ML20058L830

Forwards SSAR Markups Addressing Draft Final Sser Section 14.2 Outstanding Items to Clarify Role of start-up Administrative Manual & Scoping Documents,Per

ML20058L830
Person / Time
Site:	05200001
Issue date:	05/07/1993
From:	Fox J GENERAL ELECTRIC CO.
To:	Poslusny C Office of Nuclear Reactor Regulation
References
NUDOCS 9305130014
Download: ML20058L830 (12)

Text

-

GENuclearEnergy i

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t Genera!Dectnc Company s

175 Curtner Avenue. 5an Jose. CA 95125 t

May 7,1993 Docket No. STN 52-001 l

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l Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal i

Office of the Nuclear Reactor Regulation a

1

Subject:

Submittal Supporting Accelerated ABWR Review Schedule - DFSER Section l

14.2 Outstanding Items l

t

Dear Chet:

i i

Enclosed are SSAR markups addressing DFSER Confirmatory item 14.2.123-1 and COL Action Items 14.2 3-1, 14.2 3-2, 14.2 3-3, 14.2 3-4, 14.2.4-1, 14.2.5-1,14.2.10.4-1, 14.2.11-1, j

14.2.123-1,14.2.12.4-1 and 14.2.12.4-2.

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This letter, which replaces may letter dated April 6,1993, clarifies the role of the start-up l

administrative manual and the scoping documents. Further, this current letter properly addresses COL Action item 14.2.123-1 and Confirmatory Item 14.2.123-1; specifically, Confirmatory Item 14.2.123-1 is encompassed in markup enclosed with my letter dated l

February 12,1993. Finally, this letter suggests modifications to DFSER pages 14-47,14-48 and i

14-55 (also enclosed) for consistency.

}

Please provide a copy of this transmittal to Frank Talbot.

l Sincerely, l

Jack Fox Advanced Reactor Programs

. cc:. Norman Fletcher (DOE) l Mike Song (GE) 1 H. J. Yang (GE) 4 num m

j 9305130014 930507 PDR <ADDCK 05200001 A

PDR

ABWR 2 m.a.

CramAmyd Plant nry A 14.2 SPECIFICINFORMATIONTO include, but are not limited to, flushing and i

i BEINCLUDED IN FINAL SAFETY cleaning, hydrostatic testing, initial calibra-ANALYSIS REPORTS tion of instramentation, checks of electrical wiring and equipment, valve testing, and initial i

14.2.1 Su==nry of Test Program and energization and operation of equipment and sys.

Objectives tems. Completion of this phase will assure that systems are ready for preoperational testing.

l The initial test program consists of a series Abstracts of these tests are not provided as I

j of tests categorized as construction, preopera-part of this chapter.

tional, or initial startup tests. The construc-j tion acceptance tests determine correct instal.

14.2.1.2 W- "--

• Test C ' ;W

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lation and functional operability of equipment.

Preoperational tests are those tests normally Preoperational tests are conducted prior to I

conducted prior to fuel loading to demonstrate fuel loading in order to verify that plant 4

the capability of plant systems to meet perfor-systems are capable of operating in a safe and l

mance requirements. Initial startup tests begin efficient manner compatible with the system with fuel loading and demonstrate the capability design bases. The general objectives of the l

of the integrated plant to meet performance preoperational test phase arc as follows:

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requirements.

(1) ensure that design specification and test -

l The objectives of the initial test program are acceptance criteria are met; to:

(2) provide documentation of the performance and l

(1) ensure that the construction is complete and safety of equipment and systems; i

l acceptable; (3) provide baseline test and operating data on l

(2) demonstrate the capability of structores, equipment and systems for future reference; i

i components, and systems to meet performance requirements; (4) run in new equipment for a sufficient period so that any design, manufacturing, or l

(3) effect fuelloadingin a safe manner; installation defeets can be deteeted and l

corrected; (4) demonstrate, where practical, that the plant is capable of withstanding anticipated (5) casure that plant systems operate together l

transients and postulated accidents; on an integrated basis to the extent 1

pouible; i

(5) evaluate and demonstrate, to the extent possible, plant operating procedures to (6) give masimum opportunity to the permanent i

provide as' stance that the operating group plant operating staff to obtain practical is knowledgeable about the plant and experience in the operation and maintenance procedures and fully prepared to operate the of equipment and systems, l

fac:htyin a asse naanmer;and (7) help demonstrate safe and efficient system (6) bring the plant to rated capacity and operating and surveillance testing proce-sustained power operation.

dures to the cuent possible;and 14.2.1.1 Cenairection Test Objectives (8) demonstrate that systems and safety equipment are operational and that it is Construction tests are performed to possible to proceed to fuel loading and to demonstrate that components and systems are the startup phase.

correctly installed and operational. These tests P

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MN col M. 2. I 2. 3 - t 23^M00AN Standard Plant rmv. n designs. During the construction and testing 14.2.2.5 Internlationships and laterfaces phases of the plant cycle GE personnel are onsite to offer consultation and technical direction Effective coordination between the various with regard to GE supplied systems and equip-site organizations involved in the test program ment. The GE resident site manager is respon-is achieved through the SCG which is composed of sible for all GE supplied equipment disposition representatives of the plant owner / operator, GE, and as the senior NSSS vendor representative on-and others. The duties of the SCG are to review site is the official site spokesman for GE. He and approve project testing schedules and to coordinates with the plant owner's normal and effect timely changes to construction or testing augmented plant staff for the performance of his in order to facilitate execution of the preoper-duties which are as follows:

ational and initial startup test programs.

(1) reviewing and approving all test procedures, 14.2.3 Test Procedures I

changes to test procedures, and test results for equipment and systems within the GE In general, testing during all phases of the scope of supply:

initial test program is conducted using detail-ed, step by step written procedures to control (2) providing technical direction to the station the conduct of each test. Such test procedures staff; specify testing prerequisites, describe desired initial conditions, include appropriate methods (3) managing the activities of the GE site to direct and control test performance (includ-personnel in providing technical direction ing the sequencing of testing), specify accep-to shift personnel in the testing and opera-tance criteria by which the test is to be tion of GE supplied systems; evaluated, and provide for or specify the format by which data or observations are to be record-(4) liaison between the site and the GE San Jose ed. The procedures will be developed and home office to provide rapid and effective reviewed by personnel with appropriate technical g

solutions for problems which cannot be backgrounds and experience. This includes the solved onsite; and participation of principal design organizations in the establishment of test performance regere-(5) participating as a member of the Startup ments and acceptance criteria. Specifically, GE Coordinating Group (SCG). [ Note: The will provide the plant / operator referencing the official designation of this group may ABWR Standard Plant design with scoping differ for the plant owner / operator documents (i.e., preoperational and startup test referencing the ABWR Standard Plant design specifications) containing testing objectives and SCG is used throughout this discussion and acceptance criteria applicable to its scope for illustrative purposes only.]

of design responsibility. Such documents shall also include, as appropriate, delineation of 14.2.2.4 Others specific plant operational conditions at which 1

tests are to be conducted, testing methodologies Other concerned parties, outside the plant to be utilized, specific data to be collected.

staff organization, such as the architect-and acceptable data reduction techniques as well engineer, the constructor, the turbine-generator as any reconciliation methods needed to account supplier, and vendors of other system and equip-for test conditions, methods or results where ment, will be involved in the testing program to testing is perforrned at conditions other than various degrees. Such involvement may be in a representative design conditions. Available direct role in the startup group as discussed information on operating and testing experiences above or in an indirect capacity offering con-of operating power reactors will be factored sultation or technical direction concerning the into test procedures as appropriate.tTe s t_

testing, operation, or resolution of problems or procedures will be reviewed by the SCG and will concerns with equipment and systems for which receive final approval by designated plant,

they are responsible or are uniquely familiar management personnel. Approved test procedures for satisfying the commitments of this chapter]

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zwiaoss ABM nrv s Stanatard Plant review and approval of test results and for re-wnhin the test phases see Las,r/ +

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solution of failures to meet acceptance crite-ria and of other operational problems or design 14.2.6 Test Records deficiencies noted, it describes the various I

phases of the initial test program and establi-Initial test program results are compiled and shes the requirements for progressing from one maintained according to the startup manual, i

phase to the next as well as those for moving be-plant administrative procedures, and applicable i

yond selected hold points or milestones within a regulatory requirements. Test records that j

given phase. It also describes the controls in demonstrate the adequacy of safety related place that will assure the as-tested status of components, systems and structures sha each system is known and that will track modi-retained for the life of the plant. Retentica l

fications, including retest requirements, deemed periods for other test records will be based on i

necessary for systems undergoing or already consideration of their usefulness in having completed specified testing. Additional-documenting initial plant performance characteristics.

ly, the startup manual delineates the qualifica-tions and responsibilities of the different 14.2.7 Conformance of Test Prograin with positions within the startup group. The startup administrative procedures are intended to supple. Regulatory Guides ment normal plant administrative procedures by addressing those concerns that are unique to the The NRC Regulatory Guides listed below were startup program or that are best approached in a used in the development of the initial test

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different manner. To avoid confusion, the start-program and the applicable tests comply with up program will attempt to be consistent with these guides czcept as noted. The applicable.

normal plant procedure where practical. The revisions of the regulatory guides listed below plant staff will typically carry out their duties can be found in Table 1.8-20.

according to normal plant procedures. However,

'in areas of potential conflict with the goals of (1) Regulatory Guide 1.68--Initial Test the startup program, the startup manual or the Programs for Water-Cooled Nuclear Power f

individual test procedures will address the Plants.

required interface.

S o 5 Asec/.,. 42.s3.2 im-con txerse r-famn Arteurener+s.

(2) Regulatory Guide 1.68.1--Preoperational and I

4 14.2.5 Review, Evaluation,and Approval Initial Startup Testing of Peedwater and of Test Results Condensate Systems for Boiling Water Reactor Power Plants.

i Individual test results are evaluated and reviewed by cognizant members of the startup (3) Regulatory Guide 1.68.2--Initial Startup l

group. Test exceptions or acceptance criteria Test Program to Demonstrate Remote Shutdown violations are communicated to the affccted and Capability for Water-Cooled Nuclear Power l

Plants.

responsible organizations who will help resolve the issues by suggesting corrective actions, design modifications, and retests. GE and others (4) Regulatory Guide 1.68.3--Preoperational outside the plant staff organization, as Testing of Instrument and Control Air appropriate, will have the opportunity to review Systems.

the results for conformance to predictions and expectations. Test results, including final (5) Regulatory Guide 1.20 -Comprehensive resolutions, are then reviewed and approved by Vibration Assessment Program for Reactor designated startup group supervisory personnel.

Internals During Preoperation and Initial Final approval is obtained from the SCG and the Startup Testing.

appropriate level of plant management as defined in the startup administrative manual. The SCG (6) Regulatory Guide 1.41-Preoperational and the designated level of plant management will Testing of Redundant Onsite Electric Power also have responsibility for final review and Systems to Verify Proper Load Group approval of overall test phase results and of Assign m en ts.

that for selected milestones or hold points I

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(7) Regulatory Guide 1.52--Design, Testing, To the extent practicable throughout the pre-sad Maintenance Criteria for Engineered operational and initial startup test program,.

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-Safety-Festure Atmosphere Cleanup System test procedures will utilire operating, emer-j Air Filtration and Adsorption Units of gency, and abnormal procedures where applicable l

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Light-Water-Cooled Nuclear Power Plants.

in the perforansce of tests. The use of these l

i procedures is intended to do the following:

l j

j (8) Regulatory Guide 1.56--Maintenance of Water punty in Boiling Water Reactors.

(1) prove the specific procedure or illustrate changes which may be required; (9) Regulatory Guide 1.95--Protection of 7

Nuclear Power Plant Control Room Operators (2) provide training of plant personneli:1the

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Against an Accidents! Chlorine Release.

use of these procedures; nad v

l (10) Regulatory Guide 1.108--Periodic Testing of (3) increase the level of knowledge of plant i

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Diesel Generators Used as Onsite Electric personnel on the systems being tested.

i I-Power Systems at Nuclear Power Plants.

A testing procedure utihung an operattag, j

(11) Regulatory Guide 1.139--Guidance for emergency, or abnormal procedure will reference l

Residust Hest Removal.

the procedure directly, cztract a series of l

steps from the procedure, or both is a way that l

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(12) Regulatory Guide 1.140-Design, Testing and is optimum to accomplishing the above goals j

Maintensace Criteria for Normal Ventilation while efficiently performing the specified i

4 Eshaust System Air Filtration and Absorbtion tastieg.

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l Units of Light Water Cooled Nuclear Power 14.2.10 InitialFuelImadingandInitial risars.

j Criticality l

l 1d.2.8 UtilizationofReactor ting and Testing Experience in the puent Fuel loading and initial criticality are l'

conducted la a very controlled manner in l

oftest Progrant accordanes with specific written procedures as i

Since every reactor / plant in a GE BWR product part of the startup test phase (see Subsection

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j liac is an evolutionary development of the. 14.2.12.2). Approval for comacacement of fuel i

previous plant la the product liac (and each loading is granted by the NRC after it has beca f

product line is an evolutionary development froan verified that all prerequisite testing has beei i

l the previous product line), it is evident that d f---;;, completed. However, there may be the ABWR plaats have the benefits of caperisace maioreseem circ==ramm that arise that would i

acquired with the ssecessful and safe startup of prevent the cospiction of all preoperational i

more than 30 previous BWR/1/2/3/4/5/6 plaats. testing (including the review and approval of-the test results) that would not accessarily j

Tbc operational experience and knowledge gained justify the delay of feel loading. U j

from these plaats and other reactor types has been factored into the desi m and test speci-cir=*==e== the applicant referencing the ABWR 5

j fications of GE supplied systems and equipment design may decide to request permission from the l

that will be demonstrated during the preopera-NRC to proceed with feelloading. If portions

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i tional and startup test programs. Additionally, of any preoperational tests are intended to be I

reactor operating and testing experience of conducted, or their results approved, after i

similar naclear power plaats obtained from NRC ca--*=*

of feel loading, them the following l

Tir-me Event Reports and through other industry shall be documented in such a request: (1) list

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sources will be utilized to the exteat each test; (2) state which portions of each test practicable in developing and carrying out the will be delayed until after fuel loading; (3) provide technical justification for delaying l

initial test program.

these portions; and (4) state when each test I

i 1d.2.9 Trial Use of Plant Operating and will be completed and the results approved.

Eanergency Procedures See S.Lwe/.u A 2. /3 2. /u- (o4' m e + f 1

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will be made available to the NRC staff approximately 60 days prior to their intended use for preoperational tests and 60 days prior to scheduled fuel loading for power ascension tests.

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14.2.4 Conduct oftest Program

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The initial test program is conducted by the startup group in accordance with the startup administrative manual. This tannual contains the administrative procedures and requirements that govern the activities of the startup group and their interfaces with other organizations. The startup administrative manual receives the same level ol' review and approval as do other plant administrative procedures. It defines the spe-cific format and content of preoperational and startup tec41 procedures as well as the review and approval process for both initial procedures and subsequent revisions or changes. The start-up manual also specifies the process for I

10-3.1 Amendenent 23

23A6100AN Stannlard Plant agy,

testing at lower power levels should generally be performed prior to that at higher power levels.

The detailed testing schedule will be generated by the applicant referencing the ABWR Standard Plant design and will be made available to the i

NRC prior to actual implementation. The schedule will then be maintained at the job site so that f

it may be updated and continually optimized to reflect actual progress and subsequent revised l

projections.

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14.2.12 Individual Test Descriptions,,,p.,

14.2.12.1 PreoperationalTest Procedures The following general descriptions relate the objectives of each preoperational test. During the final construction phase, it may be necessary to modify the preoperational test methods as operating and preoperational test procedures are developed. Consequently, methods in the following descriptions are general, not specific.

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MM 21mooAN Standard PInnt arv s 14.2.13 COL ucense Inforunation :_'i' T--!

Of the tests described in Subsection 14.2.12.2 i

. p for the ABWR Standard Plant the following tests, 4

/et 2.13. f O //n -/e d or designated portions thereof, are thus n: pxn-- 9: r::g Of prr;r :!!- " : d candidates for proposed exemptions from operating i

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• rtr; -:" r "9 ' te 'Er' sp!:r: rrf license conditions requiring NRC prior approval l

rerperert:

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?!::::!; ::!:::3 te, 6: for major test changes:

l Other testing, with respect j

to site specific aspects of the plant will be (1) 14 1 12.2.13 Recirculation Flow Control-l l necessary to satisfy certain ABWR seguirements.

except for those features st7esting of such systems and components d:!! 5:**

intended to limit maximum Q adequate to demonstrate conformance to such core flow; requirements as defined throughout the specific l

u r.1,q a j

e m.a w chapters of the SSAR. Below are systems that may (2) 14.2.12.2.21 Reactor Water Cleanup System l

Performance j

require such testing-l (1) electrical switchvard and equipment; (3) 14 11 M ?'4 Plant Cooling / Service Water System Performance - those l

(2) the site security plan; portions pertaining to the turbine building and service i

co t.

4 i*.t.i2.4 1 (3) Personnel monitors and radiation survey water systerr.s; I

instruments; and c o I.

(4) 14112124 HVAC System Performance -

la 2.it.1-s (4) the automatic dispatcher control system (if Those portions pertaining to l

applicable).

the normal HVAC system and i

Tes+ h.ccA,e acci 6a bA its associated nonessential i

lI4.2 13. 2. E rr7;"-f byp/'Adm;ae COL applicantdthe.fettep.g f* a chilled water system; i

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System Performance.

The COL a pNiant shaf frovNc"aiis The COL applicant shall provide the finallist j

'"e 4 those tests to be performed as part of the power of tests proposed to be exempt from such license l

ascension test phase that are proposed to be conditions, including adoption or augmentation of 1

er.empt from operating license conditions requiring the above list, as appropriate.

i NRC prior approval for major test changes. Reg l

i Guide 1.68 specifies criteria (see Regulatory l'

1 Position C.1) for determining what structures, i

systems, components and design features are required to be tested during the power ascension

.l test phase in accordance with the requirements l

l therein. Testing of such structures, systems, l

components and design features is then subject to i

license conditions requiring NRC approval for major test changes. For completeness, the testing described in Subsection 14.2.12.2 includes testing of a limited number of ABWR structures, systems, components and design features that do not meet j

1 i

the referenced Reg Guide 1.68 criteria, and are thus exempt from such license conditions.

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2 INSERT "A"

(1) the scoping documents (i.e.,

preoperational and startup test specifications) containing testing objectives and acceptance criteria applicable to its scope of design responsibility.

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<@.2.2-1 *

(See Subsection 14.2.3) dc;c vent:-_minictrat:. >e an a (precedurc; and-any other ScofMn (2) the etcc_up decurer+e "birb-delineate plant operational conditions at which tests are to be conducted, testing methodologies to be utilized, specific data to be collected, and acceptable data (1 //22-2

=9 reduction techniques to be reviewed by the NRC at the time of combined operating licenseQSee Subsection 14. 2. 3) ar.d 14. 2. ; ;

6e Marim done.d L del;ntcM.

AODEd any reconciliation methods M eded to account for test (3) v conditions, methods or results if testing if performed at e nditions other than representative design operating Q 4 2'1 ', 4 conditions.

(See Subsection 14.2.3)

(4) the approved preoperational and startup test procedures approximately 60 days before their intended use.

Q I4.z.3-4 4 (See Subsection 14.2.3)

(5) a startup administrative manual (procedure) and any other documents that delineate the conduct of the test program to be reviewed by the NRC at the time of combined operating license.

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(See Subsection 14.2.4)

(6) a startup administrative manual (procedure) and any other documents that delineate the review, evaluation, and approval

[d A 2.5 - I n of test results for the NRC review.

(See Subsection 14.2.4)

(7) a startup administrative manual (procedure) and any other documents that delineate the method of controlling pre-fuel-load-checks, initial fuel loading, precritical testing and fx

• 2. /u -/ w initial criticality for the NRC review.

(See Subsection 14.2.10)

(8) a startup administrative manual (procedure) and any other documents that delineate the test program schedule for NRC review' w

(See Subsection 14.2.11) go. jg.., ;

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v 14.2.2.5 Interrelationships and Interfaces SSAR Section 14.2.2.5 states that the effective coordination between the various site organizations involved in the test program will be achieved through the startup coordinating group (SCG) that will be composed of repre-sentatives of the plant owner / operator, GE, and others..The duties of the SCG will be to review and tpprove project testing schedules and to effect timely changes to construction or testing in order to facilitate execution of the preoperational and initial startup test programs.

14.2.2.6 Conclusion The staff finds the organization and staffing plan meets the acceptance criteria in SRP Section 14.2 and is acceptable.

14.2.3 Test Procedures SSAR Section 14.2.3 states that testing during all phases of the initial test program will be conducted using detailed, step-by-step written procedures to control the conduct of each test. Such test procedures will specify testing prerequisites, describe desired initial conditions, include appropriate methods to direct and control test performance (including the sequencing of testing), specify acceptance criteria by which the test will be evaluated, and provide for or specify the format by which data or observations will be recorded. The procedures will be developed and reviewed by personnel with appropriate technical backgrounds and experience. This will include partici-pation of principal design organizations in the establishment of test perfor-mance requirements and acceptance criteria.

GE will provide the COL applicant with scoping documents (i.e., preoperational and startup test specifications) containing testing objectives and acceptance criteria applicable to its scope of design responsibility.

Such documents ako will include, as appropriate, delineatio6 cf spccific plant operational conditions at which tests will be conducted, testing methodologies to be used, specific data to be collected, and acceptable data reduction techniques as well as any reconciliation methods needed to account for test conditions, methods, or results if testing is performed at conditions other than representative design operating conditions.

Available information on operating and testing experiences of operating power reactors will be factored into test procedures as appropriate.

The staff finds that the content, development, and review of test procedures meet the criteria in SRP Section 14.2 and are acceptable. However, a COL applicant will need to provide the following for staff review:

the scoping documents (i.e., preoperational and star' up test specifica-t tions) containing testing objectives and acceptance criteria applicable to its scope of design responsibility. This is COL Action Item 14.2.3-1.

the start"p rt a

(precad" m ) !ad any ett:r d m ants-wM4A delineate plant operational conditions at which tests are to be i

conducted, testing methodologies to be utilized, specific data to be collected, and acceptable data reduction techniques to be reviewed by the staff at the time of combined operating license. This is COL Action Item 14.2.3-2.

ABWR DFSER 14-47 October 1992

Be scef docuen h; aebne*+e

1. any reconciliation methods needed to account for test conditions, methods or results if testing is performed at conditions other than representative design operating conditions. This is COL Action Item 14.2.3-3.

the approved preoperational and startup test procedures approximately 60 days before their intended use. This is COL Action Item 14.2.3-4.

4 These are COL action items.

14.2.4 Conduct of Test Program SSAR Section 14.2.4 states that the initial test program will be conducted by the startup group in accordance with the startup administrative manual. This manual will contain the administrative procedures and requirements that govern the activities of the startup group and their interfaces with other organiza-tions. The startup administrative manual will receive the same level of review and approval as do other plant administrative procedures.

It will define the specific format and content of preoperational and startup test procedures as well as the review and approval process for both initial pro-cedures and subsequent revisions or changes.

The startup manual also will specify the process for review and approval of test results and for resolution of failures to meet acceptance criteria and of other operational problems or design deficiencies.

It will describe the various phases of the initial test program and establish the requirements for progressing from one phase to the next as well as those for moving beyond selected hold points or milestones within a given phase.

It will also describe the controls in place that will ensure the as-tested status of each system is known and track modifications, including retest requirements, deemed necessary for systems undergoing or already having completed specified testing.

Additionally, the startup manual will delineate the qualifications and responsibilities of the different post-tions within the startup group.

~

Staff Evaluation of DSER Items In the DSER, the staff determined that GE should specify whose approval must be obtained before increasing power to the next higher test plateau.

(This was incorrectly identified as an interface requirement in Section 14.2.5). GE indicated that such specifics will be a function of the plant owner /

operator's unique organizational structure and detailed plant administrative procedures and thus left to the COL applicant.

GE revised SSAR Sec-tion 14.2.13 to reflect that the COL applicant should specify whose approval is needed to proceed to the next testing plateau. This is acceptable.

The staff finds the conduct of test program meets the acceptance criteria in SRP Section 14.2 and is acceptable. However, a COL applicant will need to provide a startup administrative manual (procedures) and any other documents that delineate the conduct of the test program to be reviewed by the staff at time of combined operating license. This is COL Action Item 14.2.4-1.

14.2.5 Review, Evaluation, and Approval of Test Results SSAR Section 14.2.5 states that individual test results will be evaluated and reviewed by cognizant members of the startup group. Test exceptions or j

ABWR DFSER 14-48 October 1992 l

the predictions would be started.

Specific actions for dealing with criteria failures and other testing exceptions or anomalies will be described in the startup administrative manual.

The specifics of the startup tests relating to test methodology, plant pre-requisites, initial conditions, acceptance criteria, analysis techniques, and so forth will ccme from the appropriate design and engineering organizations of the COL applicant in the form of plant, system, and component performance and testing specifications. The COL applicant shall provide test documents for the Nuclear Reactor Regulation (NRR) review as discussed in SRP Sec-tion 14.2.3.

14.2.12.3 Staff Evaluation of DSER Items In the DSER the staff determined that testing of systems outside the scope of the ABWR standard plant design should be included or referenced in SSAR Sec-tion 14.2.12.

(This was not tracked as a separate open item.)

GE revised Section 14.2.12.1 in SSAR Amendment 18 to state that testing of systems outside the scope of the ABWR standard plant design are discussed in SSAR Section 14.2.13. This is acceptable.

In the DSER, the staff determined that SSAR Section 14.2.12 test abstracts should be modified to address the following concerns:

(1) Several preoperational and startup test prerequisites include the requirement that interfacing support systems will be available.

The staff asked GE to identify which support systems will be required for each test and specify which individuals or groups will be authorized to make this determination.

(This was incorrectly identified as an inter-face requirement.)

~

GE has stated that the interfacing support system requirements will be specified in the detailed test procedures (and operating and maintenance procedures, if appropriate) that are required by RG 1.68 to be made available_ to NRC_ personnel at least 60 days before their intended use.

accitionally, theht:rtup :nu:1 :nd :pplic:ble ;1: t dmir.istr:ti m w, ;. y,',

-pr:: dure will delineate how such determinations of operability and availability will be authorized. Thus, these details are the responsi-bility of the COL applicant. This is COL Action Item 14.2.12.3-1.

The staff determined that the level of detail in the test abstracts is insufficient to determine conformance with RG 1.68, Positici C.2.

(0 pen Item 6.118.) The individual test abstracts in SSAR Sections 14.2.12.1.1, 14.2.12.1.7, 14.2.12.1.11, 14.2.12.1.12, 14.2.12.1.13, 14.2.12.1.18, 14.2.12.1.21, 14.2.12.1.22, 14.2.12.1.43, 14.2.12.1.45.1, 14.2.12.1.45.2, 14.2.12.1.45.3, 14.2.12.1.45.4, 14.2.12.1.53, 14.2.12.1.59, 14.2.12.1.67, 14.2.12.1.68, and 14.2.12.1.69 do not specify basic systems required to be available, interface systems, or criteria required as prerequisite or initial conditions for the preoperational tests.

GE should address specific prerequisites in these individual test abstracts. This remains Open Item 14.2.12.3-1.

l ABWR DFSER 14-55 October 1992

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