ML20246E962

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Forwards Advance Changes to Advance Containment Atmosphere Monitoring Sys & Combustible Gas Control Sys Preoperational Test Summaries for Inclusion in Future FSAR Amend
ML20246E962
Person / Time
Site: Comanche Peak  
Issue date: 08/25/1989
From: William Cahill
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TXX-89564, NUDOCS 8908300085
Download: ML20246E962 (15)


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  1. TXX-89564

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914 Ref. # 10CFR50.34(b)

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M1ELECTR/C

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August 25, 1989

- Wmise. J. Cabiu, Jr.

Executive Vice Presodent

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-. S. Nuclear; Regulatory Commission' L.

Attn.: Document' Control Desk h.4

' Washington, D.?C.

20555

SUBJ ECT'
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446

' ADVANCE FSAR SUBMITTAL CONTAINMENT ATMOSPHERE MONITORING SYSTEM & COMBUSTIBLE GAS CONTROL-SYSTEM PRE 0PERATIONAL TEST SbMMARIES Gentlemen:

LThisL1etter provides an advance-copy of changes to be included in a future d'.

' FSAR.amendiaent dealing with the Preoperational Test Summaries for the M

Containment' Atmosphere Monitoring System and the Combustible Gas Control l System.

I The Containment Atmosphere Monitoring System Test Summary hes been corrected j

.to reflect the actual system design. The Combustible Gas Control System Test Summary has been clarified by eliminating the description'of the testing of if the hydrogen analyzer and by. describing this testing within the Containment Atmosphere Monitoring System Test Summary, e

In order ^ to facilitate NRC staff review of these changes, the enclosure:is

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organized as follows:

q

'1.

Draft revised FSAR pages, with changed portions indicated by a bar in the margin, as they are to appear in a future amendment (additional pagas immediately preceding and/or following the revised pages are provided if.needed to understand the change).

2.

A line by-line description / justification of each item revised.

3.

A copy of related SER/SSER sections.

i 4.

An index page ccntaining the title of " bullets" which consolidates and categorizes similar individual changes by subject and related SER section.

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B908300085 890825 PDR; ADOCK O5000445 4M North Olive Street LB 81 Dallas, Texas 75201 A>

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m-1: g-TXX-89564 August-25, 1989

'Page 2 of 2.

5.

-A discussion of each " bullet" which includes:

The line-by-line description / justification for each item lt b if-ijw,3 related to the" bullet" which -has been screened as a group 1 f'

or 2 item or a' group 3 or 4 item which impa'ts the existing j-c SER/SSER's.

(The discussion of these groups is contained in i

TV Electric's letter TXX-88467 dated June 1, 1988).

ji The bold / overstrike version of the revised-FSAR pages.

referenced by the description / justification for each item identified above. The bold / overstrike version facilitates review of the revisions by highlighting each addition of new.

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text in bold type font and overstriking with 'a slash (/) the portion of the text that'is deleted.

If you have any questions regarding this submittal please contact Richard Berk at (214) 812-8952.

Sincerely, l'

I-William J. Cahill, Jr.

RSB/vid.

Enclosure c - Mr. R. D. Martin, Region IV

' Resident Inspectors, CPSES (3)

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s Enclosure to TXX-89564 August 25, 1989' Advance FSAR Change Regarding-the Containment Atmosphere Monitoring System & Combustible. Gas Control System Preoperational Test Summaries-F Item'l~

Draft Revised FSAR Pages" pg. 2 thru 3

Ites '2 Description / Justification pg. 4'

' Item 3

~Related SER/SSER' pg. 5 thru 8 Item 4-IndexiPage Containing the pg. 9-

' Title of " Bullets" Item 5

- Description / Justification for.

pg. 10 Screened FSAR Changes Markup of Existing FSAR Pages pg. 11 thru 13 pg. I of 13 1

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k E clos'ure tMTXX-89564 CPSES/FSAR-(

August;25511989J s <

Pg. 2sof :13

- TABLE 214.2-2 t

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?'D CONTAINMENT ATHOSPHERE MONITORING SYSTEM TEST

SUMMARY

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~ OBJECTIVE H

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To demonstrate the operability of the Containment' Atmosphere

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PRERE0VISITES

.w 1.

Setpoints for' alarms and indicating lights have been set.

TEST METH0_D_

1.

Demonstrate proper operation of the hydrogen analyzer / monitoring DRAFT-equipment' by functional' testing from the microprocessor I

keyboard.

2.

Demonstrate proper operation of the temperature and humidity ORAFT

' instrumentation.

3.

< Demonstrate proper operation:of the containment ~ pressure DRAFT transmitters.

' ACCEPTANCE CRITERIA 0423.11

.The' Containment Atmosphere Monitoring System functions'in accordance DRAFT with design requirements.

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Encibsure to'TXX-89564 CPSES/FSAR

1. August 25',.1989 ~

- TABLE 14.2-2 Pg 3 of 13 -

(Sheet 31

).

COMBUSTIBLE CAS CONTROL SYSTEMS

' TEST

SUMMARY

OBJECTIVE To demonstrate the proper operation of the Hydrogen Recombiners and the Hydrogen Purge System.

PREREQUISITES 1.

.The hydrogen recombiners are operable and their associ;+ed Dewer

. panel is energized.

'2.-

'The Hydrogen Purge System is operational.

DRAFT.

TEST' METHOD l '.

Verify the proper. operation of the hydrogen recombiners, 76 including the. heaters, controllers and temperature indicators.

2.

Verify proper operation of the Hydrogen Purge System, including DRAFT the system fans and filters.

ACCEPTANCE CRITERIA 0423.11-The combustible gas control systems operate in accordance with design 6

criteria. The hydrogen recombiners, system fans and filters perform their: design function.

Instrumentation, controls, annunciators and interlocks function properly in response to normal or simulated L

signals.

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_i__.___ _ _ _. _ _ _ _ _. _ _. _ _ _ _

Enclosure to TXXO9564.'

, CPSES FSAR AMENDMENT-(August:25, 1989 '

. DETAILED DESCRIPTION

- Page 1 J Pg.2 4. of.13 =

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FSAR Page' 0

(as amended)

Group Description l'

i 1Tcble 14.2-2 2

See Sheet No(s):23 l:

Corrects the Testing Methodology and Acceptance l

Criteria for the Containment Atmosphere Monitoring System Test Summary.

Correction:

The FSAR changes were made to more appropriately group related areas of. instrumentation testitig under the i,.

Containment Atmosphere Monitoring System Testing Program. The changes reflect the actual system design.

FSAR Change Request Number: 89-489.1 Related SER Section: 14 w.

SER/SSER Impact: Yes k

Test Summary which the NRC has not reviewed for CPSES.

lable 14.2-2' 4

See Sheet No(s):31 Clarification to the Prerequisites and Testing Methodology sections of the. Combustible Gas Control.

Systems Test Summary which eliminates the testing of-the_ hydrogen analyzer..

Clarification:

The hydrogen. analyzer will be more appropriately tested as part of the Containment Atmosphere a

Monitoring System as described. in Table 14.2-2 (Sh.23).

1 See LDCR Checklist No.89-489.1 for details.

FSAR-Change Request Number: 89-489.2-Related SER Section: 14 SER/SSER Impact: No

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Enclosure to TXX-99564 August 25, 1989 Pg. 5 of 13 14 INITIAL TEST PROGRAM The testing activities to be performed on safety-related systems at Comanche Peak are divided into three major phases:

prerequisite testing, preoperati:nal testing, and initial startop testing.

Prerequisite testing will be conducted to verify the integrity, proper installa-tion, cleanliness, and functional operability of the system components.

Preoperational testing will be performed to demonstrate the capability of systems, structures, and components to meet safety-related performance require-ments. These tests will be performed on plant systems, structures, and compo-nents that are designed to perform a nuclear safety-related function.

Preopera-tional testing will be completed before fuel loading with certain limited exceptions where tests or parts of tests will be deferred until the core has been loaded.

In such cases, sufficient testing will be performed before fuel loading to provide reasonable assurance that the postloading tests will be successful.

Initial startup tests will be performed beginning with fuel loading and ending with commercial operation.

The intent of these tests is to ensure that fuel loading is effected in a safe manner; that the plant is safely brought to rated capacity; that plant performance is satisfactory in terms of established design criteria; and to demonstrate, where practical, that the plant is capable of withstanding anticipated transients and postulated accidents.

The staff review concentrated on the administration of the test program and the complete-ness of the prerequisite, preoperational, and startop tests.

For example, the staff's Safety Evaluation Report issued at completion of the Construction Permit review (CP SER) was re-examined to determine the principal design criteria for the plant and to identify any specific concerns or unique design features that would warrant special test consideration.

Cha?ters 1 through 12 of the FSAR were reviewed for familiarization with the facility design and nomenclature.

Chapters 13 and 17 were reviewed for familiarization with the applicant's organizational structure, qualifications, administrative controls, and quality assurance program as they apply to or impact the initial test program.

Chapter 15 was reviewed to identify assumptions pertaining to perform-ance characteristics that should be verified by testing and to identify all structures, systems, components, and design features that were assumed to function (either explicitly or implicitly) in the accident analysis.

Licensee Event Reports for operating reactors of similar design were reviewed to identify potentially serious events and chronic or generic problems that might warrant special test consideration.

Standard Technical Specifications for Westinghouse PWRs were reviewed to identify all structures, systems, and components that would be relied upon for establishing conformance with safety limits or limiting conditions for operations.

Finally, the Startup Test Reports for other PWR plants were reviewed to identify problem areas that should be emphasized in the Comanche Peak initial test program.

The object of the staff review of FSAR Chapter 14 is to determine whether the acceptance criteria stated in the Standard Review Plan are met.

The staff review covered several aspects of the initial test program including the following major considerations:

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' ;(1)f TheLapplicant's organization and staff for performing the initial test,

program were reviewed.

The staff concludes that an adequate number of A

' conduct the tests,-and review the results of the tests. ap f[ W Plant staff-(personnel are utilized to maxiaize the training. benefits of the test y

program.

N L(2)' The aoplicant stated that the test procedures were developed us P

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from the N555 vendor, the architect engineer,'the applicantfs engin "g u,

steff,iand other equipment suppliers and contractors as needed.

applicant also stated that-a review of operating experiences at similar The m

plants was factcred into the development of the test procedures.

(3)

The applicant statedIthat the tests are being conducted using approved-H of' test prerequisitestest procedures and that administrative controls c o?,

(b). the completion of necessary dataisheets and

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s other documentation, a,nd (c) the review and approval of modifications-to test procedures, The applicant stated that administrative procedures also cover implementation of modifications or repair requirements identified as being required by the tests and any necessary retesting (4)' The applicant stated that the results of eacn test are reviewed for i

NSSS vendor and architect engineer personnel as app tionel test results are reviewed before fuel loading,priste.

Preopera-h 3

and the startup test results from each activity or power level will be reviewed before 4-the next activity or power level.

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-(5) The applicant stated that norr#1 plant operating and emergency procedure are used in correctness. performing the initial test program, thereby verifying the of the procedures to the extent. practical.

(6)

The applicant's schedule for conducting the initial test program allowed

adequate time'to conduct all preoperational tests and startup tests.

sequential schedule for performing the startup tests established The systems required to orevent, limit, or mitigate the consequences o(a) that postulated accidents will be tested before 25% of rated power is exceeded f

and (b) that the safety of the plant will not be dependent on the perfor-mance of untestad systems, structures, and components.

Preoperational test procedures will be available for IE revbw at least 30 days before

-the expected performance of the test, and startup test procedures will be available at least 90 days before fuel loading.

(7)

The abstract of each test procedure presented in Chapter 14 of the F5AR was' reviewed.

The staff verified that there are test abstracts for those U

structures, systems, components, and design features that:

(a) will be used for shutdown and cooldown of the reactor under normal plant condi-tions and for maintaining the reactor in a safe condition for an extended shutdown period; (b) will be used for shutdown and cooldown of the reactor under tran:ient (infrequent or moderately frequent events) conditions and postulated accident conditions and for maintaining the reactor in a safe condition for an extended shutdown period following such conditions; (c) will be used for establishing conformance with safety limits of l

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limiting conditions for operation that will be included in the facility technical specifications; (d) are classified as engineered safety features or will be relied on to support or ensure.the operations of engineered safety features within' design limits; (e) are assumed to function or for which credit is taken in the accident analysis of the facility, as described in the FSAR; and (f) will be used to process, store, control, or limit the release of radioactive materis's.

(8) The test objective, prerequisites, test methods, and acceptance criteria for each test abstract were reviewed in sufficient detail to establish that the functional adequacy of the structures, systems, components, and design features will be demonstrated.

(9) The test program's'conformance with applicable Regulatory Guides was reviewed.

The review included:

Regulatory Guides 1.20, 1.41, 1.52, 1.68, 1.68.2, 1.79, 1.80, and 1.108.

The applicant made a number of changes to the initial te.st program because of the staff's comments.

Examples of these changes include (1) Administrative controls were added to ensure that all test procedure modifications that alter the acceptance criteria or test intent would be appropriately reviewed.

(2) Additional (five consecutive, cold quick starts) testing of the steam-driven auxiliary feedwater pumps was added to further demonstrate system reliability.

(3) Testing to verify that the reactor cooled pipe penetration cooling system will maintain the pipe tunnel concrete temperature within design limits was added.

(4) The acceptance criteria for certain preoperational and startup tests involving reactor protection system hardware instrumentation delay time, remote plant shutdown validation, diesel generator starting requirements, snubber inspection, battery charger capacity, containment spray flowpath verification, sampling system flowpath and holdup, and power-operated relief valve capacities were modified.

Modified acceptance criteria were required to more accurately reflect the actual test conditions and to provide assurance that system performance will be in conformance with design predictions.

(5) The minimum qualifications for personnel who direct or supervise the conduct of testing were upgraded to conform with acceptable industry standards.

(6) Certain system tests were expanded to ensure that comprehensive system and component testing was scheduled.

Example systems included station service water, component cooling water, vent and drain, spent fuel pool cooling, residual heat removal, chemical and velume control, safety injection, containment ventilation, diesel generator compartment ventila-tion, ac and de power distribution, reactor protection, rod control, steam generator safety and relief valves, main steam and feedwater isolation valves, auxiliary feedwater, pressurizer safety and relief valves, and engineered safety features.

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August.25,-' 1989

Pg. 8 of 13 that the initial test program described in the ap

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F ance criteria of SRP Section 14.2 and that the ' successful completion o program will demonstrate the functional adequacy of plant structures, and components.

The staff also has concluded that the initial test program,

described meets the test requirements of GDC 1 and Section XI of 10 r

Appendix B.

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1 14-4

' Enclosure to TXX-89564 -

August 25 1989 0

- Pg. ;9 of 13 SECTION 14 - INITI AL TEST PROG!.AM POEB 16.

The FSAR has been revised to describe the design (77) configuration of the Containment Atmosphere Monitoring system, as it pertains to testing, to reflect plant as-built conditions.

POEB 17.

The FSAR has deleted reference to the Hydrogen Analyzer systems from the Combustible Gas Control l-system test summary.

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iCPSES TSAR AMENDMENT.

, aEnclesura to TXX-89564:

jl4 August" :25,- 1989 P5 TAILED DESCRIPTION Paga'I i

l,Pg.;10 of 13 TFSAR Page t (as amended)

Group Description W cble 14.2-2!

2-

.See~ Sheet No(s):23

.T Corrects the Testing Methodology'and Acceptance-Criteria for the Containment Atmosphere Monitoring System Test Summary.

Correction:

The'FSAR changes were'made to more appropriately group
related areas of instrumentation' testing under the Containment Atmosphere Monitoring System Testing Program. The changes reflect the actual system design.

'FSAR Change Requ3st Number: 89-489.1 Related SER'Section: 14 SER/SSER Impact: Yes Test Summary which the NRC has not reviewed for CPSES.

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T>.BLE 14'.2-2~

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CONTAINMENT ATM0 SPHERE-HONITORING SYSTEM

-TEST

SUMMARY

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OBJECTIVE To demonstrate-the operability of the' Containment dtmosphere in Monitoring System.

_ u PREREQUISITES.

1.

Setpoints'for alarms and indicating lights have been set.

' TEST' METHOD

.,1 1.

Demonstrate proper operation of the' hydrogen analyzer / monitoring equipment by functional testing from the microprocessor.

keyboard.'

2.

Demonstrate proper operation of the temperature and humidity instrumentation.

3.

Demonstrate proper operation of.the containment pressure-

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" En'closurei to -TXX-89564

August 2.5;-1989

'. TABLE 14.2 1Pgf 12 of-13 '

-:(Sheet 23a )

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. \\c ACCEPTANCE CRITERIA :

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0423.11 JThe Containment Atmosphere Monitoring System functions.in accordance 6-

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  • fM Ebclosure toLTXX-89564 CPSES/FSAR'

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August. 25, 1989

. TABLE 24.2-2, N

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COMBUSTIBLE GAS CONTROL SYSTEMS p'

TEST

SUMMARY

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-0BJECTIVE

).

To demonstrate the proper operation of.the Hydrogen Recombiners.and the Hydrogen. Purge System.

4 PREREQUISITES "1.

The hydrogen recombiners are operable and their associated power panel is energized.

2.

The Hydrogen Purge System idtiddidd fMd Hfdtdddd dddIffdt' ifffdds is operational.

TEST METHOD 1.

Verify the proper-operation of the hydrogen recombiners,

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including the heaters.. controllers and temperature indicators.

1 2.

Verify proper operation of the Hydrogen. Purge System, including-17 6

'the system fanst and filterst ddd Hfd/dddd dddIffd/ ffffddd.

ACCEPTi,1CE CRITERIA-0423.11 The combustible gas control systems operate in accordance with design 6

criteria. The hydrogen recombiners, system fans and filters perform their design function.

Instrumentation, controls, annunciators and i

interlocks function properly in response to normal or simulated signals.

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