ML20148C526
| ML20148C526 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/25/1987 |
| From: | Andognini G SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| GCA-87-493, NUDOCS 8801250206 | |
| Download: ML20148C526 (1) | |
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Wsuun SACRAMENTO MUNICIPAL L'TaLITY DISTRICT O P. O. Box 15830, Sacramento CA 95852-1830,(916) 452 3211 l
AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA AUG 2 51987 GCA 87-493 l
l U. S. Nuclear Regulatory Commission j Attn: J. B. Martin, Regional Ac'ministrator i Region V Office of' Inspection and Enforcement ,
1450 Maria lane, Suite 210 Halnut Creek, CA 94596 I l
l DOCKET NO. 50-312 '
RANCHO SECO NUCLEAR GENERATING STATION I LICENSE NO. DPR-54 I RANCHO SECO SYSTEM REVIEH AND TEST PROGRAM MANAGEMENT OVERVIEH MANUAL l l
Dear Mr. Martin:
l Enclosed for your information is the Rancho Seco System Review and Test Program (SRTP) Management Overview Manual. This manual provides the policy and guidance under which the Rancho Seco SRTP operates as well as the l objectives the SRTP will achieve to bring the plant to full power operations.
If you have any questions concerning the manual, contact Jim Shetler of my staff, who is the SRTP Director, at extension 4154.
Sincerely, arl Andog i 7 Chief Executive Officer, Nuclear cc w/o atch:
M. Claussen D. Crutchfield D. Kirs 9. w/atch F. Miraglia Dr. Hurley I
~8801250206 870825 Q / f ADOCK 05000312 PLR
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f-()l RANCHO SECO NUCLEAR GENERATING STATION O e444o Twin Cities Road, Herald, CA 95638 9799;(209) 333 2935 L.
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TABL3 0F CON"3N"S SECTION I POLICY AND SCOPE Page MISSION. 1-1 ACCOUNTABIUTIES 1-1 Oll)ECTIVES 1-1 PROGPAM 1-1 SCOPE 1-3 ORGANIZATION- -
1-3 RESPONSIBILITIES 1-3 ORGANIZATIONAL INTERFACES 1-4 ADMINISTRATIVE PROCEDURE EXAMPLES (Figu.e 1.1) 1-5 FUNCTIONAL ORGANIZATION (Figure 1.2). 1-6 0-1
SYS"3M 33V:3W AXJ "3S" '30GRAk EANAG3M3X" OV33V;3VT EAXEAm TABLE OF CONTENTS SECTION 2 PROGRAMS, CONTROLS AND PROCESSES Pge GENERAL 2-1 SYSTEM STATUS and INVdSTIGATION REPORTS 2-1 SSR/ SIR UPDATES 2-3 PERFORMANCE ANALYSIS GROUP (PAG) 2-3 TEST PROCEDURES 2-3 TEST PERSONNEL QUALIFICATION and CERTIFICATION 2-4 SYSTEM TEST MATRIX 2-4 SYSTEM INTEGRATED FUNCTIONAL TEST PROGRAM 2-4 PLINT LNTEGRATED FUNCTIONAL TEST PROGRAM 2-5 PROGRAMS TO ASSESS OPERATIONAL READINESS 2-5 CONCLUSION 2-6 SSR/ SIR APPROVAL FLOWPATH (Figure 2.1) 2-7 SYSTEM STATUS REPORT SECTIONS (Figure 2.2) 2-8 SYSTEM INVESTIGATION REPORT SECTIONS (Figure 2.3) 2-0 SSR/ SIR UPDATE PROCESS (Figure 2.4) 2-10 TEST PPOCEDURE CYCLE (Figure 2.5) 2-11 PLANT TESTING SEQUENCE (Figure 2,6) 2-12 SYSTEM TEST MATRIX (Figure 2.7) 2-13 SYSTEM FUNCTIONAL TESTING (Figure 2.8) 2- 14 SAMPLE PIANT INTEGRATED FUNCTIONAL TESTING (Figure 3.9) 2-15 PROGRAMS TO ASSESS SYSTEM OPERATIONAL READINESS FLOWCIIART (Figure 2.10) 2-16 0-2 l
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TABLE OF CONTENTS SECTION 3 TEST SCHEDULES Pye GENEP.AL 3-1 COLD SilUTDOWN TESTING 3-1 HOT SIIUTDOWN TESTING 3-1 POWER ASCENSION TESilNG 3-1 PIIASES OF RESTART TESTING (Figure 3.1) 3-3 COLD SHUTDOWN TEST SEQUENCE (Figure 3.2) 3-3 PROCEDURE B.1A OVERVIEW (Figure 3.3) 3-4 IIOT SilUTDOWN TESTING (Figure 3.4). 3-5 POWER ASCENSION TESTING (Figure 3.5). 3-6 0-3
SYS~EV REV EW As J "ES~ 3ROGRAv V ANAGEUENT- 0VERV EW MA4UA_
SECTION 1 POLICY AND SCOPE 1
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SYSTEM REVIEW AND TEST PROGRAM Mission The mission of the System Review and Test Program (SRTP) is to ensure that plant systems important to safe operation are capable of performing their required functions to protect the health and safety of the public and to support the plant staff during restart and return to normal plant operations.
Accountabilities In order to carry out the program mission, the SRTP Director reports to the AGM Nuclear Power Production and is accountable for the safe and efficient conduct of the restart test program and its associated activities.
Obiectives The SRTF is designed to accomplish the following objectives:
Svaluate and recommend corrective actions to system related problems identified by the Plant Performance and Management Improvement Program (PP&MIP) .
Identify which systems will require evaluation and the extent of that evaluation.
Monitor and control the implementation of corrective actions, such as modifications and rework, required prior to restart.
Develop and implement a testing program that will demonstrate system functional operation, particularly those functions important to safety.
Provide an orderly transition of system engineering responsibility from SRTP to the Plant Performance Department.
Procram The Plant Performance and Manacement Imorovement Procram (PP&MIP), Quality Contrcl Instruction (OCI-12), and the Rancho Seco Action Plan provide the basis and commitment for the SRTP.
1-1
O s s SYSTEM REVIEW AND TEST PROGRAM The program itself is modeled after the Davis-Besse restart test program with the addition of a series of system functional tests. The program is designed to:
- Verify the adequacy of the plant for safe power operation.
- Ensure that the plant has been properly tenk-d in accordance with the Technical Specifications, t. . a SMUD Quality Assurance Program, the applicable SMUD, state and federal codes and regulations and applicable industry codes and standards.-
- Verify the functions and responses of components and systems important to the safe operation of the plant, both individually and in an integrated mode.
- Provide experience for Operations personnel to operate the plant under both normal and, to the extent practical, transient conditions and restore operator familiarity with an operating plant.
The prognm is implemented in two chases:
- 1. Evaluation and Planninc This phase evaluates the problems identified by the PP&MIP, develops an integrated corrective action plan and identifies the testing required to verify the system's proper operation.
- 2. Imolementation and Testing This phase implements the corrective actions identified in the Evaluation and Planning phase and the testing necessary to prove that the equipment and systems are functioning properly.
The program uses existing plant administrative procedures wherever applicable or practical. When necessary, additional administrative procedures have been developed l to provide for those special circumstances of the restart !
program not covered by an existing procedure. A partial j list of administrative procedures used by the SRTP is provided in Figure 1.1.
l l
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SYSTEM REVIEW AND TEST PROGRAM Scope The scope of the SRTP includes:
The review of systems identified as Selected and Additional in accordance with QCI-12.
Review of systems that have been added to the plant or modified for restart.
Functional testing of Selected Systems.
Post modification testing.
Integrated plant tests.
Orcanization The SRTP is managed by the SRTP Director. The organization is comprised of SMUD and contractor personnel as required to support the restart effort.
The SMUD system engineers will make up the. System Engineering function of the Plant Performance Group. The SRTP functional organization is shown on Figure 1.2.
Responsibilities The responsibilities of the SRTP organization include, but are not limited to:
Acceptance of systems and equipment from the installation organization after modification completion.
- Development, coordination, and implementation of post-modification and other test procedures in accordance with the Rancho Seco Quality Program.
I
- Functional testing of plant systut nd equipment. l i
- Coordination of the review at. " . proval of test i results.
Providing technical expertise and capport of the Plant Operating staff in the performance of Plant Restart Preparation, revision and maintenance of System Status and Investigation Reports (SSRs/ SIRS).
- Preparation and implementation of system schedules and plans.
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SYSTEM REVIEW AND TEST PROGRAM (Responsibilities Cont.)
Evaluation of system operability for restart.
- Providing an orderly transition of system responsibility from the SRTP to the Plant Performance Group.
Interfaces.
The primary site organizations interfacing with the SRTP are:
Quality Assurance - provides inspection, surveillance and audit of SRTP activities. Member of the Test Working Group (TWG), and Test Review Group (TRG).
Plant Operations - provides coordination and operating support for testing and membership on the TWG.
Plant Maintenance --
provides craft support for testing, repair and re. work, and installation for assigned plant modifications (ECNs). Provides input to the TWG as requested.
Plant bioc1#ications -
provides construction services for the installation of assigned ECNs.
- Nuclear Design Engineering - provides the engineering design authority on site and membership on the TWG.
- Impleaentation Group -
provides planning, scheduling and prioritization of plant activities.
1-4
PLANT ADMINISTRATIVE PROCEDURES USED BY THE SYSTEM REVIEW AND TEST PROGRAM figure 1.1 PROGRAM - SYSTEM REVIEW AND TEST PROGRAM DESCRIPTION AND RESPONSIBILITIES (AP.92)
CERTIFICATION - QUAllFICATION AND CERTIFICATION OF SYSTEM REVIEW AND TEST PERSONNEL (AP.81)
TRAINING - TRAINING OF TECHNICAL SUPPORT PERSONNEL (AP.80)
SSR/ SIR - CONTENT AND FORMAT FOR SYSTEM STATUS AND INVESTIGATION REPORTS (AP.94)
SYSTEM STATUS AND INVESTIGATION REPORTS (AP.93)
MODIFICATION - PLANT MODIFICATIONS - ECN IMPLEMENTA-T10N (AP.44)
TEST PROCEDURES - TEST OUTLINES (AP.45)
SPECIAL TEST PROCEDURES, DESCRIPTION AND FORMAT (AP.2.27)
TEST WORKING GROUP (AP.96)
CONDUCT OF SPECIAL TESTING (AP.82)
ROUTINE TEST PROCEDURES. DESCRIPTION AND FORMAT (AP.2.30)
ROUTINE TEST PROGRAM (AP.65) 1 i-5
SYSTEM REVIEW AND TEST PROGRAM -
F UNCTIONAL GRCANIZ ATION .
Figure 1.2 SYSTEM REVIEW
- and TEST PROGRAM DIR ECTOR SYSTEM REVIEW and TEST PROGRAM DEPUTY DIRECTOR SRTP SRIP TEST ASSISTANT AGSISTANT r Sd8FT T
DIRECTOR DIRECTORS cen,cjefATORs (ADMIN) (SYSTEMS)
- Maintain test prog ra m
- Develop test p roce d u re s
- P e rfo rm ine multi- *On shif t test records and files discipline review of coordination
- Mointain and control Pe hm o n c e and re s t a rt related STPs, and - prioritization 11 review SPs, and RTs SSRs/ SIRS , Review in - p ro c e s s
- Develop and update test changes
- P re p a re and maintain
- Re vie w the results p rog ra m status tools SSRs/ SIRS of rest a rt related ,
- Develop and maintain * "
and reports test procedures and y heoules recommend a pproval
- Coordinate on-shifi
- Coordinato and schedule administrative
- Monitor and coordinate to SRTP management technical system support the installation of plant support to modifications. operations.
- Mointain status of *Evolucto system ECNs while in SRTP op e ra bility custody
- Provid e system technicci e x p e rtise to Plant O pe ra tio n s a - ti
e SYS~Ek REV EW As J ~ES~ 3ROGRAv MANAGEMENT OVERVIEW MANUAL SECTION 2 PROGRAMS, CONTROLS AND PROCESSES l
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. .. I SYSTEM REVIEW AND TEST PROGRAM General This section provides a brief description of the major aspects of the SRTP, its processes, controls and its primary goal to transfer its functions to the permanent plant staff.
Figure 2.6 provides a composite overview of the SRTP testing sequence from SSR development until plant restart.
System Status and Investication Reports The System Status Reports (SSR) and System Investigation Reports (SIR) are prepared by the System Engineer and document the selection of systems that will receive special attention under the SRTP.
The reports provide:
- A review of system problems.
- Identification of corrective actions for system problems.
- Identification of the system functions and the testing that verifies individual system functions for select systems (SSR only).
- Verification of system readiness for restart.
System Status Reports are developed for Selected Systems, which, as defined in QCI-12, are those systems meeting any of the following criteria:
- Has a history of significant or recurring problems.
- Is a system related to or contributing to the 12/26/85 overcooling event.
- Is being significantly modified. 1
- Has a potential of initiating or adversely affecting transients.
System Investication Reports are developed for A3ditional Systems, which, as defined in QCI-12, are those systems meeting any of the following criteria:
- The QCI-12 investigations identified a problem with the system.
- Open Work Request against the system as of July 1 '86.
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l .
SYSTEM REVIEW AND TEST PROGRAM The SSR/ SIRS go through a number of evolutionary phases with a major revision number indicating the completion of a phase. The format and content of the reports change with each revision as more information is compiled and activities are completed. Each revision has specific purposes. Figures 2.2 and 2.3 show the major sections of the final revisions of the SSRs and SIRS, respectively.
The purposes of each revision are as follows:
SSR/ SIR Revision 0 To identify the major problems with a system, assign a priority to each problem and release work, such as design, rework, procedure preparation, installation, etc., to begin. Additionally, it provides the justification for upgrading an Additional System to Selected status.
SSR Revision 1 This revision identifies and provides resolution for any new problems. It also identifies the system functions and the testing required to verify the functions of the system outlined in the System Functional Description.
SIR Revision 1 This revision identifies and provides resolution for any new problems, the activities that will be accomplished to resolve the system problems, reconsiders the system for Selected status, and if applicable, makes a system operability statement and recommends final acceptance of the system for plant operation.
SSR Revision 2 This revision summarizes completion of the restart required problem resolutions and the results of testing completed on the system, makes a system operability statement and recommends final acceptance of the system for plant operation.
Each revision of the reports is reviewed and approved in accordance with approved plant administrative procedures.
Figure 2.1 shows the areas that are reviewed and included in the reports, and the approval flow for each revision.
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l l
l SYSTEM REVIEW AND TEST PROGRAM SSR/ SIR UDdates
! As new information becomes available or new problems are l identified between SSR/ SIR revisions, they may be updated by assembling an updated package and submitting it for review and approval. These updates are incorporated in the next revision of the status report. This process is illustrated in Figure 2.4.
Performance Analysis Group (PAG)
A group composed of Nuclear Department Managers, provides prioritization of corrective actions and review and approval of the status reports.
Test Procedures The SRTP utilizes the following normal plant test procedures / methods in support of restart:
- Surveillance Procedures (SP) -
Used to demonstrate Technical Specification requirements.
- Routine Test Procedures (RT) -
Used to perform non Technical Specification tasks that must be completed on a periodic bases.
- Special Test Procedures (STP) -
Usually a one time only procedure. Due to the unique nature of the restart, this is the primary test procedure used by the SRTP when no other test procedure is applicable.
- Maintenance Procedures and Instructions -
Used for normal maintenance tasks and usually associated with a Work Request (WR) .
All test procedures are prepared and conducted in accordance with approved plant administrative procedures, which provide for format, change control and documentation consistent with the type of testing being performed.
The Test Working Group (TWG) provides the required multi-discipline technical review of restart related test procedures and their results. Additionally, this group assists in the review for technical adequacy of existing restart required SPs in order to meet the requirements of SMUD's NRC commitment.
The TWG membership consists of representatives matrixed from the following organizations:
- System Review and Test (chairperson)
- Nuclear Design Engineering 2-3
._ - ..- _ . ~ _ .-_ - - - - . . . . . - - _ _ . .
SYSTEM REVIEW AND TEST PROGRAM
- Quality Assurance
- Nuclear Operations Representatives from additional groups, such as Rad Protection, Nuclear Maintenance, etc., are included as a part of the TWG consistent with the type and scope of the procedures reviewed. The TWG's charter is established in AP.96.
The Test Review Group (TRG) is a sub-committee- of the Plant Review Committee (PRC) and assists the PRC in the' safety evaluation of test procedures and, as required by the Rancho Seco Action Plan.
Figure 2.5 illustrates the preparation, review and approval cycle for the various types of test procedures.
Test Personnel Oualification and Certification The qualification and certification requirements for SRTP test personnel are based on those delineated in ANSI N45.2.6 - 1978.
Each SRTP individual conducting, reviewing or approving test procedures or their results is trained and evaluated j in accordance with administrative procedure requirements.
After completion of the evaluation, a certification level is determined, documented and approved on a certification form.
Each person is certified to one or more ANSI levels .
depending on qualifications and ability. Certifications within a level may be restricted as .necessary; these restrictions are included on the certification form.'
System Test Matrix A System Test Matrix is generated for each Selected System. The matrix is used to provide a consolidated listing of the functions identified in the SSRs, the testing to be performed to demonstrate those functions and the acceptance criteria associated with the functions as included in the test procedure. Included with the Test Matrix is a system P&ID, marked-up to' indicate the testing performed on the system components.
The System T(at Matrix also provides a document with which to evaluat6 the extent of additional testing required during the Functional Test Program.
A sample of a System Test Matrix is shown in Figure 2.7.
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SYSTEM REVIEW AND TEST PROGRAM System Intecrated Functional Test Procram After completion of any required post-modification and component testing, a functional test will be performed on each Selected System to verify, to the extent practical, the system's logic, normal and emergency operating modes.
These tests are based on the requirements of the SSR functions with consideration of plant conditions and the plant Technical Specifications. The functional tests are designed to verify the system / equipment logic in normal and emergency modes of operation to ensure the systems operate in accordance with the SSR functional requirements. The scope of the Functional Tests is outlined in Figure 2.8.
The functional tests will make use of existing Operating, surveillance and other procedures in order to reverify the procedure accuracy and adequacy. Where other tests are not applicable a special test procedure is used. The functional tests may be accomplished as an individual procedure or as a series of procedures performed consistent with the required system and plant conditions.
Plant Intecrated Functional Test Procram An Integrated Testing Program has been established which will ensure the proper sequencing, scheduling and monitoring of system and component tests during the three testing phases of restart (Cold Shutdown, Hot Shutdown and Power Ascension).
Additionally, plant integrated tests (tests which usually I involve multiple systems) have been developed to verify l satisfactory system / plant interactions and responses. A sample listing of these tests is included in Figure 2.9.
Procrams to Assess System Operational Readiness A program to assess system operational readiness has been initiated by SMUD to provide an additional detailed review of the Selected Systems in order to ensure their readiness for restart.
The program is similar to an NRC Safety System Functional Inspection (SSFI). The objective of these evaluations is to assess the operational readiness of the Selected System by determining the following:
- The capability of the system to perform the safety functions required by the SSR.
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l SYSTEM REVIEW AND TEST PROGRAM
- Adequacy of systen testing performed.
- Adequacy of system component maintenance.
- Adequacy of operator or maintenance technician training.
- Reliability and effectiveness of system initiating and control functions.
The major activities related to the operational readiness program and the groups directly involved are shown in Figure 2.10.
Conclusion Upon ccmpletion of the System Review and Test Program, the systems required for the safe operation of Rancho Seco will have been tested and verified in accordance with the Rancho Seco Quality Program, to be able to perform their intended safety functions, the Nuclear Plant Operations staff will have become refamiliarized with the plant's systems and control of the ongoing system related processes will have been transferred from the SRTP organization to the Nuclear Plant Performance Department.
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SSR SIR APPROVAL FLOW PATH -
Figure 2.1 -
ItEVISION O .
QCI-12 PROBLEM _p !
IDENTIFICATION l 1
l I INITIATE WORK I
' l REVIEW OF OPEN m
. _ , PREPAllE _ ggy;"E( AND > 0 RESO M NNGE @O".j WORK REQUESTS I SSR/ SIR _yl $',"" Tgy appuuvac AppuOvE WRs_ etc.)
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REVIEW OF l MAINTENANCE 9 HISTORY TRENDS l C
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M REVIEW OF i o
N OPEN NCR's {g i g REVISION 1 I
! l PREPARE DESIGN ENGR 'I R G PAG HEVIEW OF OPE]Nf 4-- gg > ,' SIR
-> REVUEW AND -> REVIEW AND -> REVIEW AND APPHOVE APPROVE APPHOVE ABNORMAL TAGS I
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!"I'! f REQUIRED REVIEW OF I TESTING D AVIS-BESSE lh lRE l pi l
PROGRAM RESULTSl lyl p AGM-NPP _
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. . . . . . . . . . . . .[ R FlSSR REVISION 2 ONLY IUN S - --l sysTEu s l lt g OPERABILITY -> l 4' STATEMENT g _ - . - -
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system or.stcM ECR l THG 1 PAG AGM-NPP; ?TRAN6 TEM SWIEW l WALKDOWN ->. i._>. PREPARE 88" -> Review AND
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->! REVIEW AND -> REVIEW AND -> ppbOYE 1 t---> f PERFORMANCE TO PLANT p resutT- i APPROVE 4 l l APPROVE l
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I N Test REsutTs !
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SUMMARY
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SYSTEM STATUS REPORTS Figure 2.2 i
REVISION 2 MAJOR FORMAT SECTIONS Executive Summary System functional Description Problem Statements Test Identification Test Results Summary Operability Statement 2-8
. ~.. .- . . _ _ _ . . _ . _ . ._- -_ ._- . _ _ __ _ . __. _-__ _ _
e SYSTEM INVESTIGATION REPORTS
. Figure 2.3
- REVISION 1 MAJOR FORMAT. SECTIONS Executive Summary System Punctional Description l
Problem Statements l
Operability Statement I
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I 2-9
_ _ . _ . . . _ , , _ . _ . - _ . _ , _ - , - _ , . - . _ ~ .
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SSR/ SIR UPDATE Fig u re 2.4 PROCESS .
['N SYSTEM ENGINEER / \ s ASSEMBIES PACKAGE DES]GN ENGINEER / ran 'N YES
- QCI- 1:3 FORM > REVIEW AND g'N " ~ N
- REVISED SSR/ SIR CONCUR /
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's cumcs PAGE(S) p l
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C TEST REVIEh' PERFORMANCE ANALYSIS GROUP (PAG) <:
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! REVIEW AND APPROVE REVIEW AND I APPROVE AGM-NPP l
> APPROVAL T]
TO TIIE NRC AND SSR/ SIR SSR/ SIR
- 4
- OTHER MANUAL ! REVISION UPDATE FILE
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TEST PROCEDURE CYCLE Figure 2.5 .
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TEST REQUIREMENT YES p p gp M ULTI-DISP PIANT SAFETY
> (asse. car./ o> REVIEW > REvizw Jr e N SP[
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SE) (TWG)
SRTG ENG (Tuc/rac)
/ EcN N \No No QA PS V
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Y APPROVE
\ YES IR. NO/W YEs \ m PREPARE RT m RT r (3g) r
/ 1r NO C0MPLETE D TEST (SE/MAINT)
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APPROVE WR MAINT PROC INSTR (ptNy 1r NO lN PRE AkE som
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ActmTY (PLN)
Legend (RESP. CRP)
DIR O/M - DIR. NUCLEAR OPERATIONS / MAINTENANCE SUPVR ENGR - NUCLEAR ENGINEERING RMEW MAINT - NUCLEAR MAINTENANCE
FILE (SRTC)
OPS - NUCLEAR OPERATIONS --->
PLN - PLANNING (RM)
PRC - PLANT REVIEW COMMITTEE QA - QUALITY ASSURANCE I RM - RECORDS MANAGEMENT SE - SYSTEM ENGINEER RESULTS SRTG - SYSTEM REVIEW AND TEST GROUP RESULTS RESULTS REVIEW TRG - TEST REVIEW GROUP APPROVAL 4 REVIEW 4 (Two)
(DIR. O/M) (TRG/PRC) SRTG ENG TWG - TEST WORKING GROUP QA OPS O-11
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PLANT TESTING SEQUENCE -
Figure 2.6 I I I .
TEST REQUIREMENT l COMPONENT TESTING SYSTEM TNT EGRA TED l PL ANT INTEOR AT ED FUNCisONAL TESTING FUNCT60NAL TESTING l
I I I I I I POST MODIMCATON '
l l GENERATE SYSTEM i TESTING (SPECIAL y TEST MATRIX TO TEST PROCEDURES) l l i VERIFY SYSTEM i l D FUNCTIONS HAVE N l 1 BEEN ADEOUATELY l l TE"iTED l l SYSTEM STATUS y l PREVEe4TIQ POST REPORT FUNCTIONS g D kWNTENANCE TETTINO 4 l l l (WORK REQUESTS) l I I ]
4%RK UP SYSTEM f P&iO TO SesOW l i WHAT COMPONENTS I l ARE TESTED ANO I PERrORM PLANT INTECRATED l D AT WHAT PLANT --D l FbNCTCNAL TESTING TO MOOtMCATIONS ECN D
> YESTING
$U fPKILLANC E (TECH SPEC) l e
CONDITIOP.S TESTING VERsFY OVERALL PLANT REWNSE ( LOSS OF l Wlu. OE DONE Or SAT NER W SFAS l (COLO. HOT. POW ER)
PCWER. ETC.)
l I I l > A l (ROUTINE NON TECH SPEC)TESTING l g
PM/ MAINTENANCE y l l ACTtytTIES l
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= = =:,o l em l > = mar rmomtn=r% l arr Nonn openArioN) l Dwrf ng att phases of tes,ang, the SPs necessary to I
co ornoe.s & rsrN s*Ec LeeTA?oes l l e moingoen gno paont within l l Ihe Technical Specificatione l I are perforsned In addition co o, as a port of thee. SP.
l l l per f ormed to deevionstrate
- I componerit one system l l f mn ,on. , or ,h. S.T P.
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S Y S -~ ~~ tvi _ S -- ivi A- R I X -
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Figure 2.7 SSR/ SIR FUNCTION TEST PU RPOSE/EVALU ATION RUN DATE ACCEPTANCE CRITERIA A B C D E C
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A - THE SYSTEM FUNCTION AS DEFINED IN REVISION 1 OF THE SYSTEM STATUS REPORT (SSR), SECTION 4.2.
B - THE PROCEDURE (STP, SP. RT) THAT WILL BE UTILIZED TO DEMONSTRATE THE IDENTIFIED FUNCTION.
C - THE PURPOSE STATEMENT OUT OF THE TEST PROCEDURE D - THE SCHEDULED (S) OR ACTUAL (A) DATE THE PROCEDURE IS RUN.
E - THE ACCEPTANCE CRITERI A AS STATED IN THE TEST PROCEDURE.
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SYSTEM FUNCTIONAL TESTING .
PROGRAM DESCRIPTION Figure 26
- Test of systent interlocks, trips and per znissives, using actual sy s t.e r n oper a tio n and other systern o pe ra tio n al interfaces whereven possiblo.
LOGIC TESTS
- Annunciator and Counputer Points will be verified only as th ey a t e actuated as a part of or during the testing.
- To the ex te n t p rac tic al, these tests are conducted during cold and/or hot shutdown conditions. Sorne tests rn ay be perfornned during the Power Ascension Prograrn.
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- W ill show that the systent fu nc tions as required under
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NORMAL OPERATION nor1nal (or as close to norrnal) operating conditions, as p ra c t.ical.
- Will use Plant Operating Procedures and Surveillance Procedu res to verify systern functions, as practical
- Plant Integrated Teste will be used wherever practical. (Ex.
Loss of ICS/NNI or Loss of Power /ECCS testing.)
l
- Surveillance Procedures will be used.to th e extent p ra c tical .
EMERGENCY /OFF NORMAL *Will show th at th o systern functions as required under OPERATION sinnulated enxergency conditions, as p ra c ti c al.
i
- Veri fica tio n of systen1/cornpornent action or inaction, as a pp ro p rin te.
__ _ _.__ _ _ ._. . _ _ _ C'- 1i !
SAV 3 _E 3 As" 4~EGRA D UNCT Ob A_ "ES"S Pigure 2.0 0 INTEGRATED LEAK RATE TEST (ILRT) e INTEGRATED SAFETY FEATURES ACTUATION SYSTEM (SFAS) TEST 4 LOSS OF 0FFSITE POWER TEST (LOSP) 9 LOSS OF INSTRUMENT AIR TEST e EMERGENCY FEEDWATER INITIATION AND CONTROL (EFIC) FUNCTIONAL TEST 8 LOSS OF INTEGRATED CONTROL SYSTEM (ICS)/ I I
NON-NUCLEAR INSTRUMENTATION (NNI)
POWER TEST l
2-15
PROGRAMS TO ASSESS S"STEM O P ERATION AL '
READINESS F LOWC H A RT --
Figu re. 2.10 ,
Ng '
SYSTEM .
READY FOft C===\ NC.
\ >-- UPDATE 55ft/ StRl Cp[pATION OW ,
D . .
j Rabt.,
ABNCRMAL 7% .
y e EPANDED 41
" d *"/ [ g (SRTG) ,
ASRTP D [YES (SRTG) E'/ALUATIOf4 C Ew OF OPEN -
i WORK REQUESTS y E Z os - > g I (SMTG) m.c3 .
~ nEwEw or Oecu l O' m h ^
ECN"5 _y TENTDG ) O (5HTG) I'"N G ALuATE &
A55sCN COMPLETE REC"O REVEW OF OPEtJ w cc surp PmopITY SU NC RCVlEW OF Coup dTE tytTEM NCF.3 > Trur m g TECH SPECS W UPS gpg) (o g) (UC) y (3"'**
<an=> t l RrvtEW OF DAWS ,e sEssE SnTP y =ga :;7*,* YES YES w
- "" ) ENT (sma) Ni 7f2 reco\ j >
su;mr 1 PEWE* OF MAsNT (ERTC/MAINT)
H570gy TRENos y stes.c or o'
- NO NO (SHTG) ""*8 (Tenc) TJ CONOUCT SYSTEu couPdTE PER y[3 wAtroowns PL*T COM PLETE
) ComoucT suRV PROCEDe.mf
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CLOSE g ygg vs E p=ocer,asers c Legend. .
ACTivlTY I CONDUC1 OPERA 1sW.
I PROCEDURE REViiW p (au) (RESP ORG) gops3 i ALL -
ALL GROUPS PARTICIPATC OkW -
DAOCOCK & WILCOX FNCR NUCLEAR ENGINEERING co oucTs % =csn c ar=cw <.wCwoc N
smpT,urpuT <}-- l llc NIJCLFAR LICENSINC
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- * ' > MAINT - NUCLEAR MAINTEN ANC E (EN'a) ( " ^ * "T)' OPS -
PLANT OPERATIONS PAG -
PERFORMANCE ANALYSIS CONDUCT ouAurr GROUP "N*
> QA - Q U ALITY ASSURANCE
_ , oq
- INCLUDES ELEMENTS OF OTHER INPUTS TRGN - TRAINING e
i g 2- I ts
l SYS~EV REV EW As J ~ES~ 3ROGRAv l
MANAGEMENT OVERVIEW MANUAL l
l SECTION 3 TEST SCHEDULES 1
i 3-0 ,
i l
. SYSTEM REVIEW AND TEST PROGRAM General The SRTP test program consists of three separate phases:
- 1. Cold Shutdown Testing
- 2. Hot Shutdown Testing
- 3. Power Ascension Testing The required logic restraints are integrated into the schedule to establish the most practical sequence to restart completion. Figure 3.1 illustrates each phase of the restart schedule and a brief description of its content.
. Cold Shutdown Testina cold Shutdown Testing includes component, functional and integrated tests that do not require plant heat. These tests will verify that the system / component responds and functions per the SSR requirements.
Figure 3.2 illustrates a typical sequence and content of testing requirements leading up to readiness to enter the Hot Shutdown Testing mode of restart.
Hot Shutdown Testina The procedural controls established for progressing from Cold Shutdown, into and through Hot Shutdown are mainteined via procedure B.lA (Control of Plant Heatup and Operating Procedure for Power Escalation Testing) which has been generated specifically for this restart effort.
Figure 3.3 provides some guidelines as to the purpose and content of this Operations controlling procedure.
Hot Shutdown Testing includes component, functional, and integrated tests at various plant conditions to verify that the plant and systems respond appropriately at various temperatures. Figure 3.4 graphically displays the l testing plateaus and contains some general, notes pertaining to this phase of testing. l j
Power Accension Testina The procedural controls established for progressing from Hot Shutdown, into and through Power Ascension are also maintained via procedure B.1A.
The Power Ascension Testing portion of the restart effort includes functional and integrated tests that verifles the plant responcs appropriately with the reactor at various power levels. Figure 3.5 illustrates the plateaus that the plant will be maintained at to per*orm these tests.
3-1 l
DFAS BS OT lR:BS"A:R" "3S"IG Figure 3.1 e Conducted in three phases COLD HOT POWER SHUTDOWN g SHUTDOWN g ASCENSION F TESTING F TESTING TESTING PHASEI P H A S E ll P H A S E Ill ;
i _
l O PHASE I - The Plant is at cold shutdown. Tests are conducted using STPs, RTs and SPs to verify component and system operability. Some integrated tests to verify system responses are conducted during this phase.
O PHASE II - The Plant is matatained in a hot shutdown condition using pump heat.
System tests are performed using STPa, RTs and SPs to verify system interactions, functions and operability. Selected integrated tests are conducted during this phase.
4 PHASE Ill - The Plant is self-sustaining using nuclear heat. Systems are operated in accordance with normal Operating Procedures. Final alignment, tuning and testing of the plant systems is accomplished during reactor powei increases through various plateaus to the 100% plateau level. using STPs, "Ts and SPs.
Inroughout cll ihree phases opercer retcmillarizatior alth the vcrious systems' s
operating mcdee is cecomplished by direct manipuhtion of system controls end l Muipmert. Sextad tests and erclu%ns eiy be repected or their duratien, extended 10 allcw r :v' ple Opercling shifts to scriipt' ln the octivity.
l I
3-3
a ,
t COLD SHUTDOWN TEST SEQUENCE .
Figure 3.2 ,
]
1r m LOSS OF OFFSITE POST "
POWER TEST MODIFICATION TESTS PREVENTIVE / POST 1 rm SYSTEM >
unwrawancz Tests '" FUNCTIONAL TEST OTSG
> HYDRO
^ rROM
!<O st.1NE [ OTH'8 >
TLSTS ( $[sTs" SYSTEM
> WNCTIONAL TESTS TO FROM h s HOT SHUTDOWN OTHER
}
> TESTING SURVEILLANCE p q Y[dy's" f TESTS FROW OTHER -
)
o7gg",
U STS j SYSTEM )
TESs3 _
Most system functional tests are scheduled to allow for proper system restraints and interactions; where no restraint exists, they are scheduled to support the Loss of Offsite Power Test (LOSP). Some tests may be performed simultaneously with LOSP. The remainder o_f the functional tests are performed during the Hot Shutdown or Power Ascension Testing phases.
3-3
PROCEDURE B.1A OVERVIEW Figure 3.3 o Tile PROCEDURE IS Tile CONTR0ll!NG DOCUMENT WHICH ESTABLISHES THE PROGRESSION OF EVENTS FROM THE COMPLU10N OF COLD SHUTDOWN TESTING TilROUGH THE COMPLETION OF POWER ASCENSION TESTING.
- Tl[F, PROCEDURE IS MODEIID AFTER THE PROCEDURE THAT WAS SUCESSFULLY USED DURING THE DAVIS-BESSE RESTART PROGRAM.
e THE PROCEDURE INTEGRATES THE USE OF PLANT PROCEDURES, SPECIAL TEST PROCEDURES AND Tile REQUIRED MANAGEMENT AND REGULATORY APPROVALS NEEDED TO PROCEED TliROUGH THE VARIOUS PHASES OF THE TESTNG SEQUENCE.
e Tile PROCEDURE IS DIVIDED INTO SECTIONS WHICH ARE BASED ON PIANT CONDITIONS:
o HOT SHUTEDWN e POWER ASCENSION REACTOR POWER PLATEAUS (VARIOUS) e PROVISIONS ARE MADE FOR THE APPROPRIATE MANAGEMENT AND REGULATORY REVIEWS OF OPEN ITEMS FOUND DURING TESTING.
- PROVISIONS ARE INCLUDED FVR FINAL VERIFICATION AND APPROVAL OF THE COMPLMION OF RESTART TESTING.
3-(
a HOT SHUTDOWN Fig u re 3.4 TESTING I RCS
- PRRSSURE P TEST
- L E _
i A /
N 'TO T REACTOR D _
-> CRITICALITY C AND POWER O f'. ASCENSION H '
l D C -
T I
o B _
N A _
/
/
/
/
l l l l l l l l l 1 I I l I I I I I I I i APPROXIMATELY THREE (3) WEEKS DURATION NOTES:
1 - THE HOT SIIUTDOWN IIEATUP WILL COMMENCE FOLLOWING COMPLETION OF THE OTSG IIYDRO.
2- SAMPLE INTEGRATED TESTS TO BE COMPLETED IN HOT SIIUTDOWN:
TEMPERATORE/ PRESSURE LEVELS A. LOSS OF INSTRUMENT AIR - STP.1058 A - 350 F 700 PSIG B. EFIC FUNCTIONAL - STP.667 B - 410-435 r 1900 PSic C. LOSS OF ICS/NNI POWER - STP.664 C- 450 F NOP O- 552 r NOP 3 - SELECTED TESTS WILL DE PERFORMED MORE THAN ONCE TO ALLOW E- 332 F 2255-2450 PSIO MULTIPLE OPERATIONS SiiIFT INVOLVMENT.
4 - PROCEDURE B.1 A WILL DE THE CONTRO13ING DOCUMENT FOR
. HOT SIIUTDOWII TESTII:G.
5 - SYSTEM FUNCTIONAL TESTS REQUIRING HOT PLANT CONDITIONS WILL BE COMPLETED DURING THIS TIME PERIOD.
0 - THERE ARE APPROXIMATELY 28 STPs SCIIEDULED FOR THIS PHASE.
3-4
l - .
e i
POWER ASCENSION TESTING '
Figure 3.5 100 _
90 _
/ -
80 ___
r.
70 _
l 60 _._
P O
50 _
E R 40 _
L E 30 _
V E
L 20 -
10 _
f O
I I I I I I I I I I I I I I I I I ! I I I I I I I I I I I I I I I I I APPROXIMATELY FIVE (5) MONTHS DURATION NOTES:
1 - REACTOR POWER PLATEAUS AT APPROXIMATELY 40, 60, 75 AND 927. ARE TO EVALUATE OPERATOR AND PLANT READINESS PRIOR TO INCREASING TO 100% POWER.
2 - SELECTED TESTS OR EVOLUTIONS WILL BE PERFORMED MORE THAN ONCE TO PROVIDE GREATER EXPOSURE TO THE OPERATIONS SHIFTS.
3 - SAMPLE INTEGRATED TESTS TO BE COMPLETED DURING POWER ASCENSION TESTING ARE:
A. MANUAL REACTOR TRIPS AT APPROXIMATELY 20 AND 76%
B. ICS TUNING AT 10, 15, 40, 75, 92 AND 100%
4- PROCEDURE B.1 A WILL DE THE CONTROLLING DOCUMENT FOR THIS ItVOLUTION.
3-6
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