protective devices in pump and sign quantities of chilled water at the spe-valve controls; cified temperatures to the various cooling coils of the HVAC systems serving rooms and (i) proper operation of permissive, areas containing essential systems and prohibit, and bypass functions; equipment.
(j) proper system operation while powered (2) Pr: requisites from primary and alternate sources, including transfers, and in degraded The construction tests have been successfully modes for which the system is e,,ected completed and the SCG has reviewed the test to remain operational; procedure and has approved the initiation of testing. Normal and auxiliary electrical (k) acceptability of pump / motor vibration pcwer, reactor building cooling water, appli-levels and system piping movements cable HVAC system cooling coils, and other during both transient and steady s' ate required system ir.terfaces shall be avail-operation; and 3able egneeded, to support the specified r
7 system tesf ng.
(1) proper functioning of system surge tank Q) and chemical addition features.
(3) Test Meth and Acceptance Criteria System operation is considered acceptable j ormance should be obs:rved and recorded when the observed / measured performance O
V Amendment 11 14.2 29
ABWR.
ms-Standard Plant prv n characteristics, from the te.nug described (f) proper system flow paths and flow rates O
de. me "8 erii si e 's r irie ie -
ie ii erii a >e de i i ai e# r capacity and discharse head; 14.2.12.1.33 HVAC Normal Chilled Water System Preoperational Test (g) proper pump motor start sequence and margit. to actuation of protective (1) Purpose devices; To verify the ability of the HVAC normal (h) proper operation of interlocks and equip.
l chilled water system (HNCW) to supply the ment protective devices in pump and design quantities of chilled water at the valve controls; specified te:nperatures to the various cooling coils of the HVAC systems serving rooms and (i) proper ?peration of permissive, prohi.
areas containing nonessential equipment and bit, and bypass functions; systems.
(j) proper system operation while powered (2) Prerequisites from primary and alternate sources, including transfers, and in degraded The cc,nstruction tests have been saceu.
modes for which the system is expected fu:ly completed and the SCG has reviewed the to remain operational; test procedure and 1,as approved the initia.
tion of testing. Primary acd auxiliary (k) acceptability of pump / motor vibration electrical power, the assoct. sed cooling levels and system piping movements water system (s), the applicable HVAC sysicm during both transient and steady state cooling coils, and other required system operation; and es shall be available, as needed, to support e specified system testing.
(1) proper functioning of system surge tank (nwd and chemical addition features.
O (3) Test Met ds and Acceptance Criteria System operation is considered accepable
, ormance should be observed and recorded when the observed / measured performance charac.
during a series of individual component and teristics, from the testing described above, integrated system tests ;o demonstrate the meet the applicable design specifications.
following:
14.2.12.1.34 Heatir.g Ventilation,and Alt (a) proper operation of instrumentation and Conditioning Systems Preoperational Test
- quipment in all combinations of logie and instrument c' annel trip; (1) Purpose n
(b) proper functioning of instrumentation To verify the ability of the various HVAC and alarms used to monitor system systems to establish and maintain theapee' operation and availability; fled environment, with regards,t6 tempera.
ture, pressure, and airbqrtfe particulate j
(c) proper operation of system' valves, level, in the applicable ooms, are s, and l
Including isolation functions, under buildings throughout e plant, s porting
.l l
expected operating conditions; essential and noness atial equi cat and l-systems.
(d) proper operation of pumps and motors in all design operating modes; (2) Prerequisitea (c) -acceptable pump NPSH under the most The construction tests, including initial limiting design flow conditions; flow balancing, have been successfully I
.O
,s m
ABWR umme Standard Plar.t me completed and the SCG has reviewed the test (d) proper operation of fans and motors in procedure (s) and has approved the initiation all design operating modes; Os of testing. Additionally, the normal and backup electrical power sources, the applic-(e) proper system flow paths and flow rates able heating, crioling, and chilled w ater sys-including individual component and to
- s tems, and any other acquired system inter-system capacities and overall syst faces shall be available, as needed, to flow balancing; 5j' support the specified testing.
y[ j (f) proper operation of interlocks a 2 3 3 (3) GeneralTest Method and Acceptance Criteria equipment proteclive devices;
!y /
1j/
i!
There are numerous HVAC systems in the plant, (g) proper operation of permissive, p located throughout t e various buildings.
bibit, and bypass functions; i7 l Each system typically consists of some combi.
jj 3 "g nation of supply and exhaust air handling (h) proper system operation while power units and local cooling units, and the asso-from primary and alternate soure
{j i
ciated fans, dampers, valves, filters, best-including transfers, and in degrade
- 3 ing and cooling coils, and contrc! and instru-modes for which the system is expecit 3I! O j (
mentation. The HVAC systems tc be tested to remain operational; should include the following: those opport-
!j!e ing the reactor building rooms containing the (i) the ability to maintain the specifi. t01) emergency diesel generators and the ECCS positive or negative pressure (s) in t Ij U pumps and heat exchangers; those serving the c'esignated rooms and areas and to dire 5yj' electrical equipment rooms of the control local and total air flow, including a ! E]l building; those supporting the divisional potential leakage, relative to t cooling water rooms; those supnorting the anticinated contamination levels. ~
turbine / generator auxiliaries, Gos;. se;ving the secondary contsihment and the general (j) the ability of exhaust, supply, and
/7 areas of the control building, reactor recirculation filter units to maintain V
building and turbine build.ing; and the the specified dust and contamination dedicated systems of the drywell and the main free environment (s);
4 control rooin(hely A c++ 1
- MMy D
i bc.%').
(/) the ability of the heating and cooling l
Since the various HVAC systems are similar in coils to maintain the specified therma!
y design of erguipment and function, they are environment (s) while considering the subject to the same basic testing require-heat loads present during the preop test
- ments, phase; and j.
Performance should be observed and recorr'ed l} the ability of primary and secondary l
during a series of individual component and containment HVAC systems to provide n
l integrated system tests to demonstrate the sufficient purge, exhaust, and recircu.
l following:
lation flows in support of drywell inerting and deinerting operations.
(a) proper operation of instrumentation and equipment in all combinations of logic System operation is considered acceptable and instrument channel trip; when the observed / measured performance charac-teristics, from the testing described above, l
(b) proper functioning of instrumentation meet the applicable design specifiertions.
and alarms used to raonitor system operation and availability; 14.2.12.1.15 Atmospheric Control System Preoperational Test (c) proper operation of systees valves and dampers, including isolation functions, (1) Purpose under upected operating iria m
,p-gj/
~O (1) proper operanon of IIEPA filters and charcoal adsottier sections,if N applicabic, including relative to the in place testing requirements or Reguhuory Guide 1.140 regardmg mual inspections and airflow distribution. DOP penetration and bypass leakage testing;
- - m.
ABM utsim.
Standard Plant prv A tightness of charcoal adsorber section 14.2.12.1.40,1Contalement lategrated leakage per Regulatory Guide 1.$;
Rate Tett
)
- (f) proper system and cotnponent Gow paths Descript!on of and criteria for containment and flow rates including overall sptem integrated leakage rate tests are gisen in Sub.
Gow balance; secdon 6.2.6.1.
b '_'
(g) ability to maintain the specified nega-14.2.12.1.41 Pressure Suppression Containment
/
1
/
tive pressure in the secondary Bypass taskage Tesu
(
containment; i
Test procedures are identical to those us j
(h) proper operation of interlocks and for other penetrations under isolation con j
i equipment protective devices; tions as discussed in Subsecdon 6.2.6
]
n (i) proper operation of permissive, 14.2.12.1.42 Containment Isotation Valve l
l prohibit, and bypass functions; Functional and Closure 11 ming Tests j
/
7 j
?
i (j) proper operation of heaters, demister, Preoperationst functional and closure tinI
]
and moisture seperctor equipment; and tests of containment isolation valves is 5
y cussed in Subsection 6.2.4 I
(k) proper system operation while powered 3
i Irom primary aod alteraate sources, 14.2.12.1.43 Wetwell to.Drpell Vacuum Breake j i ;-
including transfers, and in degraded System Preoperational Test
/
y i;
j;f a
modes for which the system is expected it to remain operational.
(1) Purpose 5
1]
Refer also to Subsection 6.5.1.4.1.
To verify proper functioning of the w i $
j{
to-drywell vacuum breakers.
j ij
\\
the observed / measured performance characteris.
(2) Prerequisites
5&
System operation is considered acceptable when j
2 x
tics, from the testing described above, meet the applicable design specifications.
The construction tests have been suct fully completed and the SCG has reviewed the 14.2.12.1.37 Contalement isolation Valve test procedure and has approved the initia.
Laskage Rate Testa tion of testine,.
Description of and criteria for preopera- (3) GeneralTest Methods and Acceptance Criteria tional leakage rate tests of containment isola-tion valves are gma in Suhuaiaa 6.2.6.3.
Performance should be obserwd and recorded during a series of individual component and L
14.2.12.1.38 Costatement Penetraties tankage integrated system tests to demonstrate the Rata Testa following-Description of and criteria for preoperational (a) proper operation of vacuum breaker leakage rate testa of containment penetrations valves and system logic including are given in Subsesion 6.2.6.2.
verification of opening and closing setpoiou and timing; 14J.12.1.39 Costalament Alrieck Lankage Rate i
(b) proper operation of instrumentation and Tests alarms used to monitor system operation Description of and criteria for preoperational and status, such as valve position in-l leakage rate tests of containment airlocks are dication, including ver.'fication of l
given in Subsectioa 6.2.6.2.
operability during loss of preferred 14233 Amendment 2 l
l
ABM 23mimas Standard Plant Rrv A power conditions during a series of individual component and
/m integrated system tests to demonstrate Ibc d
(c) proper functioning of valve positive following:
closure devices including verification of adequate valve leak tightness; and (a) proper tracking of dryAell pressure by all instrument channels during contain-(d) proper functioning of vacuum breaker ment integrated Ir.ak rate testing; test features.
(b) proper response of all suppression pool System operation is considered acceptable when level instrumentation during actual the observed / measured performance characteristics changes in poollevel; meet the applicable design specifications.
(c) proper tracking by all suppression pool 14.2.12.1.44 Primary Containment Monitoring temperature instrument channe.ls of an Instrumentation Prtoperational Test actual change in pool temperature; (1) Purpose (d) proper functioning of associated indica-tors, recorders, annunciators, and To verify the proper operation of instru-alarms including those monitoring mentation used for long term monitoring of instrumentation status; and the drywell and wetwell atmospheres and suppression pool temperature and level during (c) proper system trips in response to the t oth aormal operations aad accident appropriate high and/or low setpoints conditions in the primary cont tituent.
and inoperative conditions.
(2) Prerequisites System operation is considered acceptable w ben the observed / measured performance character-O The construction t:tts have been success.
istics, from the testing described above, meet V
fully completed and the SCG has reviewed the the applable design specifications.
test procedure and has approved the initia-tion of testing. The suppre.sion pool shall 14.2.12.1.45 Electrical Systems Preoperational be filled and expected to undergo measurable Test level and temperature changes at some point during the scheduled testing. The required The total plant electrical distribution net-interfacing systems and components are work is described in Chapter 8 and is comprised available, as needed, to support the speci.
of the following systems:
fied testing. Additionally, any parallel t esti o be performed in conjunction witb (1) unit auxillary AC power system; I e testin'g of this subsection is appropri.
(2) unit Class E AC power system; ately scheduf d.
(3) safety system logic and control system (seneal power system; r
(3) Test Met
.s and Acceptance Criteria (4) instrument power system; (5) uninterruptible power system; l
escription of the instrumentation requir-(6) unit aimilary DC power system; and l
cd for containment monitoring is presented in (7) unit class IE DC power system.
Subsection 6.2.1.7. Preoperational testing of these instruments will be performed in Because of the similarities in their design l
conjunction with the testing of the applic-and function, the testing requirements for these l
able systems, Only that instrumentation systems, and their respective components, can be requiring special considerations is discus-divided into the four general categories as sed below.
described below. The specific testing required l
l for each system is described in the applicable l
Performance should be observed and recorded design and testing specifications.
,q V
Amendment 2 14 M4 l
l I
ABM utmoxs Sandard Plant REV A a series of individual component and diesel fuel oil transfer, diesel generator O
integrated system tests to demonstrate the starting air supply, jacket water, and tube V
following:
oil.
(a) proper operation of initiating, trans-(2) Prerequisites fer, and trip devices; The con.truction tests have been successful-(b) proper operation of relaying and logic, ly completed and th* 'CG has reviewed the including load shedding features; test procedure and b.s approved the initia-tion of testing. All interfacing systems (c) proper operation of equipment protective and equipment required to support system op-devices, including permissive and prohi.
cretion shall be available, as needed, for bit interlocks; the specified testing configuration. Addi-dhaly, sufficient diesel fuel should be (d) proper operation of instrumentation and availabihn site to perform the scheduled alarms used to monitor system and equ' tests.
h ment status (including availability);
6ewal (c) proper operation and load car ying capability of breakers, motor coot l-
_Je ormance should be observed and recorded ers, switchgear, transformers, and during a series of individual component and cables; integrated system tests te demonstrate the following-(f) that a sufficient level of redundancy and electrical independence exists as (a) proper automatic startup and operation specified for each application; of the diesel generators upon simulated loss of a c voltage and attainment of
(
(g) the capabi;ity to transfer between the required frequency and voltage with-onsite and offsite power sources as per in the specified time limits; design; (b) proper response and operation for de-(h) the ability of emergency and vital loads sign basis accident loading sequence to to start in thu proper sequence and to design basis load requirements, and operate properly under simulated verification that voltage and frequency accident conditions, while powered from are maintained within specified limits; either preferred or standby sources, and over the specified range of available (c) proper operation of the diesel genera-i bus voltage; and tors during load shedding, load sequenc-ing, aud load rejection, including a (i) the adequacy of the plant emergency and test of the loss of the largest single essentiallighting systems.
load and of the complete loss of load, verifying that voltage and frequency are 14.2.12 1 45.3 Emegency Diesel Generator maintained within design limits and that l
PreoperatJonal Test curspeed lic:its are not exceeded; (1) Purpose (d) that a LOCA signal will block generator breaker or field tripping by all protec.
To demonstrate the capability of the emer-tive relays except for the generator gency diesel generators to provide highly re-phase differential current and engine liable emergency electrical power during nor-overspeed relays; mal and simulated accident conditions when normal offsite power sources are unavailable, (e) that a LOCA signal will initiate termin-n and to demonstrate the operability of the ation of parallel operations (test or
()
diesel generator auxiliary systems, e.g.,
manual transfer) and that the diesel Amendment 2 142 4
. ~
ABM -
uxsmoxs Standard Plant prv e with the vessel internals completely in.
considered acceptable when results of tact with the exception of the fuel bun.
the measurement program correlate and
_dles, the control blades (unless fully compare favorably with those of the ans.
withdrawn), and the steam dryer assem.
lysis program, and, when the results of bly. A post fuel load, subcritical flow the inspections show no signs of de.
test will be performed later on the com.
fects, loese parts, extraneous material, plete reactor assembly unless it is or excessive wear due to flow testing, shown analyticall~y or experimentally and are consistent with the results ob.
that the preoperational results are edned frora the analysis and measurement already conservatively bounding. Addi programs. N tionally internals vibration will ) _
t.s3 measured during individual componen(or 14.2.125 Condensate and feedwater Systems system preoperational testing whe'tdoperettoriaTTest n
- operation my result in significant vibrational excitation of reactor (1)
Purpose internals, such as HPCF testing.
To verify proper operation of the The duration of preoperational testing various components that compris: the at the various flow configurations condensate and feedwater systems and should ensure that each critice' com; their capability to deliver the required ponent is subjected to at least 10 flow from the condenser hotwell to the cycles of vibration, as calculated using nuclear boiler system.
the lowest frequency for which the com.
ponent is expected to experience a sign. (2)
Prerequisites ificant structural response.
The construction tests have been (c) Post Flow Vesselinspection successfully completed and the SCG has reviewed the test procedure (s) and has h
The post flow inspection shall be per.
approved the initiation of testing, The formed after the resultant vibrational required interfacing systems shall be excitation from the preoperational flow available as needed, to support the testing described above. The structures specified testing. For all flow testing and components inspected shall be the their shall be an adequate suction same as specified for the preflow in-source available and an appropriate flow spection. Visual and remote observa.
path established.
tions are performed after the vessel has been depressurized and drained. Inspee. (3)
GeneralTest Method and Acceptance tion of critical surfaces and components Criteria should be performed prior to any disas.
sembly required for access to other Preoperational testing of the condensate internal structures, and feedwater systems will include the piping, components, and instrumentation (d) Acceptance Criteria between the condenser and the nuclear L'-
boiler but not the condensate filtens or The acceptance criteria are generated as domineralizers nor the feedwater ptrt of the analytical portion of the heaters, which will be tested separetely program in terms of maximum vibrational per the specific discussions provided response levels of overall structures for those features.
and components and translated to speci.
fie sensor locations.
Performance should be observeJ. 2d recorded during a series of indivhl Reactor vessel internals vibration is component and integrated system tests to demonstrate the following:
7 Amentment 11 14.2 44
~.
ABWR mms Standard Plant un generator hydrogen system and its associated during a series of individual component seal oil and cooling systems);
and integrated system tests to demonstrate
(,)
the following:
V (c) proper operation of interlocks and equipment prctective devices in the various generator and (a) proper operation ofinstrumentation and ausaliary system controls; equipment in all combinaticos of logic; h proper operation of pertaissive, prohibit, (b) proper functioning of instrumentation and and bypass functions; alarms used to monitor system operation and availability; (g) proper operation while powered from primary and any alternate sources, (c) proper operation of system valves, including transfers, and in degraded modes including timing, under expected openting for which the system, subsystem or conditions; component is expected to remain operational, (d) proper system flow paths and flow rates both into and out of the primary (h) proper generator alignment, including containment; acceptability of clearance and vibration levels,if possible, during both transient (e) proper operation of interlocks and
{ and steady state opera: ion; equipment protective devices in valve and recombiner skid contrcls; System operation is considered acceptable when the observed / measured performance characteristics, (f) proper operation of permissive, prohibit, from the testing described above, meet the and bypass functions; and applicable design specifications (while accounting for the testing limitations imposed).
(g) proper system operation while powered from primary and alternate sources, 7m 14.2.12.1.72 Flammability Control System including transfers, and in degraded modes
()
Preoperational Test for which the syste- ;s expected to remain operational.
j (1) Purpose System operation is considered acceptable when To verify the ability of the flammability control the observed / measured performance characteristics, system (FCS) to recombine hydrogen and from the testing described above, meet the j
oxygen and therefore maintain the specified applicable design specifications.
i inert atmosphere in the primary containment I
i during long term post accident conditions.
14.2.12.1.73 leose Parts Monitoring System Preoperational Test (2) Preregaisites (1) Purpose The construction tests have been successfully completed and the SCG has revkwed the test To verify proper functioning of loose parts procedure and has approved the initiation of menitoring equipment.
testing. The wetwell and drywell airspace regions of the primary containment should be (2) Prerequisites intact, and all other required interfaces available, as needed, to support the specified The construction tests have been successfully testing.
completed and the SCG has reviewed the test procedure and has approved the initiation of (3) GeneralTest Methods and Acceptance Criteria gting. Reactor internals shall be in place wth l
all system sensors connected.
Performance should be observed and recorded
,/
)
Amendment tl 14 W 13 U
ABWR mm Standard Pf art ps a (r) proper functioning of instrumentation approriate operational configuration wih
(
and alarms used to monitor system the specified prereqt isite testing )
operation and status; complete. All applicable instrumentation j shall be checked or calibrated as is /
(d) acceptable system s,nd cosnponent flow appropriate.
(
patbs and flow rates includlag pump l
capacities and tank volumes, (3) Description
(
\\
(e) proper opeiation of systern pumps, Proper operation of the offgas system will (
valves, and motors ueder expected be demonstrated by monitoring pertinent j operating conditions; parsmrters such as temperature, pressure, (
flow rate, humidity, hydrogen content, and t
(f) proper operation of phase separators and effluent radioacitivity. Data should be h
waste evaporators; collected at
- elected operating points such }
that each critical component of the sysitem (
(g) proper operation of concentrating, is evalusted over its particular expected solidifying, and packaging functions operating range. Performance should bc including verification of the absence of demonstrated for specif ; components such as j free liquids in packaged waste; catalytic recombiners, and activated carbon absorbers as well as the various besters, (h) proper ope r ation of filt e r a nd coolers, dryers and filters. Also to bc )
demineralizer units and their associated evaluated are the piping, valving, (
support facilities; instrumentation and control that comprise 1 the overall system.
(i) proper functioning of drains and sumps
\\
including those dedicated for handling (4) Criteria j
of specific agents such as detergents; i
\\
and Hydrogen concentration and radioactive i
O t'i
- ii i
a <
- i
> i (j) proper calibration and operation of specification limits. All applicable system radiation detectors and monitors, and component parameters should be consisten $
with design and testing specification /
System operation is considered acceptable requirements, j
when the observed and measured performanc charactcristics, from the testing describe 14.2.12.1.77 Ultimate Heat Sink Preoperational above, meet the applicable design specificatio Test Offgas System hymNTest (1) Purpose 14.2.12.2.76 h
(1) Purpose To verify that the ultimate heat sink is capable of supplying design quantities of To verify proper operation of the various make-up and/or return water to the i
components of the offgas system over the circulating water system and the reactor expected operating range of the system, turbine service water systems.
(2) Prerequisites
) Prerequisites l
The preoperational tests have been completed The construction tests have been and plant management has reviewed the test successfully completed and the SCG has procedure and has approved the initiation of reviewed the test procedure and has approved testing. For each scheduled testing the initiation of testing. The circulating iteration, the plant shall be in the water system and the reactor and turbine i
X e
k fc(oc M q W. 'I.l 2. 2-
ABWR m s, ;
Standard Plant
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l pn n ee e '
x,' -. and ei ve ea idnt.
O ser iee - <er x>'
se#io de ener 'ie >
and other required interfacing systems should If a criterion of this na/ure is not sat, be available, as needed, to support the isfied, the plant will be plfced in a suitable specified testing, hold condition until resolation is obtaIned.
Tests compatible with this hold'condificin may be (3) GeneralTest Method and Acceptance Criteria continued. Following resolution, applicable tests may be repeated to verify that the re.
Performance s!ould be observed and recorded quirements of the criterion are ultimately dering a series of component and system tests satisfied. Other criteria may be associated to demonstrate the following:
with expectations relating to the performance of systems. If this type of criterion is not satis-(a) proper operation of instrumentation and fied, operating and testing plans would not nec-alarms used to monitor system operation essarily be altered. However, investigations of and status; the measurements and of the analytical tech.
niques used for the predictions would be start.
(b) proper operation of active cooling ed. Specific actions for dealing with criteria devices, if applicable, such as forced failures a nd other testing exceptions or or natural draft towers, spray ponds, anamolics will be described in the startup ad.
l ctc.; and ministrative manual.
(c) the adequacy of intake and discharge structures, including screens or strainers, or other interfaces with the i
circulating water system, such as freeze l
protection devices, as applicable.
r'N Operation is acceptable when the observed /
't) measured performance characteristics meet the applicable design specifications.
14.2.12.2 General Discussion of Startup Tests Those tests proposed and expected to comprise l
the startup test phase are discussed in this sub-l section. For each test a general description is l
provided for test purpose, test prerequisites, l
test description and test acceptance criteria, where applicable.
Since additions, deletions, and changes to these discussions are expected to occur as the test program is developed and implemented, the l
descriptions remain general in scope. In de-l-
scribing a test however, an attempt is made to identify those operatirg and safety. oriented j
characteristics of the plant which are being explored and evaluated.
l Where applicable, the relevant acceptance criteria for the test are discussed. Some of the criteria relate to the value of process variables i
assigned in the design or analysis of the plant, 1
l l
%Y AmeMment !!
14 2-W 16
ABM zmionss Standard Plant nrv s The specifics of the startup tests relating to rating records, regular routine coolant test methodology, plant prerequisites, initial analysis, radiochemical measurements of O'
conditions, acceptance criteria, analysis tech-specific nuclides, and special chemical niques, and the likes, will come from the appro-
- tests, priate design and engineering organizations in the form of plant, system and component perfor-Prior to fuel loading a complete set of mance and testing specifications, chemical and radiochemical samples will be taken to ensure that all sample stations are 14.2.12.2.1 Chemical and Radlochemical functioning properly, if not demonstrated Measurements during the preoperstional testing, and to determine initial concentrations. Subse-(1) Purpose quent to fuel loading, during reactor heatup, and at each major power level To secure information on the chemistry and change, samples will bpakerragd measure-radiochemistry of the reactor coolant while ments will be madejo'determiac thKchemical verifying that the sampling equipment, proce-and radiocherpKal quality of reactpr water dures and analytic techniques are adequate to and incoming'Teedwater, amount of radtolytic supply the data required to demonstrate that gas in tbt steam, gaseous activitic's leaving the chemistry of all parts of the entire the ai /cjectors dec times in ibe offgas C
reactor system meet specifications and pro.
line and p for nce oNilters and q
cess requirements, de incralizers i Calibrations'will be made j
of ooitors in effluent release paths, waste (2) Prerequisites ha dling systemsgnd' process lines. (
i The preoperational tests have been completed (4) Crit:ria I
and plant management has reviewed the test I
procedures and has approved the initiation of Chemical factors defined in the Technical O
'J f
testing. For erch scheduled testing iter-Specifications must be maintained within the y
ation the plant shall be in the appropriate limits specified.
v e
operational configuration with all prete.
t '
quisite testing complete. Instrumentation The activity of gaseous and liquid effluents j],
has been checked or calibrated as appro-must conform to license limitations.
i r
- praate, j'
Water quality should be known at all times y
(3) Description and shall remain within the guidelines of is the water quality specifications and the
}'
Specific objectives of the test progtam in-requirements of the Fuel Warranty document, clude evaluation of fuel performance, eval-f untions of demineralizer operations by direct 14.2.12.2.2 Radiation Mea:urements 3.
and indirect methods, measurements of filter g
performance, confirmation of condenser inte- (1) Purpose grity, demoaatration of proper steam separa-j tor dryer operation, measurement and calibra.
To determine the background radiation levels tion of the offgas system, and evaluation and in the plant environs prior to operation for ibration of certain process instrumenta-base dets on activ ty buildup and to monitor i
tiork An additional objective of this test radiation at selected powce levels to assure is the demonstration, and adjustment if the protection' c,f personnel during plant necessary, of th: proper functioning of the operation, hydrogen water chemistry system, the oxygen injection system, the zlue injection (2) Prerequisites passivation system and the iron ion injection system. Data for these purposes is secured The preoperational tests have been completed from a variety o
- ;-* "* eeviewed the test
- Proper functioning of such monitors will be venfied, as cppropnate, including
\\
via comparison mth ' dependent laboratory or other analyses. In particular, the m
I proper operation of fmled fuel detection functions of the main steamtme and offgas pre treatment process radiation monitors mil be venfied. In this regard.
{
sufficient data will be taken to assure proper settmg of or to make needed adjustments to, the alarm and inp settings of the applicable instrumentation.
m--
m
i ABWR uA6 mas Standard Plant Rrv A (3) Description (a) the status of all systems required for f) fuel loading will be specified and will
-j A survey of natural background radiation be in the status required; throughout the plant site will be made prior to fuel loading, Subsequent to fuelloading, (b) fuel and control rod inspections will be during reactor heatup, and at several power complete. Control rods will be install.
levels up to and including rated power, gamma ed and tested; dose rate measurements and, where appropri.
ate, neutron dose rate mesurements will be (c) the required number of neutron detectors made at specific locations throughout the will be calibrated and operable, con-plant. All potentially high radiation areas nected to conservatively set high flux will be surveyed including:
scram trips, and located and adjusted to provide acceptable signals during fuel (a) containment penetrations; loading; (b) all accessible areas where intermittent (d) nuclear instruments will be source activities have the potential to produce checked with a neutron source prior to transient high radiation conditions loading; before, during, and after such opera-tions; and (e) the status of secondary containment will be specified and established; (c) a complete survey of all accessible floor areas within the plant prior to (f) reactor vessel status will be.pecified fuel loading, at intermediate powers, relative to internal component placement and at full power.
and this placement established to make the wssel ready to receive fuel; (4) Criteria l (p reactor vessel water level will be estab-
/"(
The radiation doses of plant origin and the lished above the minimum level pre-occupancy times of personnel in radiation stribed; and zones shall be controlled consistent with the guidelines outliued in 10CFR20
- Standards for J (f) all other required systems shall be Protection Against Radiation".
operable as defined by the plant tech-f nical specifications and as demonstrated 14.2.12.2.3 Fuel bading by the applicable surveillance tests.
(1) Purpose (3) Description To load fuel safely and efficiently to the Fuel loading will commence and proceed fuli core size.
according to detailed written procedures in a predetermined si.quence that will assure a (2) Prerequisites safe and efficicut loading. The neutron
/
9 count rates shall be monitored as the core l
The plant has received the prop lifce se loading progresses to ensure continuous sub-from the NRC to proceed with fuelI adin and criticality and shutdown margin demonstra-i plant management has reviewed the app icable tions will be performed at specified loading l
procedures and the overall plant readiness, intervals.
and has approved the initiation of loading.
l (4) Criteria t
Additionally, the followina renuirements will
(
be met prior l' - - ~-
, at the applicable-l assure that th (8) final functional testing of the reactor protection system to demonstrate itical by at leasI safe manner:
proper trip points and logic. r.s well as the operability of scram tertns of reacti-breakers and valvet, and manual scram functions mil have been completed; Amendm<nt 2 102-4
' (h) final reactor coolant system leak rate test (s) to verify that system leak rates are within specified limits will have been completed,'
1
ABM u s u oo m Standard Plant nrv A Thus, after it is verified that all CRDs shall be checked or calibrated as is O
eversie vreeerix w8en in>< iiea. ie t re<eeri>>e.
performed periodically during heatup to assure that theie is no significant binding (3) Description caused by thermal expansion of the core components and no significant effect on per-Testing of the neutron monitoring system formance due to increased pressure, power or will commence prier to fuel load and will flow. Additionally, software functions such continue at intervals up to and including as those associated with the RC&lS are tested rated power. The SRNMs and operational to the extent that they could not be checked sources will be tested during fuel loading during preoperational testing.
and during rod withdrawal on the approach to criticality and heatup to rated temperature (4) Criteria and pressure. The LPRMs, APRMs and TIPS will be tested as soon as sufficient flux Each CRD shall have a measured scram time levels exist and at specified intervals
,\\
that is less than the technical specifi-during the ascension to rated power. Test-cations requirements and consistent with ing will include response checks, calibra.
f 5.}[
T safety analysis assumptions during both in-tions and verification of system software dividual rod pair and full core scrams, as calculations using actual core flus levels 2f2 aplicable. Each CRD shall have a measured and other live plant inputs.
j2s inser,/ withdrawal speed consistent with spe-y3) cified deQn requirements including those (4) Criteria gEg associated with group or gang movement.
s3?
Additionally, the CRDs shall meet friction The SRNMs, in conjunction with the installed
!4 test requirements and those for demonstra-neutron sources, shall have count rates and j $ j,,
}.
ting proper operation of rod deceleration signal to noise ratios that meet technical Qf j 5 d
devices. Also, all software functions or specifications _ and/or design requirements, cj features shall perform as specified, as applicable. The respective range func-d )- }d *$
14.2.12.2.6 Neutron Monitoring Sptem for overlappin8 neutron flux indicatica as y
tions of the SRNMs and APRMs shall prodde 2j W
Performance g i ;{,S reqeired by plant technical specifications and the applicable design specifications.
dj2j l(1) Purpose The APRMs shall be calibrated against core 8
2 2 [i 3
thermal power by means of a heat balance.
j3m}j To verify response, calibration and operation The accuracy of this calibration should be I
y
}
of startup range neutron monitors (SRNMs),
consistent with technical specifications.
y { 2. j local power range monitors (LPRMs), average When technical specifications are not appli-yj5 J :;.g ;
power range monitors (APRMs), traversing cable the APRMs should conservatively indi-F2a[
in core probes (TIPS), and other hardware and cate reactor power. The LPRMs should be g
E software of the neutron monitoring system calibrat:d consistent with design calibra-during fuel loading, cont-)I rod withdrawal, tion and accuracy requirements. Addition.
heatup and power ascension, ally, all system hardwere and software shall function properly in response to actual core (2) Prerequisites flux levels.
The applicable preoperational phase testing 14.2.12.2J Process Computer System 0peration is complete and the plant management has reviewed the test procedure (s) and has (1) Purpose approved the initiation of testing. For each scheduled test iteration the plant shall be To verify the ability of the process compu-in the appropriate operational configuration ter system (PCS) to collect, process, and with all specified prerequisite testing display plant data, execute plant perfor-p complete. The applicable instrumentation mance calculations, and interface with d
Ameridment 2 14.248
ABM ax6mors Standard Plant PIV A various plant control systems during actual (2) Prerequisites C;]
plant operating conditions.
The applicable preoperational tests base (2) Prerequisites been completed and plant management has reviewed the test procedure (s) and has The applicable preoperational tests have been approved the initiationj testiug. For completed 'atFplan't'ina.nagement has reviewed cach scheduled test %g iffer) tion the plant festing ipteration the/)'For each scheduled the,te' sting procedure (s and has approved the shall be in the appt.opdate oprational initiationjf testing.
configuration with all specified prerequi-plant shall be in the site testing complete, especially on plant appropriate op[erational configuration withsystems to be used for collection or 41 pr quisite testing complete.
evaluation of pertinent data.
(3) Description (3) Description During plant bestup and the ascension to rat-This test will collect data sufficient to ed power the various NSSS and BOP process demonstrate that reactor and core perfor-variables that are monitored by the PCS begin mance characteristics remain within design to enter their respective ranges for normal limits and expectations for all operational plant operation. During this time it will be conditions which the plant is normally ex-verified that the PCS correctly receives, va-pected to encounter. Beginning with rod lidates, processes, and displays the applic-withdrawal and continuing through initial able plant information. Recording and play-criticality, plant heatup, and the ascension back features will also be tested. Data ma-to rated power, pertinent data will be col.
nipulation and plant performance calculations lected at various rod patterns and power and using actual plant inputs will be verified flow conditions sufficient to determine the for accuracy, using independent calculations axial and radial core power distributions.
O for comparison. Also, the ability of the PCS compliance with core thermallimits, and the U
to interface correctly with other plant con.
level of consistency with predicted core trol systems during operation will be reactivity and power versus flow characteris-demonstrated.
tics. Unusual plant conditions such as dur-ing control rod sequence exchange or natural l
(4) Criteria circulation will also be investigated, if l
applicable.
The performance of the PCS shall be as speci-fied by the applicable design requirements. (4) Criteria l
Additionally, plant performance calculations,
/
especially those used to demonstrate com-Technical specification and lifcenj condi-l pliance with core thermal limits, shall meet tion requirements invo ving cpre thermal the accuracy requirements of the applicable limits, maximum power evel, total core plant safety analysis design assumptions, flow, and any observed reactivity anamolies or core instabilities shall be met when 14.2.12.2.8 Cote Performance applicable. Other observations should meet predictions and expectations or else should (1) Purpose be evaluated and explained accordingly.
1 To demonstrate that the various core and 14.2.12.2.9 Nuclear Boller Procesa Moeltoring l
reactor performance characteristics such as power versus flow, core power distributions, (1) Purpose and those parameters used to demonstrate compliance with core thermallimits and plant To verify proper operation of various nucle-license conditions are in accordance with ar boiler process instrumention and to col-design limits and expectations.
lect pertinent data from such instrumenta-iO Amendment 2 1424 l
ABM 23^siaors Srmadard Plant REV A 14.2.12.2.12 Reactor laternals Vibration response characteristics of the recircul.
ation flow control system are in accordance (1) Purpose with design requirements for all applicable modes of control across the span of crpected To collect information needed to verify the operational conditions, adequacy of the design, manufacture, and assembly of reactor vessel internals with (2) Prerequisites respect to the potential affects of flow induced vibration.
The preoperational tests have been completed and plant management has reviewed the test (2) Prerequisite procedure and has approved the initiation of testing. For each scheduled testing itera.
The applicable preoperational phase testing tion the plant shall be in the appropriate is complete, including the required inspec-operational configuration with all specified tiewspe plant management has reviewed the prerequisite testing complete. This in.
[ test proc dure ard has approved the initia.
' cludes preliminary adjustment and optimiza.
tioJ of te ting. For each scheduled testing tion of control system components, as appro.
fi terati a the plant shall be in the appro-
- priate, pria operational configuration with all cified prerequisite testing complete. The (3) Description necessary specialinstrumentation should be calibrated and operational.
Startup phase testing of the recirculation flow control system is intended te demon.
(3) Description strate that the overall response and stabil.
ity of the system meets design requirements
- Reactor internal vibration testing subse-subsequent to controller optimization. Per.
quent to fuel loading is merely an exte.nsion formance shall he demonstrated at a suffi.
)
of the program described during the preope-cient number of power and flow points to rational phase in Subsection 14.2.12.1.52.
bound the expected system operational cond.
The vibration measurement portion of that itions including applicable modes ~of control program should be expanded during the power (speed, flow and automatic load following) ascension phase to include intermediate and for each such demonstration. Testing will critical power and flow conditions during be accomplished by manual manipulation of steady state operation and anticipated controllers and/or by direct input of demand operational transients that are expected to changes at various levels of control.
result in limiting or-significant levels of Special control features such as those used reactor internals vibration over and above to maintain a specified margin to the high what was observed during the preoperational flux scram setpoint or to avoid regions of phase; potential core instability should also be demonstrated as appropriate.
l (4) Criteria (4) Criteria Criteria for limits on reactor internals vibration levels are developed during the Above all else, system perform <nce shah be vibration analysis portion of the ass:ssment stable such that any type ol divergent program as described in Subsection response is avoided. The resp <.nse should l
14.2.12.1.52.
also be sufficiently fast but with any oscillatory modes of response wel! damped, 14.2.12.2.13 Recirculation Flow Control usually with decay ratios less than.25.
The overall response o' ne syste.u, at all (1) Purpose levels of control, should be withir design requirements with respect to such standard To demonstrate that the stability and control system criteria as respons: tim e, -
Anwndment 2 14252 l
1 AMVR
- wmc Standard Plant RE Q rise time, overshoot, and settling time.
nonlinearities or dissimilarities in system
(
Also, the overall system perfortnance should response at various conditions should also be in accordance with expectations for be demonstrated. The above testing will anticipated transients.
also serve to demonstrate overall core stability to subcooling changes.
14.2.12.2.14 feedwater Control (4) Criteria (1) Purpose Above all else the feedwater control system To demonstrate that the stability and performance shall be stable such that any response characteristics of the feedwater type of divergent response is avoided. The control system are in accordance with design response should be sufficiently fast but requirements for applicable system configura-with any oscillatory modes of response well tions and operational conditions.
damped, usually with decay ratios less than 0.25. Additionally, the open loop response (2) Prerequisites of the system should meet design require-ments with respect to such standard control The pie 6pnational tests are complete and system criteria as response time, rise time, j plaliit manag' ment has reviewed the test overshoot, and settling time. Also, the procedure and has approved the initiation of overall system response should be as expect-
~
t ting. F r each scheduled testing ed following major plant transients and
' teratio the plant shall be in the trips.
approprpte operational configuration with W,cified prerequisite testing complete.
14.2.12.2.15 Pressure Control This includes preliminary adjustments and optimization of control system components, as (1) Purpose appropriate.
To demonstrate that the stability and l
(3) Description response characteristics of the pressure l
regulation system are in accordance with the l
Startup phase testing of the feedwater design requirements for all modes of control l
control system is intended to demonstrate under expected operating conditions.
~
that the overall response and stability of the system meets design requirements sub-(2) Prerequisites sequent to controller optimization. Testing will begin during plant heatup for any The preoperational tests have been completed specia! configurations designed for very low and plant management !.as reviewed the test feedwater or condensate flow rates and will procedure and has approved the initiation of continue up through the normal full power testing. For each scheduled testing itera-line up. Testing should include all modes of tion the plant shall be in the appropriate control and should encompass all expected operational configuration with all specified plant power levels and operatienti cocdi-prerequisite testing complete. This in-tions. Testir.g will be accomplished by man-ciudes preliminary adjustment and optimiza-ual manipulation of controllers and/or by tion of control system components, as appro-direct input of demand changes at various pria'e.
levels of control. System response should also be evaluated under transient operation- (3) Descriptica al conditions such as an unexpected loss of a feedwater pump or a rapid reduction in core Startup phase testing of the pressure con-flow and/or power level and after plant trips trol system is intended to demonstrate that such as turbine trip or main steam line the overall response and stability of the isolation. Proper setup of control system system meets design requirements. subsequent p
components or features designed to handle the to control system optimization. Performance U
Amendment 2 14253
M
- Such testing willinclude demonstration (s) that the dynamic response of the Standard Plant sani io oesign ivad s.ings ror ihe raciiiey. iac8ud'as hmiims sieP and ramp
^
thanges as appropriate. is in accordance with design
- E shall be evaluated..
nas approved the i
-anticipated steam flows for botn tne preuure
/
su......uu or testing. Affected systems and regulation and load-following modes of l
equipment, including lower level control control, as applicable. Testing should systems such as RC&IS, recite flow control, demonstrate acceptable response with either feedwater control and turbine control, as the turbine control valves or b) pass valves well as monitoring and predicting functions in control and for the transition between the of the plant process computer and/or auto.
two. Testing will be accomplished by manual mation computer, shall have been adequately manipulation of controllers and/or direct tested under actual operating conditions, input of demand changes at various levels of cont;ol. It should also be demonstrated that (3) Description other affected parameters remain within acceptable limits during such pressure regu.
A comprehensive series of tests will be per.
lator induced transient maneuvers. Overall-formed in order to demonstrate proper func.
system response will be evaluated during tioning of the various plant automation and other plant transients as well. Addition.
control features. This testing shall in-ally, proper setup of components or features clude or bound all expected plant operat.
i designed to deal with the nonlinearities or ing conditions under all permissable modes dissimilarities in system response that may of control and shall also verify, to the exist under various conditions should be extent possible, avoidance of prohibited or demonstrated.
undesirable conditions or control modes.
ALF capabilities will be demonstrated under (4) Criteria control of the APR for both control rod movements _and c_ ore flow changes including Above 'all else, system performance shall be anucipaTed transition regions
- The ability stable such that any type of divergent re.
of the PGCS to properly orchestrate auto.
O-onse is avoided. The response should be mated plant startup, shutdown and power ma-sufficiently fast but with any oscillatory neuvering will be shown. Also to be tested modes of response well damped, usually with are system components or interfaces that decay ratios less than.25.
The overall perform monitoring, prediction, processing, response of the system, for each mode and validation, alarm, protection or control level of control, should be within design functions.
requirements for such standard control system i
criteria as response time, rise time, over- (4) Criteria shoot and setting time. Also, the overall system performance should be in accordance The PGCS, APR and other features and func.
with expectations for anticipated transients.
tions of plant automation and control shall perform in accordance with the applicable 14.2.12.2.16 Plant Automation and Control _
design and testing specifications. Auto-matic maneuvering characteristics of plant (1) Purpose and systems shall meet the appropriate re-sponse and stability requirements. Safety To verify proper plant performance in auto-and protection features shall perform con-matic modes of control such as during auto.
sistant with safety analysis'assun;ptions and
- matic plant'startup o_r automatic load fol-predicsions-lowing (ALF) under the direction of the power generation control system (PGCS) and the 14.2.12.2.17 Itaaeter Recirculaties System automatic power regulator (APR).
Pedormance (2) Prerequisites (1) Purpose The applicable preoperational tests have been To verify that reactor recirculation system E
completed and plant management has reviewed performance characteristics are in accor.
Aniendment 2 14.2 54 i-
ABM 11A61 'oAN Standard Plant prv 4 dance with design requirements.
(2) Prerequisites bq (2) Prerequisites The preoperational testing is complejt*
plant management has reviewej 6e test The preoperational testing is compipc7nd procedure and has approved thegnitiation of )
plant management has reviewed thyfest pro-testing. For each scheduled testing i tera /
j cedure and has approved the initiatigp'of tion the plant shall be in thh appropriate /
testing. For each scheduled te ting i.stera-operational configuration withsgcjie'd tion the plant shall be in the ppropriatp prerequisite testing complete. Applicable operational configuration with 11 spejifet'd instrumentation has been checked or prerequisite testing complete. I strirmenta-calibrated u is appropriate.
tion has been checked or calibrated, as is appropriate.
(3) Description (3) Description Pertinent parameters will be monitored throughout the feedwater system, and con.
Pertinent recirculation system and related densate system if appropriate, across the parameters will be monitored at a variety of spectrum of system flow and plant operating power and flow conditions in order to demon.
conditions in order to demonstrate that sys-strate that system operation is in accordance tem operation is in accordance with design.
with design. Parameters to be monitored and Parameters to be monitored may include tem-evaluated should include RIP speeds, pump peratures, pressures, flow rates, pressure deck and core plate differential pressures, drops, pump speeds and developed heads, and pump efficiencies, maximum core flow capabil-general equipment status. Of special inte-ity, and any number of other variables that rest will be data that serves to verify de-may indicate the status of the RIPS and their sign assumptions used in plant transient shafts, motors, or heat exchangers. Data performance and safety analysis calculations (Q>
shall also be taken and evaluated during tran-like maximum feedwater runout capabilities sient conditions such as pump trips and re-and feedwater temperature versus power lesel starts, and during off normal conditions such relationships. <
as one pump out of service operation. Of par-
~~
ticular interest might be the onset of re-(4) Criteria
}
verse flow through idle pumps and the cali-l bration of total core flow indictions during When applicable, measured parameters shall both normal and off normal operating compare conservatively with safety analysis conditions.
design assumptions. Additionally, test data should demonstrate that system steady state j
(4) Criteria and transient performance meets design requirements.
When applicable, measured parameters shall compare conservatively with safety analysis 14.2.12.2.19 Mala Steam System Performance design assumptions. Additionally, test data should demonstrate that system steady state (1) Purpose and transient performance meets design re-quirements.
To verify that main steam system related l
performance characteristics are in accord.
14.2.12.2.18 Feedwater System Performance ance with design requirements.
(1) Purpose (2) Prerequisites To veiify that the overall feedwater system The preoperational tests are complete and operates in accordance with design require-plant management has reviewed the test pro-
[]
ments.
cedure and has approved the initiation of
' Steady state and transient testmg wdl be conducted, as necessary to assu Amendment 2 adequate margins exist between sptem variables and setpoints of instruments 34 2,55 monitonng these vanables to prevent spunous actuations or ions of sptem pumps and motor-operated valves.*
ASWR 2-xs Sandard Plant PfV A 1
Startup phase testing of the RWCU system is throttle rap discharge pressure in order to 4
7(V an extension of the preoperational tests for simulate reactor pressure sad the expected rated temperature end pressure conditions, pipeline pressure drop. This testing is System parameters will be monitored in the done to demonstrate general system various modes of operation at critical operability and to make most controller tr g:tature, pressure and flow conditions.
adjustments. Reactor vesselinjection tests will follow to complete the controller The performance of system heat exchangers and adjustments. Proper controller adjustinent filter /demineralizer units will be evaluated is verified by introducing small step at hot operating conditions. The ability of disturbances in peed and flow demand and the system to reject excess vessel inventcay then demonstrating satisfactory system during plant heatup will be verified. Other response and stability. This will be done system features should be demonstrated as at both low RCIC pump flow (but above appropriate, minimum turbine speed) and near rated RCIC pump flow conditions, and at reactor
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(4) Criteria pressures of 150 psig and rated,in order to
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span se EK opera % range.
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{jgy, System performance should meet the specified E
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Afler all controller and system adjustments j j ] f H @.!
have been made a defined set of demonstra.
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[$j 14.2.121.42 RCIC System Performance tions will be performed with the final set-j[]2gga 3:. g ",g tings. This will include two consecutive (1) Purpose successful reactor vessel injections, by j g3 h 3, 7 l automatic initiation from the cold standby j y {t <
- o. 2 jSg To verify proper operation of the RCIC sys-condition, to demonstrate system reliabil-ga tem over its expected operating pressure and ity. Cold is defined as a minimum of 72 0~{[{l5 flow ranges, and to demonstrate reliability hours without any kind of RCIC operation.
h"a!1 in automatic starting from cold standby with Following these tests, system data will be i
i)]$ ! 81 i
the reactor at power.
collected while operating in the full flow j
s [.la 7 g. g g test mode to provide a benchmark for compar.
- c. M (2) Prerequisites ison with future surveillance tests. Addi.
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- T j' tionally, a demonstration of extended oper.
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The preoperational tests are complete and ation of up to two hours (or until the pump
- Fc plant management has reviewed the test and turbine and their auxiliaries have sta-
[ $ $ a.I$jj procedure and has approved the initiation of bilized) of continuous operation at rated
- n.e g testing. For each scheduled testing itera.
flow conditions will be performed. For all i' ]3 {.4 l,y G,
c-tion the plant shall be in the appropriate testing proper operation of the system and 2
3; 20p operational configuration with all specified related auxiliarics will be evaluated.
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prerequisite testing complete. All appli.
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< Wt cable instrumentation shall be checked (4) Criteria calibrated as is appropriate.
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The RCIC turbine shall not trip or isolate (3) Description during the manual or automatic start tests and should avoid the applicable trip or iso-The RCIC system will bc tested in two ways, lation setpoints by the specified margins.
-thmugh a full flow test line leading to the For automatic initiations tbc time to rated suppreMion pool and by flow injection flow shall reect technical specification and M% tHte4ydts will consist of manual and auto.
idto the reactor vessel. The first safety analysis requirements. Overall sys-sets.L4 tem operation, aad :: sat of the applicable matic mode starts and steady state operation, auxiliary equipment, shall meet safety de.
at 150 psig and near rated reactor pressure sign requirements and should be consistent conditious, in the full flow test mode, with performance expectations. The RCIL During these tests an attempt will be made tr-control system shall not evidence divergent OV Amendment 2 14 2-57
i 23A610oAN Signdard Plant nrv s tendencies and should provide quick but To verify various HVAC systems performance stable response.
for the loads present during reactor power operation.
14.2.12.2.23 Plant Cooling / Service Water System (s) Performance (2) Prerequisites (1) Purpose The preoperational tests are complete and i
plant maaagement has reviewed the test pro-To verify performance of the various plant cedure(s) and has approved the initiation of cooHogfrervice water systems, including the testing. For each scheduled testing itera-7Jasitor building cooling water system, the tion, the plant shall be in the appropriate t
reactokservice' water system, the turbine operational configuration with the specified
/
brilot coolin water system, and the prerequisite testing complete. All t W.- ervice w er system under expected applicable instrumentation shall be checked reactor ower oper'ation load conditions, or calibrated as is appropriate.
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(3) Description The preoperational tests are complete and Power ascension phase testing of plant HVAC plant management has reviewed the test systens is necessary only to the extent that procedure and has approved the initiation of fully loaded conditions could not be app-testing. For each scheduled testing iters-roached during the preoperational phase.
tion, the plant shall be in the appropriate Pertinent parameters should be monitored in operational configuration with the specified order to provide a final verification of prerequisite testing complete. All appli-proper system flow balancing and cooler cable instrumentation shall be checked or performance under near design or special p
calibrated as is appropriate.
situation conditions, as is appropriate. y V
(3) Description (4) Criteria Power ascension phase testing of plant System performance should be consistent with cooling water system 4 is necessary only to design requirements. For systems that are tha. extent that fally loaded conditions could taken credit for in the plant safety not be approached during the preoperational analysis, performance shall meet the aJmimum phase. Pertinent parameters should be moni-requirements assumed in such analysis, tored in order to provide a final verifica-tion of proper system flow balariing and heat 14.2.12.2.25 Turblae Valve Performance exchanger performance under near design or special conditions, as is appropriate.
(1) Purpose (4) Criteria To demonstrate proper functioning of the main turbine control, stop, and bypass System performance should be consistent with,
valves during reactor power operation.
design requirements. For systems that are taken credit for in the plant safety analy. (2) Prerequisites sis, performance shall meet the minimum requirentents assumed in such analysist The preoperational tests are complete and plant management has reviewed the test pro-14.2.12.2.24 HVAC System Performance cedure(s) and has approved the initiation of testing. For each scheduled testing itera-(1) Purpose tion, the plant shall be in the appropriate operational configuration with the specified f%
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' ins m!! include extrapolation of results cutained under normal or test Amendewnt il e nditions as needed to demonstrate required perSrmance at limiting or 14.2 58 accident conditions.*
In eJJition, at rated temperature and pressure, proper functioning and stroke Mk timing of branch steamhne isolation varves (e g. on common drain hne) mil be UA6100AN Standard Pla demonsiraied EVA s
actor at a moderate power level and with the (
sponse observed. Closure times will be eva-O turbine generator on line, the operability of luated consistent with technical specifica-U the control, stop, and bypass valves will be tion and safety analysis requirements, if demonstrated. This testing should be similar appropriate, it is also desirable to deter-to the individual valve testing required by mine the maximum power level at which such the technical specification survei:iance pro-tests can safely be performed by observing gram. In addition to valve operability the plant response during such tests at overall plant response will be observed.
successively higher power levels.
Since turbine valve testing is required rou-tinely duricg power operation, it is also de-(4) Critena sirable to determine the maximuto power level at which such tests can safely be performed MSIV closure times shall be within the li.
by observing plant response during such tests v.its required by plant technical specifi-at successively higher power levels, cations and those assumed in the plant safe-ty analysis. Overall valve performance (4) Criteria should be in accordance with design require.
n' e n t e. During higher power level tests All turbine valves shall operate properly and nA uum p' ant trip avoidance margins should in accordance with applicable technical be miirnained.
specification requiremems. Valve perfor-mance and plant response. auld be consistent 14.2.12.2.27 SRV Performance with design requirements. During high power testing, minimum trip avoidance margins (1) Purpose should be maintained.
To demonstrate that each safety / relief vahe 14.2.12.2.26 MSIV Performance can be opened and closed properly in the relief mode during reactor power operation.
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(1) Purpose V
(2) Prerequisites To demonstrate proper operation of and to verify closure times for main steamline iso.
The preoperational tests are complete and lation valves durin wer op..uon.
plant management has reviewed the test pro-bem sfertme.y cedure(s) and has approved the initiation of
>,ncladd testing. For each scheduled testing itera-(2) Prerequ..isites g g>
tion, the plant shall be in the appropriate The preoperational testIa~re complete and operational configuration with the specified plant managemect has reviewed the test prerequisite testing co nplete. All applic-procedure (s) and has approved the initiation able instrumentation shall be checked or of testing. For each scheduled testing calibrated as is appropriate, iteration, the plant shall be in the appro-priate operational configuration with the (3) Description specified prerequisite testing complete. All applicable instrumentation shall be checked A functional test of each SRV shall be made or calibrated as is appropriate, as early in the power ascension as is practicable based on the valve manufac-(3) Description turer's recommendations. This is normally the first time the plant reaches rated At rated temperature and pressure, and then temperature s'id pressure. Opening and again at an intermediate power level, each closing of each valve, as well as evidence MSIV will be individually stroked in the fast of steam flow, will be verified by response closure mode. Valve operability and closure of SRV discharge tailpipe sensors and by time will be verified and overall plant re-observed changes in steamflow in the main O
V Amendment 2 14250
_ _ =
- the testing desenbed will also help to venly proper operation of the SCRRI MM logic and function in inponse eo actual R1r inp. and wiii help demonsirate 2.1AstooAN Standard Plant I
es REV A conjunction with specified mitigt. ting fea.
I to provide increased margin to core thermal M
tures, to prevent a reactor trip due to the limits. Therefore, an evaluation will be j
v water level transient. Separate tests may be made during the testing of Subsection required to demonstrate fessores such as 14.2.12.2.33 to demonstrate that coastdown automatic core flow runback o' auto start of characteristics are conservative relative to a standby feedpump,if appropriat9.
safety analysis assumptions. g)
(4) Criteria (4) Criteria From normal operating condi: ions, the reactor The reactor should not trip following any should remain operating with adequate margin RIP trip scenario for which it is designed to a water level setpoint trip.
to remain operating. Recirculation system performance and overall plant response 14.2.12.2.30 Recirculation Pump Trip should be in accordance with design expecta-hons. RIP and core flow coastdown charac.
(1) Purpose teristics shall be conservative relative to safety analysis design assumptions. During To demonstrate acceptable plant response and all RIP trip and restart scenarios tested, to obtain recirculation system performance the applicable parameters should maintain data during and subsequent to potential the specified minimum margins to their reactor intrmal pump (RIP) trip transients.
associated trip setpoints.
(2) Prerequisites 14.2.12.2.31 Shutdown Froan Outside ths Main Control Roon:
The preoperational tests are complete and pir.nt management has reviewed the test (1) Purpose procedure and has approved the initiation of O
testing. The plant shall be in the To demonstrate that the reactor can be shut appropriate operational configuration with down from normal power operation to the the specifi:d prerequisite testing com-point where a controlled cooldown has been l
plete. The applicable instrumentation shall established, via decay heat rejection to the l'
be checked or calibrated as is appropriate, ultimate hr9 sink, with vessel pressure and water level under control, all using means (3) Description entirely outside the main control roon).
A potential threat to plant availability is (2). Prerequisites the reacter trip due to high water level that i
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may result from an unexpected trip of one or The preoperational tests are complete and more of the RIPS. From near rated power and plant management has reviewed the test flow the most liar.iting, credible RIP trip procedure and has approved the initiation of scenario, for which the plant is designed to testing. The plant shall be in the appro-remain operating, will be initiated in order priate operational configuration with the to verify proper plant response. Of major specified prerequisite cesting complete.
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concern is the feedwater control systems The applicable instrumentation shall be ability to control reactor water level in checked or calibrated as is appropriate. An time to avoid a high water levet trip Also adequate number of qualified personnel shall to be demonstrated are the coastdown charac-be on site to perform the specified testing teristics of the triped pump (s), the onset as well as their normal plant operational.
of reverse flow through the idle pump (s), and duties.
the ability to restart the pump (s). The coastdown characteristics are of importance (3) Description especially during a high power turbine or
. generator trip where the RPT logic actuates This test should be performed from a low Amndant 2 14241 l ~.
t I
a-
ABWR zusinom Standard Plant PfV B 14.2.12.2.34 Reactor Full isolation priate design and testing specifications.
I 1
(1) Purpose 14.2.13 Interfaces To ve.rify that the dynamic response of the The preceding discussion of preoperational reactor and applicable systems and equipment and startup tests were limited to those systerns is in accordance with design for a simulta.
and components within, or directly related to, neous full closure of all MSIVs from near the ADWR Standard Plact. Other testing, with rated reactor power.
respect to site specific aspects of the plant will be necessary to satisfy certain ABWR in.
(2) Prerequisites terface requirements. Testing of such systems and components should be adequate to demonstrate The preoperational tests are complete and conformance to such requircrnents as defined plant management has reviewed the test proce-throughout the specific chapters of the SSAR.
dure and has approved the initiation of test. Below are systems that may require such testing:
ing. The plant shall be in the appropriate operational configuration with all specified (1) electrical switchyard and equipment; and-prerequisite testing complete. All appli-cable instrumentation shall be checked or (2) the site security plan; calibrated as is appropriate.
(33 pu wnne.A m d.rs W ra a b (3) Description seg inn,e,_.ds. W A simultaneous full closure of all MSIVs will y % d e @ p % rcd.lsdkm be initiated from near rated power in order to verify proper reactor and integrated plant g,I response. Reactor dynamic response, as deter.
p mined by such parameters as vessel dome pres-g 4 g Mg g
y V
sure and simulated fuel surface heat flux, will be compared with analytical predictions g ebewng A %ua9sdo'.y b h.Stary in order to verify tbc adequacy and conserva-t tism of the models and assumptions used in WWrM%dMM-hM#
the plant safety and licensing analysis, y,u a 6tl Ae.eiNc, wg #
Proper response of systems and equipment such 1
J as the MSIVs, SRVs, the reactor protection
%p, M M C' F * *#
system, and the feedwater and recirculation
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g,(.y coah 4 %
systems will also be demonstrated.
g gg y 4 (4) Criteria gem The reactor dynamic response should be con-sistent with predictions based on expected system characteristics and shall be conser-vative relative to safety analysis results
]
based on design assumptions. Safety related and essential equipment and systems shall re-spond, as applicable, consistent with techni-cal specification and safety analysis require-ments. Other plant systems and equipment should perform in accordance with the appro-l
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Amendment 11 14144 I
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