NSD-NRC-96-4772, Forwards Draft Rev to Section 14.2 of AP600 Ssar Addressing AP600 Initial Test Program
| ML20116A404 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 07/16/1996 |
| From: | Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Quay T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20116A409 | List: |
| References | |
| DCP-NRC0554, DCP-NRC54, DCP-NRC554, NSD-NRC-96-4772, NUDOCS 9607260080 | |
| Download: ML20116A404 (31) | |
Text
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a Westinghouse Energy Systems Box 355 Electric Corporation Pittsburgh Pennsylvania 15230 0355 l
NSD-NRC-96-4772 DCP/NRC0554 Docket No.: STN-52-003 )
July 16,1996 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION: T.R. QUAY
SUBJECT:
S- :HAPTER 14 - INITIAL TEST PROGRAM, DRAFT
Dear Mr. Quay:
P The enclosure to this letter provides a draft revision to Section 14.2 of the AP600 SSAR addressing the AP600 initial test program. This revision addresses and incorporates review comments received from the NRC via the Draft Safety Evaluation Report, Requests for Additional Information and discussions with review staff. This section is provided at this time to facilitate the review effort and will be included in Revision 9 of the AP600 SSAR along with revisions to Section 14.3, Certified Design Material, and Section 14.4, Combined License Applicant Information.
The incorporation of staff review comments has resulted in significant revision to Chapter 14. To assist the staff review efforts, the following materials are included with this letter: Selection Criteria used in the development of the AP600 Initial Test Program Selectiw Criteria used in the determination of AP600 First Plant Only Tests Comparison Table of Reg. Guide 1.68 Appendix A to Chapter 14 Table comparing the revised Chapter 14 table of contents with the old table of contents. As the revised Chapter 14 has undergone significant reorganization, this table is useful to facilitate comparison between the revised Chapter 14 and the previous revision.
l 96072600EiO 960716 PDR ADOCK 05200003 A PDR
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l NSD-NRC-96-4772 DCP/NRC0554 July 16,1996 l
I Please contact John C. Butler on (412) 374-5268 if you have any questions concerning this transmittal, j l
Dr Brian A. cIntyre, a ll Advanced Plant Safety and Licensing 1
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l Enclosures Attachment cc: T. Kenyon, NRC (w/o Enclosures / Attachments)
J. Sebrosky, NRC (I A, IE)
J. Peralta, NRC (I A, IE)
R. Gruel, PNL (I A, IE)
N. J. Liparulo, Westinghouse (w/o Enclosures / Attachments) t h
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Attachment 1 I
p Test Selection Criteria for the AP600 Initial Test Program l
Introduction i.
n The " initial test program" for the AP600, as described in Chapter 14 of the SSAR, is a pan of the i whole plant test program. The whole plant test program includes all the tests required to bring the ,
AP600 on-line in a power producing mode.
! The initial test program consists of preoperational and initial stanup tests. Preoperational testing
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- consists of those tests conducted following completion of construction inspections and tests, but prior
- to fuel loading, to demonstrate the capability of structures, systems and components to meet i performaace requirements. Startup testing consists of those tests performed during and following fuel )
i loading that confirm the plant will operate in accordance with design and the plant is capable of 1 j responding as designed to anticipated transients.
l The initial test program is designed to demonstrate the performance of structures, syrtems, j components, and design features that 1) are used for safe normal operation with sufficient tolerance for system malfunctions and transients, (2) arrest or limit the consequences of errors, malfunctions, and off-normal condi tions, and (3) provide adequate safety margin for events of extremely low probability.
The focus of the initial test program is on those functions required for safe operation of the AP600.
While it is imponant that al! structures, systems, and components imponant for plant operation and , ;
safety be tested, it is not required that all of them be tested to the same stringent requirements.
Specifically, Criterion 1 of Appendix A to 10 CFR 50 requires, in part, that stmetures, systems, and components imponant to safety be tested to quality standards commensurate with the importance of the safety functions to be performed. This allows the initial test program to be developed and !
implemented using a graded approach. The graded approach allows the greatest attention be given to those structures, systems, and components considered most important to safety.
AP600 Graded Approach to Initial Testing The design philosophy for the AP600 allows the graded approach to be uniformly applied in developing the initial test program for the AP600 A graded approach to testing is consistent with the graded approach to quality assurance, ITAACS, and PRA for the AP600 System functions for the AP600 are identified with respect to their importance as related to safety. In l order of imponance, these functions are (1) safety related, (2) non-safety related but with defense in j depth (DID) functions, (3) Nonsafety related, Quality Group D systems which may contain radioactive !
material, and (4) non-safety related.
The AP600 system functions for the above four categories were initially delineated by system in :
response to RAI 100.11, previously submitted to the staff in Westinghouse letter NTD-NRC-94-4128,
Westinghouse Responses to NRC Requests for Additional Information on the AP600", dated May 11, 1994. The initial test program for the AP600 incorporates this graded approach based on functions such that the safety related functions of most importance receive the greatest attention.
A graded approach to initial testing in the AP600 is evident in the SSAR Chapter 14, Initial Test 1-1
l Programs, where preoperational test abstracts are delineated in varying degrees of detail for each of the four categories of tests. The safety-related test abstracts have the highest degree of detail as these systems are those that perform the functions assumed in the design basis safety analysis. DID systems have test abstracts sufficient to assess the performance of their DID functions. Quality Group D systems, important for storage and containment of radioactive material have test abstracts of sufficient detail to assess this function. Other nonsafety-related systems that are recommended for inclusion in the initial test program by Regulatory Guide 1.68 Rev. 2 Appendix A also have test abstracts of sufficient detail to assess their system function.
Chapter 14 allows the graded approach to be followed throughout the initial test program for the :
AP600 by distinguishing the imponance of the tests to be performed. Quality assurance requirements are determined by the COL applicant using a graded approach as recognized by Regulatory Guide 1.68. Revision 2. Quality requirements are provided for all levels of testing and are included in the quality assurance plan for the initial test program.
NRC oversight consists of review of the quality assurance plan for the initial test program for compliance, completeness and applicability. As outlined in Appendix B of Regulatory Guide 1.68, Revision 2, the NRC monitors and reviews the initial test program implementation with respect to the quality requirements. This includes review of applicable test procedures and surveillance of applicable testing. The following quality assurance requirements and NRC level of oversight are envisioned for the AP600 initial test program.
The highest level of quality assurance is applied to the preoperational tests of safety related functions ,
and to the startup tests identined in Chapter 14. Applicable portions of NQA-1, both the basic and supplemental ponions, are applied as required for testing. The level of quality assurance for tests of safety-related functions are commensurate with those of current operating plants. Test procedures for these tests would be made available to the NRC for inspection and review about 60 days prior to the conduct of the individual tests.
The quality assurance requirements applied to preoperational tests of DID functions are less stringent I than those applied to safety-related functional tests. These quality requirements would be based on i standards consistent with those applied for procurement of DID/RTNSS structures, systems and I components (SSC) as cited in Westinghouse letter, NSD-NRC-96-4670, " Quality Assurance Requirements for AP600 RTNSS Systems, Structures and Components", dated March 26,1996. These standards are comparable to those described in Generic Letter 85-06 for ATWS, as well as Regulatory Position 3.5 and Appendix A of RG 1.55 for station blackout equipment. Test procedures for these tests would be made available to the NRC for inspection and review upon request.
For the tests of non-safety related Class D equip.nent used to process, store, control, or limit the release of radioactive materials, the COL applicant specines quality requirements commensurate with testing of pressure vessels and piping, for example, as required by the ASME pressure code and the ANSI B.31.1 piping requirements. Appropriate requirements for test control, calibration of test equipment, and quali6 cation and training of test personnel are speci6ed in the quality assurance plan for these tests. Procedures for these tests are required and can be made available for NRC review and inspection upon request.
Tests of non-safety related equipment use quality requirements sufficient to provide adequate control of the tests and test equipment. The use of trained, quali6ed personnel and procedures for test 1-2
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performances are required, as a minimum. The test procedures would not require NRC review or I inspection, however, they would be available upon request. l Categorization Criteria for Chapter 14 Preoperational Test Abstracts l The following criteria for categorization of the preoperational test abstracts included in Chapter 14, ;
the initial test program for the AP600. The initial test program demonstrates that the AP600 can be j operated in accorcance with design requirements imponant to safety, as defined by Appendix A to 10 CFR Pan 50. The test abstracts selected describe only those tests that are imponant to safety and l
are conducted to verify the performance capabilities of those portions of structures, systems, and I components that:
- 1. Are designated as safety-related as specified in Section 3.2 of the SSAR. The AP600 safety- l related functions include, but are not limited to, those necessary to perform the functions specified by criterion C.I.b, d and e of Regulatory Guide 1.68, Revision 2. l l
- 2. Are de.cignated to perform defense-in-depth functions as specified in Section 3.2 of the SSAR.
The AP600 defense-in-depth functions include, but are not limited to, those necessary to perform the functions specified by criteria C.I.a of Regulatory Guide 1.68, Revision 2.
- 3. Are designated as Quality Group D in accordance with Regulatory Guide 1.26. These are used to process, store, control, or limit the release of radioactive materials, and are tested as )
specified by criterion C.I.f of Regulatory Guide 1.68, Revision 2. ,
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- 4. Will be used for establishing conformance with safety limits or limiting conditions for )
operation that will be included in the facility technical specifications as specified by criteria C.I.c of Regulatory Guide 1.68, Revision 2.
- 5. Tests of structures, systems, and components considered to be nonessential to the safe performance of the AP600, but are discussed in Regulatory Guide 1.68 Revision 2, Appendix A.
As allowed for in Regulatory Guide 1.68, Revision 2, the initial test program is developed and implemented using a graded approach. This graded approach is used to provide the greatest attention to the most imponant structures, systems and components. For the AP600 initial test program, this graded approach specifies the following:
- 1) For AP600 structures, systems, and components that perform safety-related functions (selection criterion 1 above), a test abstract is provided in Chapter 14 that identifies:
safety-related functions tested prerequisites necessary to perform the safety-related functional tests specific test methodology and acceptance criteria including references to applicable SSAR sections and applicable design documentation l
- 2) For AP600 structures, systems, and components that perform defense-in-depth functions, (selection criteria 2 and 4 above), a test abstract is provided in Chapter 14 that identifies:
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- - - - . . - . - - - . . . - _ . . - . - - - - . . - - - . ~ - - - -. __
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! - DID functions tested l
- prerequisites necessary to perform the DID functional tests i -- general test method and acceptance criteria including references to applicable SSAR l sections and design documentation
- 3) For AP600 structures, systems, and componen:s that meet (criterion 3 above), a test abstract is !
provided in Chapter 14 that identifies: )
Class D radioactive material processing equipment functions tested prerequisites necessary to perform these tests
- broad outline of test methodology and acceptance criteria 4), For AP600 structures, systems, and components that meet (criterion 5 above), a test abstract is provided in Chapter 14 that identifies:
- Nonsafety related functions tested prerequisites necessary to perform these tests
- broad outline of test methodology and acceptance criteria .
Startup Test Selection Criteria The startup test program consists of (1) initial fuel loading and precritical tests, (2) initial criticality tests, (3) low-power testing, and (4) power-ascension testing. The tests are performed after the successful completion of the preoperational tests and are intended to test the ability of the plant to load fuel, achieve initial criticality and ascend to power in a safe and orderly manner.
1 The startup tests demonstrate that the facility operates in accordance with design during normal steady-state conditions ard, to the extent practical, during and following anticipated transims. De startup tests focus on those aspects related to safe power production and for the AP600, are typical of those startup tests performed on currently operating Westinghouse PWR's.
Regulatory Guide 1.68, Revision 2. Appendix A, sections 2 through 5 are used to select the tests required for the startup tests of the AP600. Each phase of testing is delineated in Chapter 14 and test abstracts are provided for each test.
Summary Through the use of a graded approach to the AP600 initial test program, structures, systems and
, components important to safety are tested in accordance with their level of importance. The graded ,
approach is used throughout the entire test program, as allowed by Regulatory Guide 1.68, Revision 2, enabling the proper attention and resources be applied in the planning and implementation of the test l program. He graded approach is evident in Chapter 14 of the AP600 SSAR, where test abstracts are provided in varying degrees of detail. Table 1-1 provides an overview of the graded approach as applied to the initial 'est program for the AP600. l l
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! The graded approach will be applied to all p..ases of the initial test program including quality l
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assurance requirements. Quality requirements can be applied to the different tests as described in Chapter 14, such that those tests most important to safety receive the highest level of attention.
NRC oversight is commensurate with the level of quality requirements assigned to each phase of testing allowing NRC resources to focus on the most imponant test activities. In addition, review of test procedures by the NRC staff, a resource consuming process, can be directed to those tests that require the most oversight.
l Overall management by the COL applicant and NRC oversight, of the AP600 initial test program is l enhanced by the graded approach to testing. By focusing on those tests most imponant to the safe operation of the AP600, the initial test program can be effectively implemented with a high degree of confidence that'the AP600 structures, systems, and components will function as designed.
l Table 11, Chapter 14 Graded Approach to initial Testing of the AP600 FUNCTION TEST TYPE EQUIP CHAP 14 QA REQTS REGULATORY CLASS OVERSIGHT Safety Preoperational A,B,C Test Applicable Test procedure Related Abstract ponions of available to NRC at NQA-1 Basic & about 60 days prior Supplemental to test Defense Preoperational D Test Comparable to Test procedure .
In Depth Abstract QA requirements available to NRC (DID) for RTNSS SSC upon request procurement Radioactive Preoperational D Test ASME code, test Surveillance and ;
material Abstract controls as audits confinement applicable Other Non- Preoperational E F. List of Test controls as Surveillance and safety G,etc. Tests applicable audits Fuel Load, Stanup All Test Applicable Test procedures Criticality. Abstract ponions of available to NRC at Low Power, NQA-1 Basic & least 60 days prior to Power Supplemental fuel loading Ascension 1-5
I Attachment 2 Test Selection Criteria for First Plant Only Testing during the AP600 Initial Test Program l Screening criteria have been established to select those initial test program tests that are to be performed only for the first AP600 plant. This criteria is applied to each of the preoperational and l
sta tup test abstracts in the AP600 initial test program described in the Chapter 14 of the AP600 SSAR.
The screening criteria used to determine which tests are only required for the first AP600 plant are:
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- 1) A plant performance parameter (s) is measured v pch has not been provided by previous testing performed in support of design certification, an quipment qualification test or a production test of a prototype component or system, and l 2) Construction and installation inspections and other preoperational tests are performed on subsequent AP600 plants which ensures the plant parameter does not change.
l Examples of previous tests which have been performed for the first plant only, with NRC concurrence, ,
l have been the reactor internals vibration and RCS natural circulation testing. These tests have been )
accepted by the NRC as first plant only tests for the AP600 in the Draft Safety Evaluation Report.
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Westinghouse has made a determination of the AP600 first plant only tests to be submitted in Chapter 14 of the SSAR, Revision 9. Six preoperational and three startup tests have been selected as first plant only tests. This represents a reduction of eight in the number of first plant only tests relative to Revision 3 of the SSAR as shown in Tables 2-1 and 2-2, These tables also show the plant parameter (s) to be measured for each first plant only test. ,
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2-1 1
Table 2-1 Preoperational First Plant Only Testing Chapter 14, Revision 3 Chapter 14, Revision 9 Section No. First Plant? Section No. First Plant?
Reactor Vessel Internals 14.2.8.1.77 YES 14.2.9.1.9 (a thru e) YES, all items Flow induced vibration of the reactor Vibration Testing internals as allowed per Reg Guide 1.20 Expansion, Vibration and 14.2.8.1.78 YES 14.2.9.1.7 (a thru d) YES, item (d) Surge line and pressurizer spray line Dynamic Effects Testing only temperatures for thermal stratifkation and thermal cycle monitoring ADS 14.2.8.1.80 YES 14.2.9.1.1 (o thru r) YES, item (r) Loads imposed on the IRWST by the only sparger during blowdown Passive Core Cooling 14.2.8.1.85 YES 14.2.9.1.1 (a thru t) See ADS, System CMTand PRIIR for individual tests CMT 14.2.8.1.66,70 NO 14.2.9.1.1 (h thru k) YES, item (j) Net mass injection during recirculation only PRilR 14.2.8.1.87 YES 14.2.9.1.1 (d thru g) YES, item (g) 1RWST water temperature gradient due only to heatup during PRilR operation Remote Shutdown 14.2.8.1.94 YES 14.2.9.1.12 (d and h) NO PCS 14.2.8.1.98 YES 14.2.9.1.4 (a thru f) NO MCR Emergency 14.2.8.1.100 YES 14.2.9.1.6 (a thru e) Yes, item (e) MCR air supply and PMS liabitability System only temperatures during long term loss of Testing j VBS 2-2
Table 2-2 Startup First Plant Only Testing Chapter 14, Revisicsa 3 Chapter 14, Revision 9 Section No. First Plant? Section No. First Plant?
Dynamic Response 14.2.8.2.20 YES 14.2.10.4.19 NO Natural Circulation 14.2.8.234 YES 14.2.10.3.6 YES RCS flow and steam generator heat removal capability with no
. RCPs running
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Process Measuremerit 14.2.8.238 YES 14.2.10.4.9 NO Loss-of-Offsite Power 14.2.8.2.41 YES Deleted, see Att. 4 N/A RCCA Out of Bank 14.2.8.2.47 YES 14.2.10.4.6 NO 100% Load Rejection 14.2.8.2.51 YES 14.2.10.4.21 YES Reactor power, RCS and SG pressuresand temperatures Load Follow Demo 14.2.8.2.52 YES 14.2.10.4.22 YES Reactor core power distribution Plant Trip from 100% 14.2.8.2.55 YES 14.2.10.4.24 NO 2-3 i
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Attachment 3 Comparison of Regulatory Guide 1.68, Revision 2, Appendix A, Section 1, "Preoperational Testing," to AP600 Chapter 14 ;
l AP600 Not an Chapter 14 AP600 Test Design i 1.68 App. A Test Abstract Feature Comments I (14.2.9.-)
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- a. Reactor Coolant Spiem a.1 Integrated Systems Test 1.1 a.2 Components Test
- a. Pressurizer 1.1
- b. RCPs 1.1 I
- c. Steam Generators 1.1,1.2
- d. Pzr relief valves x
- e. MSIVs 1.2 l i
- f. Other valves 1.1,2.1
- h. RV, internals, and 1.9 AP600 does not employ internals vent valves internals vent valves
- i. Safety valves 1.1 1 I
- j. Jet pumps x a.3 Vibration Tests 1.7 a.4 Pressure Boundary Integrity 1.1
- b. Reactivity Control System b.1 Control Rod System Tests 1.8 b.2 Chemical Control System 1.5,2.3 b.3 Standby Liquid Control x System 3-1
! Attachment 3 Comparison of Regulatory Guide 1.68, Revision 2, Appendix A, Section 1, !
"Preoperational Testing," to AP600 Chapter 14 AP600 Not an Chapter 14 AP600 Test Design 1.68 App. A Test Abstract Feature Comments (14.2.9..)
- c. Reactor Protection - ESFAS 1.12
- d. Decay Heat Removal Systems d.1 Turbine bypass valves 2.1 d.2. Steam line atm. dumps 2.1 d.3 Relief valves 1.2 d.4 Safety valves 1.2 ,
d.5 Residual heat removal system 2.4 d.6 Reactor core isolation cooling x system d.7 Steamline isolation valves 1.2 d.8 Auxiliary feedwater system 2.2 d.9 Condensate storage systems 4.1 d.10 Emergency cooling towers 2.6 Nonsafety-related service water cooling towers d.11 ~ Cooling water systems 2.5,2.6
- e. Power Conversion Systems l e.1 Steam generators 1.2,2.1,2.2 c.2 Main steam system 2.1 'l e.3 MSIVs 1.2 e.4 SG pressure relief and safety 1.2 l valves 3-2 l
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l Attachment 3 Comparison of Regulatory Guide 1.68, Revision 2, Appendix A, Section 1, "Preoperational Testing," to AP600 Ckpter 14 AP600 Not an Chapter 14 AP600 Test Design 1.68 App. A Test Abstract Feature Comments (14.2.9..)
e.5 Steam extraction system 2.1 e.6 Turbine stop, control, bypass 2.1 and intercept valves e.7 Main condenser hotwell level 4.1 control system e.8 Condensate system 4.1 4 e.9 Feedwater system 2.2 e.10 Feedwater heater and drains 4.1 e.11 Makeup water and chemical 4.6, 4.7 '
treatment systems e.12 Main condenser auxiliaries 4.2, 4.8
- f. Waste Heat Rejection Systems f.1 Circulating water systems 4.6 f.2 Cooling towers and associated 4.6 auxiliaries f.3 Raw water and service water 4.6 cooling towers
- g. Electrical Systems g.1 Normal AC Power 2.15 Distribution System g.2 Standby AC Power Supply 2.17 g.3 DC System 1.14, 2.16 3-3
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Attachment 3 Comparison of Regulatory Guide 1.68, Revision 2, Appendix A, Section 1, "Preoperational Testing," to AP600 Chapter 14 AP600 Not an i Chapter 14 AP600 l Test Design )
1.68 App. A Test Abstract Feature Comments (14.2.9..)
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- h. Engineered Safety Features h.1 Emergency Core Cooling 1.3 l
Systems I
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l h.2 Autodepressurization system 1.3 h.3 Containment post-accident 1.4 I
heat removal systems h.4 Containment combustible gas 1.11 control system . I h.5 Cold water interlocks x j h.6 Air return fans 2.10, 2.11 Not an Engineered Safety Feature for the-AP600 )
i h.7 Ventilation, recirculation, and 2.10, 2.11 Not an Engineered I filter systems Safety Feature for the AP600 h.8 Tanks and other sources of 1.3,1.4 water used for ECCS h.9 Containment recirculation fans 4.11 Not an Engineered Safety Feature for the AP600 h.10 Ultimate heat sink 1.4
- i. Primary & Secondary Containments l i.1 Containment design 1.10 overpcessure 3-4
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l Attachment 3 Comparison of Regulatory Guide 1.68, Revision 2, Appendix A, Section 1, )
"Preoperational Testing," to AP600 Chapter 14 l
AP600 Not an 1 l Chapter 14 AP600 l
Test Design l 1.68 App. A Test Abstract Feature Comments (14.2.9..)
i.2 Containment isolation valve 1.10 l
i.3 Containment isolation valve 1.10 leak rate tests i.4 Containment penetration 1.10 leakage i.5 Containment airlock leak rate 1.10 i.6 Integrated containment leakage 1.10 j i.7 Main steam line leakage 1.2 .
i.8 Primary and secondary 1.10 AP600 does not employ containment a secondary containment i.9 Containment purge system 4.12 i.10 Containment & containment x annulus vacuum-breaker i I1
. Containment supplementary x leak collection i.12 Containment air purificati'on 4.12 i.13 Containment inerting system x ,
1 i.14 Standby gas treatment x l
i.15 Containment penetration 1.10 pressurization I
i.16 Containment ventilation 4.12 i.17 Secondary containment system x i.18 Containment annulus and x cleanup 3-5
l Attachment 3 j Comparison of Regulatory Guide 1.68, Revision 2, Appendix A, Section 1, l "Preoperational Testing," to AP600 Chapter 14 i
I AP600 Not an Chapter 14 AP600 Test Design
, 1.68 App. A Test Abstract Feature Comments j (14.2.9..)
i.19 Bypass leakage tests on x
, pressure suppression l
l 1.20 Ice-condenser containments x i.21 Containment penetration x cooling j . Instrumentation & Control '
Systems j.1 Pressurizer pressure and level 1.1, 2.12 .
control systems l
j.2 Main, auxiliary and emergency 2.1, 2.12 feedwater control l
l j.3 Secondary system steam 2.1, 2.12 pressure j.4 Recirculation flow control x j.5 Reactor coolant system leak 1.1 ,
detection j.6 Loose parts monitoring system 4.16 Loose parts monitoring is part of the Special l Monitoring System.
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i Attachment 3 Comparison of Regulatory Guide 1.68, Revision 2, Appendix A, Section 1, "Preoperational Testing," to AP600 Chapter 14 AP600 Not an Chapter 14 AP600 Test Design 1.68 App. A Test Abstract Feature Comments (14.2.9..)
j.7 Leak detection systems used to 2.4,3.4 AP600 passive core detect ' failures in ECCS & cooling system does not containment recirculating spray recirculate coolant (outside containment) outside containment.
RNS may be used if radiation levels inside containment are within limits. Radioactive waste drain system testing perform some aspects of this function.
j.8 Automatic reactor power 1.1, 2.12 control system j.9 Pressure control systems 1.1, 2.12 j.10 Seismic instrumentation 4.15 j.11 Traversing incore probe x system j.12 Failed fuel detection system 2.20 Failed fuel is determined by periodic sampling using the Primary Sampling System.
j.13 Incore & excore neutron 1.13, 2.14 I instrumentation l j.14 Instmmuntation and controls 2.12 that effect transfers of water i supplies I
.15 Automatic dispatcher control x systems j.16 Hotwell level control x l
j.17 Feedwater heater temperature 2.12 l
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! Attachment 3 l- Comparison of Regulatory Guide 1.68, Revision 2, Appandix A, Section 1, "Preoperational Testing," to AP600 Chapter 14 AP600 Not an Chapter 14 AP600 Test Design 1.68 App. A Test Abstract Feature Comments l (14.2.9.-)
j.18 Auxiliary startup instrument 2.12 l
j.19 Instrumentation & controls 1.12 used for shutdown from outside control room j.20 Instrumentation used to detect 1.3,3.4 Instrumentation that external & internal flooding det'ects containment water level is tested as l part of passive core cooling system testing.
Instrumentation that detects flooding of the -
auxiliary hilding is tested as part of the radioactive waste drain system testing.
j.21 Reactor mode switch and 2.12 associated functions j.22 Instrumentation that can be each system This instrumentation is used to track the course of tested as part of the postulated accidents various system testing.
j.23 Post accident hydrogen 1.11 monitors and analyzers used in the combustible gas control system j.24 Annunciators for reactor 2.13 control and engineered safety features j.25 Process computers 2.12
- k. Radiation Protection Systems 3-8
l l Attachment 3 i Comparison of Regulatory Guide 1.68, Revision 2, Appendix A, Section 1, I "Preoperational Testing," to AP600 Chapter 14 AP600 Not an Chapter 14 AP600 Test Design 1.68 App. A Test Abstract Feature Comments (14.2.9.-)
k.1 Process, criticality, effluent 3.1,3.2,3.3, and area radiation monitor 2.18 tests k.2 Personnel monitors and 2.18 radiation survey instrument k.3 Laboratory equipment used to 2.20 analyze or measure radiation levels k.4 High Efficiency Particulate Air 2.10, 2.11 Testing of HEPA filters (HEPA) is also performed as part ,
of applicable system testing
- 1. Radioactive Waste Handling
& Storage Systems 1.1 Liquid radioactive waste 3.1 handling systems 1.2 Gaseous radioactive waste 3.2 handling system 1.3 Solid waste handling systems 3.3 1.4 1 solation features for steam 1.2, 1.10 generator blowdown 1.5 Isolation features for x condenser off gas systems 1.6 Isolation features for 2.10, 2.11 ventilation systems 1.7 Isolation features for liquid 3.1 radwaste effluent systems 3-9
Attachment 3 Comparison of Regulatory Guide 1.68, Revision 2, Appendix A, Section 1, "Preoperational Testing," to AP600 Chapter 14 AP600 Not an Chapter 14 AP600 Test Design 1.68 App. A Test Abstract Feature Comments (14.2.9.-)
1.8 Plant sampling system 2.20, 4.17 1
- m. Fuel Storage & Handling Systems m.1 Spent fuel pit cooling system 2.7 tests m.2 Refueling equipment tests 1.15 m.3 Operability and leak tests 2.7
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m.4 Dynamic and static load 1.15 testing m.5 Fuel transfer devices 1.15 m.6 Irradiated fuel pool or building 2.10, 2.11 ventilation system
- n. Auxiliary & Miscellaneous Systems n.1 Service & raw water cooling 2.6,4.6 n.2 Closed loop cooling water 4.5 n.3 Component cooling water 2.6 systems n.4 Reactor coolant makeup 2.3,4.9 This function is system performed by the demineralized water transfer and storage system.
n.5 Reactor coolant & secondary 2.20, 4.17 sampling systems 3-10
T Attachment 3 i Comparison of Regulatory Guide 1.68, Revision 2, Appendix A, Section 1, l "Preoperational Testing," to AP600 Chapter 14 l
AP600 Not an Chapter 14 AP600 l Test Design 1.68 App. A Test Abstract Feature Comments (14.2.9..)
n.6 Chemistry & control systems 2.4,4.7,4.8 for reactor cool. int and secondary coolrat n.7 Fire protection systems 2.8 including demonstrations of proper manual and automatic operation of fire detection n.8 Seal water systems x n.9 Vent and drain systems for 3.4 contaminated systems and .
pumping systems serving essential area, pumps, electical components.
n.10 Purification and cleanup 2.3 systems n.11 Compressed gas systems 4.10 supplying pneumatic equipment, etc.
n.12 Boron recovery system x n.13 Communication systems 4.13 n.14 Heating, cooling and ventilation systems serving the following:
- a. Spaces housing 1.6, 2.10, engineered safety features 2.11
- b. Primary containment 4.11
- c. Battery rooms 2.10
- d. Diesel generator buildings 2.11 3-11
l 0
Attachment 3 Comparison of Regulatory Guide 1.68, Revision 2, Appendix A, Section 1, "Preoperational Testing," to AP600 Chapter 14 AP600 Not an Chapter 14 AP600 Test Design 1.68 App. A Test Abstract Feature Comments (14.2.9.-)
- e. Auxiliary buildings, 2.10. 2.11 reactor building, turbine building, etc.
- f. Control room habitability 1.6, 2.10 systems n.15 Shield cooling systems x n.16 Cooling and heating systems x for refueling water storage tank n.17 Equipment and controls for x establishing & maintaining subatmospheric pressures n.18 Heat tracing and freeze 1.4 Tested as part of system protection testing for those systems with heat tracing.
Y
- o. Reactor Components Handling Systems l t
1.15, 4.14 i o.1 Dynamic and static load tests of crancs, hoists an associated )
lifting & rigging i i
o.2 Demonstration of the 1.15, 4.14 l I
operability of protective devices and interlocks j 1.15, 4.14 O o.3 Demonstration of the operability of safety devices on equipment 3-12
Attachment 4 Table of Contents Roadmap for Chapter 14 (Revision 9 vs. Revision 3)
New Section Old Section Section Title Number Number (Rev.9) (Rev. 3)
Specific Information to be Included in Preliminary / Final Safety Analysis 14.1 14.1 Reports Specific Information to be Included in Standard Safety Analysis Reports 14.2 14.2 Summary of Test Program and Objectives 14.2.1 14.2.1 Construction and Installation Test Program Objectives 14.2.1.1 14.2.1.1 Preoperational Test Program Objectives 14.2.1.2 14.2.1.2 Startup Test Program Objectives 14.2.1.3 14.2.1.3 Organization, Staffing, and Responsibilities 14.2.2 None Test Procedures 14.2.3 14.2.2 Conduct of Test Program 14.2.3.1 14.2.2.1
~ l Revieve of Test Results 14.2.3.2 14.2.2.2 s.
Test Records 14.2.3.3 14.2.2.3 Compliance of Test Program with Regulatory Guides 14.2.4 14.2.3 Utilization of Reactor Operating and Testing Experience in the 14.2.5 14.2.4 Development of Tes Program Use of Plant Operating and Emergency Procedures 14.2.6 14.2.5 Initial Fuel Loading and Initial Criticality 14.2.7 14.2.6 Initial Fuel Loading 14.2.7.1 14.2.6.1 Initial Criticality 14.2.7.2 14.2.6.2 Power Ascension 14.2.7.3 14.2.6.3 Test Program Schedule 14.2.8 14.2.7 Preoperational Test Descriptions 14.2.9 14.2.8 Preoperational Tests of Systems with Safety-Related Functions 14.2.9.1 14.2.8.1 4-1
New Section Old Section k-tion Title Number Number ;
(Rev.9) (Rev. 3) i Reactor Coolant System Testing 14.2.9.1.1 14.2.8.1.25 ,
14.2.8.1.40 14.2.8.1.41 i 14.2.8.1.55 14.2.3.1.62 j 14.2.8.1.64 l 14.2.8.1.67 14.2.8.1.68
. 14.2.8.1.81 Steam Generator System Testing 14.2.9.1.2 14.2.8.1.32 l Passive Core Cooling System Testing 14.2.9.1.3 14.2.8.1.53 14.2.871.65 14.2.8.1.70 l 14.2.8.1.79 14.2.8.1.80 14.2.8.1.84 14.2.8.1.85 14.2.8.1.86 14.2.8.1.87 Passive Containment Cooling System Testing 14.2.9.1.4 14.2.8.1.19 l 14.2.8.1.83 14.2.8.1.96 14.2.8.1.97 l Chemical and Volume Control System Isolation Testing 14.2.9.1.5 14.2.8.1.73 1
14.2.8.1.74 Main Control Room Emergency Habitability System Testing 14.2.9.1.6 14.2.8.1.100 4-2 l
l New Section Old Section '
Section Title Number Number !
(Rev. 9) (Rev.3) {
Expansion. Vibration and Dynamic Effects Testing 14.2.9.1.7 14.2.8.1.49 14.2.8.1.77 l 14.2.8.1.78 14.2.8.1.82 Control Rod Drive System 14.2.9.1.8 14.2.8.1.69 )
14.2.8.1.71 Reactor Vessel Internals Vibration Testing (First Plant only) 14.2.9.1.9 14.2.8.1.77 Containment Isolation and Leak Rate Testing 14.2.9.1.10 14.2.8.1.92
. 14.2.8.1.93 14.2.8.1.102 .
Containment Hydrogen Control System Testing 14.2.9.1.11 14.2.8.1.39 Protection and Safety Monitoring System 14.2.9.1.12 14.2.851.59 I4.2.8.1.72 14.2.8.1.95 Incore Instmmentation System Testing 14.2.9.1.13 14.2.8.1.45 Class IE DC Power and Uninterruptible Power Supply Testing 14.2.9.1.14 14.2.8.1.2 l 14.2.8.1.15 14.2.8.1.16 Fuel Handling and Reactor Component Servicing Equipment Test 14.2.9.1.15 14.2.8.1.21 14.2.8.1.22 14.2.8.1.23 14.2.8.1.24
^
Long-Term Safety Related System Support Testing 14.2.9.1.16 None Preoperational Testing of Defense-in-Depth Systems 14.2.9.2 None 43
l
[ New Section Old Section Section Title Number Number l (Rev. 9) (Rev. 3) ,
Main Steam System Testing 14.2.9.2.1 14.2.8.1.32 14.2.8.1.33 14.2.8.1.50 14.2.8.1.58 Main and Staitup Feedwater System 14.2.9.2.2 14.2.8.1.30 14.2.8.1.91 Chemical and Volume Control System Testing 14.2.9.2.3 14.2.8.1.73 14.2.8.1.74 14.2.8.1.75 14.2.8.1.76 Normal Residual Heat Removal System Testing 14.2 9.2.4 14.2.8.1.42 Component Cooling Water System Testing 14.2.9.2.5 14.2 1.3 Service Water System Testing 14.2.9.2.6 14.2.8.1.5 Spent Fuel Pool Cooling System Testing 14.2.9.2.7 14.2.8.1.90
)
Fire Protection System Testing 14.2.9.2.8 14.2.8.1.7 Central Chilled Water System Testing 14.2.9.2.9 14.2.8.1.26 Nuclear Island Nonradioactive Ventilation System Testing 14.2.9.2.10 14.2.8.1.88 l 14.2.8.1.99 l
14.2.8.1.101
)
Radiologically Controlled Area Ventilation System 14.2.9.2.11 14.2.8.1.29 14.2.8.1.88 14.2.8.1.98 Plant Control System Testing 14.2.9.2.12 14.2.8.1.17 14.2.8.1.63 14.2.8.1.94 Data Display and Processing System Testing 14.2.9.2.13 14.2.8.1.17 14.2.8.1.51 4-4
i f
New Section Old Section Section Title Number Number (Rev. 9) (Rev. 3)
Diverse ^ctuation System Testing 14.2.9.2.14 New Section Main AC Power System Testing 14.2.9.2.15 14.2.8.1.8 14.2.8.1.9 14.2.8.1.10 14.2.8.1.13
. 14.2.8.1.14 4
j Non-Class IE de and Uninterruptible Power Supply System Testing 14.2.9.2.16 14.2.8.1.11 Diesel Generator Testing .
. 14.2.9.2.17 14.2.8.1.12
- 14.2.8.1.46 s
14.2.8.1.47 l
! 14.2.8.1.48 14.2.8.1.89 Radiation Monitoring System Testing 14.2.9.2.18 14.2'8.1.20
$ Plant Lighting System Testing 14.2.9.2.19 14.2.8.1.1 Primary Sampling System Testing 14.2.9.2.20 14.2.8.1.31 l
i I4.2.8.1.60 l
Preoperational Testing of Nonsafety-Related Radioactive Systems 14.2.9.3 None -
l Liquid Radwaste System Testing 14.2.9.3.1 14.2.8.1.35 l l' Gaseous Radwaste System Testing 14.2.9.3.2 14.2.8.1.34 Solid Radwaste System Testing 14.2.9.3.3 14.2.8.1.36 4
i Radioactive Waste Drain System Testing 14.2.9.3.4 14.2.8.1.37 j Steam Generator Blowdown System Testing 14.2.9.3.5 14.2.8.1.54
- i i Waste Water System Testing 14.2.9.3.6 14.2.8.1.35 7
Preoperational Tests of Additional Non-Safety Related Systems 14.2.9.4 None f
Condensate System Testing 14.2.9.4.1 14.2.8.1.43 j Condenser Air Removal System Testing 14.2.9.4.2 14.2.8.1.44 j r
j- 4-5 4
s
New Section Old Section Section Title Number Number )
(Rev.9) (Rev. 3) ;
l i
Main Turbine System and Auxiliaries Testing 14.2.9.4.3 None 1
Main Generator System and Auxiliaries Testing 14.2.9.4.4 None l
l Turbine Building Closed Cooling Water System Testing 14.2.9.4.5 14.2.8.1.4 l l Circulating Water System Testing 14.2.9.4.6 14.2.8.1.61
! Turbine Island Chemical Feed System Testing 14.2.9.4.7 14.2.8.1.52 l l \
None Condensate Polishing System Testing 14.2.9.4.8 j Demineralized Water Transfer and Storage System Testing 14.2.9.4.9 14.2.8.1.38 Compressed and Instrument Air System Testing 14.2.9.4.10 14.2.8.1.6 Containment Recirculation Cooling System Testing 14.2.9.4.11 14.2.8.1.27 l Containment Air Filtration System Testing 14.2.9.4.12 14.2.8.1.28 Plant Communications System Testing 14.2.9.4.13 14.2.8.1.18 Mechanical Handling System Crane Testing 14.2.9.4.14 None Seismic Monitoring System Testing 14.2.9.4.15 14.2.8.1.56 Special Monitoring System Testing 14.2.9.4.16 l'4.2.8.1.57 Secondary Sampling System Testing 14.2.9.4.17 None Stanup Test Procedures 14.2.10 14.2.8.2 Initial Fuel Loading and Precritical Tests 14.2.10.1 None Fuel Loading Prerequisites and Periodic Checkoff 14.2.10.1.1 14.2.8.2.3 Reactor Systems Sampling for Fuel Loading 14.2.10.1.2 14.2.8.2.4 Fuel Loading Instrumentation and Neutron Source Requirements 14.2.10.1.3 14.2.8.2.5 Inverse Count Rate Ratio Monitoring for Fuel Loading 14.2.10.1.4 14.2.8.2.6 l
4-6
i l
New Section Old Section !
Section Title Number Number j (Rev. 9) (Rev.3) s Initial Fuel Loading 14.2.10.1.5 14.2.8.2.1 l 14.2.8.2.2 l
Post-Fuel Loading Precritical Test Sequence 14.2.10.1.6 14.2.8.2.7 Incore Instrumentation System Precritical Verification 14.2.10.1.7 14.2.8.2.16 l
Resistance Temperature Detectors-In ore Thermocouple Cross Calibration 14.2.10.1.8 14.2.8.2.17 Nuclear Instrumentation System Precritical Verification 14.2.10.1.9 14.2.8.2.44 l Setpoint Precritical Verification 14.2.10.1.10 14.2.8.2.22 l l
Rod Courol System 14.2.10.1.11 14.2.8.2.8 j i
Rod Position Indication System 14.2.10.1.12 14.2.8.2.9 j Control Rod Drive Mechanisms 14.2.10.1.13 14.2.8.2.10 Rod Drop Time Measurement 14.2.10.1.14 14.2.8.2.11 l
Rapid Powet Reduction System 14.2.10 1.15 14.2.8.2.12 Process Instrumentation Alignment 14.2.10.1.16 14.2.8.2.24 j Reactor Coolant System Flow Measurement 14.2.10.1.17 14.2.8.2.13 Reactor Coolant System Flow Coastdown 14.2.10.1.18 14.2.8.2.14 i
Pressurizer Spray Capability and Continuous Spray Flow Verification 14.2.10.1.19 14.2.8.2.15 Feedwater Valve Stroke Test 14.2.10.1.20 14.2.8.2.36 Initial Criticality Tests
- 14.2.10.2 None Initial Criticality and Low-Power Test Sequence 14.2.10.2.1 14.2.8.2.26 Initial Criticality 14.2.10.2.2 14.2.8.2.27 Nuclear Instrumentation System Verification During Criticality 14.2.10.2.3 14.2.8.2.44 i
Post-Critical Reactivity Computer Checkout 14.2.10.2.4 14.2.8.2.28 Low Power Tests 14.2.10.3 None Low-Power Test Sequence 14.2.10.3.1 None Determination of Physics Testing Range 14.2.10.3.2 14.2.8.2.29 Boron Endpoint Determination 14.2.8.2.30 14.2.10.}.3 4-7 l
1 h ev - + w .~- -- - ,--- * ,,m,. -.. , , , . ,w,,.
l l
f si ,
i i
New Section Old Section Section Title Number Number t (Rev. 9) (Rev. 3)
Isothermal Temperature Coefficient Measurement 14.2.10.3.4 14.2.8.2.31
! Bank Worth Measurement 14.2.10.3.5 14.2.8.2.32 Natural Circulation (First Plant Only) 14.2.10.3.6 14.2.8.2.34 Power Ascension Tests 14.2.10.4 None Power Ascension Test Sequence 14.2.10.4.1 14.2.8.2.37 Incore Instrumentation System 14.2.10.4.2 14.2.8.2.16 Nuclear Instrumentation System 14.2.10.4.3 14.2.8.2.44 Setpoint Verification 14.2.10.4.4 14.2.8.2.22 Startup Adjustments of Reactor Control Systems 14.2.10.4.5 14.2.8.2.45 Rod Cluster Control Assembly Out of Bank Measurements 14.2.10.4.6 14.2.8.2.47 -
Axial Flux Difference Instrumentation Calibration 14.2.10.4.7 14.2.8.2.48 l Primary and Secondary Chemistry 14.2.10.4.8 14.2.8.2.19 Process Measurement Accuracy Verification 14.2.10.4.9 14.2.8.2.38 Process Instrumentation Alignment at Power Conditions 14.2.10.4.10 14.2.8.2.24 Reactor Coolant System Flow Measurement at Power Conditions 14.2.10.4.11 14.2.8.2.13 Steam Dump Control Sysxm 14.2.10.4.12 14.2.8.2.39 Steam Generator Level Control System 14.2.10.4.13 14.2.8.2.40 Radiation and Effluent Monitoring System 14.2.10.4.14 14.2.8.2.21 Ventilation Capability 14.2.10.4.15 14.2.8.2.63 Biologicd Shield Survey 14.2.10.4.16 14.2.8.2.33 Thermal Power Measurement and Statepoint Data Collection 14.2.10.4.17 14.2.8.2.43 Dynamic Response 14.2.10.4.18 14.2.8.2.20 i
Reactor Power Control System 14.2.10.4.19 14.2.8.2.46 Load Swing Test 14.2.10.4.20 14.2.8.2.49 l 100 Percent Load Rejection 14.2.10.4.21 14.2.8.2.51
! Load Follow Demonstration 14.2.10.4.22 14.2.5.2.52 48
l l
I New Section Old Section Section Title Number Number l (Rev.9) (Rev. 3)
Hot Full Power Boron Endpoint 14.2.10.4.23 14.2.5.2.53 Plant Trip from 100 Percent Power 14.2.10.4.24 14.2.8.2.18 Thermal Expansion 14.2.10.4.25 14.2.8.2.55 Specific tests deleted from SSAR Revision 3:
Rev. 3 Sect No Test Abstract Justification for deletion l
14.2.8.2.41 Loss of Offsite Power Each aspect of a loss of offsite power transient is tested separately. These tests include the RCP Flow Coastdown Test (14.2.10.1.18), the DG start and load l
test (14.2.9.2.17), the Rod Control System Test
. (14.2.10.1.11) and the Rod Drop Time Measurement Test (14.2.10.1.14). Performance of this test at power conditions 12 not warranted. ,
l 14.2.8.2.42 Plant Performance ne plant is operated at 100% power as part of other startup tests and the objectives of this test are I encompassed in other startup test abstracts. Since there was no performance criteria for this test and the test l was for data collection only, a test abstract is not l required in the SSAR.
l 14.2.8.2.50 50% Load Rejection De AP600 is designed for 100% load rejection which !
is more a demanding transient than a 50% load rejection. A test abstract (14.2.10.4.21) for the 100%
load rejection is included in Revision 9.
14.2.8.2.54 NSSS System Performance The plant is operated at 100% power as part of other startup tests. Since the criteria for this test is to satisfy a commercial requirement to operate continuously for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, this test is not required in the SSAR.
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4-9 .
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-- - . ,