ML20080H409
| ML20080H409 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/31/1983 |
| From: | KANSAS GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20080H400 | List: |
| References | |
| PROC-830831-01, NUDOCS 8402140192 | |
| Download: ML20080H409 (46) | |
Text
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SNUPPS-WC CHAPTER 14.0 INITIAL TEST PROGRAM 14.2 INITIAL TEST PROGRAM 14.2.2,,0,R,GANIZATION AND STAFFING 14.2.2.1 General Description Kansas Gas and Electric Company is responsible for the over-all administration and technical direction of the WCGS startup program.
In recognition of this responsibility, the Director of Nuclear, Operations, under the direction of the Vice President
. Nuclear, has established a startup organiza-tion to coordinate and direct the comprehensive planning, development, implementation and performance of the test program.
The Startup Organization is headed by the Startup Manager who reports to the Director of both administratively and, technically.
Muclear-OperationsV4af h frl During the preoperational startup program, the Startup Mana-ger will act to coordinate activities between the Startup Organization, the construction staff, and the operating staff.
Prior to commencing preoperational testing activities, a
Joint Test Group (JTG) as described in Section 14. 2. 3. 2. 2 l will be formed to review and recommend for approval startup administrative procedures, preoperational test procedures, and preoperational test results.
A Plant Safety Review Com-mittee (PSRC) as described in Section 14.2.3.2.3 is organ-ized with the Plant Manager acting as chairman and will review and recommend for approval initial startup test pro-cedures and results.
14.2.2.2 Startup Orcanization The Startup Organization, shown in Figure 14.2-1, is direct-ly responsible for the conduct of the WCGS preoperational test program.
The duties and responsibilities of the start-up organization also include:
1.
Familiarization of support personnel with specific tests.
c, 2.
Direction to support personnel and others during performance of tests including appro-priate interface with station operators.
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Authority to disallow or terminate testing due to conditions which could endanger personnel or equipment.
4.
Identification of deficiencies that could adversely affect test performance.
5." issembly of test data and preparation of test reports for evaluation of test results by others.
O The Startup Organization is composed of system startup engi-neers, technicians, schedulers, craft labor, and other sup-port personnel.
KG&E will provide these personnel and use contractors to supply manpowcr for those positions that it cannot staff.
The staffing level for the Startup Organiza-tion will increase as the test program progresse jsnd%
construction activities decrease.
Schedules for 4shq> test program are given in Section 14,2.11 of the Standard Plant FSAR.
Staffing and training of personnel involved in test-iny at WCGS is planned to provide sufficient manpower to support the testing schedule.
The Startup Organization, shown in Figure 14.2-1, reports administratively and technically to the Startup Manager; the duties performed by key individuals within the Startup Orga-nization are summarized below.
14.2.2.2.1 Startup Manager The Startup Manager fas the authority and responsibility, as delegated by the CizlidMcicarOperatir.e, for the aver-l all direction and administration of the functions and acti-vities required to conduct the Startup Program.
The respon-sibilities and duties of the Startup Manager also include:
1.
Development of plans and schedulas regarding the status of-.the ctartup program.
2.
Review. and approval of administrative and technical test procedures and results.
3.
Continuing analysis of construction and equip-ment installation schedules for compatibility with testing schedules and recommendations for corrective actions to minimize conflict.
I 4.
Review and submital of design related pro-blems requiring engineering resolution, en-countered by the Startup Organization in accordance with the appropriate Startup Ad-ministrative Procedures.
14.2-2
SNUPPS-WC 14.2.2.2.5 Quality control Section The Quality Control Section formulates and implements the Startup Quality control Program.
This program monitors the conduct of the Startup Organization's testing activities by reviewing administrative and technical test procedures, by witnessing major evolutions and selected flushes, hydros, and preoperational tests and by reviewing turnover packages.
J O$
ti St f The WCGS operating staff is involved in the startup program i
'in several capacities throughout preoperational and initial startup testing.
This involvement includes review of test procedures and results and the direct participation in test activities.
Operating staff personnel are utilized by the startup organization as required for performance of testing under the direction of system startup engineers.
Station operators assist system startup engineers in performing tests and in the routine operations of systems.
The oper-ating staff directs the fuel loading and is responsible for plant operation during initial startup testing.
The o gr,ati g s d).vided i sections hegded by the
e y,
_ _ _ ny,.cp Support,#7?eEGIEf6a1 Support, - c a r h Anim.,
_R 1
ory Quality and Admin-istrative Services sueesineendeats.
These section superin-tencents report administrative 1y and technically to the Plant Manager.
The duties and responsibilities of the oper-ating staff during plant operations are described in Chapter 13.0.
The duties of key operating personnel with regard to the startup program are summarized below.
14.2.2.3.1 Plant Manager The Plant Manager has overall responsibility for the station operations and for the conduct of the Startup Program,-dering th: Initial c+ * "p N e + D h -i m He serves as chairman of the PSRC for startup activities as well as operational responsibilities for the PSRC (See the Technical Specifica-tions).
He also approves preoperational test procedure re-sults after JTG review.
14.2.2.3.2 Ocerations Section w ~i. u h /
s The ' Operations superintendent is responsible for the routine l operation of all equipment and for ensuring that the conduct of the startup program does not place the plant in an unsafe T
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He is chairman of the JTG and reviews preopera-tional test procedures.
He also reviews initial startup test procedures as directed by the Plant Manager.
He pro-l vides personnel from the operating staff as required to support the conduct of testing activities.
mornsis. der $ of The Shif t.. Supervisors report to the*0perations sup M h dent and are responsible for the safe operation of the plant during their assigned shift.
They are ;esponsible for the implementation of appropriate safety tagging procedures and have the responsibility to disallow or terminate testing due to conditions which could endangor personnel or equipment.
14.2.2.3.3 Maintenance Section f
ff The rMaintenance eririgendent8 s responsible for perform-l ing preventive an corrective - maintenance on components and systems as assigned.
He provides personnel from the mainte-nance section to support,. testing activitiec as required.
14.2.2.3.4 Plant Support Section
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The (Plant Suppor Superintendent is responsible for provid-ing engineers to r
in the Startup Section as system startup engineers.
At the end of the Startup Program, these engineers will be integrated within the WCGS operating staff.
- 14. 2. 2. 3. 5 "perst og o
Technical Support Section l
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The Technical Support Section was discussed in Section f 14.2.2.2.3.
14.2.2.3.6 Nuclear Training Section The Nuclear Training Manager reports to the Plant Manager.
He is responsible for insuring training staff qualifica-tions including reviewing instructor evaluation records with the Training and Simulator Supervisors.
He reviews the contents of training programs for technical completeness and compliance with Regulatory Standards.
He is also respon-sible for auditing the quality of onsite training programs.
Additional information is provided in Section E.1.1. c..r: 1.
t3J).3.6 14.2.2.3.7 Regulatory Quality and Administrative Services Section T[e latory Quality and Administrative Servi (Suy_erinD endent eports to the Plant Manager.
He is charged with tne responsibility for providing direction and guidance to the Document Control Supervisor, Administrative Supervisor, Safety Supervisor and Site Emergency Plan Administrator and to provide liaison for the Plant Manager and staff with other organizations.
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SNUPPS-NC l
14.2.2.4 Major Participating Organizations 14.2.2.4.1 Bechtel Bechtel, as power block architect-engineer for, 'iCGS, is re-sponsible for the design and engineering of power block sys-tems, review and approval of design changes and engineering input into the startup program.
In addition, KG&E has also contracted Bechtel to provide personael experienced in nuclear plant startup to augment the startup organization for WCGS.
Bechtel employees are assigned consistant with the startup program schedules.
14.2.2.4.2 Daniel International Corporation (DIC)
DIC, as contractor for WCGS, is responsible for rne con-struction completion, and orderly release of components and Rev. 11 14.2-5a
SNUPPS-WC turnover of systems.to KG&E consistent with the startup program schedules.
This responsibility includes:
1.
Certification thac documentation for compo-nents, systems and structures, as required by purchase and installation specifications, is complete and available; and the maintenance of these certification files which provide the documentary evidence, and 2.
Provision of dedicated craft manpower support
. 'a s required for. performance of the startup program.
14.2.2.4.3 Westinghouse Electric Corporation Westinghouse, as the Nuclear Steam Supply System (NSSS) supplier, is responsible - for providing technical assistance to KG&E_ during preoperational and ' initial startup testing performed on the NSSS equipment and systems.
Technical assistance is ' defined as. technical guidance, advice and counsel based on current engineering, installation, and testing practices.
Westinghouse employees are assigned consistent with the Startup Program schedules.
This respon-sibility includes:
1.
. Assignment'of personnel to provide advice and assistance to KG&E for test and operation of all equipment and systems in the Westinghouse area of responsibility.
2.
Supportive-engineering
- services, including special assistance during the initial fuel loading.
3.
' Providing test procedure outlines and techni-cal assistance for tests' of Westinghouse furnished components and systems.
14.2.2.4.4 General Electric (GE)
GE is the supplier and installer of the turbine generator.
GE supplies technical support for the startup and testing of the turbine generator.
-Some of the prerequisite testing (i.e.,
turbine oil flush) will be performed by the GE per-sonnel.
GE has supplied recommended procedures for starting, ope rating,- and shutting down equipment in their technical manuals for the turbine generator.
14.2.2.5 Quality Assurance Br"Och The KG&E -Quality Assurance M n c m is responsible for I assuring the quality of - construction, plant testing, and op3 rations activities in accordance with the UCGS Quality Program which is described in Chapter 17.0.
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,14.2.2.n Qualifications of Key Personnel The qualifications for key plant operating personnel are described in Chapter 13.0.
The qualification requirements for starthp personnel involved in the WCGS startup program conform to capaoility levels per A:ISI N45.2.6 and Regulatory Guide 1.8 recommen-dations.
All test personnel will be indoctrinated in the startup administrative procedures, methods and controls.
14.2.3 TEST PROCEDUREd 14.2.3.2 Procedure Review and Accroval 14.2.3.2.1 Prior to submittal' to the JTG for review and approval recommendation, each preoperational test procedure receives the review specified in Section 14.2.3.2 of the Standard Plant FSAR.
The preoperational test procedures are then designated SU3 (Safety-Related) or SU4 (:lon Sa f ety-Related) as appropriate in lieu of the Standard ?lant FSAR (S03, SO4) designators.
14.2,3.2.2 Joint Test Group (JTG)
A subcommittee of the PSRC, the JTG will be organized 'cy KGLE to revied preoparational test procedures and preccara-tional test rasul ts.
The primary JTG functions will be to:
1.
Review preoperational test procedures and re-commend their approval by the Startup :.lanager.
2.
Evaluate and authorize changes to preopar-ational test procedures as detailed in the Startup Administrative L!anual.
3.
Evaluate preoperational test procedure re-sults and. recommend their approval to the Startup '!anager and Plant i:an age r.
4.
Recom:nend system transfer f ro'n etar ap to Operations to the Startup ?!anager rid the Plant :ta nage r, for their Tpproval.
l 3.
TMviea sa f e ty-re l a ted aspect 2 of tha startup administrative procedures.
- le aba rchip in tha JTG Nill include tad folloatng personnal or their designatad representativos:
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. Superintendent of Operation - Chairman 2.
Superintendent of Plant Support 3.
Superintendent-of Regulatory, Quality and Administrative-Services
'4.-
Startup Technical Support Supervisor, 5.
Assistant Startup Manager 6.
Operations
. Quality Assurance (non-voting member) 7.
Bechtel Power Corporation-Engineering (non-
-voting member)
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-8.
Westinghouse-Engineering (non-voting member)
Others may be requested to provide ~ technical support to the JTG.
This support will be. based on the procedure being reviewed, required technical expertise or other applicable
. factors..
Participation in the JTG meeting will be with the concurrence of..
only.
_ the JTG and is. limited to technical input 14.2.3.2.3 Plant Safety Review Committee (PSRC)
I The PSRC is organized ~ by KGGE to ensure 'ef fective coordina-
-tion of the engineering, construction, and operations activ-ities affecting the startup program.
^
The appropriate PSRC members ensure sufficient review of initial startup test procedures and results.
~The primary PSRC startup functions are:
1.
Review all initial startup test proceduras and make recommendations to the'?lan: '4an a ge r.
l 2.
Evaluation and authorization of changes to initial startup. test procedures.
- 3..
Evaluation of initial startup best procedure results.
' Membership L in tha PSRC is given in the Technical 3pecifica-uions,.dection o.,.1.2.
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- 1. 4. 2. 4 CONDUCT OF TZST PROGRAM 14.2.4.1 Administrative Procedures The conduct of the preoperational s:artup program is con-trolled by administrative procedures.
The preparation, maintenance,, and implementation of these proceduras is the responsibility of'the Startup 'lanager.
The startup adminis-trative procedures prescribe controls for startup activities auch ac:
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SNUPPS-WC All components released in this manner shall be inco rpo ra tad into the scope of a subsequent system or subsystem turnover.
14.2.4.3 Comoonent and Prerecuisite Testing Upon Startup acceptance of a turned-over system, subsystem, or released component, preraquisite-type tasting is perform-ed to demonstrate proper operability and functional ability in support of, and prior to, the performance of pr? opera-tional testing.
Local containment leak rate testing, as described in SNUPPS FSAR Section 14.2.12.1.78, is performed l
at WCGS as part of the prerequisite test program.
Administrative procedures are established to ensure that all prerequisites are met before testing is initiated.
Upon completion of all prerequisite tests applicable to a systam or subsystem, a documented review is conducted by Startup personnel to verify that appropriate documentation is avail-able and that required prerequisite tests have been satis-factorily completed.
All. deficiencies which would prevent performance of preoperational tests or generate negative test results ara identified and dispositioned prior to implementation of the preoperational tests.
14.2.4.4 Preoperational Testina Technical direction and administration, including test exe cut:.on, ano data recording, of the precoerational testing is the responsibility of the startup organ'ization.
The avs-tem startup engin2ers ar3 responsible for tha nerformanca of
^
tests and providing apprcpriate interface with' station 0:er-ators.
The Startup '!anager is responsible for the adminis-trat:.on and surveillance of all testing activities durina the preoperational tast program.
The UCGS coerating staff assumes control and responsioility for each' system after preoperational testing is completed on the system and a tormal transfer is executed.
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SNUPPS-NC 14.2.4.5 Initial Startuo Testina During the initial startup testing phase, the Plant Manager l
has overall authorit"1 and responsibility for the startup program.
Th+ Startup Organization providas support to the plant operating staff 'ehich has responsibility for perfora-ing equipment operations and maintenance in accordanca " tith the provisions of the plant operating license.
The UCGS operating staff is also M responsible for ensuring that the conduct of testing does not place the plact in an unssfa condition at any time.
The shift supervisors have the authority to terminate or disallow testing at any time.
14.2.4.6 Test Prereauisites Each test procedure contains a set of preraquisites and ini-tial conditions as prescribed by the startup administrative procedures.
The system startup engineer ensures that all specified prerequisites are met prior to performing tne test.
The foraat for test procedures is described in Sec-tion 14.2. 3.1 of the S tandard ?lant I'S A R.
14.2.4.7 Test Evaluation Upon completion of system preoperational :esting, the c3st results are submitted to the JTO for its revie.i and subsa-quent recommendation for approval ca the Startup 'unager Tad Plant 'lanager.
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39 tween each major. chase of the initial startup test prtgram
+
r the test results for all tests that hav2 been performed n11 be reviewec by the PSRC.
This review ensures that Tll
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required systems have been tested satisfactorily v.i that test results are approved before proceeding to the a c::t stage of testing.
These reviews are described in Section 14.2.5.
14.2.4.3 7esion Modifications
!!odi fic ations to the design of the equ:.pment during th-3 c3st prcgram aay be initiated in ordar to 3rrect deficiencias s
discovered as a rasult of testiag.
Any auch aod :. f ica t io ns
,till eithar ce developed by :he cr.Jinal 13 sign organi.:ati an or other Iasignatai organt:2tions.
edifications aade a
ccmpon0nts or systems aft 3r COapl9 i0n Of,Jrr3 operational cr initial st3rtlp t-2 s t i n g Will Oe. 2 vie. led la r r3t3stin; ;3-juirement3 on aIf3ctei portions 05 Ch2 S79023.
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SNUPPS-WC 14.2.5
- REVIEW, EVALUATION, AND APPROVAL OF TEST RESULTS The responsibility for review, evaluation, and recommenda-tion for approval of test results from all preoperational tests rests with the JTG.
In the case of all initial start-up tests, it rests with the..PSRC.
Following completion of a preoperational test, the respon-sible system startup engineer will assemble the test data package for submittal to the members of the JTG for evalua-tion.
Each test data package will be reviewed to ensura that the test has been performed in accordance with the approved procedure and that all required data, checks, and signatures have been properly recorded and that system performance meets the approved acceptance criteria.
Members of the JTG will review the evaluation findings and recommend corrective action to be taken to resolve any cut-standing deficiencier.
If the deficiencies are not resolved to the satisfaction of the JTG, then appropriate ratesting may be required.
If the evaluation indicates that deficien-cies in the test method are responsible for unsatisfactory test results, the test procedure will be revised accordingly before retesting is initiated.
The review and approval pro-cess for procedure revisions is carried out in the aanner described in Section 14.2.3.
Whenever an evaluation of tast results indicates deficiencies in system performance, the JTG will refer the problem to the responsible engineering organization for evaluation.
If the test documentation and systam cerformance ar2 acceptable, the JTG will reccamand approval of the test by Startup Manager and the Plant Manager.
l Following each major phase of the initial startup bast pro-gram, the PSRC will verify that all required tests have been performed and-that the test results have been approved.
This verification will ansure that all required syste.as 2ra operating properly and that testing for the next aajar phase will be conducted in a safe snd efficient manner.
~'h i s tvne of review will be performed to the extent required befEre major initial startup test phases.3uch as fuel load, initial criticality, and power ascension.
Nring the power ascan-sion phase,- review and -apprcval of initial startup test procedure results will be completed for each of thesa pla-25 percent, 30 percent, lad
~3 percent, prior :o taaus proceeding to the next plateau.
14.2.6 TEST RECORDS Test procedures and tast data calating to preoperational and initial startup testi ng will be racained la accordance Jith the measuras described in Section 17.2.17.
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SNUPPS-WC 14.2.8 UTILIZATION OF REACTOR OPERATING AND TESTING EXPERIENCE IN DEVELOPMENT OF TEST PROGRAMS The operating ~ experience assessment for Wolf Creek Gen-erating Station Unit No. 1 (WCGS) will be conducted by the nuclear divisions and plant. staff who possess the appropri-ate experience in the area of concern.
The sources of operating experience information includes the use of the Erwoe 6 system and the INPO/NSAC SEEIN system. -An adminis-I trative system which.will control the flow of. information s paw N,
INPO/NSAC SEEIN, etc., to the cognizant orga-1 nizations including the Independent Safety Engineering Group (ISEG) will be developed and functioning prior to fuel load.
The Licensing Section is responsible for coordinating the review by the Applicant's of the NRC Information and En-forcement (IE) Bulletins, Circulars, and Information Notices.
The.Startup Group reviews information provided by the other KG&E Nuclear Divisions and information provided by Bechtel and Westinghouse to determine its effect on the Wolf Creek Initial Test Program, making revisions to test and adminis-trative procedures as required.
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SNUPPS-WC 14.2.12.1.2 Essential Service Water Pump Preoperational Test (SU3-EF02)
This test was combined with Test SU3-EF01, Essential Service Water System Prooperational Test, which is described in Section iU 2.12.1.32 of the Wolf Creek Addendum.
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SNUPPS-WC 14.2.12.1.4 Power _ - Conversion. and ECCS. Thermal Expansion Test'(SU3-0004).
l 14.2.12.1.4.'1 Objective To. demonstrate snubber ~ operability on all safety-related systems'whose operating temperature exceeds 250 F.
14.2.12.1.'4.2 -Prerequisites a ~.
Preservice examinations as specified in the Tedesco -letter.to KG&E dated 3/10/81 have been completed on the ~ systems being checked within the last 6 months.
-b.
Other required conponent testing and instrument calibration are completed.
c.
Required electrical power supplies and control circuits are operational.
d.
Preoperational tasting is in progress.
14.2.12.1.4.-3 Test' Method a.
During initial system heatup and cooldown, at specified temperature intervals, verify the ex-pected thermal movement. for any system which attains operating temperature.
b.
For ' those systems which do not attain operating temperature, verify-by observation and/or calcula-tion - that the snubber will accommodate the pro-jected thermal movement.
-Verify snubber-swing. clearances at specified heat-c.
up and cooldown intervals.
14.2.12.1.4.4 Acceptance Criteria a.
The -expected ' thermal movement for any system that attains operating -temperature is eithin design specifications.
.b.
The~~expacted thermal movement determined by obser-vation and/or calculation for any system that does not. attain operating temperature' is within design specifications.
c..
Snubber. saing clearance at ' spacified heatup and cooldown intervals is within design specifications.
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114.~2.12.1.5 Auxiliary Feedwater Pump Turbine Preoperational.
Test (SU3-FC01) l'4. 2.12.~ 1. 5 '.1 ' objectives
~
a..
To-demonstrate the operation of-the auxiliary feedwater pump ~(AFWP) turbine and its support equipment, while uncoupled from the pump.
b.
To demonstrate control of the 'AFWP turbine from the. control room as-well as the auxiliary shundown
. panel.
14.2.12.1.5.2 Prerequisites-
- a.
Required _ component
- testing, instrument calibra-
. tion and system flushing / cleaning are complete.
b.
Steam is available-to the AFWP turbine.
14.2.12.1.5.3 Test'itethod-a.
AFWP turbine ' system valves are operated and. re-quired response ' to. various. signals is verified.
.b.
The turbine is. operated and proper control is ver-ified from-.the' cont'rol room as-well as the auxili-ary shutdown panel,. and operating data are raccrded.
The-turbine is brought to high speed at uhich time c.
the mechanical and electronic cverspeed trips ra
. verified.
14. 2 ~.' 12 '.1. 5. 4 Acceptance Critaria a.
The AFWP turbine can be controlled fr0m the can-trol room panel and ~ the au::iliary shutdoun panel, b.
'The -mechanical-. and electronic overspeed trips actuate to shut down the turbine in accordance Jith the' design.
s Rev. il 14.2-13'o
SfiUPPS-WC 14.2.12.1.8 Auxiliary-Feedwater Turbine-Driven Pump and Valve Preoperational Test (SU3-ALO2) 14.2.12.1.8.1 Objectives 4..To verify the. auxiliary feedwater pump turbine mechnical trip.and throttle valve automatic operation -on an auxiliary feedwater actuation signal ( AFAS ).I, To perform the initial
~
f coupled operation of the turbine-driven auxiliary feedwater
' pump.
Full flow ~ characteristics of the turbine-dgivenpump will.be demonstrated during hot functional testing. C. To per-
' form five consecutive, successful, cold starts of the tur-bine-driven auxiliary feedwater pumps.
14.2.12.1.8.2 Prerequisites a.-
_ Required component
- testing, instrument calibra-tion, and system flushing / cleaning are complete.
b.
Required electrical power supplies and control circuits are operational.
c.
The steam generators are available to receive water from the auxiliary feedwater pumps.
d.
The steam generator blowdown system is available to maintain the normal operating levels in the steam generators during cuxiliary feedwater pump operation.
e.-
The auxiliary steam system is available to supply steam to the auxiliary f eedwa ter pump turnine, f.-
For the performance characteristic test of this pump,-hot functional testing (HFT) is in progress.
14.2.12;1.8.3 Test Method a.-
An AFAS is simulated, and opening of the mechan-ical trip and throttle valve is verified.
b.
The-turbine-driven auxiliary feedwater pump is operated during HFT, and performance charactaris-tics are recorded.
c.
The ability of the turbine-driven auxiliary feed-water pumps to start successfully five consecutive times from cold conditions is verified.
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--14.2.'12.1.8.4 Acceptance Criteria a.
The auxiliary feedwater pump mechnical - trip and
. throttle valve opens automatically on an AFAS.
.s b.
operating-characteristics _of the _ turbine-driven auxiliary feedwater pump are in accordance with design.
C, We farbine. driven aup'/'<ry. Seedu'aie,*"9 b
'succesfu/ty S caracan yo G,, no, a colo(.ryg,t ReV. 11
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SE4UPPS-WC 14.2.12.1.26 Charging System Preoperational Test (SU3-BG03) 14.2.12.1.26.1 Objective [
To demonstrate positive displacement charging pump operating characteristics and to verify the operation of the regenera-
-tive heat exchanger inlet isolation valves and the letdown isolation valves, _ including their response to a safety in-
-jection signal (SIS).
14.2.12.1.26.2 Prerequisites a.
Required component
- testing, instrument calibra-tion, and system flushing / cleaning are ccmplete.
b.-
Required electrical power supplies and control circuits are' operational.
c.-
The volume control tank contains an adequate supply of demineralized water for the perforpance of this test.
d.
The component cooling water system is available to provide cooling water to the positive displacement charging pump.
e.
The reactor coolant system is available to receive charging system flow.
14.2.12.1.26.3-Test Method
- a..
The positive displacement charging pump is oper-ated, and pump operating data are recorded.
b.
Regenerative heat exchanger inlet isolation valve and letdown system isolation valve control cir-cuits are verified, including valve response to safety injection signals.
14.2.12.1.26.4 Acceptance Criteria' Positive displacement charging pump operating char-a.
acteristics are within~ design specifications.
b.-
Charging pump to regenerative heat exchanger inlet isolation valves close on receipt of an SIS.
Valve closure times are within design specifica-tions.
c.
The letdown line containment isolation valves close. on receipt of. a containment isolation signal.
Valve closure times are within design specifications.
Rev. 11 14.2-13e 1
\\
(.
r SNUPPS-WC 14.2.12.1.27 Boron Thermal Regeneration System Praopera-tional Test (SU3-BG04) 14.2.12.1.27.1 Objectives To' verify the operation of the boron thermal regeneration system, and associated cong'ol circuitsgn:ludi: r-",1"
-rc "cphe a 293 c i-y '
Performance characteristics of the chemical and volume control system chiller pumps are also verified.
14.2.12.1.27.2 Prerequisites a.
Required component testing, instrument calibration and system flushing / cleaning are complete.
.b.
Required electrical power supplies and control circuits are operational.
c.
The volume control tank contains an adequate supply of demineralized water for the performance of this test.
d.
The chemical and volume control system chiller surge tank contains an adequate supply of demin-eralized water for the performance of this test.
14.2.12.1.27.3 Test tiethod a.
The chemical-and volume control system chiller pumps are operated and performance characteristics are verified.
b.
Boron thermal regeneration system component con-trol circuits are verified.
14.2.12.1.27.4 Acceptan'ce Criteria a.
The chemical and volume control system chiller pumps' operating characteristics are within design specifications.
b.
The chemical and volume. control system chiller pumps start automatically when the boron thermal regenercition system is placed in the borate or dilute mode of operation.
Rev. 11 14.2-13f
- t.,
SNUPPS-WC 14.'2.12.1.32 Essential Service Water System Preoperational Test (SU3-EF01) 14.2.12.1.32.1 -Objectives a.
- To. demonstrate the capability of the essential service water system to provide cooling water flow during the LOCA ' mode of operation.
The operation and response of system valves to align the system in the LOCA flow mode on safety injection signals, load sequence signals, and low suction pressure signals are also verified.
b.
To demonstrate the operating characteristics of the essential service water (ESW) pumps and verify their response to safety signals.
c.
To demonstrate ' the operability of the; backpres-sure ' control valves, including their response to safety signals.
'14.2.12.1.32.2 Prerequisites a.
Required' component testing, instrument calibration, and system flushing / cleaning are complere.
b.
Recuired electrical cower supplies and control
[/s/
circuits are operation'al.
c.N The 1te es enrial ser;iice ate cumo are m
- il-
- b:
Dab to - 0 oly f1 w to thp essentia ervice y'a
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s K
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Cd.
The compressed. air system is available to the sys-tem air-operated valves.
14.2.12.1.32.3 Test Method a.
System operating characteristics are verified in the'LOCA mode'of operation, b.
- Safety signals are simulated, and the responses of the system valves and the ESW pumps are verified.
The ESU pumus are operated and pump operating data c.
-are recorded.
d.
The operability of the backpressure control-valves, including their response to safety signals is verified.
Rev. 11 14.2-131
SNUPPS-WC
-14.2.12.1.32.4 Acceptance criteria a.
Components supplied by the essential service water system receive flows that are within design speci-fications in the LOCA mode of system operation.
b.
System valve operation in response to safety sig-nals is within design requirements.
c.
System valve operating times are within design specifications, d.
The ESW pumps' operating characteristics are with-in design specifications.
e.
Each ESW pump responds properly to load sequence and load shed signals.
f.
The time required for each ESW pump to reach rated flow is within design specifications.
g.
System backpressure valves close upon receipt of a LOCA sequencer or safety injection signal.
h.
An auxiliary feedwater pump low suction pressure signal will close the ESW pump breakers if a zero sequencer signal is not present.
i Rev. 11 14.2-13h j
10siAT 1.
h p;, t.wr gts s SNUPP S-w c.
r Mf' t.
b 14.2.12.1.39 Boron Injection Tank and Recirculation Pump
(
Test (S-09fM04)
'j j
Uu 2 - e s o9)
/
14.2.12.1.39.1 Objective [
To demonstrate the operating characteristics of the boron in-jection recirculation pumps and verify that the associated instrumentation and controls are functioning properly.
The pump and valve responses to safety signals are also verified.
14.2.12.1.39.2 Prerequisites a.
Required component testing, instrument calibration, and systen flushing / cleaning are complete.
b.
Required electrical power supplies and control circuits are operational.
d Thejchemical, volume and, con ~ol system
"/CS) is ail e to' sue-
- flow
..rou die-oron }'uer
.lon ank to.t.
on rec-e ystem.
i
s.,
N,,-
Nf
, Th tor mak
' water sys
.a'is ava' ale to,e
==1 ysem di ic ' flow tri..
'the S tbsb~o".. rec, 'e t
ow ver "
tion.
/
p..
14.2.12.1.39.3 Test-Method
.(.
a.
The boron injection recirculatica pumps are operated in the recirculation mode, and their operating character:.stics are verified.
Th charginy ;ftTmps are oc.ated thrMh t.
bo n
- '>y]ection tan mos.the boror.ecycle Dur..g.this d
,otem.
/ evolution,'
lution flo" rom th
.eactor mak o water
_ Q verified
/-
b.
The boron recirculation system control circuits are verified, including the operation of system pumps and valves on receipt of safety signals.
14.2.12.1.39.4 Acceptance Criteria a.
The boron injection recirculation pump perfornance characteristics are within design specificaticns.
b.
Boron recirculation pump and valve responses to load shed and safety injection signals, respectively, and response times are in accordance with design specifications, w
CL
. Rev. ' ? -
?
h3 9dl
J.
SMUPPS-WC 14.2.12.1.43 Miscellaneous Building HVAC System Preopera-tional Tests (SU3-GF01, SU3-GF02, SU3-GF03) 14.2.12.1.43.1 Objectives To. demonstrate the capacity of 1) the auxiliary feedwater pump room cooler fans, 2) the main steam enclosure building supply and exhaust fans and 3) the tendon gallery transfer fans and to verify that the associated instrumentation and controls are functioning properly.
The responses of the main steam enclosure building dampers and tendon access gallery dampers to safety signals are also verified.
(At Wolf Creek Generating Station, this test will be per-formed in three independent parts.
In addition, the auxili-ary boiler room fan will be treated as part of preoperation-al test SU4-GF01.)
14.2.12.1.43.2 Prerequisites Required component testing and instrument calibra-a.
tion are complete.
b.
Required electrical power supplies and' control cir-cuits are operational.
The miscellaneous building HVAC system is air bal-c.
anced.
14.2.12.1.43.3 Test Method Flow data are recorded while the fans are operat-a.
ing.
b.
The response of system dampers to a safety injec-tion signal (SIS) is verified.
14.2.12.1.43.4 Acceptance Criteria System fan capacities are within design specifica-a.
tions.
b.
The. main steam enclosure building and tendon access gallery dampers close on receipt of a SIS.
Rev. 11 14.2-13i
S14UPPS-WC 14.2.12.1.54 Spent Fuel Pool Crane Preoperational Test (3U3-KE01) 14.2.12.1.54.1 Objectives a.
To. demonstrate proper operation of hhe spent fuel pool bridge crane control circuits and associated interlocks.
b.
To document the data obtained during testing of the spent fuel pool bridge crane at 125 percent of rated load.
c.
To verify the ability of IEs spent fuel pool bridge crane and associated fuel handling tools to transfer a dummy fuel-assembly.
14.2.12.1.54.2 Prerequisites a.
Required component testing and instrument calibra-tion are' completed.
b.
Required electrical power supplies and control circuits are operational.
c.
A dummy fuel assembly is available.
14.2.12.1.54.3 Test Method
~
a.
-Operability of the spent fuel pool bridge crane control circuits and associated interlocks is verified.
.b.
Ability of the spent fuel pool bridge crane and
' associated. fuel handling tools to transfer a dummy fuel assembly is verified.
~14.2.12.1.54.4 Acceptance Criteria The spent-fuel pool bridge crane electric and man-a.
ual hoists support 125 percent of their rated load.
b.
The spent fuel pool bridge crane monorail center span ' daflection at cated load is within design specificacions, c.
Tha spent fuel. pool crane bridge, trolley and hoist speeds at rated loads are within design specifications, d.
All control circ' its and interlocks associated u
with the spent fuel pool bridge crane operate in accordance.with system design.
Rev. 11 14.2-13j
.~.
g SNUPPS-WC
(
t 14.2.12.1.55 New Fuel Elevator Preoperational Test (SU3-KE02) 14.2.12.1.55.1 objectives-a.
To demonstrate proper operation of the new fuel elevator control circuits and associated inter-locks.
b.
, To verify the ability of the new fuel elevator to raise and lower a dummy fuel assembly.
14.2.12.1.55.2 Prerequisites a.
Required component testing and instrument calibra-tion are complete.
b.
Required electrical power supplies and centrol circuits are operational.
c.
A dummy fuel assembly is available.
14.2.12.1.55.3 Test Method operability of the new fuel elevator including control cir-cuits and associated interlocks is verified.
14.2.12.1.55.4 Acceptance Criteria sa.
All control circuits and interlocks associated with the new tuel elevator operate in accordance, with system design.
b.-
While raising and lowering a dummy fuel assembly, the new fuel elevator operates in accordance with s stem design.
w c.
The spent. fuel cask handling crane hoist supports
-N 125 percent of rated load.
\\
\\
d.
The spent fuel cask handling crane bridge center g
span deflection at rated load is within design specifications.
/
\\
{
'e.
The spent fuel cask handling crane bridge, trol-ley and hoist speeds at rated loads are with-
-in design specifications.
l
/
kelo arTyp Rev. 11 14.2-131
SNUPPS-WC e.
While transferring a dummy fuel
- assembly, the spent fuel pool bridge crane and associated fuel handling tools operate in accordance with system design.
P e
Rev. 11 11.2-13k
r b
SNUPPS-WC an d Sl*!*] U Y
.4.2.12.1.56 Cp; u.. Fuel--C;;h Handling Crar~ Preoperational Test (SU3-KE03) 14.2.12.1.56.1" Objectives a.
To verify the ability of the spaht fuel cask handling crane, and associated fuel handling tools to transfer a dummy fuel assembly.
b.
To demonstrate proper operation of the spant fuel cask handling crane control circuits and associ-ated interlocks.
c.
To document the data obtained during testing of the spent fuel cask handling crane at 125 percent of rated load.
114.2.12.1.56.2 Prerequisites a.
Required component testing and instrument calibra-tion-are complete.
_b.
Required electrical power supplies and control circuits are operational.
c.
A dummy fuel. assembly is available.
14.2.12.1.56.3 Test Method a.
'During the transfer of a dummy fuel assembly, the operability of the spant fuel cask handling crane and associated fuel. handling tools is verified.
Eb.
. Operability of the spent fuel cask handling crane control circuits and associated interlocks is verified.
14.2.12.1.56.4 Acceptance' Criteria a.
While transferring a dummy fuel
- assembly, the spent fuel cask handling crane and associated fuel' handling tools operate in accordance with system design.
b.
-All control circuits and interlocks associated with the spent fuel cask handling crane operate in accordance.with system design.
//.
[N55(
from prevo'oas
?ff t-Rev. 11 14.2-13m
=
r L
SNUPPS-WC 0
ptem Infeymted FuelHandling(andCtcrage.PreoperationalTest l
14.2.12.1.56a
-(SU3-KE07) 14.2.12.1.56a.1 Objective
(-
To verify the ability of the' refueling machine, new fuel
- elevator, fuel transfer system, spent fuel bridge crane, spent fuel cask handling crane and associated fuel handling tools to transfer'a dummy fuel assembly.
14.2.12.1.56a.2 Prerequisites a..
Required component testing and instrument calibra-tion are complete.
b.
Required electrical power supplies and control circuits arc operational.
c.
The reactor
- vessel, refueling
- pool, rafueling canal and spent fuel pool are filled with demin-eralized water.
A du[y fuel assembly is available.
d.
14.2.12.1.56a.3 Test Method
' During the transfer of a dummy fuel assembly, the operabil-ity of the refueling machine, new fuel elevator, fuel trans-fer. system, ' spent fuel bridge crane, spent fuel cask han-dling crane and associated fual handling tools is verified.
- 14.2.12.1.56a.4 Acceptance Criteria Uhile. traneferring a dummy fuel assembly, the refueling machine, new fuel elevator, fuel transfer system, spent fuel bridge crane, spent fu21 cask handling ~ crane and associated fuel handling. tools operate in accordance with system design, s
4' Rev. 11 14.2-13n
f e
g
(
SNUPPS-WC 4
~
\\
114.2) 2.1.57'. Fuel Transfer System Preoperational Test (SU3-KE04)
'14.2.-12.1.57.1 Objectives
~
a.
' To demonstrate proper operation of the fuel trans-fer. system control circuits and associated inter-1.ocks.
b.-
To verify the ability of the fuel transfer system
- knd associated handling tools to transfer a dummy fuel, assembly.
14.2.12.1.57.2 Prerequisites
-a.
Required component testing and instrument calibra-tion are complete.
b.
Required electrical power supplies and control' s;
circuits are operational.
'c.
' A dummy-fuel assembly is available.
14.2.12.1.57.3 Test Method i
a.
Operability of the fuel transfer system control s'
circuits and associated interlocks is verified.
1~
b.['During the transfer of 'a dummy - fuel assembly, the operability of the fuel transfer system and asso-ciated handling tools is verified.
~
14.2.12.1.57.4 Acceptance Criteria a.
All control circuits and interlocks associated with the fuel transfer system operate in accord-ance-with system design.
~
\\
t b. --
While transferring a dummy fuel assembly, the fuel transfer system and associated handling tools operate in accor, dance with system design.
s b
Rev. 11 14.2-13o
-'e-i
SNUPPS-WC g
=14.2.12.1.58. Refueling Machine and RCC Change Fixture Pre-operational Test (SU3-KE05) 14.2.12.1.58.1 Objectives a.
To demonstrate proper operation of 'the refueling machine, rod cluster control change fixture and containment building polar crane control circuits and associated interlocks.
b.
To document the data obtained during testing of the containment building polar crane at 125 per-cent of rated load.
c.
To verify the ability of the refueling machine to transfer a dummy fuel assembly.
14.2.12.1.58.2 Prerequisites a.
Required component testing and instrument calibra-tion are complete.
b.
Required electrical power supplies and control circuits are operational, c.
A dummy fuel assembly is available.
d..
A dummy control rod assembly is available.
14.2.12.1.58.3 Test-Method a.
Operability of the refueling machine and rod clus-ter control change fixture control circuits and associated
- bridge, trolley, hoist and gripper interlocks is verified.
b.
Operability - of the containment building polar crane control circuits and associated interlocks is verified.
14.2.12.1.58.4 Acceptance Criteria a.
All control circuits and interlocks associated with'the refueling machine and rod cluster control change fixture operate in accordance with system design..
b.
The control circuits and interlocks associated with the containment building polar crane operate in~accordance with system design.
Rev. 11 14.2-13p
___.m.____._____.____m_
)
ju F
SNUPPS-WC p
- c.
The containment polar crane main and auxiliary hoists support 125 percent of their rated load.
s i -- ' I' d.
The containment polar crane bridge conter span deflection at rated load is within design specifi-cations.
~
e.
The ~ containment polar crane bridge, trolley, and hoist speeds at rated loads are within design specifications..
f.
While transferring a dummy fuel assembly, the re-fueling machine operates in accordance with system design.
44 Rev. 11 14.2-13q.
___._.______m__
SNUPPS-WC 14.2.12.1.77 Integrated Containment Leak Rate Test (SU3-GP01) 14.2.12.1.77.1 Objective To demonstrate that the total leakage from th_e containment does not exceed the maximum allowable leakage rate at the calculated peak containment internal pressure.
The opera-bility of the containment cooling fans at design accident pressure is also verified.
14.2.12.1.77.2 Prerequisites a.
T;.e containment penetration leakage rate tests (type B tests) and containment isolation valve leakage tests (type C tests) are complete and the containment has been pressurized to 115 percent of the design pressure.
b.
All containment isolation valves are closed by normal actuation. methods, c.
Containment penetrations, including equipment hatches and personnel airlocks, are closed.
d.
Portions of fluid systems that are part of the containment boundary,SE-outside that may be opened directly to the containment atmosphere under post-accident conditions, are opened or vented to the appropriate atmosphere to place the contain-ment in as close to post-accident conditions as possible.
e.
Required instrument calibration is complete.
14.2.12.1.77.3 Test Method a.
The integrated containment leak rate test (type A test) is conducted, using the absolute method, de-scribed in the ANSI /ANS 56.8-1981 Containment System Leakage Testing Requirements.
Measurements of containment atmosphere dry-bulb temperature, dew point and pressure are taken to calculate the leakage rate.
A standard statistical analysis of data is conducted, using a linear least squares fit regression analysis to calculate the leakage rate.
Rev. 1 ?_
14.2-13r
l SNUPPS-WC 14.2.12.1.78 Local Containment Leak Rate Test (SU8-GP01!
This test is described in St10PPS FSAR Section 14.2.12.1.78.
It has been assigned a different test number for WCGS.
h Rev. 11 14.2-13t
t SNUPPS-WC o
14.2.12.1.79 Reactor Containment Structural Integrity Acceptance Test (SU3-GP02)
This test is described in SMUPPS FSAR Section 14.2.12.1.79.
It has been assigned a different test number for WCGS.
Rev. 11 14.2-13u tl l
l
5 SNUPPS-WC 14.2.12.1.87 Auxiliary Feedwater Motor-Driven Pump Endurance Test (SU3-ALO3) 14.2.12.1.87.1 Objectives a.
To demonstrate that the motor-driven auxiliary feedwater pumps can operate for 48 continuous hours without exceeding any of their limiting design specifications.
b.
To demonstrate that the motor-driven auxiliary feedwater pumps can nperate for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after a cool down from the 48-hour test.
c.
To demonstrate that the room environmental condi-tions are not exceeded during-the 48-hour test.
14.2.12.1.87.2 Prerequisites a.
Required component. testing, instrument calibra-tion and system flushing / cleaning are complete.
b.
Required electrical power supplies and control circuits are operational.
c.
The appropriate auxiliary feedwater pump room coolers are operational.
d.
The condensate storage tank is available as a water source and to receive recirculation flow.
14.2.12.1.87.3 Test Method Each motor-driven pump will be started and operated for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching rated speed and r.ted discharge pres-sure and flow, or a greater pressure and less flow.
During the endurance run, pump-operating data and the pump room environmental conditions will be recorded.
At the completion of each endurance test, the pump will be cooled for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and until pump data returns to within 20*P of the original pretest data.
The pump will then be started and operated for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
.14.2.12.1.87.4 Acceptance Criteria a.
The operating parameters (vibration, bearing temp-eratures,- etc.)
of each motor-driven auxiliary feedwater pump do not -exceed the design specifica-tions.
).
T$e. enVironinenytt/ condMbar fenc$ mofordr&en aigipkry da & Wed yXe dc}n pnec,Lp,4 fe haferpay rwn L
Rev. 11 14.2-13v
SNUPPS-WC 14.2.12.1.87a Auxiliary Feedwater Turbine-Driven Pump Endurance Test (SU3-ALOS) 14.2.12.1.87a.1 Objectives
~
a.
To demonstrate that-the turbine-driven auxiliary feedwater pump can operate for 48 continuous hours without exceeding any of its limiting design spec-cifications.
b.
To demonstrate. that the turbine-driven auxiliary
)
feedwater pump can operate for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after a cool l
down from the 48-hour test.
c.
To demonstrate that the room environmental condi-tions are not exceeded during the 48-hour test.
.14.2.12.1.87a.2 Prerequisites a.
Required. component
- testing, instrument calibra-tion and system flushing / cleaning are complete, b.
Required' electrical power supplies and control circuits are operational.
c.
The appropriate auxiliary feedwater pump room coolers are operational, d.
The condensate storage tank is available as a water source and to receive recirculation flow.
e.
-A steam source is available.
14.2.12.1.87a.3 Test Method
' The ' pump will be started and operated for 48 bours after reaching rated speed and rated discharge pressure and flow,
.or a greater pressure and less flow.
The turbine-driven auxiliary feedwater pump operating steam will be as close to normal operating temperature as possible and will be at least.400*F.- During: the endurance run, pump-operating data and the pump room environmental conditions will be recorded.
'At the completion of the endurance test, the pump will be
- cooled for.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and until pump data returns to within 20*F of the original pretest data.
The pump will then be started and oporated for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
14.2.12.1.87a.4 Acceptance Criteria a.
- The operating parameters (vibration, bearing temp-e ra tures, e tc. ) do not exceed the design specifi-cations.
b.
The environmental conditions of the turbine-driven ad'F'7
[e.dwater pump room do not exceed the design specifi-c a r:.ons.
11 14.2-13w
StSUPPS-WC
'14.2.12.2 Nonsafety-Related Precoerational T3st Drocedur_e_s
-14.2.12.2.1 Circulating Water System Preoperational Test
( C " 2 ^ 0 0.". i (RAbf-DA dd 14.2.12.2.1.1 Objectives a.
To demonstrate the operating characteristics of the circulating water pumps, water box venting pumps, and the condenser drain pump and verify the operation of their associated control circuits.
b.
To demonstrate by operational test that the cir-culating water pump discharge valves operating times are within design specifications.
s c..
To demonstrate that the gland water system flow to the circulating water pumps - is within design specifications.
14.2.12.2.1.2 Prerequisites a.
Required component testing, instru.nent calibra-tion,_ and system flushing / cleaning are completed.
b.
Required electrical power supplies and control circuits are operational.
c.
The circulatng water system and condenser are available to receive flow from-the circulating water pumps.
14.2.12.2.1.3 Test Method a.
The-circulating water pumps, water box venting pumps, and the condenser drain pump are operated and' pump operating data is recorded, b..
Tae - response of the circulating water pumps and the condenser drain pump - to control signals is
- verified, c.
Circulating water pump discharge valva operating times are recorded.
Rev. 10 14.2-14 4/83
SNUPPS-WC 14.2.12.2.3 Fire Protection System Preoperational Test (SU4-FP03) 14.2.12.2.3.1 Objectives a.
To demonstrate the operating characteris tics of the Fire Protection (FP) system jockey pump, motor-driven fire pump and the diesel-driven fire pump and verify i
the operation of their associated control circuits.
b.
To demonstrate the operability of the diesel oil system, including system instrumentation and controls.
14.2.12.2.3.2 Prerequisites a.
Required component
- testing, instrument calibration, and system flushing / cleaning are completed.
b.
Required-electrical power supplies and control circuits are operational.
14.2.12.2.3.3 Test Method The jockey pump, motor-driven fire pump and the diesel-a.
driven. fire pump are. operated and operating data are recorded.
b.
The response of the motor-driven fire pump and diesel-
' driven fire pump to automatic start signals are veri-fied.
c.
With the diesel-drivan-fire pump operating at rated capacity, the capacity of the diesel oil day tank is
' verified.
14.2.12.2.3.4 Acceptance Criteria a.
The FP pumps -- ope rating characteristics are within de-sign specifications.
b.
The. motor-driven fira pump and the diesel-driven fire pump automatically start upon-receipt of their asso-ciated decreasing fire protection system pressure signal.
c.
With the ' diesel fire pump operating at rated capcity, the - capacity of the diesel oil day tank is ~ within design-specifications.
d.
With the diesel fire pump operating at rated capacity
.and upon receipt of a diesel oil day tank low level alarm, the remaining capacity of the diesel oil day tank is within design specifications.
~ #3#
14.2-16
.i/N
4 w ~ o e w p.p S d*n(WaTc
?reopera oi,al Teet J% 2. t 2. L 11 Fa'ro Prafec: lion
/
i Su 4-kcod 71is lest s's dererile el ih FAIUPPs fsAR Sedbr>112n2 At WcGs du kt u,:ll.Le accanpi,deJ ih 1Le ya<fs (SW/-NCofA a,,d Su4-kcot8) h A
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=
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SNUPPS-T l
l 11.2.12.2.27 Plant Performance Test (508-0007)
This test is described in S!1UPPS FSAR Section 14.2.12.2.27.
It has been assigned a different test number for WCGS.
=g
g SNUPPS-WC 4
l l
l 14.2.12.2.36 Loose Parts Moni toring System Test (SU4-5002)
This test is described in SNUPPS FSAR Section 14.2.12.2.36.
It has been assigned a different test number for WCGS.
1 Rev. 11 l
14.2-13
i a
SNUPPS-WC TABLE 14.2-1 (Sheet 1)
SAFETY-RELATED PREOPERATIONAL TEST PROdEDURES Test Abstract T2st Number Title FSAR Section SU3-NG02 480 V Class IE System (ESW) 14.2.12.1.1 Preoperational, Test Deleted 14.2.12.1.2 SU3-GD01 Essential Service Water System 14.2.12.1.3 Preoperational Test SU3-0004 Power Conversion and ECCS Thermal 14.2.12.1.4 Expansion Test SU3-FC01 Auxiliary Feedwater Pump Turbine 14.2.12.1.5 Preoperational Test SD3-ALO2 Auxiliary Feedwater Turbine-Driven 14.2.12.1.8 Pump and Valve Preoperational Test SU3-3G03 Charging System 14.2.12.1.26 Preoperational Test SU3-BG04 Baron' Therma'l Regeneration System 14.2.12 1.27 Preoperational Test
~SU3-EF01 Essential Service Water System 14.2.12.1.32 Preoperational Test su3-KnoV-geren Hesr4 Ten + angara,,t.Wes rert 19 3.4* I*U SU3-GF01 Miscellaneous Building IIVAC System 14.2.12.1.43
~GF02 Preoperational Test GF03 SU3-KE01
_ Spent Fuel Pool Crane 14.2.12.1.54 Preoperational Test
.SU3-KE02 New Fual Elevator 14.2.12.1.55 Preoperational Test g gy SU3-KE03 Spant Fuel h IIandling#re 14.2.12.1.56 Preoperational Test Fuel !Iandling.Sprem /nfeyated'
-SU3-KE07
' ' "'~ 232 14.2.12.1.56a Preoperational Test Rev. 11
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SNUPPS-WC TABLE 14.2-1 (Sheet 2)
SAFETY-RELATED PREOPERATIONI.L TEST PROCEDURES Test Abstract Test Number Title FSAR Section SU3-KE04 Fuel Transfer System 14.2.12.1.57 Preoperational Test SU3-KE05 Refueling 11achine and RCC Change 14.2.12.1.58 Fixture Preoperational Test SU3-GP01 Integrated Contaihment Leak 14.2.12.1.77 Rate Test SU8-GP01 Local Containment Leak Rate Test 14.2.12.1.78 SU3-GP02 Reactor Containment Structural 14.2.12.1.79 Integrity Acceptance Test SU3-ALO3 Auxiliary Feedwater Turbine Pump 14.2.12.1.37 Endurance Test SU3-ALOS Auxiliary Feedwater !otor Pump 14.2.12.1.37a Endurance Test
?.ev. 11
5 SNUPPS-WC TABLE 14.2-2 NONSAFETY-RELATED PREOPERATIONT.L TEST EROCEDURES Test Abstract Test M".:nber Title FSAR Section SU4-DA01 Circulating Water System 14.2.12.2.1 Preoperational Test SU4-EA01 Service Water System 14.2.12.2.2 Preoperational Test SU4-FP03 Fire Protection System 14.2.12.2.3 Preoperational Test sytf.Arol F,k pronaron Sr.rnmfiva Ar) hey *'an%I fr7/fa2 /.2 2
- II SU3-0007 Plant Performance Test 14.2.12.2.27 SU4-SQ32 Loose Parts Monitoring System Test 14.2.12.2.36 Rev. 11
(
L SNUPPS-WC b.
On. completion of the leak rate test, a verifica-tion test is conducted to confirm the capability of the data ' acquisition and reduction system to satisfactorily determine the calculated inte-grated leakage rate.
The verification test is accomplished by imposing a known le~akage rate on the containment, or by pumping back a known quan-
'tity of air into the containment through a cali-brated flow measurement device.
c.
While at the design accident pressure, data is re-corded for the containment cooling fans.
14.2.12.1.77.4 Acceptance Criteria The containment integrated leakage does not exceed the maxi-mum allowable leakage rate at a calculated peak containment internal pressure, as defined in 10 CFR 50, Appendix. J.
The containment'. cooling fan. operation at design accident pressure is in accordance with design.
t Rev. 11 14.2-13s j