ML20066C486
| ML20066C486 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/18/1990 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20066C482 | List: |
| References | |
| NUDOCS 9101100149 | |
| Download: ML20066C486 (397) | |
Text
{{#Wiki_filter:_ SIMULATOR CERTIFICATION REPORT BEAVER VALLEY POWER STATION l UNIT 1 I l p-e l l i l l l l
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U.S. NUCLE AW RE GUi.QTOWY t;OMMisslON AFPMWtD ev OMB- No. stmotsa l g POZM 474 10 CFR && aS(td. ESTIMQTED ,URDEN PER ctSPONSE TO COMPLY wtTH THl$ 66.a ene 86 A INF ORM A TION COLLECTION R EQUEST : 120 HR$ FORW ARO SIMULATION FACILITY CERTIFICATION =A~',*Jy,^C!= a
,:gawi '"^ ,4*J3 ;"l,,";g i g U$ NUCLEAR REOULATORY COMMISSION. W A8HiNGTON. DC i
70666, AND TO THE PAPf PMORK REDU l 0138L OFflCE OF MANAGEMENT AND ,CTION UDOCT, PROJECT W ASHINQ tDN, t3tn DC 20bOJ l INSTRUCTIONS. This form is to be fuod for inrtia: certifiestion recertificaten Of requiral), and for any change to a sirr.uistion facihty performance testing plan made after initial l ( tubmittal of such a plan Provide the following informaten, and check the appropriate box to irdicate rsesori for submntal. F ACILITY lDOCAEl NUMBER Beaver Valley Power Station Unit 1 N1334 LICENSEE lDATE Duquesne Light Company 12/18/90 I Vhis is to co ti'y tP.st:
- 1. The above named facility licenm is usmg a simulation facihty coisistmo solely of a plantveferenced simuistor that meets the requirements of 10 CF R 66.45.
- 2. Documentation is aveasbie for NRC review in accordance with 10 CF R 66.46(bL
- 3. This simulation facihty tnests the guidance contamed in ANSI /ANS 3.6 1986, as endorsed by N RC Repletary Guide 1,149.
1 If there are any eEceptions to the certification of IN: Item, check here I X} and describe fully on additional pages as necessary, NQME for other Nfent/ fret /on) AND LOCATION OF SIMULATION F ACILITY Beaver Valley Power Station Unit 1 Simulator Beaver Valley Training Center Shippingports PA 15077 SIMULATION F ACILITY PERFORMANCE TEST ABSTRACTS ATT ACHED. frorpe tonnance tects conducted in the penod endir.g with the dsro of this certification) y OLSCRIPTION OF PER FORMANCE TESTING COMPLETED IArtech eddrtionnipagelsl oe necennery, and ksentify the trem descriprmn bemg continual) Initi'l Certif1 Cation - See attached Transient Steady State, Malfunction and Normal Operating Tests, v 5lMULATtON F ACIklTy PE RFORMANCE TESTING SCHEDULE ATT ACHLD. (for the conduct of appronnwtely 25% of perharmance toets per veer for the tour yeer
^ pernc' commeni;mg wrth the date of this certifocatiott.)
SCRIPTlON OF PER F0RMANCE TsSTlNG TO 8E CONDUCTEO. IArtsch orkirtionelpagets)es neceanery,andidentify the kom doncnprnors being continued) Re fer To Enclosed Test Schedule. PE RF0RMANCE TESTING PLAN CHANGE. Iforairy moditmetion to a portbrmanes testingpten submittat on a previous certificatiors) DESCRIPTION OF PEP Ft1RMANCE TESTING PLAN CHANGE (Attach additkinetpage(slas neceanery,andidentify the kam description heing contavat) Not Applicable. Initial Submittal R ECE R TI F iCATLON (Deectibe conecttw ectksnt taken, etisch results of completed performance testing in accorttence with 10 CFR g 65.45(b)(5)lv). Attach s&fitionalpagels) es neceanery, and identh*y the kom es sacription oeing continued.) Not Applicable. Initial Submittal Any falso statement or omission in this document, meludmg attachments, may be skO to civil and criminal sanctions. I certify under pensity of perjury that the infottnetton in this - wnt and attact ments 6s true and conect. IGN A JR - HORIZED REPRESENTATIVE lDATr
% lT6TLE i g .D. Sieber Vice President Nuclear Group bb O in accstdance With 10 CFR g 66.6, Commurucations, Vies form shall be sutimitted to the NRC as follows:
BY MAIL ADDRESSED TO: Directet,0ffice of %cieet Reector Regulation BY DE LIVE RY IN PE RSON One WMte Flint %rth UA. Wetent Reputasory Commiss6en TO THE NRCOFFICE AT: 11666 RodviHe Ptka Weehin,,an, DC 20H6 RockelHe, MD NFtC PORM a7a (140)
1 ; I p Exceptions to ANSI /ANS 3.5 and/or Regulatory Guide 1.149 ( ";
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The following exceptions represent equipment function required by ANSI /ANS 3.5, which are not available in the Unit 1 Simulator. The training imp.act i and/or plan to address their differences are as follows. Scheduled changes to the simulator will reduce the number of exceptions taken in future reports.
- 1. Unit I Plant Process Computer (P-250)
ANSI /ANS 3.5 Section 3.2.1 - Currently the Unit I plant process computer is not reolicated on the simulator. The Unit I plant process computer is scheduled for replacement during the 1991 refueling outage. Training impact is limited to the inability to perform computerized monitoring and trending. These functions are currently provided by the training instructor. The replacement plant process computer hardware for the - simulator has been ordered, and should be available for training within 18 months after plant acceptance. (Refer to Section 3.6 for planned completion)
- 2. Normal Plant Evolutions ANSI /ANS 3.5 Section 3.1.1 (7) -
Normal Plant Evolutions - The evolution of plant startup, shutdown and power operations with less than full coolant flow will not be performed as BVPS-1, is not licensed to, or have procedures to operate with less than full core fl ow.
- 3. LR.F. Electrical Distribution / Turbine Water Induction Panel
(] U ANSI /ANS 3.5 Sections 3.1.1 (3) and 3.2.1 Normal Operations and Panel Simulation - E.R.F. Electrical Distribution / Turbine Water Induction Panel is retired in place in the Unit I Control Room with the exception of 4 control switches for reheater excess vent valves. The panel is not installed in the simulator and the control switches are controlled by a Local Operator Action feature of the simulator. The four (4) reheater excess vent valve control switches change the vent path of the reheater and do not have any observable affect on any plant parameter. The panels and switches will not be installed.
- 4. Radiation Monitorina System Control Console ANSI /ANS 3.5 Section 3.2.1 - The Radiation Monitoring System Control Console which includes the steam generator blowdown radiation monitor-is not installed in the simulator control room. After review of this console functions, it was determined to install this console and to integrate the steam generator blowdown radiation monitor. The steam
, generator blowdown rcdiation monitor is .ddressed in the emergency and abnormal procedures as an indicator for steam generator tube leaks.
The training impact is a concern Lince the operator is unable to access -the . correct panel in the' simulator. Administrative action to purchase and integrate the console has commenced. Expected integration to occur within 18 months after procurement is authorized. j i 1 i V' l 4- - 4
l lO BEAVER VA_* ' POWER STATION UNIT I SIMULATOR I4f' SAL CERTIFICATION REPORT O O i
TABLE OF CONTENTS Section Title
- 1. Simulator Information i 1.1 General 1.2 Physical Comparison of Unit I and Simulator Control Room 1.2.1 Controls Area Physical Arrangement 1.2.1A Panel / Equipment Not Included in Control Area-1.2.1B Resolution of Control Area Differences 1.2.2 Controls Area Equipment Differences 1.2.3 Systems I 1.2.4 - Simulator Control Room Environment 1.3 Instructor Interface 1.3.1 Initial Conditions 1.3.2 Malfunctions 1.3.3 Controls Provided for Items Outside of Control Room 1.3.4 Additional Special Instructor / Training Features Available.
1.4 Operating Procedures for Reference Plant Ox 1.5 Changes Since Initial Delivery
- 2. Simulator Design Database. - :
i. 3 ' -3. Simulator Tests 3.1 Computer Real Time Test 3.2 Steady State-3.3 Normal Operations : 3.4 Transient Tests h 3.5 --Malfunction Tests 3.6 Deficiency List and Correction Schedule-
- 4. Simulator-Trouble Report Resolution and Change Request Program
-5. Simulator Operating-Limits 1
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O U-t Section Title L APPENDIX I List of Initial Conditions APPENDIX 2 List of In Plant Local Operator Actions APPENDIX 3 Proposed Simulator Halfunction Testing Schedule APPENDIX 4 Simulator Discrepancy Reporting and iissolution APPENDIX 5 Simulator Data Base Tracking APPENDIX 6 BVPS Transient Review Committee Expereince ":.immaries O (O l I 1 l i
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- l. Simulator Information i
O General 1.1 l The Duquesne Light Company is submitting ;this report as the. initial certification report _ prescribed by 10CFR55.45(b)(1) ! (ii). The Duquesne Light Company operates Beaver I Valley Power ' 1 1 Station Unit I which is a Westinghouse PWR 3-loop.2652 MWTH power : l ! pl ant . The Beaver Valley Power Station Unit 1 simulator i replicates the controls crea of ~ Unit I. The simulator._ was constructed by Westinghouse in the early 1980's with the first training classes conducted in February nf 1985, The Unit I simulator is currently used for training the Beaver Valley' Unit I ; and Unit II operators. A Unit II. simulator is currently being built by Westinghouse and is scheduled to be available for l training in 1991. Duquesne Light Company and Westinghouse has entered. an agreement to install the - Westinghouse Advance. Primary . Systems Models (SIMARC 4.0)into the Unit I simulator. The- installation , of' the upgrade is to commence it' January 1991. Completion. of integration and testing of the upgrade is' scheduled for May 1992. .i i i O . f
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1.21 Physical: Comparison of Unit-l' and Simulator Control' Rooms A physical comparison of the -BVPS Unit I ' control room 'and 'the Unit I simulator was conducted.- This'comparision was to- ensure that sufficient controls, instrumentation, alarms and > other man-machine interfaces are installed to perform normal' operations J and respond to - the malfunctions. - -The : comparison- was subdivided .i into four areas; controls area physical' arrangement ~ (1.2.'l), , controls area -(1.2.2), systems- (1.2.3) and . general control room j i environments (1.2.4) .-- The . controls - area' comparison- is intended , to identify . any differences. in panel arrangement or major-equipment dif ferences. In the- Controls ' Area Equipment
-1 Differences Section -(1.2.2) - the details of the. panel _ equipment 1 differences are provided,- i.e', a switch' on = a. specific panel - not ~ ,
l being installed. Section.1.2.3 Systems,- compares the. systems which can be operated from the Unitul controls. area versos the t systems which.are interactively modelled in the Unit-I simulator. Since the delivery of the simulator, Beaver Valley : Power Station ! i Unit I changes have been tracked by1 reviewing -the, Design Change Packages (DCP's) issued by: DLC engineering._ If this1 review indicates that action- i.s required,- a simulator Change- Request (CR) is ~ implemented per Appendix- 5--Simulator Dat'a= Base Tracking ; Procedure. The Change. Requests hich have been installed- in: the~. simulator are listed in Section:1.5. l i T
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4 Another method used - to maintain - hardware fidelityJ has been! to take several series of detailed photographs of_ the Beaver Valley Power Station Unit I control- boards. These. photographs were 4 compared to the Unit I simulator by the simulator staff. The ! last series of photographs were taken in February of ~1990 and' ; were the data . point for hardware comparison for this report.- Specific data sheets covering _ meter scales, pointers, -labelling etc. of the Beaver Valley Power- Station Unit I control boards were completed and-. compared with - the Unit I simulator's l configuration. During these reviews the demarcations of the control boards were compared. Al so, the placement and color of - markings used as operator aids were visually checked and verified. Following the completion of these comparisons, a differene.e valuation committee was convened to evaluate the impact of differences and - to recommend any further action. The committee was composed of the Unit I Operations Manage. , -the Training i Manager, the_ Director .of Operations Training, Supervisor _ of Licensed Operator Training, Supervisor of Simulator Training and: the Coordinator of Simulator Training. The differences o f-sections 1. 2.1, 1. 2. 2. 1. 2.3. , 1.2.4 - between Unit I and the Unit I simulator were evaluated as to potential training impact or detritaental effect on operator - performance ' during simulator training. The actions undertaken as a result of the committee's
- review are summarized _in the appropriate sections of this report.
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a d 1.2.1: -Control Room Physical Arranaement? > The' physical. arrangement $f the ' simulator's control room-
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duplicates the; Beaver: Valley Power - Station _ Unit' I~_ controls 1 area. The controls area is_ defined:in Figure 1.2.-l.l. .LThe BVPS Unit I control room drawing is -; provided- as Figure- 11.2.1.2, - and the-simulator control room ircFigure 1.2.3. lO t l i i j i i 4 Li i q 1 i 1
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1.2. l A - Panel /Eauioment Not included-in Controls Area- j
.The - following. are layout or major panel differences between the Unit I controls area and the Unit simulator.
- 1. Plant P-250 computer operator console and associated support equipment.
- 2. Electrical Fault.Manitoring Panel.
- 3. Pressurizer _ PORV and safety. valve acoustic monitoring panel.
- 4. ERF electrical distribution / turbine water inductionipanel.
- 5. . Radiation monitoring system control console.
- 6. Sequence of events computer printer.:
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i 1.2.1B Resolution of Control Area Differences
- 1. Plant Process Comouter (P-250)
The simulator was ordred - without a ' fully scoped plant process compute'r because _the Unit I plant had. intended to upgrade the plant computer hardware. The' simulator plant process computer hardware 'is only partially modeled. Also not installed are the alarm and trend typewriters, which ! interface though the P-250 computer.- . Not all parameter trends are available to the operator while training with.the simulator. Examples of some of the parameter trends used during normal operation are:
- h. Main generator hot gas temperatures
{ b. Main feed pump motor temperatures O se ever. ees oet meoed 81 the ePereters, is Previoeo ex the computer engineer, role-played by- the simulator instructor. The :urrent . scope of the' plant computer installation does cot impact tha. operators ablity to ! U l correctly use emergency or abnormal procedures. , Unit I .is to install a new plant' computer' system during the next refueling -outage scheduled in the spring of'.1991. . The Unit I simulator be upgraded to replicate the new. computer system. The new hardware will be installed in.the simulator following installation in Unit I. Thist acton is being tracked by CR 0093. O .
- 2. Electricat W 1onitorina Panel The equipment mounted within the panel is for reviewing post i electrical distribution faults. The system uses magnetic tape for recording and must be read off-site.
The electrical fault monitoring equipment has no training value or direct impact on operations during normal or emergency procedures. The cwnittee determined that there would be no training value in panel installation.
- 3. Pressurizer P.O.R.V. and Safety Valve Acoustic Monitorina f.U111 This panel houses interface equipment between field-mounted
. acoustic monitors and control room area alarms and IAty indication. The panel also suppleme ..s the pl ant 's-l annunciativr system with its own- local alarm, alarm reset - and acknowledge push-buttons. Alarm reset functions are performed by the simulator instructor via ;a local operator action (LOA). The committee directed that the local panel alarm has limited training value.- The Pressurizer P.O.R.V. Valve Acoustic Monitoring panel that require operator actions are addressed in alarm response procedures. The committee directed that a simulation of the noise generated by a lifting valve be installed. This additional feature of the Unit I Simulator is tracked by CR 77. O .
- 4. Emeroency Resnonse Facility (E.R.F.1/ Turbine Water Induction O
v Panel This one panel has controls mounted on both sides. One side is the E.R.F. black diesel conticls and indication. On the l other side of the panel is mounted the turbine water induction equipment. The design change for water induction has been cancelled and the ERF distribution panels are being phased out. The panel will be retired in place. Located on i the turbine water induction panel are switches for heater l l excess vent valves. These switches are addressed in normal l operations procedures for turbine start up. This function is performed by using a local operation (LOA) feature of the simulator. The committee determined that the panel need not be installed as there is no impact on training.
- 5. Radiation Monitorina System Control Console (Sping) l l This console gathers and processes data from three 1
ventilation particulate monitors, three ventilation noble gas monitors anJ the steam generator blowdown monitor. These partictlate and noble gas radiation monitors are not addressed in any normal or emergency operating procedures. The steam generator blowdown radiation monitor was later installed on this console due to a recent plant modificaton which added a new blowdown system. This steam generator blowdown radiation monitor is addressed in the Unit I emergency operating procedures and abnormal procedures as an
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l _ indicator. for- steam- generator tube leaks or - rupture. The committee ' recommended the installation of the SPING l Radiation Console with _the: features. required to use this j blowdown radiation monitor. (CR-149)
- 6. Seouence of Events comouter printer (SER)
The Sequence of Events Computer Printer is a- high. speed > sequence. recorder which has 1400 digital inputs and 200 thormocouple analog inputs. The digital . inputs operate on contact change of state and print in sequence to the nearert ; 2 milliseconds. There are no normal or E0P. procedures that address the use of the Sequence of Events. Computer / Printer. This system is , used primarily as a -diagnostic tool . for post plant upsets, and therefore, has limited training- value. Information to N support training is provided by the simulator instructor during simulator operations.- The committee did not l recommend the installation of the . SER, as instructor supplied information adequately replaces the hardware, based upon training experience .and feedback 'from the Unit. I operations staff. i lO 6 v - , , , . - - _ , , . . , ,
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The Beaver Valley Power StationJ Unit' l' simulator controls area , comparison was conducted usingL actual plant photographs and check-sheets for each control switch, controller,- indicator recorder and meter. -j A detailed review of . hardware, meters, recorders controllers, :; i control; switches, -indicators annunciators -and other disp 1ays -that i would function during ' normal, abnormal andl emergency evolutions ! were reviewed by the committee. l l The committee's review of Leontrol board ' switches included the 'i following' details: l Switch type-Lable color, wording, letter size Location l Available positions-I O
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The committee's review of ' indicators, recorders and meters included the following details:. 1 Correct scale Correct engineering units-Lable color, wording, letter size Calibration sticker color Location Pointer color and -shape Placement of operator aids-A review of each annunciator window and.. status -light was conducted-with the following details reviewed for each:- Annunciator location Wording and wording size Annunciator window color (green or red) Status light color The committee concluded that> none of the ' differences are of -a significance that would cause an operator -to takecany- different action in the simulator than in the Unit I control room.- -The-committee did recommend - that actions be taken to correct some minor differences in : scale demarcations and - lettering.- These actions are being tracked by the Simulator-Discrepancy Reporting and Resolution System. i l . o
i O i.2.3 Svstems not Mode,ed or not rullv sede,ed 4 The Beaver Valley Power Station Unit 1 Simulator models most of Unit I control room operated systems. The _ following systems are ; not modeled or not fully modeled .in the Simulator. These systems provide information to the control room operator during normal, _ 1 i abnormal or emergency operating procedure usage.
- l. Fire Protection (Not Modelod)
- 2. Radiation Monitoring System Control Console (Sping)
(Not Modeled)
- 3. Plant Variable Computer (Partial)
- 4. Plant Computer System P-250 (Partial)
- 5. Pressurizer PORV and safety (Acoustic Monitor) (Partial)
- 6. Sequence of Events Recorder (Not Modeled)
O 7. Safety eeremeter oisp,ey System (SeoS) (eert4el)
- 8. Liquid Waste (Partial)
- 9. Gaseous Waste (Partial)
- 10. CTMT Wide Range H2 Analyzer (Partial)
- 11. Main Generator Systems (Partial)
- 12. Auxillary Building Vontilation (Partial) i l _Y 1
1.2.3 (Con't) c% lj in order for the operator to take expected actions during normal, abnormal- and emergency operations during simulator training and evaluation sessions, the committee reviewed systems controlled from the control room or system interfaces that would be observable to the control room operator. Their recommendations are as follows:.
- 1. Fire Protection Add deluge valve operation. ano it's effects. (CR-132)
- 2. Radiation Monitorina System Control-Console (Soinal Add Sping console and interactively model steam generator blow down rad monitor. -(CR-149) 3&4. Plant Variable Comouter-Access the P-250 upgrade to determine _ training impact of m
U removing current P-250 features then upgrade PVC to Unit 1. (CR-93)
- 5. Pressurizer-PORV and Safety Valve Acoustic Mon'itorina Panel Research methods available_ to simulate noise of liting PORV or safety. (CR-77)
- 6. Seauence of Everts Recorder The committee found that the current method of simult ion was adequate.
- 7. Safety Parameter Disolav System (SPDS)
Determine why; it is necessary.to depress the " SHIFT" key in
- order to page when _ using- the simulator's SPDS - correct if possible. (TR-324) 8&9. Liauid Waste and Gaseous Waste D
(_) . The committee found these systems to be adequate in present s' cope.
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1.2.3-(Con't)
- 10. Rydroaen Analyzer After the analyzer is started (via LOA feature), a set 'velue >
is recorded - committee suggested that a calculated-value be recorded based on LOCA size and activity. (CR-143)-- s-
-11. Main Unit Generator.
Include "Backfeed" feature and the. means to monitor generator gas : temperatures -with the 'new plant computer upgrade. (CR-154)
- 12. Ventilation System Considering adding feature for vibration cutout for containment fans. (CR-154)
-c Items 6, 8, 9- The committee found these systems to be tdequate in present scope.
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=/ 1.2.4 Simulator Control koom Environment The -Beaver Valley Power Station ' Unit 1 Simulator replicates the I
Unit I . control room environment with differences as- noted. The-plant communication systems that an operator needs to communicate t with an- auxiliary operator or other-in plant support activities are present and opera'tional in the simulator. This_ communication.- equipment includes Bell Telephone, plant paging system, PAX phone , i and system- operator phone. The plant's- radio system is physically simulated but not operable. All- annunciator panels are operable and have identical tones as the-Unit I panels'. O . I e t i i
1 I l 1.2.4A l 1 I Existing differences in Controls Area Environments are: BVPS 1 Simulator BVPS Unit I
- 1. Computer flooring Carpet covered
- 2. Limited AC emergency lighting DC emergency lighting
- 3. Flourescent lighting Non-glaze full spectrum tube lighting
- 4. Unit 11 simulator will be Unit II control room sepa-installed in a separate building rated by glass partition
- 5. Small video camera and several Four large overhead T.V.
small overhead microphones cameras
- 6. Phones - 1 Bell,1 system Phones - EPP direct ringdown operator (2), Mansfield (1), Red NRC phone (1), Bell phones (4)
(3 Q 7. No noise upon CREBAPS initiation Air in-rush noise upon CREBAPS initiation l
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l 1.2.4B Resolution of Environment Differences
- 1. The actual control room floor was fully carpeted in 1988 to reduce overall noise. The simulator floor is standard computer flooring, and has remained uncovered. Committee determined that there was no training impact involved with this item and recommended no furter action.
- 2. Simulated emergency lighting is limited to partially deenergizing normal fixtures. This adequately lowers lighting levels during evolutions involving losses of associated power sources.
Committee recommended no further action.
- 3. Actual control room flourescent fixtures were recently relamped using non-glaze, full spectrum tubes. As a result, the existing simulator ambient light level is relatively brighter. However, this does not detract from training. Committee recommended no further action.
- 4. Since the Unit 11 simulator was not planned as part of the original Unit I simulator building layout. The Unit 11 simulator will be located in an adjacent building. Since simulator exercises involve phone or page communication between units,
. " visual contact is in not necessary. Committee recommended no further action.
- 5. The simulator video camera and microphones are used to record crew performance for reviews and critiques. The four large cameras in the actual control room were originally used for remote ERF (Emergency Response Facility) viewing of control s during abnormal / accident conditions.
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=1.2.48 (Con't)
These cameras are currently . retired in place. The size and appearance difference Les not -affect operator line of-sight. Committee determined there was no training impact and recommended no further-action.
- 6. Although the simulator telephone capability is less than the control room, adequate equipment to all support activities. (via~
instructor booth) is supported. Currently, plans are to install multiple phone channels to simulate calling specific groups; this will enhance the simulator instructor's . ability to act - as these groups / individuals. Also, the committee recommended that a non-functional Red NRC phone be acquired, if available, and installed on the communications console.
- 7. Control Room Emergency Bottled Air - Pressurization System <
(CREBAPS) actuation in the control room yields a noticeable sound. CREBAPS actuations on the simulator result in changes in . associated control and indications. The committee felt that the lack of audible noise upon initiation had ilimited training impact.- The committee recommended the' installation of simulated noise. (CR-77) i I l O
1.3 Instructor Interface 1.3.1 Initial Conditions The Beaver Valley Power Station Unit 1 Simulator has 30 protected initial conditions with the capacity of an additional 24 initial conditions to be used by the instructor when required to store non-protected initial conditions. Additionally, the simulator has backtrack capabilities to backup the simulator from 5 to 30 minutes. A list of i'itial conditions can be found in Appendix 1. O G n V
i 1.3.2 Malfunctions The Beaver Valley Power Station Unit 1 Simulator presently has approximately 200 malfunctions. These malfunctions can be entered in sequence or simultaneously. The insertion of malfunctions cannot be detected by the trainee on the floor. The number of malfunctions can be expanded to approximately- double the current number or approxmately 400. The Malfunction Test Abstracts are included in Section 3.0. The Malfunction ' st Abstracts provide a brief overlook of variations, ramp time, leak magnitude and provides initial and final conditions.
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The malfunctions available on the simulator to create the conditions required by the ANSI /ANS-3.5 1985, Section 3.1.2 follows: Simulator Halfunctions ANSI /ANS-3.5-1985 corresponding to the Section 3.1.2 ANSI reouirement
- 1. Loss of coolant:
a, Significant PWR S/G tube leaks a. RCS-3
- b. Inside/outside primary b, RCS-1, RCS-2, containment RCS-4, RCS-5 RCS-6, RCS-7, CHS-3, CHS-11, CHS-12, CHS-16 SIS 13, CCW-9, CCW-2
- c. Large/small Rx coolant c. PRS-5, CRF-6, breaks (including saturation RCS-1, RCS-2, condition)
- d. Failure of safety / relief valves d. PRS-1, PRS-2, PRS-3, PRS-4 O
Simulator Malfunctions , ANSI /ANS-3.5-1985 corresponding.'to the Section 3.1.2 ANSI reouirement~
- 2. Loss of instrument air to the 2. _ AUX-l =, AllX-2, extent that the whole system or AUX-3, AUX-4, i
individual headers can lose' CCT-1, CCT 3,- pressure and affect the- plant's CCT-4
= static or dynamic performance.
7
- 3. Loss or degraded electrical' power - 3. EPS-1, EPS-2, to-the station, including loss of - EPS-3, EPS 4, offsite power, loss of emergency EPS-5, EPS-6,;
power, loss of emergency generators,- EPS-7, EPS-8, loss of power to the plant's EPS-9,.EPS-Il, ( electrical distribution buses and EPS-13,- EPS-14, loss of power to the individual EPS-17,-EPS-12, : instrumentation buses (AC as'well EPS-15, EPS-16, a as DC) that provide power to control EPS-18,:TUR 5,- room indication or plant control ~ TUR-4', _ TUR p functions-affecting the plant's - response.-
- 4. Loss of forced core coolant flow 4. RCS-5, RCS-6, i- due to single or multiple . pump -RCS-8, RCS-9, failure. .RCS-10 O
1
)
Simul ator . Mal funct' ions = - i
; ANSI /ANS 3.5-1985 corrresponding to the .
t Section 3.1.2 ANSI reouirement
- 5. Loss of condenser vacuum-including 5. AUX-6, CND-8, loss of condenser level control.- CND 9, CND-12,-
CND-13, CND-1, CND-17, CND-18
- 6. Loss of service water or cooling 6.- AUX 10,. AUX-12 to individual components
- 7. Loss of shutdown cooling 7. RHR-1, RHR-2, RHR-5
- 8. Loss of component cooling system - -8. . CCW-2, CCW-4, or cooling to individual components CCW-5, CCW 1, -- ;
CCW-6, CCW-3, CCW-8, CCW ' AUX-10, AUX-12 l
'9. Loss of--normal feedwater or - 9. CND'-l ~,CND 3; normal feedwater system failure - CND 14, FWM-1, FWM-2,.FWM-3, FWM-5 ~, - FWM-4, FWM-6, FWM-7, FWM-8, FWM-9 O
r
, , - - . . - , , - - - . . . . . ~ - . .
k Simulator Malfunctions
;h-. ANSI /ANS-3.5-1985 corresponding;to the Section 3.1.2 ANSI- reauirement-
'i 10.- Loss of all feedwater (normal 10.- FWM-ll, FWM 13, and emergency) FWM l' CND-1, , I
' MSS 11. Loss of-protective system channel 11' . RCS-14, RCS-16, RCS-19, PRS-6..
PRS-8,. SIS-10 -
- 12. Control rod failure including stuck 12. CRF-4,-CRF-5, rods, drifting rods, rod. drops, CRF-11, CRF-3 I and misaligned _ rods. .
- 13. Inability to drive control-rods 13. -CRF-2, CRF-6, l
- 14. Fuel cladding. failure resulting in: -14. RCS'll'-
high activity in reactor coolant' or
~
t off gas and the assc 1. Rd high-radiation alarms
' 15. Turbine trip '
- 15. ,TUR-1,,TUR-8, TUR-6 n .
a y= + , . v,-- --rw,~., , --..,,-ve ,,,.--e ,,
H
~
Simu1ator Malfunctions- I ANSI /ANS-3.5-1985 corresponding to the Section 3.1.2 ANSI recuirement 4
- 16. Generator trip 16. EPS-18
- 17. Failure in automatic control Il7. CRF-6, CRF-7, system (s) that affect reactivity CRF-14,= SIS-8,- '
and core heat removal CHS-7, CHS-8,- CHS-9, CHS-10i CHS-20', CHS-17, CHS-19
- 18. Failure of reactor coo _lant pressure 18. CHS-1,:CHS-2, '
i and volume control systems (PWR) =CHS-4,- CHS-5, CHS-6, CHS-13, CHS-14,-CHS-15, CHS-21, CHS-22, CHS-24,-PRS-7, I PRS-13 , l.
- 19. Reactor trip- -19. CRF 1.
l l
- O i
(
--w- .,3- - y v.w.. -- w- , ,,,--,w+ , , , -,--~-..--m, - , -
Simulator Malfunctions i ANSI /ANS-3.5 1985 corresponding to the Section 3.1.2 ANSI reouirement 20.- Main steam line as well as main - 20. -MSS-1, MSS-2, feed line break (both inside'and . MSS-6, MSS-12, outsidecontainment) MSS 17, FWM-3, FWM-4, CND-3 NIS-1, NIS '
- 21. Nuclear instrurentation failure (s)_ 21.
NIS-3, NIS-4, NIS-5, NIS-6, NIS-7, NIS 22. Process instrumentation, alarms, 22. MSS-14,: MSS-15, and control system failures MSS-16,' MSS-9,
-MSS-7, MSS 10, l MSS-11, MSS-12, MSS-13, EPS 6, l EPS-8, CRF-6, CRF-7, CRF-8, L CRF-10, .FWM-'14, FWM-15, FWM-16
)
Simulator Malfunctions () ANSI /ANS-3.5-1985 corresponding to the Section 3.1.2 ANSI reaulrement
- 22. (Con't) PRS-6, PRS 7, PRS 8, PRS-9, PRS-10, PRS-11, PRS-12, PRS-13, RCS-15, RCS-17, RCS-20, TUR-18, TUR-12, TUR-14, RHR-3, RHR-4, SIS-14, RCS-18
- 23. Passive malfunctions in systems, 23. SIS-13, SIS-11
() such as engineered safety features SIS-7, SIS-4, feedwater systems SIS-1, MSS-17, FWM-13 A
- 24. Failure of the automatic reactor 24. CRF-12 trip system
- 25. Reactor pressure cor. trol system N/A BWR failure O
V
1.3.3 Controls orovided for comoonent operation outside of the fT control room. U l The Unit I Simulator has the capability .to duplicate -the ' actions taken by operators outside the Unit I control room during normal and emergency operations. Appendix 2 is a listing of Local Operator Actions (LOA's) for the Unit I simulator. 4 O l l 1 l O
1,3 4 Additional special instructor /trainina features available-
- a. Backtrack As previously mentioned, the-Beaver Valley Power - Station-1 i Simulator _ has . the capability _ ' of ,
backtracking. Normally, the j students can - be backtracked anywhere from 5- to 30 : minutes. However, the time frame for tracking the backtrack snapshots is adjustable so that, if the= instructor desires, he can offer a _ backtrack capability - of 6 discrete steps. The' time - between discrete step is-variable, but .is- normally set- at 5 minutes..
- b. Freeze The Beaver Valley Power - Station Unit-1 Simulator- has the capability to freeze -the dynamic
- simulation.
- c. Simulator Speed- The Bever- Valley -Power -Station--
Unit 1 s i mul a tor- -h a s .- t h e: capability to vary the speed - of - simulation. O 4.
. - - . - - . . . . . - . - . - . . - - . - - . - . - . . - - . - , . - . . - . - . . . - - . . . - . . ~ . - . . - - - . -
[ 1.3.4 (Con't) This feature can- be usedi to slow
't down the simulation to allow the observation of- parameters at less than real. time for training 4 7 discussions and for model trouble shooting.-- - The . simulator
'has the capability for fast-time, but this. - capability . _is limited- to specific = models,' ie.
Xenon, RCS and pressurizer heatup rate,
- d. Override .The. Beaver Valley Power Station- _
Unit 1 - Simulator' has the O c P 8414t> er < 414#9 er 1 control board panel control switch or : light either in- the on-or off -' position. In: addition, each control' board- meter can be overriden to various positions.
- e. Annunciator. The' BeaverL Valley - Power Station
-Unit l' Simul a to r- h a s: ..the -;
capability of: failing any- driven-annunciator either on or off. ; o e i
+,,-n..-..e.,n,,,7... , , , , . . , ;,.,,,. , . , , _.,...w,_,,s. nam,_,,,.. .,,w,,+,,-,,,,,,y'., .--c.s,.....,m . , , . . . e
1.3.4 (Con't)
;G f. Plant The Beaver Valley Power Station Unit \j Parameters 1 Simul ator .al so uses plant parameters which give the instructor the flexibility to modify parameters which are outside the operating staff's control. Examples include atmospheric temperature, pressure and river water temperature. This feature is primarily used for the setup of initial conditions.
- g. Local Operator The Beaver Valley Power Station Action Unit 1 Simulator has the capability l which enables the instructors to operate selected remote valves, pumps, air compressors, etc. -The LOA listing is included in Appendix 2.
l h. Remote Control The remote control device permits _the instructor to initiate various commands from the simulator floor. Which provides him additional , opportunity ' to interface with the students.
l.3.4 (Con't) C)
\J Some of the remote control devices keys (e.g., run, freeze, horn on/off, and annunciator acknowledge) provide direct simulator response without any.
advance preparation at the instructors console preparation at the console keyboard. The other 12 keys, however, must be assigned at the instructor's console. O O
1.4 Operatina Procqdures for Reference Plant Simulator training is performed using the Beaver Valley Power f] Station Unit 1 operating procedures for all normal, abnormal and emergency operating procedures. Therefore, there are no significant differences. o u
1.5- Chanaes Since initial Delivery The following = list is _ the Change Requests -which have been-installed -in the Beaver Valley Power Station Unit I simulator as a result of design change packages or training requests to facilitate training-l There are currently change requests being tracked by the Simulator Data Base Tracking Changes and Modifications- procedure . -! which is presented in Appendix
~
5._ Change Requests can exist in several conditions: in-progress, under review, . waiting installation in the plant or cancelled. The following list is the Change Requests which have been fully implemented in the Beaver Valley Power Station Unit I Simulator. O O
O BVPS UNIT I SIMULATOR INSTALLED CHANGES s Change Date Number Comnleted Description 01/19/90 Simulator Annunciator Window Changes 2 05/23/85 Reactor Protection System Inhibit 3 11/07/86 Annunciator Window Changes-4 10/22/85 A & B USST Tap Changes 5 08/08/85 Removal of Emergency Bus Supply Brk U.V. Lockout 6 11/04/85 Modified S/G Trip Valve Logic 8 09/06/86 Adjusted Stroke Time for Feed Water Recirc Valves 9 10/22/85 Diesel Air Compressor Unloader Addition i 10 09/06/85 Added-Boron Concentration to-Containment Model 11 10/18/85 Aux Fw Flow Control Valve Stroke Time 12 08/23/85 SI-Actuation Status Light Logic Change 13 18/23/85 PORV Open Alarm logic 15 02/05/87 MSIV Closes--an Loss of Air 16 10/22/85 Loss of Chill Water to Containment Air Compressors 17 10/22/85 ' Added Out of Service Control Room Annunciators 18 10/17/85 Turbine Trip. Logic-Change 20 10/17/85 Turbine Lube Oil System-Trip ~Setpoint 21 10/18/85 _ Reorganize LOA File 23 06/16/88 Under Voltage Reactor. Trip Power Supply Change 24 08/26/86 New S/G Blowdown System Installation 25 04/30/87- Added Dedicated Aux-. Feed Pump-and Tank 26 08/26/86 Added Black Diesel 28 04/16/87 Removed . Reactor Trip / Trip Open Signal to-Steam Dump logic-29 01/14/86 IRPI Power Supply Back Up Addition 30 01/14/86 Aux Feed. Pumps Auto. Start ~ Logic Change 31 04/09/87 -Power Range NIS Rate Setpoint Change 32 06/11/87 EDG Governor Valve-Indication Change-34 01/08/87 Added ReactorL Trip -Breaker Position-
-Indication.to: Bench Board-36 03/17/86 Control Room Air Bottle Indication Change -
37- 03/17/86 Malfunction ~CCW 2 Logic Change 38 03/17/86 Change Rod Drop Alarm Power Supply 39 03/17/86 Change Rod Bottom Light Power Supply
- - l 40 03/17/86 Rad: Monitor. Response After Being Isolated l 41 03/17/86 Aux _ Steam Condensate Rad Monitor Logic l Change 1 O 42 43 03/26/86 03/26/86 Dump: Control Power Supply Change Steam Dump Logic Change l
v , Change Date Number [.omol eted Descriotion 44 03/26/06 SI Accumulator Drain Down Effects 45 04/01/86 Flow Transmitter Power Supply Change 46 08/03/87 PAB Auto Sprinkler Protection Annunciator Window 47 04/07/86 Added Anti Motoring Turbine Trip 49 05/01/86 Malfunction RCS 19 Loop Flow Failure 50 04/18/90 Improve Response of Feed Water Bypass Valve 52 01/13/89 Added Control Room Rad Monitor 54 03/06/87 Changed Condensor Vacuum.Setpoint 56 05/08/89 Inadequate Core Cooling Monitor 57 01/09/87 Install Core 6 58 07/30/87 Added Turbine Supervisory Instruments 59 01/08/87 CH142 Position Ind Lights Addition 60 03/28/89 Delete PT-BR-102B/111 Instruments 61 06/13/88 Added Refueling Cavity Annunciator Alarm 62 04/15/88 Added AMSAC System Logic 65 08/10/87 Added Aux Building Ventilation Flow Recorder 67 02/10/88 Loose Parts System Removal 68 03/20/89 Instrument Air Dryer Installation a 70 02/25/88 Added Steam Header Rad Monitors V 71 02/08/88 Changed Containment Pressure Setpoints ! 72 02/08/88 Added Inverter Static Switches to Electrical Model 73 04/14/90 Main Feed Pump New Impeiler 74 03/14/88 Fast Bus Transfer Logic Change 76 04/07/90 Heater Drain System Pressure Reduction 79 02/29/88 P-9 Setpoint Changed l 81 06/30/88 Aux Steam Supply Added from Unit 2 82 07/19/88 CNMT Press & RWST Level Setpoint Change 83 02/19/89 NIS Miscellaneous Drawer Added Plexiglass Plate 84 08/22/88 Simulator Running Lights Removal 85 01/20/90 SPDS Color Hods 86 09/19/88 MFR Valve Stroke Time Chango 88 01/13/90 Modify Core Bypass Flow 91 101/2/88 Chlorine Leak Detection Logic Addition 94 04/20/90 SPDS/ Bailey Terminal Clear Screen 95 01/05/89 SG Level Shrink / Swell Effects 96 01/29/90 Auto Spnkl Protection Annunciator Wir. Cow 97 02/07/89 AFW Initiating Signal Deletion 98 04/07/90 STM/FW Flow Selector Switches 100 02/08/88 DC Bus 1-5 Battery Breaker Trip Logic Change 103 05/03/89 Malfunction RCS 15 & 17 Increase Range A of Malfunction V
1 i O Change Date Number Completed Descriotion 109 01/13/90 RWST Setpoints Changed 110 01/13/90 Turbine Overspeed Protection Controller 111 01/29/90 Turbine EHC Controller Modification 112 01/18/90 Unit I Core 8 Upgrade 113 01/19/90 Simulator Limits Alarm , 114 10/27/89 Instructor Booth Recorder Power Supply Switch 116 01/11/90 Annunciator Window Labelling 126 04/14/90 Added L.0.A. for MOV-lFW-150 A & B 128 04/07/90 Switch Check Addition O v . f f%
'%/
- 2. Simulator Desian Database Information from which upgrading has been based and will be based for future changes is primarily plant design change information generated from the plant's engineering section. The procedure is included in Appendix 5 Data Base Tracking Information supplied to the vendor from which the simulator was designed is included for reference within this section.
O a [G l l
VENDOR TECHNICAL MANUALS TITLE Unit I Instruction Book Index Air Operatead Control Valves (7.62) Air Operated Control Valves (7.65) Air Operated Control Valves (7.62) Aurora vertical Submerged Pumps Autotransformer (1.81-28A) Autotransformer 2-4 Renewal Parts (1.1-3A) Auxiliary Boiler Chemical Feed Pump & Phosphate Feed Pump (2.72) Auxiliary Boiler Condensate Pump (2.45) Auxiliary Boiler Fuel Oil Pumps (2.44) Auxiliary Feed Pcmp Turbine Drive (2.18) Auxiliary Heat Exchanges (4.10) Auxiliary Steam Generating Equipment (Erle City) (5.50) Auxiliary Steam Generating Equipment (Zurn) (5.50) d Back-Panel Remote Alarm (7.71-2) Blowdown Drain Heat Exhanger (4.20-73) Booster Pump or Vacuum Deaerator (PG-P-1) Pump & Motor (1/29-22A) Boric Acid Transfer Pumps (2.30) Boron Injection Recirculation Pump (2.54) Boron Recovery and Liquid Waste / Misc Pumps (2.38) Boron Recovery and '..'aste Disposal Evaporation Circ Pump (2.34)- Boronmeter (3.41-1A) Carbon Steel Valves 1-12" and Larger (6.48) l
.O U
l i
1 l VENDOR TECHNICAL MANUALS- ; TITLE Centrifugt.1 Fans (10.1-13A through 186B) Centrifugal Fan Unit Heaters (10.1) t Centrifugal Fan Unit Heaters (10.1-478) ; Centrifugal Fan Unit Heaters (10.1-223A) Centrifugal Pumps - 16 x 18 x 24 B (2.40)- Centrifugal p M P - (2.25-100A) Centrifugal Water Chillers (iq.1-56A) Centrifugals (2.11) Centrifugals (2.82) , Ceramic Heat Pipe Heat. Exchanges (1.30-348) Charging Pumps (2.31) Charging & Safety Injection Pump I Chilled-Water Cire Pumps A/C Cond Water Booster PJMP (2,52) Circuit Breaker - 345 KV (1.83-228) Circulating Water Flow Instruments (BV-737) (7.11) Class IE Instrument Design and Test Requirements.(7.72-235) Class VOC Pumps _(2.39) Composite Instruction Bok for Foxboro Equipment (7.75) Composite Instr Manual- for Trans & Indicator: '(7.71, 7.72, 7.73) , Composite Instr Manual for Pressure & Flow Trans (7.71, 7.72, 7.73 Computer Systems (7.50-10A) CondensatePumps(Byron-Jackson)-(2~41). Condensate Pumps (Ingersoll Rand) (2.41); Consolidated Safety Relief Valves (6.39) Containment Recirculation Spray Pump --Inside Containment (2.51) Containment Recirculation Spray Pump Outside Containment (2.51A) O
VENDOR TECHNICAL MANUALS TITLE Containment Vaccum Ejector (2.99) Containment Vacuum Pump (2.43) Control & Protection Instrumentation System - Volume 1 (7.701B) Control & Protection Instrumentation System - Volume II (7.70) Control Rod Drive Mechanism Connector Crimp Procedures (1.28-261A) Control Systems for Auxiliary Steam Generating (5.50) Controlled Leakage Pump Test Report (1.10) Cooling Tower Pump Motors (1.10-101 A) Cooling Tower Pump Motors (2.42) Cyclo-Phram Metering Pumps (2.39) Cyclo-Phram (R) Pumps (2.39) Diesel Driven Fire Pump (10.1 25-39A) (q/ Diesel Generator Ground Switch (1.28-55A) E-H Control System - Volume Ill - Book 1 (2.13) E-H Control System - Voluem 111 Book 2 (2.13) E-H Controller Option List (2.1315A) Electro Motive Power Specifications (1,30 32A) Electric Motor 0perated Gate Valves (6.48 92A) Electro Pane Annunciators (5.50) Emergency Diesel Generators 999 System (130-30A) Environmental Radiation Monitor (7.503) Feedwater Control Valves (6.26) feedwater Control Valves (7.81) Feedwater flow teinents (7.19) Feedwater Heaters (4.22) Fesdwater Vibration Monitoring Procedure (1.55 6) , O l 1 l
L v VENDOR TECHNICAL MANUALS TITLE Field Assembly of Multi-Piece Stator-Main Generator (1.13-124A) Fire Protection Pressure Main Pump (10.1) FlowIndicatorMeter(7.131A) , Flow Instruments (7.71) Flow Sight Glasses (7.17) FluxMappingMiniatureDetectors(1.213A)
- Full Length Control Rod Drive Mech (5.15)
Full Length Rod Control System - Volume 1 (5.10) ! Full Length Rod Control System - Volume II (5.10) Full Length Rod Control System - Volume III (5.10) Gate Valves, 20" L9000, 16" & 6" L900 (1.25) General Step Up Transformer (1.14 89A) Gylcol Chilled Water Heat Exchangers (10.1-261A)- Heat Exhangers (1.30 4A) Heater Bypass Control Valve (7.67-58 A) HeaterDrainPumps(2.41) Heavy-Duty Single Stage Compressors (2.62) High Pressure Feedheater (4.22) High Range Contaiment Monitor 875(1.56198) Hot & Chilled Water Centrigugal Pumps (10.1-ll5A throughIl8A) Hot Water Heating System Heat Exchangers (10.1 263A) : Hot Water Heating System. Heat Exchangers (10.1 264A) Hydrazine', Morpholine & Phosphate Feed Pumps (2.39) Hydrogen Containment Monitor (5.31-26) Hydrogen Inner cooled Turbine Generator (1.13-124A) Hydrogen Inner-Cooled Turbine Generator (2.15, 2.14, 2,13,1.13) O
-y y ., 7.--.+ y- y,n g ,,-,-,.-cw,+.-. n --y , .,gA,s -
- - , w. - , . e , y -;.."- w ,c-,..-,
! I t VENDOR TECHNICAL MANUALS TITLE 4 l Hydrogen Inner Cooled Turbine Generator (2.14) Hydrogen Recombiners (4.31)_ In Core Instrumentation - Volume I (7.79 through 12) In Core Instrumentation - Volume II (7.79 through 12) Indicating & Recording Pressure Gauges (7.34) Induction Motors (1.28-257A) Inside Recirculation Spray Pump Motor (1.10 Il8A) Installation & Maintenance Instructions for Nuclear Valves (6.43) , InstrumentTransformers(1.18123A) Instrumentation & Control Block Diagrams (7.7) Large AC Motors Vertical Induction Motor (1.10) targe Motors (1.10) Large Motors & Generator (1.10) Linear Mass Flow Meters (7.503) V Local Pressure Indicators (7.33 25) Low Head Safety injection Pump - Ingersol Rand (2.29) Low Head Safety Injection Pump - Westinghouse-(2.29) Low Pressure Carbon Dioxide Fire Protection System (10.1-2888) Magnetic Amplified Controlled Voltage Regulator (1,30 36A) Magnetic Flow Meters (7.19) Main Control Board Instr, Flow Press & Level Vol ! l (7.1through7.5) Main Control Board Switches (1.12-140A) Main.SteamAtmosphereDumpPumps(6.49) i MainTransformer(1-1488A) ! Main Transformer (1-14 91A) Manually Operatead Bellows Valves -(7.45) O u i
) l l ! VENDOR TECHNICAL MANUALS TITLE Mechanalysis Mcdels 1224 & 1225 Vibration Monitoring (7.551) ! Miscellaneous Pumps (2.30) Model 999 System Generating Plants (1.30 35A) Model 3196 STD & 3197 STD Pumps (2.20) Model XS & XSL Self Priming Centrifugal Pumps (2.65) Model Control Center Install, Oper, Main Instr (1.16 78A) Motor Control Centers (1.13) ; Motor Equipment (1,10) Motor Operated Angle Stop Valves (6.48) Motor Operated Valve S 867A, B (6.48 108A) Motor Operated Valve QS 104A, B (6.48 112A) Nameplate List 125 VDC Switchboards, 1 5 (1.26-6BA) l Nuetron Shield Tank (3.61) NuclearCountingSystems(7.503) m Nuclear Instrumentation Manual (7.781A) Nuclear Instrumentation System (1.21214A) Nuclear Steam Supply System Startup Manual - Volume I (5.10) Nuclear Steam Supply System Startup Manual Volume II (5.10) Nuclear Steam Supply System startup Manual - Volume Ill (5.10) Nuclear Steam Supply System Startup Manual Volume IV (5.10) Oil Circuit Breakers - 138 KV (1.84 5A) Operating Procedure for PWR Hydrogen Control System (4.31) P250 Computer Continuous Monitoring Systems SG-2 Series (7.9311A) P250 Computer Software Manual (7.93-6A) P250 Process Computer System Design Information Part III (7.93) O i
a l l
- I j VENDOR TECHNICAL MANUALS TITLE Part length Control Rod Driven Manual Model 121J001 (5.15)
, Part Length Control Rod Driven Manual Model 121J380 (5.15) i Perfortrance Curve for A/C Chilled Water Unit 500HP (1.10 52A) Pows: Plant Motors (1.10) Power Range Uncompensated lonization Chamber (1.20-467A) PressureIndicatorSystem(7.338A) Pressure Transmitters - Model 1153(7.31-25) Pressurizer - 1400 Ft (4.15) u Pressurizu Relief / Safety Valve (6.39-24B)- Pressurizer Spray Valves (7.83-108) Primary Plant Component Cooling Heat-Exchangers (4.11-0)
~
Primary Plant Cooling Water Pumps (2.27) Primary Water Storage Tank Heaters $ Pumps (2.222.24) q Radiation Analysis Design Manual (5.12)- l V Raw Water Pumps (2.42 21) Reactor Coolant Loop Stop Valves (6.44) Reactor Coolant Pump, Controlled Leakage Seal (2.31)' Reactor Coolant Pumps (2.31) ReactorTripSwitchgear(1.ll-235A) Reactor Vessel (5.11) Recirculation Spray Water Cooler (4.21) Refueling Water Circulating Pump (2.30 38) Refueling Water Pump (2.30)-
. Residual Heat Removal' Pumps (2.28)
River Water Pumps (2.42) Rod Control Cluster Change Fixture -(2.101) Rod Control Reactor Trip Switchgear (1.20 493A) Rod Position Indication System (7.75)- Seal Injection Pumps (2.42-24A) O
1 VENDOR TECHNCIAL MANUALS TITLE l Seal Maintenance Feasibility Study of Model 93A RCP (2.31) , Secondary Component Cooling Water Pumps (2.27) j Seismic Acceptance on Poorly Welded TB Support - BB A 4 (1.12 150A) l Seismic Qualifications, MCB Vertical Sections (1.12137A) Sequential Event Recorder - Model 5000(1.2371A) l- Series &Chempump(4.18) : Soft Wtr Chlorination Booster, Seal Wtr & Brine Sol. Pumps i (2.30) Source & Intermediate Range Housing (1,20 468A) ; l , Speed Torque Curve or A/C Chilled Water Unit Motors (1.10-53A) { Standard Program Descriptions (7.93) Steam Flow Elements (7.71 1A & 2A) Steam Generator - 51 Series (4.13) Steam Generator Auxiliary feed Pump (2.40) O Steam Generator Drain Pumps (2.49) Steam Turbine Auxiliary Equipment - Volume I (2.10-2.17) Steam Turbine 7.uxiliary Equipment Volume 11 (2.10 2.17) l StorageTankHeaterPumps(2.3023A) Storage Tank Heaters (4.20 5B) Switchboard Watthour & Demand Meters (1.50 56A) l SwitchgearDiagramLegend(1.1512B) Switchyard (1.75) Technical Support Complex System Installation Guide (1.22 354) , j Temperature Switches (7.46-1A, 2A, 3A) Test Report for Steam Generator Feed Pump Motor (1.10-114A) Thermal Limit Curves - Auxiliary Feed Pump (1,10 46A) Thermal Limit Curves-- Circulating Water Pump (1.10 45A) Thermal Limit Curves - Circulating Water Pump (1.10 45A) l Thermal Limit Curves - Circulating Water Pumps (1.10 29A)- i O :
4 VENDOR TECHNICAL MANUAL TITLE Thermal Limit Curves Condentato Pump (1.10 47A) l Thermal Limit Curves - Heater Drain Pump (1.10-48A) Thermal Limit Curves Outside Recirculation Spray Pump j , (1.1030A) Thermal Limit Curves - Outside Recirculation Spray Pump (1,1043A) Thermal Limit Curves Primary Plant CCW Pump (1,10 44A) Thermal Limit Curves - Raw Water Pump (1.10 41A)
. Thermal Limit Curves - Secondary CCW Pumps (1,10 40A)
Thermal Limit Curves Steam Generator Feed Pump (1.10 42A) Thermowell Actuated Temperature Indicators (7.43) Transistorized Annunciator System, Series 5000 Constalert (1.23) i Turbino Generator Prese,vation Manual Nuclear PWR Units (2.10-2,17) Two Step Demineralizer Volume 1 of 2 (2.68) Two Step Demineralizer -. Volume 2 of 2 (2.68) Two Way Internal Pilot Operated Solenoid Valves (7.66). Type EKC 2 Oil Switch (1.28 154A)' Type RG/RGS InGuction Motors'(1.28 256A)- Type W SW - Board item 20(1.12-135A) Unit Station Service Transformer (1,14-46A) Vaccum Priming Pump (2.43) Valveline Mark 1 Motor Control (1.16 6A) Valve Operators (6.47) , Valve Positioner and Motion Transmitter (6.49) Velan Motor Operated & Manual Valves-(6.43 5B 80) Vibration & Loose Parts Monitoring System (1.55 30A)' Virbation Testing & Analyss of 7700 Line (1.16) Volume Control Tank (7.83) Wafer Type Butterfly Valves - 8",14",16",(6.42)
.i i
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- MU ZOE Operating Manual l Model 999 System Generating Plant (1.30-328)
Special 999 Operating Manual (1.30 302)
- Operating Manual 999 System (1.30 298) j Bailey Controls - Human Communications Functions- _i
- Bailey Controls 1055 Sys. Point Data Base Description
. Bailey Controls Plant Variable Computer System Bailey Controls - Graphic Displays D'.a Base Master input File Inplant Computer Log Characteristics
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1 VENDOR TECHNCIAL MANUALS TITLE Tank Sump Level / Capacity Data Precautions, Limitations, Setpoints for NSSS - Reactor Control & Protection i 1 Reactor Excore Instrumentation Incore Instrumentation. System i Plant Process Control System -j i Main Computer i Sequence of Events Computer
- Reactor Coolant System Chemical and Volume Control System Boron Recovery and Primary Makeup System l Reactor Plant Vents & Drains System ,
Risidual Heat Removal System Safety injection System Containment Vacuum l-O Containment Depressurization System ; Reactor Plant Sample System Turbine Plant Sample System Post Accident Sample System i Reactor Plant Component and Neutron Tank Cooling Water ; Supplementary Leak Collection and Release System l Liquid Waste. Disposal System l Solid Waste Disposal System
- Gaseous Waste Disposal . System.
i Fuel Pool Cooling and Purification System j Main Steam System Condensats System j Extraction-Steam System Heater Drain System Steam Generator Feedwater System : Steam Generttor Blowdown System' O
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f i I. ! VENDOR TECHNICAL MANUALS I + !] i I TITLE ! s Main Turbine & Condenser i p Auxiliary Steam ;
- j. Turbine Plant Component Cooling Water System
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i Chilled Water System r l River Water System ; l Circulating Water System - I l Water Treating Fire Protection System -l l Compressed Air Systems , i Main Generator and Transformer i ! 4KV Station Service System !
- 480V Station Service System i 120 V AC Distribution and Lighting !
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- Bldg Service Glycol Heating System i I
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Warehouse Steam Heating System l Sewage Treatment Plant ! Radiation Monitoring Systems ' Area Vent-Control Area f Area Vent Cooling Systems ; i Area Vent Containment [ Area Vent Auxiliary Building j Area Vent' Air Conditioning System j Area Vent Miscellaneous Systems- ' { l l l O !
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i 1 i VENDOR TECHNICAL MANVALS TITLE Miscellaneous Safety Related Systems i Post DBA Hydrogen Control System Containment l Conduct of Operations Reactor Engineering Procedures Station Startup Station Shutdown e General Operating Instructions Emergency Operations Abnormal Operating Procedures Station Logs Periodic Checks injury and Casualty Control Fire Prevention and Control lg Westinghouse P250 Computer inputs U Bailey 1055 Computer inputs Signal Instrument Listing for P250, Bailey 1055 and SPDS Techneial Specifications Bill of Materials Addressable Point Compiler Technical Support Center Operators Manual Technical Support Complex Maintenance Manual Nameplate. Indentification Control Board Labels - Volume 1 l Control Board labels Volume 2 Specifications for BVPS
- Control Room Annunciator Windows A 1 Control Room Annunciator Windows A-2 Control Room Annunciator Windows A-3 O
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MISCELLANEOUS INFORMATION TITLE Control Room Annunciator Windows A 4 Control Room Annunciator Windows A 5 , Control Room Annunciator Windows A 6 Control Room Annunciator Windows A 7 Control Room Annunciator Windows A 8 Control Room Annunciator Windows A-9 Control Room Annunciator Windows A-10 Control Room Annunciator Windows A-11 Control Room Annunciator Windows A-12 '
- Control Room Annunciator Windows A-13 Setpoint Study Inplant Computer Simulation Calibration Data - Volume 3 Calibration Data - Volume 4 Calibration Data Volume 5 Calibration Data Volume 6 Calibration Data - Volume 7 .
Calibration Data - Volume 8 Calibration Data - Volume 9 Calibration Data - Volume 10 Calibration Data - Volume 11 l Calibration Data. - Volume-12 l Calibration Data - Volume 13 Calibration Data - Volume 14 Calibration Data - Volume 15 Calibration Data - Volume 16 ! Test Results - Volume 1 Test Results - Volume 2 a Test .Results - Volume 3 Test Results - Volume 4 Test Results - Volume 5 O -
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- . MISCELLANEOUS INFORMATION h-U TITI.
Test Results - Volume 6 Test Results - Volume 7 Test Results - Volume 8 Test Results - Volume 9 Data Void Requests Design Specifications P250 Process-Computer System - Design information , Preliminary Installation and Instruction Manual for Radiation l Monitoring System &
.Victoreen Instrument Division - Radiation Monitoring System Instruction Manual ,
Complete Set of. Plant Logics Heat Balance Diagram l Final Safety Analysis Report O I J
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- 3. Simulator Tests O General Test Guidelines The certification testing program is controlled by the procedure presented in the Nuclear Group Training Administrative Manual Vol. II Section 12, Simulator Qualification Tests. This administrative procedure was used for the initial Certification Testing Program. An abstract of the procedure is provided for reference below.
A. PURPOSE This instruction outlines the method used to ensure that the Beaver Valley Unit i Simulator meets qualification standards based on the requirements of AN51/ANS/ 3.5 (1985) and USNRC Regulatory Guide 1.149. The purpose of these requirements, and the qualification testing program as a whole, is to O est e>4,8 eeae te s4 1 ter Perrer ece cr4ter4 eecess r> <er errect4ve training. B. DEFINITIONS
- 1. Best Estimate Reference plant response data based upon engineering evaluation or operational assessment.
- 2. Critical Parameters
- a. Those parameters that require direct and continuous observation to operate the power plant under manual control,
- b. Input parameters to plant safety systems.
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- 3. Real Time Simulation of dynamic performance i n the same time base
; relationships, sequences, duration, rates and . accelerations as l l
! the dynamic performance of the reference plant..
- l i Reference Plant l 4.
t Beaver Valley Power Station Unit I was the reference plant from
- which the simulator control room configuration, system control, l arrangement and simulator design data was derived. ,
- 5. Neantive Trainino-Simulator responses that - would/could cause- the operator to misdiagnose the transient in effect. ;
C. PROCEDURE This instruction is divided into four major areas of simulator l qualification testing, defining each test procedure per ANSI /AW- ?. 5 l (1985) and/or Reg. Guide 1.149, Rev. 1 (1986). ,
- 1. Simulation Real Time Test A simulation real time test shall be conducted annually to ensure I
that the simulator operates in real time. ! This test shall be conducted in accordance with the Simulation ; Real Time Test Procedure (SQT-1.0) and documented per Section F. i
- 2. Steady State r,J Normal Operations Tests Simulator- s teady state drift tests- shall be- conducted annually to ensure that the steady st' ate parameters do not exceed the 2% -
L tolerances of Beaver Valley -Power Station Unit I critical j i l parameters and 10% of noncritical parameters. . t O :
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l' Normal operations tests shall be conducted annually to ensure that the simulator operates- in accordance with selected plant i operating procedures. These tests shall be conducted in accordance with the Steady State / Normal Operations Test Procedures (SQT-2.0). l Steady state drift tests shall be conducted at approximately 35%, 75% and 100 % power, or where data is available. The steady j state drift test at 100% will be sustained - for - a continuous duration of at least 60 minutes. Normal operations tests shall 4 use Beaver Valley Power Station Unit- 1 normal operating procedures and/or operating surveillance tests as the comparison i standards for sinulator I -formance. l These tests shall be documented per Section F of this procedure.
- 3. Transient 1ests simulator transient tests shall be conducted annually to ensure s
that the simulator transient response is similar to the expected i response as indicated by actual reference- plant results, design data, best estimate, or operational analysis, i All required transient tests shall be conducted at 100% steady state power, equilibrium xenon and decay -heat, and with - no 4 operator actions, except the main; turbine trip, which shall be1 conducted at less than permissive P-9. These tests shall be conducted in accordance with Transient. Tests-Procedures (SQT-3.0) and documented per Section F.
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l ) - l- 4. Malfunction Tests ] Simulator malfunction tests shall be conducted on a four year , cycle (25% of the tests will be completed annually) to ensure t i that proper simulator resoonse and system interaction is obtained , l for all generic malfunctions. Response shall be compared to the ! reference plant, best estimate or operational assessment. [ i These tests shall be conducted in accordance with Malfunction ; ! Test Procedures (SQT 4.0) and documented per Section F.
- D. IEST METHODOLOGY The Initial Certification tests were generally performed using a designated Certification Pack. This certification. pack was frozen at 3
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- the commencement of the testing cycle, with no further changes to the
; software being.made. Some exceptions-to this methology were necessary I
because of hardware upgrades completed during the testing phase. . Example - Unit I simulator hardware was changed to: reflect a plant modification that removed the RTD manifolds and associated control l board hardware (meters, status lights,-etc.). -The malfunction testing associated wth these changes were performed on a t' raining pack that had been upgraded to reflect the removal of the RTO manifolds.
- 1. Simulator Real Time Test The . simulator real time test w;s. conducted. using the computer program OSPEXEC, which provide
- a continuous display of percent execution time for the simulation and peripheral tasks. .The test was run with all normal peripherals in service, and utilizes the (LOCA with loss of offsite power). DSPEXEC was continuously i monitored during the test to - verify that- percent execution remained at less than 100%
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- 2. Steadv State and Normal Operations Tests j The simulator steady state drift test was conducted by the use of j i computer program DRIFTEST. ,
i , This program: ) L ! a. Samples the desired data points (parameters) once per , ! 6 simulator model iteration. ! I b. Permanently records data to disk file or tape file. _ ! c. Provides a short form summary of data point maximum value, j
- minimum value, maximum deviation and message if - parameter
- i exceeds tolerances, j
- d. Provides long form printout of all data point values and l
] deviations from reference values, i t
- The normal operation tests consists of performing normal Beaver !
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- Valley Power Station Unit I operating procedures or operating i O >#rve41' ce te t> #8 ce a r4#9 the re>#it, te the ccePt ce criteria of the plant. j The following guidelines are utilized -during normal operations )
I
- testing:
0 Ar/ unexpected / unexplained alarms or indications. that-f occur should be noted and Trouble Reports initiated if .
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not consistent with the actual. plant, ! O All performed steps will be initialed.
'J Steps that require the use of the instructor console will -
have the appropriate LOA- or override noted on the l procedure close to the actual step. !
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- i 0 Parameters that must be monitored locally in plant via the use of a variable on the instructor console will be noted on the procedure using the FORTRAN name.
0 Operations that cannot be performed or parameters that c -it be monitored will be noted on the procedure. l O Dates, start and stop times of various procedures used will be noted on the procedure. l 0 Steps requiring approval or communications outside of the l
- Control Room are marked NA.
0 Operational Surveillance Tests (OST's) will be conducted using Beaver Valley Power Station Unit I surveillance test procedures- utilizing ' the simulator control board l switches, controls and indicators. I The required test of 3.1.1 (7) startup, shutdown and power operations with less than full reactor coolant flow will not be perfonued as BVPS Unit 1 is - not licensed and does not intend to operate with less than full core flow. 1 The required test of 3.1.1 (9) core performance testing such as heat
- balance, determination of shutdown margin are performed using plant operating procedures. Startup from cold shutdown to 100% power, refer to SQT Test Abstract .
l The requirement of performing measurement of reactivity coefficients and control rod worth using permanently - installed instrumentation are also performed, in part, by performing ECP calculation, refer to SQT Test Abstract. Measurement of rod worth, bank worth doppler, moderator coefficients etc. cannot be _ performed _using installed control room. instruments. However, those reactivities are measured when the core model change is performed and documented using existing Change Request (CR) program, refer to Appendix 5 for a description of the Change Request l
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1 f- program. Unit I control room does not have a permanently installed l reactivity computer to measure those reactivities. ! 3. Transient Tests The transient tests shall consists of transient initiation and data collection of the recommended parameters. Each - parameter j listed in the training administrative manual for the associated ) 3 transient test shall be continuously recorded and compared to _;
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i actual reference - plant data, best estimate or operational 'y J 4 assessment. Operational assessments will be conducted .by the l t BVPS Transient Review Committee. This committee is comprised of 4 a panel of training, licensing and SRO licensed personal. The resumes of these individuals are in Appendix 6.
- 4. tia]fynglion Tests i The simulator malfunction tests shall be conducted using test i O Prece8ere deveiePe8 rre the er494# ' 4 e, ter accept #ce test !
Procedures (ATPs), _w here applicable. Appropriate malfunction , t test parameters shall be recorded on .a computer printout for each i i malfunction test. .if. applicable. Verification of. expected - f
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indications and alarms is part of each test,. unexpected or - l 1 unexplained alarms and or indications will be.noted and Trouble j Reports generated if necessary. ; LO q a 1
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, 5. Test Procedure Review All test procedures are reviewed by two levels of supervision for completeness and applicability prioc to use. Completed tests are also reviewed and approved for sat)sfactory performance by two levels of supervision.
- 6. Revisions Revisions to the qualification test program such as procedure -
additions / deletions, modifications required by regul atory changes, etc., shall-be recorded on a revision sheet. Performance tests may be revised during the actual performance of the test, provided that the original intent of the procedure is not altered. The change shall. be noted in ink by the designated , test performer. These changes are the responsibility of the test ! performer. Supervision review and approval is necessary for any ( intent changes. E. ACCEPTANCE CRITERIA Acceptance criteria are included 'in each simulator qualification test procedure, and are generally delineated' as follows: !
- 1. Comouter Real Time Teit ' The computer shall. be demonstrated to remain in real time during any and' all . evolutions / transients as j defined in Computer Real Time Test Procedure'(SQT 1,0).
! 2. -Steady State Drift Test --The simulator shall be demonstrated to have parameter values within i2% tolerance for critical parameters and i10% or non critical parameters when compared _ to the . reference plant data for the same parameters. For:the 100% , Drif t Test, parameters will not drift from the initial value- by i- more than approximately 2%. lO
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- 3. Normal Ooerations Tests The s.lmulator-shall be demonstrated to j have the proper response and system inter-relationships.
i Response should be compared to reference plant data as applicable. Acceptance criteria will be the same as plant ! criteria where applicable.
- 4. Transient Tests - The simulator shall- be demonstrated to have the >
correct response- to required transient evolutions. parameter-changes must correspond to- those expected from actual plant response, best estimate, or other available information. ]'
- 5. Malfunction Tests The simulator shall be demonstrated to have the proper response and system interaction as specified in the l test procedure.-
F. DOCUMENTATl0B , l Each simulator qualification test shall be recorded on an approved Simulator Qualification Test Procedure. All ' pertinent parameter lists, . charts, printouts, and other data will accompany the completed 2 procedure. A hard copy printout of 100Y. the Steady State Drift Test shall have a , maximum resolution of one minute. Transient tests shall be recorded for each parameter listed in -the
- applicable' test procedure. Maximum resolution shall be 0.5 seconds.
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G. REFERENCES
- 1. ANSI /ANS 3.5 (1985)
'; 2. USNRC Regulatory Guide 1.149, Rev.1 (11/5/86)
- 3. NUREG 1258 (12/87)
- 4. Computer program DRIFTEST i
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i l 3.1 Real Time Test (SOT-1.01 ( A simulator real time test was performed as required by ANSI /ANS 3.5 1985 Appendix A.3.1 to test the computer for verification of real time simulation. V O
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Simulation Real Time Test SQT-1.0 t REQUIRED BY ASI/ANS 3.5 SECTION: 5.4.2 DATE TESTED:08/24/89 GENERAL DESCRIPTION: The purpose of this test is to verify the Simulator remains capable of operating in real time for a worst case situation which
- would tax it's capacity. A DBA LOCA combined with a blackout is iniated and IPU and CPU duty cycles are monitored to insure they do not exceed 100%.
'l W AVAILABLE OPTIONS: N/A 1 OPTION TESTED: N/A INITIAL CONDITIONS: IC 18 100% PWR. CORE AGE - MOL None ()LISTOTHERSPECIALCONDITIONS: i FINAL CONDITIONS TEST DURATION: 1 HRS. i-DBA LOCA and-blackout in progress. IPU and CPU recorded Data Collected. Neither value exceeded 100%. l BASELINE DATA: Software Program DSPEXEC DEFICIENCIES: None 1 CORRECTIVE ACTION /DATE: N/A I; -None
)EXCEPTIONSTAKENTOANS.3.5:
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/7 3.2 Steady State Tests (50T-2.0) results NJ Steady state tests were performed per Appendix B of ANSI /ANS 3.5 1985.
A comparison of digital displayed information from the instructors station, and the information displayed on the control board meters identified several meters which required calibration. These meters have been calibrated utilizing the trouble report program identified in Appendix 4. A meter calibration program similar to the plant meter calibration program has been implemented to upgrade the calibration status of the control boards meters. Igit Pfscriotion 2.1 Simulator drift test at approximately 100% power. 2.2 Simulator drift test at approximately 75% power. 2.3 Simulator drift test at approximately 30% power. (O J ,
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT l TEST. TITLE: 100% Steady State Drift Test' SQT 2.1 ()REQUIREDBYASI/ANS3.5SECTION: 4.1- DATE TESTED:09/13/89 GENERAL DESCRIPTION: This test verifies the simulator's ability!to duplicate the BVPS Unit I characteristics within tolerance and to maintain-stability at
- 100% for at least a one hour period. A computer program verifies computer variables to plant data and prints out a display noting any problems. Control
- Board Indication is compared by Tester using an attachment for data gathering i and comparison. The computer program also displays any drift from the iriitial values and flags any drift of 2% or greater.
a AVAILABLE OPTIONS: N/A s N OPTION TESTED: N/A INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL t None ()LISTOTHERSPECIALCONDITIONS: i FINAL CONDITIONS TEST DURATION:. 2' HRS. Plant at 100% steady state conditions, all parameters within-2% of initial values. - 4 BASELINE DATA: BVPS Plant Logs dated 07/15/88 p61nts used as acceptance criteria are marked in blue. - 1 DEFICIENCIES: Control Board Meter Calibration, problems- found for many~ meters CORRECTIVE ACTION /DATE: TR-195 written for meter calibration, calibration !' . schedule implemented. TR-195-has been resolved. E EXCEPTIONS.TAKEN T0 ANS. 3.5: None 1 4 fTeW7 T' TW7"Y7T- u8 r - %* f"*-49' m Yw w=w=W4" .'re-- 'f a w-.Mw e -- 'ser err uw--iren' Wvvf tw p+ y<iw*-ofYrf' wwvT 'w'ww'T'974*'--ti
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- flVPh i SIMULATOR'CERTIFICA110N TEST ABSTRACT
! TEST TITLE: 75% Steady State Test SQT 2.2 REQUIRED BY ASI/ANS 3.5 SECTION: 4.1 DATE TESTED:10/25/90 GENERAL DESCRIPTION: The simulator is initialized at the 75% 1.C. Parameters specified in Appendix B.2.1 are compared to those from the UI Plant. A print out of the required parameters is taken and verified to be within tolerence , allowed in ANS 3.5 1985, 4.1. i AVAILABLE OPTIONS: N/A i OPTION TES1ED: N/A i INITIAL CONDITIONS: 10 35 75% PWR. CORE AGE - BOL LIST OTHER SPECIAL-CONDITIONS: Use Pack A FINAL CONDITIONS TEST DURATION: 1 HRS. Plant stable at 75% power. Print out of required parameters complete. BASELINE DATA: Plant Logs 10/5/90 BVPS Unit;I Actual Data used-is marked and placed in file. DEFICIENCIES: None-CORRECTIVE ACTION /DATE:' N/A D EXCEPTIONS TAKEN TO ANS. 3.5: None IV , L
u...- ...u . -u. s .<.a. -- r >~.e. .n - u -.a+ - ~ ~ - ., .a,..-.u- u -y .m. m.a.- _ s BVF3 I SIMULATOR CERTIFICATION TEST ABSTRACT s TEST TITLE:'.30% Steady State Test SQT-2~.3 RE0VIRED BY ASI/ANS 3.5 SECTION: -4.1- .DATE TESTED:10/25/90-GENERAL DESCRIPTION: The- Simulator is-initialized at the 30% I.C. - Parameters specified in Appendix-B.2.1 are compared to those from.the VI Plant. A print u out of the required parameters is-taken and verified to be within tolerances-allowed in ANS 3.5-1985, 4.1. AVAILABLE OPTIONS: N/A OPTION TESTED: N/A INITIAL CONDITIONS: ~10-34 30%-PWR. CORE AGE-- BOL-LIST OTHER SPECIAL CONDITIONS: Use Pack A l FINAL COND :' IONS TEST DURATION: 1 HRS. Plant stable at' 30% power. Print out of required parameters complete.
- BASELINE-DATA: P1 ant Logs 10/6/?0 BVPS Unit I Actual Data Used is-marked and placed in file.
DEFICIENCIES: None + CORRECTIVE ACTION /DATE: N/A D None: Q ) EXCEPTIPNS TAKEN TO ANS. 3.5: l
-.t 3.3. Normal- Ooerations ' f S0T-2.4) results -
Normal operation tests- were performed per Section 3'. l .1 of ANSI /ANS 3.5 1985.- 1931 Qgiqriotion 2.4.1 P1 ant shutdown from_ rated power to Mode 5 per normal procedures 2.4.2 Power Range-Surveillance Test OST-1.2.1 2.4.3 Intermediate Range _ Surveillance Test OST-1.2.2 2.4.4 Source Range Surveillance Test OST-1.2.3 2.4.5 Plant start'up from !1 ode 5 to rated thermal -power - O 248 ^cc48e#t se#4ter4#9 i#str# e t tie # Surveillance test OST-1.6.7 2.4.7 RCS Leakage Surveillance Test.0ST-1.6.2 2.4.8 Boric Acid Pump Surveillance Test OST-1.6.1/2 2.4.9 Diesel Generator #1 Monthly Surveillance Test ~ OST-1.36i1
- i. 2.4.10 Diesel generator #2 Monthly-Surveillance Test OST-1.36.2 2.4.11 Containment -Isolation Valve Stroke Surveillance Test.0ST-1.47.3A 2 d.12 Cold Shutdown Valve Exercise-Surveillance Test _ ,
OST-1.1.10 l 2.4.13 Main Steam Isolation Valve Stroke Surveillance Test s I
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l . 3 Descriotion1 0 Ini OST-21 4/5/6'. 2.4.'14 Auxillary Feedwater -Pump-Discharge Valves Stroke Time , :.; Surveillance Test'0ST h 2.4.15- Motor Driven AFWP Sureillance Test. ; i OST-1.24.2/3. j 2.4.16 Turbine Drive Aux Feedwater Pump _. -! k
- Surveillance Test'0ST'l-.24.4.
2.4.17 Reactor Trip and Recovery lto Rated Power- j g I
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'BVPS-I SIMULATOR CERTIFICATION TEST ABSTRACT' e TEST TITLE: Plant Shutdown- From 100% =to Mode 5 with R.H.R. SQT+2.4.l.
REQUldED BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTED:09/12/89 GENERAL DESCRIPTION: This test verifies that the operators can, on the simulator, use B.V.P.S. Unit 1 operating procedures to' conduct a plant shut: down from 100% Pwr, to Mode 5 conditions with.the R.H.R.1 System in service. The test requires each procedure used -to be initialed and each Local Operation (LOA) utilized to be documented to verify proper response. AVAILABLE OPTIONS: N/A OPTION TESTED: N/A f INITIAL CONDITIONS: 10-42 ~100% -PWR, CORE AGE - BOL s LIST OTHER SPECIAL CONDITIONS: None. FINAL CONDITIONS TEST DURATION: 24 HRS. Plant shut down,-Hode 5 conditions achieved, RCS cooling being performed _by R.H.R. System. BASELINE DATA: B.V.P.S. Operating Manual Procedures 1.51.4A, .B, C, D,- E, ?F 1 DEFICIENCIES: Incorrect CCT (delta-P), RCS-Pzr unexplained boron changes,- 6th ; point heater low level problems, Exciter Base Adjust not working-properly. p CORRECTIVE ACTION /DATE: Trouble Reports 197, 198, 199 and 200 written. These TR's have been cleared (v,)'-EXCEPTIONSTAKENTOANS.3.5: None. _- j
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT 4 TEST TITLE: Power Range Functional Test OST 1.2.1. SQT-2.4.2 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTED:09/13/89 GENERAL DESCRIPTION: This test involves running the Operations Shift Test to verify the operability of the Power Range NIS Channels. The OST 1.2.1 is run the same way it is in the plant, including use of the actual plant procedure, LOA's were used as necessary to. simulate process rack bistables. AVAILABLE OPTIONS: N/A OPTION TESTED: N/A ' O INITIAL CONDITIONS: 10-40 100% PWR. CORE AGE - MOL LIST OTHER SPECIAL CONDITIONS: None 1 FINAL CONDITIONS TEST DURATION: 8 HRS. Test OST 1.2.1 complete, data logged, plant at 100% Steady State Operation, NIS channels returned to operable status. BASELINE DATA: Operating Shift Test 1.2.1 DEFICIENCIES: Several Trip and Reset Setpoints on the NIS channels did not meet acceptance criteria. Not all computer printouts worked. 1 CORRECTIVE ACTION /DATE: l Trouble Report 204 Written, T.R. resolved. l EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Intermediate Range Functional Test OST 1.2.2 SQT-2.4.3 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATETESTED:09/12/89 GENERAL DESCRIPTION: This test involves running the Operating Shift Test to verify the operability of the Intermediate Range NIS Channels. The same procedure as used in the plant is used to test the channels on the simulator, i AVAILABLE OPTIONS: N/A C HION TESTED: N/A O INITIAL CONDITIONS: 10-51 0% PWR. CORE-AGE - HOL LIS: OTHER SPECIAL CONDITIO!N None FINAL CONDITIONS TEST DURATION! 1.5 HRS. OST 1.2.2 complete, both channels returned to operable _ status, plant t in Mode-3. BASELINE _ DATA: Operating Shift Test 1.2.2 DEFICIENCIES: Some Trip and Reset setpoints for N-35'did not meet acceptance criteria. l CORRECTIVE ACTION /DATE: G Trouble Report 202 Written, T. R. resolved. 1 O EXCEPTIONS TAKEN TO ANS. 3.S: None i
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.c j BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Source Range Functional Test SQT 2.4.4 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTE0:09/13/89 4
GENERAL DESCRIPTION: . The test involves running the Operating Shift Test to verify the operability of- the Source Range N.I.S. channels.- The same procedure is used as used in the plant. LOA's are used to simulate any actions not done-on the NIS Rack or Main Control Board. AVAILABLE OPTIONS: N/A OPTION TESTED: N/A INITIAL CONDITIONS: IC-51 0% PWR. CORE AGE - MOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1 HRS. Rx Shut Down Mode 3, S.R. NIS Channels returned to operable- status. BASELINE DATA: Operating Shift Test 1.2.3 DEFICIENCIES: Meter-Calibration Problems Found-CORRECTIVE ACTION /0 ATE:
. Trouble Report 205 Written /TR cleared 4/18/90.
EXCEPTIONS TAKEN TO ANS. 3.5: None l w w ap.-et r-rw - r - --m--e v *'wwwa*' - q' -
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Plant Start Up From Mode 5 to 100% Power SQT 2.4.5 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTED:09/12/89 GENERAL DESCRIPTION: The plant -is.taken from Mode 5 with R.H.R. in service to 100% power using Unit I normal operating procedures. . All applicable steps are 3 initialed and LOA's or variables used to determine plant statues are noted. The ability to use plant procedures on the simulator to do this plant start up- ' a is verified and any deficiencies are noted. i AVAILABLE OPTIONS: N/A i OPTION TESTED: N/A i INITIAL CONDITIONS: . IC- b 0% PWR, CORE AGE BOL O, LIST OTHER SPECIAL CONDITIONS: Plant on R.H.R. in Mode 5. FINAL CONDITIONS TEST: DURATION: 32 HRS. Plant at 100% power following a normal plant start up. BASELINE DATA: Plant Operating Procedures 1.52.4A,1.50.4 (A,B,C,0) DEFICIENCIES: TV-GV Transfer did not work correctly, P-11 Permissive not correct. - i CORRECTIVE ACTION /DATE:
- Trouble Reports 207 and 165 written. TR-207 has been cleared, TR-165 has been 7 resolved.
[}'EXCEPTIONSTAKENTOANS.3.5: None. l
l- BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Accident Monitoring Inst. Channel Checks SQT 2.4.6 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTED:09/14/89 l GENERAL DESCRIPTION: This test checks the operability of the Accident Monitoring Channels for the Core Cooling Monitor, Relief and Safety Valve discharge temp. indication, Containment Sump Indication.-P.O.R.Vi Indication, Pzr Level and Pressure Channel Checks. This test is perfornned using the actual plant procedure only the Acoustic Panel test was not done as:it is not modeled, i i j AVAILABLE OPTIONS: N/A i OPTION TESTED: N/A O INITIAL CONDITIONS: 10-38 100% PWR, CORE AGE MOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1.5 HRS. Plant 100% Steady State, all' Accident Monitoring Channels returned-to operable status,
- j. BASELINE DATA: Operating Shift Test.l.6.7
'e DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A A
-U EXCEPTIONS TAKEN TO ANS. 3.5: None l
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST. TITLE: Reactor Coolant System Water. Inventory Balance SQT-2.4.7 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTED:09/14/89 GENERAL DESCRIPTION: The test procedure requires monitoring of RCS and CVCS tank levels and water makeup to perform an inventory balance using the actual plant procedure OST-I.6.2. Data needed for calculations will be recorded on the printer at 5 minute intervals for review and analysis of results which will have the same acceptance criteria as the actual plant, AVAILABLE OPTIONS: N/A OPTION TESTED: N/A INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: O FINAL CONDITIONS TEST DURATION: 3.0 HRS. Plant steady state at 100% power, all data-has been collected for the surveillance test (OST-I.6.2) and compared with actual results.
' BASELINE DATA: -Unit I OST-1.6.2 R.C.S. Water Inventory Balance DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None O
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT O TEST TITLE: Boric Acid Transfer Pump Operability Tests. SQT-2.4.8 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTED:09/15/89 GENERAL DESCRIPTION: The Boric Acid Transfer Pump operating characteristics are checked against the plant data using actual plant test procedures and-acceptance criteria. The ability to_ transfer in service Storage Tanks is done using LOA's with the actual plant procedure. 1 AVAILABLE OPTIONS: N/A' OPTION TESTED: N/A O INITIAL CONDITIONS: IC-42 100% PWR. CORE AGE BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 3 HRS. Plant at 100% Power, "B" Boric Acid Tank and Pump are in service. l l BASELINE DATA: Operating Shift Tests 1.7.1, 1.7.2 and Procedure OM 1.7.4R l DEFICIENCIES: One meter calibration problem noted (LT-CH 108) CORRECTIVE ACTION /DATE: Trouble Report 195 Previously Written,-TR-195 to be resolved by Dec.1991 ( }) EXCEPTIONS TAKEN TO ANS. 3.5: Nono
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BVPS.I SIMULATOR CERTIFICATION TEST ABSTRACT ; TEST TITLE: Emergency Diesel Generator #1 Monthly' Surveillance Test SQT-2.4.9 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTED:11/20/90
. GENERAL DESCRIPTION: This test has the operator perform those control room actions necessary to verify operability of the #1_ Emergency Diesel Generator and be able to compare the data taken to that required as acceptable 'in the ;
Monthly Test Acceptance Criteria (OST-1,36.1). 1 i AVAILABLE OPTIONS: N/A OPTION TESTED: N/A I INITIAL CONDITIONS: 1C-42 100% PWR. CORE AGE - BOL h'--LISTOTHERSPECIALCONDITIONS: None t FINAL CONDITIONS TEST DURATION: 1 HRS.
#1 EDG tripped and idling down.at approximately 500 RPM. All data that could be taken from the control room has been entered on the OST Form. Test is complete as far as Control Room operator actions are necessary.
BASELINE DATA: Plant Operating Shift Test (OST-1.36.1)' ! DEFICIENCIES: -None 4 CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None 'I r - - n, . . . , . . .- -
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST. TITLE: -#2 Diesel _ Generator Monthly Test SQT-2'.4.10 REQUIREC BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTED:12/18/89 l GENERAL DESCRIPTION: This test uses the Operating Shift Test 1.36.2 to check o the operability of the #2 Diesel Generator and compare its performance against ' actual plant data.- The-diesel is started,- loaded .and parameters recorded and verified against OST -1.36.2 acceptance criteria- and plant data. Only parameters that can be seen in the control room are verified. AVAILABLE OPTIONS: N/A OPTION TESTED: N/A INITIAL CONDITIONS: 1C-42 100% PWR. CORE-AGE-- BOL i LIST OTHER SPECIAL CONDITIONS: None j- FINAL CONDITIONS- TEST DURATION: -I HRS. Plant at 100% steady state, #2 Diesel Generator is running at-Approx. 500 RPM.- BASELINE DATA: Operating Shift Test 1.36.2 l DEFICIENCIES:. None CORRECTIVE ACTION /DATE: N/A R !. EXCEPTIONS TAKEN TO ANS. 3.5: None i .
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d. BVPS I. SIMULATOR CERTIFICATION TEST ABSTRACT--
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TEST TITLE: Containment Isolation Valve OST'l.47.3. A- SQT-2.4.ll REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.) DATE TESTED:ll/13/89 11/09/89 GENERAL DESCRIPTION: This test verifies containment isolation valve stroke times against actual plant data. -The operator uses OST-1.47.3.A~ to increase stroke times then verifies them in tolerance to actual plant values, d AVAILABLE OPTIONS: N/A OPTION TESTED: N/A , INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL O LIST OTHER SPECIAL CONDITIONS: None I FINAL CONDITIONS TEST l DURATION: 3.5 HRS. Plant at same initial conditions with all valves tested returned to original position. l BASELINE DATA: BVPS Operating-Shift Test OST 1.47.3.A l
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-DEFICIENCIES: Several valves did not meet stroke time requirements.
CORRECTIVEACTION/DATE: Trouble Report 216 written. TR-216 has been cleared. l-EXCEPTIONS TAKEN TO ANS. 3.5: None
1 I BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT l l % TEST TITLE: Cold Shut Down Valve Exercise Test SQT-2.4.12 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2,1 DATE TESTED:08/24/90 GENERAL DESCRIPTION: This test uses appropriate parts of tne Operating Shift Test (OST) 1.1.10 to test the valve stroke time of seier.ted power operated or automatic valves specified by Technical Specifications -Table 3.6.1 and . insure the Simulator performance is within allowable tolerance to the actual plant date. AVAILABLE OPTIONS: N/A OPTION TESTED: N/A O G INITIAL CONDITIONS: IC-51 0% PWR. CORE t.GE - BOL LIST OTHER SPECIAL CONDITIONS: Open closed valves as necessary to set them up for measurement of their closing time per the:0ST. l FINAL CONDITIONS TEST DURATION: 5 HRS. Required sections of OST 1.1.10 completed, valves returned to NSA position. BASELINE DATA: Plant OST 1.1.10 Valve / Check Valve Summary Log Sheet 1989/1990 DEFICIENCIES: Twenty-nine valve stroke times were-out of limits, specific valves are listed on the trouble report. CORRECTIVE ACTION /DATE: Trouble Report 323 written. To be resolved by December, 1991. , EXCEPTIONS TAKEN TO ANS. 3.5: None.
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT l TEST TITLE: Main Steam Trip Valve full Closure Test SQT-2.4.13 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTED:12/20/89 t GENERAL DESCRIPTION: This test verifies the stroke time of the Main Steam Isolation Valves and checks the data received against actual plant acceptance criteria and actual values. All three MSIV's are checked using the Operating Shift Test (OST) for each. l l AVAILABLE OPTIONS: Loop A,B,C MSIV's OPTION TESTED: All of the above O INITIAL CONDITIONS: IC-11 0% PWR. CORE AGE - MOL LIST OTHER SPECIAL CONDITIONS: Pack "0" Used FINAL CONDITIONS TEST-DURATION: .5 HRS. Rx in Mode 3, all MSIV's closed. l BASELINE DATA: Operating Shift Tests 1.21.4, 1.21.5, 1.21.6 L DEFICIENCIES: None-l CORRECTIVE ACTION /DATE: N/A . O EXCEPTIONS 1AKEN TO ANS. 3.5: None
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, f l BVPS 1: SIMULATOR CERTIFICATION TEST-ABSTRACT
' TEST TITLE: 1 Aux Feedwater Pump Discharge Valve Exercise Test-. .SQl 2.4.14 REQUIRED BY ASI/ANS 3.5.SECTION: 4. 2.1 - DATE TESTED:12/18/89 >
GENERAL DESCRIPTION: The test uses.the Plant Operating Shift Test Procedure > .j 1.24.1 to verify the stroke time of the AFW Pump Discharge Valves and verify i them operable per actual plant acceptance criteria and actual: values. Valves-are stroked-and times recorded. AVAILABLE OPTIONS: N/A s k OPTION TESTED: N/A O INITIAL CONDITIONS: 1C-42 100% PWR. CORE AGE BOL5 LIST OTHER SPECIAL-CONDITIONS: None FINAL. CONDITIONS TEST DURATION: 1 HRS. Plant at 100% Steady State, . AFW Systems returned to normal-line up. L i BASELINE DATA: Operating-Shift Test 1.24.1 (6/5/89) DEFICIENCIES: None l l CORRECTIVE ACTION /DATE: .N/A L EXCEPTIONS TAKEN TO ANS. 3.5: None 3
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT $ l TEST TITLE: Motor Driven AFW Pump Tests SQT 2.4.15 REQUIRED BY ASI/ANS 3.5'SECTION: 4 .~ 2 .1 DATE-TESTED:12/18/89 GENERAL-DESCRIPTION: This test uses OST's.l.24.2 & 1,24.3 to verify the i operability of-the Motor Driven AFW Pumps. The test basically checks that the pump operates at the correct AP. LOA's are used as necessary to_ set the conditions for conducting the test. Results are compared to-plant data. l I AVAILABLE OPTIONS: FWP-3A, FWP-38 OPTION TESTED: FW P-3A & 3B INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE'- BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1.5 HRS. Plant at 100% SS, AFW Syston returned to normal system _line up. BASELINE DATA: Operating Shift. Tests (1'24.2 & l.24.3) DEFICIENCIES: Pump AP's too high CORRECTIVE ACTION /DATE: , Trouble Report 235 Written /T. R. cleared 1/19/90 EXCEPTIONS TAKEN TO ANS. 3.5: -None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT O V TEST TITLE: Steam Driven AFW Pump Test SQT 2.4.16 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTED:12/21/81 GENERAL DESCRIPTION: This test uses OST 1.24.4 to verify operability of the Terry Turbine AFW Pump AP is used as a measure of pump performance and conditions are set up to measure LP using L.O.A.'s and following the 0.S.T. Procedure, Results are compared to plant data. AVAILABLE OPTIONS: N/A OPTION TESTED: N/A l O V INITIAL CONDITIONS: IC- 18 100% PWR. CORE AGE MOL LIST OTHER SPECIAL CONDITIONS: None i i FINAL CONDITIONS TEST DURATION: 2 HRS. l Plant at 100% S.S., AFW System returned to normal line up. l BASELINE DATA: Operating Shift Test 1.24.4 (Plant Procedure) l DEFICIENCIES: AP of Pump incorrect l l i CORRECTIVE ACTION / DALE: 3 Trouble Report 235 Written /TR-235 has been cleared. (O EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Reactor Start Up Following a Trip- SQT - 2. 4 ~.17 - REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATETESTED:10/10/90 l GENERAL DESCRIPTION: The reactor is tripped from 100% power, E-0 and ES.-0.1
- have been completed. A post trip reactor start up is conducted using 3
procedures 1.50.4J and 1.50.4D. including ECP calculation and 1/M plot. Ability to conduct the start up using plant procedures on the simulator is verified. L AVAILABLE OPTIONS: N/A OPTION TESTED: N/A 10-42 100% PWR. CORE AGE - BOL ist otata seccia' O ' INITIAL conoitions: CONDITIONS: Rx Trip has occurred from 100%, E-0 & ES-0.1 have been completed as necessary 1 to allow a reactor start up, i' FINAL CONDITIONS TEST DURATION: 3 HRS. Reactor start up complete, reactor critical at slightly less than 5% power, Procedure 1.50.4D completed. BASELINE DATA: Plant Operating Procedures 1.50.4J and 1.50.4.0 DEFICIENCIES: None. CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None, r j l _ _ _ ~. . . . . - . , . . _ , - _ . . _ -
3.4 Transient Tests (SQT-3.0) Transient tests -(TR 1 through 11) were performed per Appendix B.2.2 of. ANSI /ANS-3.5 1985. Jasi Description 3.1 Hanual reactor-trip. 3.2 Complete loss of'all feedwater. . 3.3 Simultaneous closure of all main steam. isolation valves. 3,4 Simultaneous trip of all reactor coolant pumps. 3.5 Trip of one reactor coolant pump. - 3.6 Main turbine trip less than P-9 with manual rod control. 3.7 Maximum power ramp (100% to approximat'ely 75% to 100%).. 3.8 DBA LOCA with loss of offsite power. 3.9 Maximum-steam break inside containment. - 3.10 Pressurizer safety valve leak. 3.11 Main Turbine Trip, rod control.in auto. O
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BVPS'I SIMULATOR UERTIFICATION TEST ABSTRACT TEST TITLE: Manual Reactor Trip SQT-3.1 > REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTED:10/05/89 GENERAL DESCRIPTION: A manual reactor trip from 100% power is -performed. All alarms received are recorded, parameters required to be recorded are recorded and graphed out for later analysis. Data is collected until N.R. levels are increasing, then the simulator is frozen. No operator actions were taken.. l AVAILABLE OPTIONS: N/A OPTION TESTED: N/A INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Recording Procedure 3.1.D followed'for data collection. FINAL CONDITIONS TEST DURATION: '2 HRS. The reactor is tripped, S/G levels are increasing, no SI has occurred, the RCS is cooling down. BASELINE DATA: BVT-l'.1-9.4.6, BVPS Certification Test Review Committee Sequence of Events Evaluation Program Acceptance Criteria ES-0.1 Background- Document DEFICIENCIESi S/G level indication on S.P.D.S. does not go below 1% ' indicated NR, AFW Flow Oscillations, Containment Press. Response not-correct. CORRECTIVE ACTION /DATE: TR-214 Written for S/G -Level Indication problem. TR-220 Written' for AFW Flow Oscillation problem. 'TR-218: Written for Containment Press. Response problem. Trouble report.218.and 220 have been I I cleared. TR-214 has been resolved. EXCEPTIONS TAKEN TO ANS. 3.5: None. ( l
d BVPS-I SIMULATOR CERTIFICATION TEST ABSTRACT , TEST TITLE: .-Complete Loss of All Feedwater SQT-3.2-REQUIRED BY-ASI/ANS 3.5.SECTION: 4.2.1 DATE TESTED:10/05/89 GENERAL DESCRIPTION: At 100% power the Main Feed Pumps are tripped using 1 malfunctions FWM 1A & 18. The malfunctions-for the Aux Feed Pumps were activated previously to prevent their auto start. - All alarms received were recorded for review. Simulator was run until loss of heat sink effects could be noted on the RCS or S/G pressure response . Required parameters were recorded for graphs and future Review Group analysis. r AVAILABLE OPTIONS: N/A f OPTION TESTED: N/A INITIAL CONDITIONS: 1C 100% PWR. CORE AGE - BOL. LIST OTHER SPECIAL CONDITIONS: Recording Procedure 3.1.0 followed for data collection. FINAL CONDITIONS TEST DURATION: - 2 HRS. Loss of all feedwater still.present, RX tripped, SI, CIA, SLI, and.FWI have , all occurred. Large S/G pressure drop has occurred due-to the loss of feedwater with some increase after Steam Linei'rolation (SLI).
'i BASELINE DATA: F.S. A.R. Accident' Analysis for lors of -feedwater E.0.P.
Background Information for FR-H.1 B.V.P.S.,--Certification' Test Review Committee. DEFICIENCIES: High Pzr. Temperature- Alarm not expected, other problems noted-but TR's previously written. CORRECTIVE ACTION /DATE: TR-306 ' written for High Pzr Temperature- Alarm. Resolution by December-1992. None. O EXCEPTIONS-TAKEN TO ANS. 3.5:
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BVPS 1 SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Simultaneous Closure of all M.S.I.V.'s SQT-3.3 O k/ REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTED:10/25/89 GENERAL DESCRIPTION: At 100% all MSIV's are failed closed using malfunctions MSS-1A, 18 and IC at the same time. All alarms received are recorded, all ESF actuations are recorded. Data required by ANS 3.5 is collected. Simulator is run until normal post trip conditions have been established and have stabilized. AVAILABLE OPTIONS: N/A OPTION TESTED: N/A
,, INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE-BOL
( ] LIST OTHER SPECIAL CONDITIONS: Recording Procedure 3D used to gather data. FINAL CONDITIONS TEST DURATION: 2 HRS. Rx tripped, partial FWI, AFW pumps-supplying S/G's. RCS temperature and pressure relatively stable at post trip values. S/G levels increasing due to AFW flow. BASELINE DATA: BVPS Certification Test Review Committee FSAR 14.1.7.1 Loss of Electrical Load / Turbine Trip DEFICIENCIES: Same problems noted in other tests, no new TR's needed. CORRECTIVE ACTION /DATE: N/A
. EXCEPTIONS TAKEN TO ANS. 3.5: None
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s BVPS _I SIMULATOR . CERTIFICATION TESTL ABSTRACT . l Simultaneous ~ Trip of All Reactor coolant- Pumps SQT 3.4 : O TEST TITLE: REQUIREDBYASI/ANI3.5SECTION: 4.2.1- DATE. TESTED:10/23/89-
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GENERAL DESCRIPTION: Plant is at 100% power when the three.RCP's are-tripped using Mal RCS-8A, 8B, 80.- ~ All alarms and auto actions are -recorded as-well: as data required by ANS 3.5 being recorded.: 1 Simulator is run until natural circulation is established. Data recorded will be graphed for Review Committee . analysis. J l 4 t AVAILABLE OPTIONS: N/A OPTION TESTED: N/A INITIAL CONDITIONS: 10-42 100% PW'R. CORE AGE - BOL O LIST OTHER SPECIAL CONDITIONS: Procedure 30 followed-for data gathering. ' FINAL CONDITIONS TEST DURATION:. 2 HRS. Ii All RCP's off, RX tripped, No SI occurrence, partial FWI has occurred, AFW 4 pumps supplying feedwater, natural circulation in progress. j
-BASELINE DATA: BVT-1,1-10.4.3, BVPS Certification Test Review: Committee.
FSAR-14.2.9 Complete loss of forced RX coolant flow.; E0P - Background document for ES-0.2.
. DEFICIENCIES:. Alarms for auto bus transfer and auto trip of-RCP's did.not-occur as they should.
CORRECTIVE ACTION /DATE: Trouble reports '2S2 and 307 written. TR-252 is resolved,'TRe307 to be resolved' by December 1991. , EXCEPTIONS TAKEN TO ANS. 3.5: None.
BVPS I SIMULATOR CERTIFICATION! TEST ABSTRACT TEST TITLE: Trip of 1 Reactor Coolant Pump' SQT-3.5-REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTEDi10/25/89 GENERAL DESCRIPTION: The Loop A Reactor: Coolant Pump is tripped at'100% . i power using Hal RCS 8A. All alarms are recorded, data required by . ANS-3.5 is collected for generating graphs. The transient is. allowed to run till post' .' trip valves are returning to normal and S/G levels are11ncreasing on N.R. - indication. AVAILABLE OPTIONS: RCP's A, B, or C. OPTION TESTED: RCP-A. f% INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE -~BOL ( ) LIST OTHER SPECIAL CONDITIONS: Procedure 3D followed for data gathering. FINAL CONDITIONS TEST DURATION: 1.5 HRS. RCP A off,- RCP's B&C running, Rx tripped-due to low flow,' S/G levels increasing.
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BASELINE DATA:- LER-88-007 B.V.P.S. Certification Review Committee. DEFICIENCIES: Containment Press. Alarms. not expected, Auto Bus Transfer Alarms not received. CORRECTIVE ACTION /DATE: No .new TR's required as above problems were previously documented.
- () EXCEPTIONS TAKEN T0 ANS. 3.B: .None.
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BVPS'I SIMULATOR CERTIFICATION TEST ABSTRACT
~ TEST TITLE: Main Turbine Trip (Rods In Manual) SQT-3.6 ;
O REQUIRED BY ASI/ANS 3.5 SECTION: '4.2.1 DATETESTEDi!0/II/89 GENERAL DESCRIPTION: The plant is reduced in power to below P 9 whwe o turbine trip will not cause a Rx' Trip. The turbine-is tripped and selected parameters plotted per the test procedure and all alarms noted. The test O run until stable plant conditions are reached. , AVAILABLE OPTIONS: N/A OPTION TESTED: N/A INITIAL CONDITIONS: IC -'34 50% PWR. CORE AGE --BOL I O LIST OTiiER.SPECIAL CONDITIONS: Reduce power to less than P-9 prior to turbine trip. Use Procedure D to set up to record data. FINAL CONDITIONS TEST' DURATION: 3 HRS..- Turbine tripped, Rx critical, AFW supplying the steam generators, Plant at stable power approximately 3 to 5% below' initial value. - BASELINE DATA: Abnormal Operating Procedure 1.26.1 " Turbine Trip" 8 V.P.S. Certification Test Review Committee. DEFICIENCIES: Steam Dump controller setpoint incorrect - -(Tave 'Iref) CORRECTIVE ACTION /DATE: Trouble Report 279 written. . TR-279 has been resolved.
- EXCEPTIONS TAKEN TO ANS. 3.5: None i
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BVPS.I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Maximum Power Ramp SQT-3.7-REQUIRED BY ASI/ANS 3.5 SECTION: 4. 2.1 - DATE TESTE0:04/ll/89 . GENERAL DESCRIPTION: .The plant is ramped from-100% to 75%~at'5%/ min. -The i plant is stabilized at 75% then ramped.back to 100% power.at 5%/ minute. Monitored parameters are compared to acceptance criteria BVT 1.1-9.42 by the. Review Committee, i i AVAILABLE OPTIONS: N/A i OPTION TESTED: N/A l INITIAL CONDITIONS: 10-42 . 100% PWR. CORE AGE -BOL l ()LISTOTHERSPECIALCONDITIONS: Use Procedure D to set up to record data. I FINAL CONDITIONS TEST DURATION: 3 HRS. 1 Rx at 100% power, almost equilibrium conditions. BASELINE DATA: Beaver Val.loy Test Procedure 1.1-9.4.2 LoadESwing Test.. B.V.P.S. Certification Test Review. Committee. DEFICIENCIES: A (-Alarm not received. CORRECTIVE ACTION /DATE: Trouble Report 308 written. TR-308 will be resolved- : by December 1991. None _ / } EXCEPTIGNS TAKEN-T0 ANS. 3.5:
BVPS 1 SIMULATOR CERTlflCATION TEST ABSTRACT TEST TITLE: CBA LOCA with Loss of Offsite Power SQT-3.8 l REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTED:10/ll/89 l GENERAL DESCRIPTION: A DBA LOCA is initiated in Loop A after a blackout l condition is caused using file BLKOUT. Parameters and alarms are recorded as required by the procedure until Si flow stabilizes and containment is at subatmospheric pressure. No operator actions were taken. AVAILABLE OPTIONS: Loop "A" RCS 20 Loop "B" RCS-2E Loop "C" RCS 2F OPTION TESTED: Loop A RCS 20 INITIAL CONDITIONS: 10 42 1007. PWR, CORE AGE - BOL O LIST OTHER SPECIAL CONDITIONS: Procedure D used to set un to record data. FINAL CONDITIONS TEST DURATION: 2.5 HRS. LOCA in progress. Rx tripped, Cl"A", Cl"B", SLI, FW1 have occurred. Centainment Press is subatmospheric and S! flow is relatively constant. BASEllNE DATA: B.V.P.S. Certification Test Review Committee FSAR Section 14, DBA LOCA DEFICIENCIES: Pzr. Temp. spikes too high, incore Sump Alarm does not come on. Pzr. Control Press low, alarm did not come on, Prz, Relief.Line Temp improper response. CORRECTIVE ACTION /DATE: Trouble Reports 309, 318, I'9 a,.d 320 written. TR-309 will be resolved by Decenb' r 1992, TR 318, 319 and 320 will be resolved by Decc.0er 1991. O
\_/ EXCEPTIONS TAKEN TO ANS. 3.5: None.
BVPS I SIMULATOR CERTIFICATION TEST ABS 1RACT TEST TITLE: Steam Break In Containment SQT 3.9 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATE TESTED:ll/28/89 i GENERAL DE5CRIPTION: The plant is at 100% power when a steam break of maximum size IE7 lbm/hr is activated. Required parameters are graphed and all alarms-4 are noted. The transient is run with no operator action. The transient is run , out until containment pressure is approximately' stable and pressurizes press. ] is increasing, i l l AVAILABLE OPTIONS: A, B or C Steam Generator l l OPTION TESTED: A Steam Generator a 10-42 100% PWR. CORE AGE -BOL is' o'"ta seocia' co"oi'io"s: O'INITIALCONDITIONS: Use Procedure D to set up to record data, i ! flNAL CONDITIONS TEST DURATION: 2.0 HRS. 1 Rx Tripped, SI in progress, Cl "A" and Cl "B'~ activated, containment-pressure slowly decreasing, Faulted Steam Generator still blowing down, i
- BASELINE DATA
- OM 53.4 E-2 Background Document Safety Evaluation Per Amendment 71 to License BVPS Simulator Certification Test Review Committee
~
DEFICIENCIES: None, that have not been previous.ly noted on other tests.- 1 CORRECTIVE ACTION /0 ATE: T.R.'s previously written. EXCEPTIONS TAKEN TO ANS. 3.5: None 6-q'e'pe' at yr*w .w g- weese w - n-dy -g+ w e. y-,4 *&w.i-ya y .e-rwgwvrww a ,,-- - -'
BVPS I SIMULATOR CERTiflCATION TEST ABSTRACT TEST TITLE: PZR Safety Valve Leak (No HHSI) 507 3.10 REQUIRED BY ASI/ANS 3.S SECTION: 4.2.1 DATE TESTED: 11/01/BP GENERAL DESCRIPTION. The test is run at 100% power with the *B* HHS1 Pump failed off. The malfunction causes PZR Safety Valve S51 C to fail 100% open. Upon Safety Injection activation, the "A" HHS! Pump is failed off. Required data points are plotted and all alarms are recorded until the test is terminated upon the Pressurizer going solid and Source Range NIS decreesing. AVAILABLE OPTIONS: N/A OPTION TESTED: N/A A INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL U LIST OTHER SPECIAL CONDITIONS: Use Procedure D to set up to record data. FINAL CONDITIONS TEST DUPATION: 2 HRS. Rx Tripped, SI, CIA, SLI, FW1 have occurred except for HHSI, PZR level 2 100% and S.R. NIS counts decreasing. BASELINE DATA: BVPS Simulator Certification Test Review Committee DEFICIENCIES: None, not previously noted on othe tests. CORRECTIVE ACTION /DATE: T'.R.'s previously written. O EXCEPTIONS TAKEN TO ANS. 3.5: None \.3
I BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT l TEST 11TLE: Main Turbine Trip (Rods In Auto) SQT 3.ll j
-REQVIRED BY ASI/ANS 3.5 SECTION: 4.2.1 DATETESTED:10/ll/89 l GENERAL DESCRIPTION: Power is reduced to less than P 9 and the turbine is manually tripped with rod control in auto. Required paraneters are plotted and all alarms are recorded. No operator action is taken. The transient is allowed to run until reactor and secondary plant parameters are steady state, j i
l- l l l l 1 l AVAILABLE OPTIONS: N/A i j OPTION TESTED: N/A INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE BOL j LIST OTHER SPECIAL CONDITIONS: i Set up to record data usin's Procedure D. i FINAL CONDITIONS TEST DURATION: 2 HRS.- Turbine Tripped, Plant stable at <-1% Power, with Steam Dumps controlling Tavg. [- BASELINE DATA: BVPS Simulator Certification Test Review Committee Abnormal Operating Procedure . DEFICIENCIES: None not previously noted. [' I CORRECTIVE ACTION /DATE: T.R.'s previously written.. EXCEPTIONS TAKEN TO ANS. 3.5: None L u
[ 3.5 Malfunction Tests 150T-4.0) The following Malfunctions have been tested in accordance with Section 4.2.1 or 4.2.2 of ANSI /ANS 3.5 1985. l leit Description 4.1 (AUX 1)Containmentinstrumentair
' compressor trip.
4.2 (AUX 2)StationAircompressortrip. i 4.3 (AUX 3) Instrument air leak (outside containment) } j 4.4 (AUX 4)Instrumentairleak(inside containment) 4.5 i (AUX 5) Station air header isolation valve
- failure.
i 4.6 (AUX 6) Auxiliary steam header leak. 4.7 (AUX 8) Surge tank effluent leak 4.8 (AUX 9) Gas waste decay tank header
, leak.
l 4.9 (AUX 10) River water pump trip. j 4.10 (AUX-11) Turbine plant river water pump trip. 4.11 (AUX 12) Auxiliary river water pump trip- ! 4.12 (AVX 13) Containment ventilation fan failure. 4.13 (AUX-14) Radiation monitor failure. O
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litt Description 4.14 (CCW-1) Non regenerative heat exchanger tube leak. 4.15 (CCW 2) Reactor coolant pump thermal barrier heat exchanger leak. 4.16 (CCW3) Reactor plant componet cooling water pump trip. 4.17 (CCW4) Reactor plant- component cooling temperature control valve failure. 4.18 (CCW.5) Non regenerative heat exchanger temperature control valve failure. 4.19 (CCW 6) Reactor plant componet cooling pump water suction header leak. 4.20 (CCW 8) - Reactor plant componet cooling supply line to RCP leak. 4.21 (CCW9) Reactor coolant pump seal water heat exchanger 4 tube leaks. 4.22 (CND1) Condensate pump trip. 4.23 (CND2) Feedwater heater. bypass valve ' failure. 4.24 (CND3) Condensate pump discharge header leak. 4.25 (CND5) Feedwaterheatertubeleak.(2nd point). O ,
I Tests Descrintion 4.26 (CND-6) Fourth point heater level l control valve failure. 4.27 (CND-7) Fifth point heater control valve oscillation. 4.28 (CND 8) Air ejector failure. l 4.29 (CND-9) Vacuum breaker leak. 4.30 (CND 10) Condenser ~ tube leak. 4.31 (CND-12)Coolingtowerpumptrip. 4.32 (CND13)Coolingtowerpumpdischarge valve failure. 4.33 -(CND 14) Condensate recirculation control valve failure. 4.34 (CND-15) Hotwell level control valve O < 41"re. i- ! 4.35 (CND-16) Heater bypass valve to drain pump suction failure. 4.36 (CND-17) Vacuum priming pump vacuum breaker valve failure. 4.37 (CND-18) Vacuum priming pump trip. 4.38 (CRF-1) Loss of rod drive MG set. l 4.39 (CRF 2) Failure of rods to move. 4.40 (CRF-3) Improper bank overlap 4.41 (CRF-4) Dropped rod. 4.42 (CRF-5) Uncontrolled rod motion. 4.43 (CRF-6) Automatic rod speed control-failure. lO
. - . - - . _ . ~ . - - . . _ _ - - - - . - - - . . . - - _ - . - - --.. .. - . - ..
I l i j Igit Descriotion 4.44 (CRF-7) Reference temperature (Tref) l failure. . 4.45 (CRF-8) Individual rod position indicator l l loss of voltage. 4.46 (CRF 10) Rod position _ step counter failure. 4.47 (CRF-ll) Stuck rod. I 4.48 (CRF 12) Reactor trip failure. i 4.49 (CRF-13) Rod stop failure, s 4.50 (CRF-14) Reactor trip. 4.51 (CHS 1) Letdown back pressure regulator valve failure. 4.52 (CHS-2) Letdown relief valve failure. 1 4.53 (CHS3) Letdown line leak in containment O V (unisol able) . 4.54 (CHS-4) Plugged seal water injection
-filter.
4.55- (CHS-5) Volume control tank level control valve failure. 4.56 (CHS 6) VCT degasifier modulating level control i valve failure. 1 4.57 (CHS7) RCS boron dilution accident-4.58 (CHS8) RCS boration: accident. 4.59 (CHS-9) Boric acid to blender flow > transmitter failure. 4.60 -(CHS-10) Blender outlet flow transmitter failure.
. . . . , . . ~ - . -
t l [ Ig11 Deserietion 4.61 (CHS 11) Charging header' leakage. s 4.62 (CHS 12) RCS fill header leakage.
- 4.63 (CHS 13) RCP pump seal injection flow control i
valve failure. ! i 4.64 (CHS 14) Excess letdown divert valve i failure. 4 4.65 (CHS 15) Hydrogen supply pressure regulator- ; 4 , ) - valve failure. ! 4.66 (CHS 16) Volume control tank leak.
- 4.67 (CHS 17) Blender outlet valve (FCV CH 113B failure, j i
4.68 (CHS 19 Boric acid transfer pump trip. 4.69 (CHS 20) VCT level transmitter failure. l-4.70 (CHS 21) Letdown inlet isolation h valve failure. i 4.71 (CHS 22) Charging flow control valve failure. 4.72 (CHS24)Letdownhightemperaturedivert j valve failure.. 4.73 (EPS-1) Station blackout. 4.74- (EPS 2) Unit station service transformer l .> failure. 1 4.75 (EPS-3) System station service transformer ; failure. , 4.76 (EPS-4) Loss of 4160' volt . bus. . O . 1 m9iw ww wp e e-i w .=W y y 9 ' Mg wge y,q gw g- 9-gp y y -y +c w eng g 4 smie, cgw i 9 p y- 9 i- r - y e yymy -+yy_7..,7 3 7p y ,y g 9 p,yigy-qw-y gr.g=,y..rygig9_. ,'S-*?i^ r*-TTI'E TP
- 3 9"Y 'TlW'" T' I*" Y' N' " " ' ' Y
Ig11 Description 4.77 (EPS 5) Loss of 480 volt bus. 4.78 (EPS 6) Loss of 120 volt bus. 4.79 (EPS 7) Loss of 120 vac inverter. 4.80 (EPS 8) Loss of DC bus. 4.81 (EPS 9) Grid voltage variation. 4.82 (EPS ll) Diesel generator trip. 4.83 (EPS 12) Diesel generator erratic speed control. 4 4.84 (EPS 13) Diesel generator erratic volt regulation. 4.85 (EPS 14) Diesel generator output breaker trip, 4.86 (EPS 15) Load rejection. 4.87 (EPS 16) Main generator output breaker failure. 4.88 (EPS 17) Voltage adjuster setpoint failure. 4.89 (EPS 18) Main transformer failure. 4.90 (FWM 1) Main feedwater pump trip. 4.91 (FWM 2) Heater drain pump trip. 4.92 (FWM 3) Feedwater leak (inside containment). 4.93 (FWM 4) Feedwater leak (outside containment). 4.94 (FWM 5) Feedwater recirculation control valve failure. A V
1 1 i l Igit Dascriotion l 4.95 (FWM6) High pressure feedwater heater i tube leak. I j 4.96 (FWM7) Feedwater regulating valve failure. 4.97 (FWM8) Feedwater regulating valve { bypass valve failure. I 4.98 (FWM9) Erratic feedwinter flow control. r 4.99 (FWM-II) Auxiliary feedwater pump trip. 4.100 (FWM 12) Auxiliary feedwater flow control valve failure. ! i j 4.101 (FWM 13) Auxiliary feedwater pump l suction leak. [ 4.102- (FWM 14) Feedwater flow transmitter O < 41 re- ! 4.103 (FWM 15) Steam generator programmed i level signal failure. l 4.104 (FWM 16) Steam generator level trans-l mitter failure, 4.105 (MSS 1) Steam leak upstream of main steam- isolaton j valve. J 4.106- (MSS 2) Steam leak downstream of main -steam isolation < r i l valve. 4.107 (MSS 3) Main steam _ isolation valve ] . drifts shut. 4.108 . (MSS 4) Non-return valve to first point (HP) feedwater heater sticks open or-
-closed, a
'I
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1 0 . l Int Descriotion j
- 4.109 (MSS 5) Non return valve to third point feedwater heater sticks open or closed.
4.110 (MSS 6) Selected steam generator safety relief i valve fails to reseat. i 4.111 (MSS-7) Steam dump valve fails to operate 4.112 (MSS 8) Steam dump valve sticks. 4.113 (MSS 9) Erratic T-average control. 4.114 (MSS-10) Reference temperature (Tref) signal to steam dumps. fail:. 4.115 (MSS-ll) Steam pressure signal to steam dumps fails. 4.116 (MSS 12) Atmospheric steam dump valve
- fails.
O 4 ii7 (ass-i>> <rr 14c ce tre, er tme as e ic steam dump valve. , 4.118 (MMS-14)l Steam flow transmitter failure. , 4.119 (MMS-15)Steampressuretransmitter (atmospheric dump control) failure. 4.120 (HMS 16) Steam pressure transmitter I (safeguards logic) failure. - 4.121 (MMS 17) Steam leak in auxiliary l feedwater pump supply line. 4.122 (NIS-1) Source range channel failure. 4.123 (NIS-2) Intermediate range channel failure. l 4.124 (NIS3) Power range channel failure. O
. _ _ . _ . . _ . . _ _ _ _ _ . _ _ _ . _ . ~ . _ ..__..._..__ __ _ __ _ . _ _ _ _ ...__ _ _..____ ___--
I i i l In.t Description 4.125 (NIS4) Intermediate range compensating voltage failure. l 1
- 4.126 (NIS 5) Source range high voltage
' cutoff failure, i i i 4.127 (NIS6) Source range fuse blown. ; 4.128 (NIS-7) Intermediate range fuse blown. 4.129 (NIS8) Power range fuse blown. 4.130 (CCT-1)_ CCT pump trip. (cet lA,lB) 4.131 (CCT-2) CCT temperature control valve failure. (TCV-CC 215) 4.132 (CCT-3) CCT supply line to selected component. leak. 4.133 (CCT-4) CCT pump suction header leak, 4.134 (PRS 1) Pressurizer safety valve < 1eakage. 4.135 (PRS-2) Pressurizer safety valve failure, i
~
4.136 (PRS-3) Pressurizer power operated relief valve leakage. ! 4.137 (PRS-4) Pressure power operated relief valve reseat failure.-- 4.138 (PRS _5) Pressurizer steam, space-leak : 4.139 (PRS-6) Pressurizer level transmitter failure, i 4.140- (PRS-7) Pressure reference level signal failure. O
I len Description 4.141 (PRS 8) Pressurizer pressure transmitter ! failure. 4.142 (PRS 9) Pressurizer spray valve failure. 4.143 (PR$ 10) Pressurizer heater control failure (BankC) 4.144 (PRS ll) Pressurizer spray valve control failure. 4.145 (PRS 12) Pressurizer master pressure control failure. 4.146 (PRS 13) Pressurizer level control failure. 4.147 (RCS1) Surgeline leak. 4.148 (RCS2) Cold leg leak. IO 4.149 (acs >> steem eeeer tor tede ,eex. 4 150 (RCS4) Reactor vessel head flange leak. 4.151 (RCS 5) Reactor coolant pump Seal No. 1 failure. 4.152 (RCS 6) Reactor coolant pump - Seal No. l l 2 failure. 4.153 (RCS7) Reactor coolant pump - Seal No.
- 3. failure.
4.154 (RCS8) Reactor coolant pump trip. 4.155 (RCS9) Reactor coolant pump locked rotor. 4.156 (RCS 10) Reactor coolant pump vibration high. 1 _ - - . . . _ . . _ . _ , _ . _. _ . . ~ . _ . _ , .
J 1 In1 Descriotion 4.157 (RCS ll) Reactor coolant system activity high. I 4.158 (RCS-12)- Fuel handling accident.
'b 4.159 (RCS 14) Hot leg narrow range temperature
! sensor failure. (Hot leg RTD) 4.160 (RCS 15) Hot leg wide range temperature sensor failure.
- 4.161 (RCS-16) Cold leg narrow range temperature sensor failure. (Cold-. leg RTD)-
4.162 (RCS-17) Cold leg wide range temperature sensor failure. 4.163 (RCS 18) Hot leg pressure transmitter failure. O 4 >e4 (acs t') 'e a rie tr># 4tter < 41#r - 4.165 (RCS 20) In-core thermocouple failure. 4.166 (RCS-21) Unexplained RCS boron concentration change. 4.167 (RHR-1) Residual heat removal pump trip. 4.168' (RHR-2) Relief valve . leak. (RV 721) l 4.169 (RHR 3) Residual heat removal' flow transmitter failure. (FT-RH 605) 4.170 (RHR-4) Residual heat removal flow control valve failure. 4.171 (RHR 5 Residual heat removal ~ pump shaft l failure. 4.172 (SIS-1) Refueling. water storage tank leak. O l.
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t 1111 Description l ( 4.173 (SIS 2) Quench spray pump failure. 4.174 (SIS 3) Recirculation spray pump failure. 4.175 (SIS-4) Recirculation spray heat exchange tube leaks to river water. 4.176 (SIS 5) High head safety injection pump failure. 4.177 (SIS 6) Low head safety injection pump failure. 4.178 (SIS-7) Containment in-leakage. 4.179 (SIS 8) Spurious safety injection signal. 4.180 (SIS 9) Spurious containment isolation Phase A signal. 4.181 (SIS-10) Automatic safety injection l ) actuation failure. 4.182 (SIS-II) Accumulator leak. 4.183 (SIS-12) Safety injection signal fails to selected valves. 4.184 (SIS-13) Safety injection line leak. l 4.185 (SIS-14) Refueling water storage tank level transmitter failure. 4.186 (SIS-15) Low head safety injection pump suction valve failure. 4.187 (TUR-1) Turbine trip. 4.188 (TVR-3) Turbine bearing high vibration 4.189 (TUR-4) Governor valve failure, q \ I O
i
\
i l ! Igit Descrietion 4.190 (TUR5) Erratic governor valve control. , j 4.191 (TUR6) Main turbine throttle (trip) valve failure. ' i l 4.192 (TVR7) Erratic main turbine throttle (trip) valve i
- control.
4.193 (TUR8) Electrohydraulic control-pump
- trip.
! 4.194 (TVR 10)-Turbine bearing lift oil pump ' i I failure. 4.195 (TVR 12) Electrohydraulic' control speed channel failure. t 4.196 (TVR-14) Turbine runback failure. 4.197 (TVR 15) Governor valve position limiter failure. 4.198 (TUR-16)Firststagepressuresignalloss O to electrohydraulic system. 4.199 (TUR-17) Moisture separated reheater steam supply . valve-failure.- ! 4.200 (TUR-18) First stage steam-pressure transmitter failure. i-e I e LO l, 4 1
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Containment Instrument' Air Compressor Trip SQT 4.1 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:12/27/89 GENERAL DESCRIPTION: The operating A' Air Compressor is tripped, Containment Inst. Air Press. decreases until "B" Air Comsressor auto starts.- The "B" Compressor is then turned off to verify furtier system depressurization will occur and then the Station Instrument Air cross connect (IA 90) is opened.to verify this system can supply Containment Inst. Air. l l 1 AVAILABLE OPTIONS: Aux 1A A Compressor Aux 1B B Compressor OPTION TESTED: Aux 1A INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL None O LIST OTHER SPECIAL CONDITIONS:
\
FINAL CONDITIONS TEST DURATION:. 1 HRS. Plant remains at 100% power. The "A" Compressor remains tripped, the "B" is restarted and returns pressure to normal. The Station Instrument Air cro3s connect (IA 90) has been closed. BASELINE DATA: Malfunction Description 6.3.4.1.1 Plant Alarm Response Procedures A6104, A6110, A6 79 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None 4
i i i BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT i ! TEST TITLE: Station Air Compressor Trip SQT-4.2 i REQUIRED BY AS!/ANS 3.5 SECTION: 4.2.2 OATETESTED:12/27/89 i GENERAL DESCRIPTION: The running air compressor is tripped off. Decrease in system presst *e is verified and auto start of standby compressor is also verified. The standby diesel is then turned off and proper operation of the j diesel compressor is verified. i 4 i AVAILABLE OPTIONS: Aux 2A "A" Compressor i Aux 2B "B" Compressor l Aux 20 "C" Compressor OPTION TESTED: Aux 2A . INITIAL CONDITIONS: 10 42 100% PWR, CORE AGE BOL l ()LISTOTHERSPECIALCONDITIONS: None FINAL CONDITIONS TEST DURATION: .9 HRS.
"A" Compressor tripped due to malfunction, "B" Compressor turned off, system pressure decreasing even though the diesel air compressor is running.
BASELINE DATA: Malfunction Description 6.3.4.1.2 Plant Alarm Response Procedure A6 98, A6 97 DEFICIENCIES: Diesel air compressor cannot properly change _ station air press. ,
~
CORRECTIVE ACTION /DATE: -TR 244 written. TR-244 has been resolved. i None ,-[}.EXCEPTIONSTAKENTOANS3.S: ew q ,-e,,,w+--_..g e -- r,_y-. ,g g3-+ nin.-ts-a.mp g.__,w,m w. 9 wip -tw y. -gg., p .v , t- e-r u y =?Mw*-g rg^%,-Y'+ 5 F y * "'
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Instrument Air Leak SQT-4.3- 1 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:12/27/89 GENERAL DESCRIPTION: The malfunction causes a large air leak in the system decreasing pressure and causing the standby air compressor to start, Inst Air is then isolated from Station Air when TV-SA 105 goes shut. All valves that fail upon loss of air are verified to fail in or to that-position. AVAILABLE OPTIONS: 0-2000 cuft/ min variable leak rate ft j OPTION TESTED: 2000 cuft/ min ' INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL O LIST OTHER SPECIAL CONDITIONS: Open close valves as necessary to verify failed position after loss of inst Air takes place. FINAL CONDITIONS TEST DURATION: 4.5 HRS. Rx Tripped, Mode _3, Instrument Air System depressurized with malfunction active, all valves that failed closed with loss of air are closed. BASELINE DATA: Malfunction Description 6.3.4.1.3 Alarm Response Procedure A6-99
~
, DEFICIENCIES: Improper response for valves TV-DA-108A, TV-CC-126, TV-CC-127-CORRECTIVE ACTION /DATE: Trouble Report 321 written. TR-321 will be resolved by December, 1991. ; EXCEPT10NS'TAKEN TO ANS. 3.5: None __-___,,u_ _ . _. _ - _ - - - . ---. - -
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Instrument Air Leak in Containment SQT-4.4 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:01/17/90 l GENERAL DESCRIPTION: A 2000 cuft/ min leak is iniated to the Containment Inst. Air System. System pressure loss is verified and auto start of Standby Air Compressor is verified. Failure position of valves supplied by this air system are verified as pressure drops, i AVAILABLE OPTIONS: 0 2000 cuft/ min, variable J OPTION TESTED: 2000 cuft/ min. ' 10-42 100% PWR, CORE AGE BOL O'INITIALCONDITIONS: is' o'"ta seccia' co"oi'ioas: "e#e l FINAL CONDITIONS TEST DURATION: 2 HRS. , Plant tripped and many problems exist due to the air operated valves going to their failed positions The Pzr. is filling u), RCPs lose cooling, Containment is heating up and the lant trip is due to higi Pzr. Press. Air pressure is not. restored as the ma function is still active.
-BASELINE DATA: Malfunction Description 6.3.4.1.4 DEFICIENCIES: None
, CORRECTIVE ACTION /DATE: N/A 4 EXCEPTIONS TAKEN TO ANS. 3.5: None
.- . . _ . _ _ . _ _ . _ _ _ . . . . , . . . . . ~ _ . _ - . . , . _ . _ . _
_ _ _ . . . _ _ . . _ - . -- , _ - - _ . . _ _; . _,.,J
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT g TEST TITLE: Station Air Header Isolation Valve f ailure SQT 4.5 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:01/03/90 GENERAL DESCRIPTION: An air leak is iniated in the station air system. As pressure drops to the setpoint at which TV SA 105 should close, it is verified that it remains open. AVAILABLE OPTIONS: Open Failure of TV SA 105 Close Failure of TV-SA 105 OPTION TESTED: Open Failure of TV-SA 105 INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIO!iS TEST DURATION: .25 HRS. Air leak in progress, station air pressure decreasing malfunction active with TV SA-105 remaining open. BASELINE DATA: Malfunction Description 14.4.7.1.5 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
l BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Leak In Aux. Steam Header SQT-4.6 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE_ TESTED:01/03/90 GENERAL DESCRIPTION: A leak of Aux Steam is iniated. Pressure decrease is verifiedt expected alarm is verified. Components served by Aux Steam are checked to verify correct response to a lack of Aux Steam. j i i i AVAILABLE OPTIONS: 0 10,000 lbm/hr. variable leak size-
-. t e
OPTION TESTED: 8,000 lbm/hr. INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1 HRS.- Plant remains at power, mal is still active, i.e., leak is still .in progress. The Aux Steam isolation valve HYV-AS 101A is closed isolating Aux Steam to the P.A.B. - I BASELINE DATA: Malfunction Description 6.3.4.1.6 ! Plant Alarm Response Procedure A2 81 ! DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A l EXCEPTIONS TAKEN TO ANS. 3.5: ~ None f i
*mW--g-+ 1 t:q - A Tv g -Pg g g r-pm 4ryy-ex-m y==-+g 9q-g y- p -e g m.; m-ggm , c4*gn y tyga.gg --m-r y y e W gp+= e '?Ne
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT l TEST TITLE: Gaseous Waste Surge Tt.nk Effluent Leak SQTL4.7 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2. DATE TESTED:01/03/90 GENERAL DESCRIPTION: A leak is iniated on the Waste Gas Surge Tank effluent
- header. The leak is verified by a decreasing tank pressure as well as expected increases in radiation levels due to the leak. .
1
\d l
l AVAILABLE OPTIONS: 01 SCFM variable leak size 1 OPTION TESTED: 1 SCFM leak rate INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Flow lined up to "B" Decay Tank Ch 9 selected on RMS Multipoint Recorder e FINAL CONDITIONS TEST DURATION: 1 HRS. Malfunction is active, leak in progress, Surge Tank pressure continues to decrease, expected radiation levels increasing. BASELINE DATA: Malfunction Description 14.4.7.1.8 1
~
DEFICIENCIES: None ' CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS 3.5: None - O
^
! i
BVPS I SIMULATOR CERTIrlCATION TEST ABSTRACT TEST TITLE: Gas Decay Tank Effluent Header Leak SQT-4.8 REQUIRED BY ASI/ANS 3.S SECTION: 4.2.2 DATE TESTED:01/16/90 GENERAL DESCRIPTION: The 1A Gas Decay Tank is lined es for discharge and then the malfunction is activated. The decay tank pressure decrease rate increases. Various radiation monitors in the PAB and ventilation system are monitored for expected increases. AVAILABLE OPTIONS: Variable Leak Rate 0-1 SCFM OPTION TESTED: 1 SCFM l INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: l Gas Decay Tank 1A must be lined up for discharge in order for test to work FINAL CONDITIONS TEST DURATION: 3 HRS. Malfunction is active but operator actions have been taken to isolate the leak and the Decay Tank Pressure remains constant BASELINE DATA: Malfunction Description 6.3.4.1.9 l DEFICIENCIES: Improper Radiation Monitor Response CORRECTIVE ACTION /DATE: TR-276 Written. TR-276 will be resolved by December 1991. D)EXCEPTIONSTAKENTOANS,3.S: (, None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: River Water Pump Trip SQT-4.9 1 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:01/IS/90 i GENERAL DESCRIPTION: The "A" operating River Water _ Pump trips expected flows and pressure changes are verified to River Water Sys. Appropriate automatic actions for back up pump starting and valve operation are also checked.- Expected " low press" alarms and auto start /stop" alarms are also checked. l ( l AVAILABLE OPTIONS: Aux 10-A Pump A Trip Aux 10-B - Pump B Trip ; Aux 10 C Pump C Trip j OPTION TESTED: Aux-10A - River Water Pump A Trip INITIAL CONDITIONS: 1C 42 100% PWR. CORE AGE - BOL ! O LIST OTHER SPECIAL CONDITIONS: Nore i l FINAL CONDITIONS TEST DURATION: .5 HRS. Plant remains at power. The "A" River Water Pump is tripped, the "B" River - Water Pump has auto started and is supplying loads. Overall River Water System operation is back to pre event. BASELINE DATA: Malfunction Description 6.4.3.1.10-Plant Alarm Response Procedures Al 82, Al-40, Al-59, Al 67, Al 48 , t DEFICIENCIES: None CORRECTIVE ACT10N/DATE: N/A .I
- EXCEPTIONS TAKEN_TO ANS. 3.5: None !
I
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Raw We, tar Pump Trip SQT 4.10 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:01/16/90 GENERAL DESCRIPTION: The malfunction is activated to trip the 6A Pump. System pressure and flow initially decrease until the 6B Pump auto starts. Appropriate alarms for pump auto start /stop and low discharge pressure should ; occur based on component conditions. ! AVAILABLE OPTIONS: Aux-11A - Pump 6A ; Aux llB Pump 6B i OPTION TESTED: Aux-llA INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE -'BOL None OLISTOTHERSPECIALCONDITIONS: FINAL CONDITIONS TEST DURATION: .5 HRS. Plant at 100% power. The 6A Pump has tripped, the 6B Pump has auto started. Raw Water System Pressure, Flow and Temperature have returned to normal. Expected alarms were received and cleared as appropriate. i BASELINE DATA: Malfunction Description 6.4.3.1.11 Plant Alarm Response Procedures A6117, A6118, A6 5) DEFICIENCIES: ^None 1 CORRECTIVE ACTION /DATE: N/A None ()EXCEPTIONSTAKENTOANS.3.5:
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT i I I ! TEST TITLE: Aux River Water Pump Trip SQT-4.ll
- REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:01/16/90-1
! GENERAL DESCRIPTION: The malfunction is actuated, pump is verified tripped via
- breaker position and pump amps. Auxiliary ocuipment associated with the pump; ,
- discharge valve, screen wash booster pump anc traveling screen pump, close or ,
!- stop as appropriate for this condition. i [ AVAILABLE OPTIONS: Aux 12A - Pump 9A Aux 128 - Pump 9B - OPTION TESTED: Aux 12A Aux River Water Pump 9A INITIAL CONDITIONS: IC-42 100% PWR. CORE AGE - BOL O LIST OTHER SPECIAL CONDITIONS: Aux River Water Pump 9A started prior to test, as it is not normally operating. , l i FINAL CONDITIONS TEST DURATION: .5 HRS. Plant operating 100%, no applicable 'fect on River Water System as River Water Pump 1A is supplying normal systen ' requirements. . ; I BASELINE DATA: Malfunction Description 6.4.3.1.12 i Plant Alarm Response Procedure Al-122
- DEFICIENCIES: None l
l l J ' + CORRECTIVE ACTION /DATE: N/A
. EXCEPTIONS TAKEN TO ANS. 3.5: None i
. , - . - . . .- .- - . . . _. .-., .~
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT
'iST i TITLE: Conti.inment Ventillation Fan Failure 'SQT-4.12 REQUIRED BY ASI//SS 3.5 SECTION: 4.2.2 DATE TESTED:01/16/90 ,
t i GENERAL DESCRIPTION: The malfunction activates the fan trip. Pump trip is-verified by alarms and indication of amps and breakers. Affect on containment is verified by checking for containment temperature' increase. 3 AVAILABLE OPTIONS: Ventillation Fans IA, 28, IC, 2A, 28, 2C, 4A, 4B OPTION TESTFi'; Ventillation Fan 1A INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL-None O LIST OTHER TJECIAL CONDITIONS: l t FINAL CONDITIONS TEST DURATION: . .25 HRS. L Plant at 100% pwr. Containment Vent. Fan lA is tripped. Containment
- temperature is slowly rising.
L BASCLINE DATA: Malfunction Description 6.34.1.13 Plant Alarm Response Procedure All-25 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A l EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS l' SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Radiation Monitor failure SQT-4.13 l O REQUIRED BY ASI/ANS 4.2.2 3.5 SECTION: DATETESTED:01/17/90 l GENERAL DESCRIPTION: RIS-CC100 (CCW Sys. Rad Monitor) is failed to 100% of scale. Proper meter, recorder and alarm indication is verified correct for , this failure. No auto actions are expected. 4 AVAILABLE OPTIONS: 0100% scale; for CH101A, CC100, 80100, GW108A, SV100, VS103A, VS204A, RM215A, RM21SB OPTION TESTED: CC100 failed to 100% INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE BOL OLISTOTHERSPECIALCONDITIONS:-None FINAL CONDITIONS -
-TEST DURATION: .: ..
Plant 100% steady state, CC100 indication normal and alarms clear. BASELINE DATA: Malfunction Description 6.3.4.1.14 Plant Alarm Response Procedures ARP A4-71, A4-72 DEFICIENCIES: None CORRECTIVEACTION/DATE: N/A G EXCEPTIONS TAKEN TO ANS. 3.5: None D
BVPS I SIMULATOR CERTIFICATION ~ TEST ABSTRACT
. .. t TEST-TITLE: Non Regenatative Heat Exchanger Tube-Leak SQT-4.14 REQUIRED BY ASI/ANS 3.5-SECTION: 4.2;2 DATE TESTED:12/19/89 GENERAL DESCRIPTION: Malfunction activates a leak in CVCS NRHX,. -letdown flow
-increases, VCT level decreases. The leak carries primary. water to the CCW system increasirig surge tank level and system activity.
3 1 AVAILABLE OPTIONS: Variable leak rate 0-100% i t OPTION TESTED: 100% leak rate L 10-42 100% PWR. CORE: AGE - BOL l ist o1"ta seccia' O ' INITIAL conoiTrons: "e e CONDITIONS: l- i FINAL CONDITIONS . TEST DURATION: .75 HRS.
. Malfunction active, letdown flow reduced, VCT-level..being maintained ~ by auto
. makeup.
BASELINE DATA: Malfunction Description 6;3.4.2.1 P1 ant _ Alarm Response' Procedure A6-37 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A , EXCEPTIONS TAKEN TO ANS. 3.5: None-
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT: i TEST TITLE: Rx Coolant Pump Thermal Barrier HX Leak SQT-4.15 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2- DATETESTED:11/30/89 ; GENERAL DESCRIPTION: Malfunction causes a leak-of seal injection water to the ,- CCW System. Increase in CCW System inventory is verified,-decrease in RCS- ,
. inventory is verified, auto operation of TV-lCC-107 is-verified. . -0verall plant-response to loss of RCS make up_is also verified to occur..
i i i h
'[
AVAILABLE OPTIONS: Variable leak 0-200 gpm selectable RCPs CCW-2A - Loop 1 RCP , CCW-2B Loop 2 RCP CCW-2C Loop 3 RCP OPTION TESTED: CCW 2A, leak rate 20.gpm, increased to 80 gpm. INITIAL CONDITIONS: 10-42 100% PWR. CORE. AGE - BOL LIST OTHER SPECIAL CONDITIONS: None-
,4 l FINAL CONDITICNS TEST DURATION: l' HRS.
Malfunction active, RCP 1A indications returned to normal except for isolation of. thermal barrier CCW flow. VCT.'is-being made up to. CCW surge tank higher than pre-event level conditions. BASELINE DATA: Malfunction Description 6.3.4.2.2 Plant Alarm' Response Procedure A3-73
' DEFICIENCIES: None l
l CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN.T0 ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: CCW Pump Trip- SQT 4.16 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:11/30/89 GENERAL DESCRIPTION: The 'A' CCW pump is tripped by malfunction. Decrease in CCW flow and press are verified as are indications of pump trip amps and breaker position. Auto response of CCW system components are also verified, i.e., "B" CCW pump auto start, AVAILABLE OPTIONS: CCW ~m "A" CCW Pump 1 CCW-3B "B" CCW Pump CCW-3C "C" CCW Pump OPTION TESTED: CCW-3A "A" CCW Pump INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL Turn off the "B" CCW Pump and allow the system OLISTOTHERSPECIALCONDITIONS: to stabilize. FINAL CONDITIONS . TEST DURATION: .45 HRS.
"A" CCW Pump tripped, "B" CCW Pump running after auto starting, CCW system flows and pressures approximately back to pre-event values.
BASELINE DATA: Malfunction Description 6.3.4.2.3 P1 ant Alarm Response Procedure =A6-33 l' DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A 3CEPTIONS TAKEN TO ANS. 3.S: None N
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: CCW Temperature Control Valve Failure SQT-4.17 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:12/19/89 GENERAL DESCRIPTION: This malfunction will cause the temperature control valve to open based on a faulty signal at the output of the CCW HX. Actual temperatures should increase as more CCW flow is bypassed around its heat exchanger. Individual components are checked for temperature increases. AVAILABLE OPTIONS: Selectable range 0 2000F OPTION TESTED: 500F 1 l c INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL (j)LISTOTHERSPECIALCONDITIONS: None l l FINAL CONDITIONS TEST DURATION: 1 HRS. Temperature indication at CCW HX outlet indicates failed valued. Actual CCW temperatures higher than pre-event. i l BASELINE DATA: Malfunction Description 6.3.4.2.4 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A
/3 None N]EXCEPTIONSTAKENTOANS.3.S:
i
BVPSLI SIMULATOR CERTIFICATION TES'T A'BSTRACT-TEST TITLE: .NRHX Temperature Control Valve f ailure- SQT-4.18 G b REQUIRED BY_ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:11/30/90 GENERAL DESCRIPTION: Malfunction will cause TI-CH-144 to fail to 500 F, appropriate alarms and auto actions verified. Domineralizers will be bypassed, 7 letdown rad monitor will isolate, coo' ling water will be cut back to the NRHX i Actual letdown line temperature will increase until:TCV-CH-144 is operated manually. AVAILABLE OPTIONS: Variable Range 50-2000F OPi!0N TESTED: 500F g INITIAL CONDITIONS: 1C-42 100% PWR. CORE AGE - BOL Q LIST OTHER SPECIAL CONDITIONS: None r
;_ FINAL CONDITIONS TEST DURATION: 1.5 HRS..
l Malfunction active, manual operation of TCV-CH-144 is returning letdown _line to normal, ! l BASELINE DATA: Malfunction Description 6.3.4.2.5 Plant Alarm Response Procedure A3-91' DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A i l.
._ o
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST. TITLE: CCW Pump Suction-Header Leak = - SQT-4.19. 1O-V REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:12/19/89 GENERAL DESCRIPTION: Leak'should cause.CCW surge tank to decrease, CCW pumps should cavitate then trip, temperatures of components supplied-by'CCW should
. increase significantly._
i i AVAILABLE OPTIONS: Variable leak rate 0-200 gpm OPTION TESTED: 200 gpm INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL f LIST OTHER SPECIAL CONDITIONS: None L FINAL CONDITIONS- TEST DURATION: -1 HRS ~. 4 Malfunction active, CCW pumps are cavitating, system component temperatures not increasing as much as-might be expected. l
-BASELINE DATA: Malfunction- Description 6.3.4.2.6 Plant Alarm Response Procedure A6-37 DEFICIENCIES: CCW system does not-seem to empty, norLdo CCW pumps trip after a-
- significant amount of cavitation.
CORRECTIVE ACTION /DATE: TR-278 written.: TR-278 has -been resolved. EXCEPTIONS-TAKEN TO ANS. 3.5: None w ,- rw - -, m., - , -- --
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: CCW To Rx Coolant Pump Leak SQT-4.20 O 4.2.2 DATE TESTED:ll/20/90 V REQUIRED BY ASI/ANS 3.5 SECTION: l GENERAL DESCRIPTION: Malfunction will cause a leak on the supply line to RCP-A , CCW supply line. CCW surge tank level should decrease, flow should decrease to l the affected RCP with a noticable temperature increase. Flow to the other components should decrease a small amount, l i l AVAILABLE OPTIONS: Variable Leak 0-800 gpm, selectable RCPs CCW-8A - RCP 1A CCW-8B RCP IB CCW-8C - RCP IC OPTION TESTED: 200 gpm leak, RCP-1A selected (
, ~g INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL
( g LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1 HRS. Improper response found. Flow to RCP same as pre-event, flow to other RCPs greater than pre-event. CCW surge tank level decreasing. BASELINE DATA: Malfunction Description Plant Response Alarm Procedures A3-75, A3-77, A3-83, A3-37 DEFICIENCIES: Improper flow response in CCW Sys to components. CORRECTIVE ACTION /DATE: TR-277 written will be resolved by December 1991. O EXCEPTIONS TAKEN TO ANS. 3.5: None b
. . _ . . . _ _ _ _ _ _ _ _ _ . _ _ . _ ... _ _ _ ______~
BVPS.I'. SIMULATOR CERTIFICATION TEST-ABSTRACT TEST TITLE: Rx Coolant Pump Seal Water HX Tube Leak' 'SQT-4.21-REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE' TESTED:ll/30/89-GENERAL DESCRIPTION:' When the malfunction is activated,' CCW-water will leak into the CVCS via the tube leak. A decrease in CCW surge tank level-is i verified, the dilution caused by CCW water-is verified and the back pressure i effect causing #1 seal leak off to decrease is verified. ; i t AVAILABLE OPTIONS: Variable rate 0-100% ,
- i OPTION TESTED: 100%
INITIAL CONDITIONS: IC-42' 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Line up. auto makeup to CCW surge tank. FINAL CONDITIONS . .
-TEST DURATION: 1 HRS.
Malfunction active, CCW system leaking into C.V.C.S. RCS dilution occurring with rods moving in to compensate, i BASELINE DATA: Malfunction Description 6.3.4.2.9 '
'0EFICIENCIES: None i
i- CORRECTIVE ACTION /DATE: N/A ! A EXCEPTIONS TAKEN TO ANS. 3.5: None-lU u l .
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT = H TEST TITLE: Condensate Pump Trip SQT-4.22 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 -DATETESTED:04/16/90'. GENERAL DESCRIPTION: The test _is-done at 100%, then 25% power. From 100% the 1A pump is tripped, effects on feed flow and press are verified. ; Alarms - 4 should come in for pump trip, low press. and-low feed flow as well as for an j expected Rx trip. At 25% the test is run with IB pump off to verify its' auto i start when the 1A pump trips. t AVAILABLE OPTIONS: CND-1A - 1A Condensate Pump CND 1B - 18 Condensate Pump t OPTION TESTED: CND-1A [ l INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE BOL LIST OTHER SPECIAL CONDITIONS: Use IC 45, 25%, BOL for auto start feature test. FINAL CONDITIONS TEST DURATION: 1.25 HRS. Ist Option - Rx Tripped, lA Condensate Pump tripped, IB Condensate Pump running 2nd .0ption - Plant-at- 25% pwr.,1 A Condensate Pump- tripped, LIB Auto started-i. BASELINE DATA:. Malfunction Description 6.3.4.5.1 _ B.V.P.S. Alarm Response Procedures A7-1, A7-5, . A7 DEFICIENCIES: None. CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None.
-l BVPS I SIMULATOR CERTIFICATION! TEST ABSTRACT !
TEST TITLE: Feedwater Heater Bypass Valve f ailure' SQT-4 23 REQu! RED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:04/17/90 GENERAL DESCRIPTION: The malfunction -causes the heater bypass valve to open. Feedwater temperature decreate is verified, affects on feedwater flow increase are verified. Rx power increases to the point where a turbine runback occurs. AVAILABLE OPTIONS: Selectable Position Failure (0-100% Open) 1 OPTION TESTED: 100% Open INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE BOL ()LISTOTHERSPECIALCONDITIONS: None FINAL CONDITIONS TEST DURATION: .75 HRS. Malfunction active, feedwater heater bypass valve open, power reductionLin progress due to OP Delta T' runback occurrance. BASELINE DATA: Malfunction Description 6.3.4.5.2. Plant Alarm Response Procedure A6-88 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A
/ None ,
~ U) EXCEPTIONS TAKEN TO ANS. 3.5: 1
BVPS I SIMULATOR CERTIFICATIONlTESTL ABSTRACT
+
. TEST TITLE: Condensate Pump-Discharge: Header leaki SQT-4.24-REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:04/17/90 GENERAL-DESCRIPTION: The malfunction is activated and:the effects of the leak. !
on condensate pump. discharge pressure.and main feed pumpisuction are verified. 3 Feedwater flow will decrease and S/G levels,will decrease'to the.Rx trip. setpoint. Condensate pumps.are tripped and a resultant change,in vacuum is: noted.
- i AVAILABLE OPTIONS: Variable leak' rate 0-10,000 gpm OPTION TESTED: 10,000 gpm leak ratt INITIAL CONDITIONS: 10-42 100% FWR.- CORE AGE -LBOL ~
n LIST OTHER SPECIAL CONDITIONS: None Li FINAL CONDITIONS TEST DURATION: . .75 HRS. . Leak in progress, Rx tripped, condenser vacuum' decreasing both condensate pumps tripped as well as the 1A main feed pump. i
- BASELINE DATA: Malfunction-Description 6.3.4.5.3 Plant- Alarm Response Procedures A7-05 and A7-061 it
.j DEFICIENCIES: None- i
]
CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None t
I BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Feedwater Heater Tube Leak SQT-4.25 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:04/17/90 GENERAL DESCRIPTION: The leak occurs and affects on condensate pump. discharge press. decrease and M.F.P. discharge press. decrease are verified. Heater drain tank level and pump operation are verified as they try to compensate for the leak. i AVAILABLE OPTIONS: CND-5A (Train A) CND 5B (Train B) Variable leak rate 0 10,000 gpm OPTION TESTED: CND-5A INITIAL CONDITIONS: 1C-42 -100% PWR. CORE AGE - BOL l LIST OTHER-SPECIAL CONDITIONS: None-t FINAL CONDITIONS TEST DURATION: .75 llRS. Leak in progress, both heater drain pumps in operation,- aiaintaining.cdequate-suction to the main feed pumps. BASELINE DATA: Malfunction Description 6.3.4.5.5 - Plant Alarm Response Procedure:; A6-71 and A7-09 i DEFICIENCIES:- None L CORRECTIVE. ACTION /DATE: N/A (' EXCEPTIONS TAKEN TO ANS. 3.5: None
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BVPS:1-SIMULATORCERTIFICATION,TESTiABSTRACT
. TEST TITLE: 4th Point Heater Level Control Value' Failure SQT-4;26_ y REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE: TESTED:04/18/90L GENERAL DESCRIPTION: The valve is failed closed and the heater level:should increase, a small temp. effect may be seen on _feedwaterl temperature and possibly a small effect. on. Rx _ plant temperatures. . A high . level Lalarm will 3 occur on the affected heater and will result' in' a decreasing hotwell level.-
Lj
~'
-AVAILABLE OPTIONS: .CND-6A = FW-E-4A -
CND-6B - FW E-4B 0-100%' of- valve position . , [ t OPTION TESTED: ~ CND-68, 0% Valve Position , 4 INITIAL CONDITIONS: IC-42 100% PWR.- . CORE. AGE-BOLL >
. ' LIST OTHER SPECIAL CONDITIONS:
None. p q FIhAL CONDITIONS TEST DURATION: 1 HRS ~. . 1
- Halfunction active, -4th Point Heater level. increasing,. Tavg -slightly higher than initial value, Condensor hotwell level increasing, l
i BASELINE DATA: Malfunction Description 6.3.4.5.6 Alarm Response Procedure A7-13-- t I I DEFICIENCIES: None.
'l J f CORRECTIVE ~ ACTION /DATE: N/A .
h EXCEPTIONS TAKEN TO None ANS. 3.5: I
i BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: 5th Point Heater Level Control Valve Oscillation- SQT-4.27-REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:04/17/90 l GENERAL DESCRIPTION: The malfunction is activated and the cycling of the ' effected heater cycles up and down over the appropriate period.- Only a very small effect is expected to be seen in the overall plant response. AVAILABLE OPTIONS: 0-50% Oscillation,.0-999:sec period CND-7A Train "A"' CND-7B Train "B" OPTION-TESTED: CND-78, 50% oscillation, 300 sec' period r e INITIAL CONDITIONS: IC-42 - 100% PWR.- CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None w , fit!AL CONDITIONS TEST DURATION: 1 HRS. . -- Malfunction active,-level cycling toward low level alarm =setpoint in the 5B feedwater heater. BASELINE DATA: Malfunction Description 6.3.4.5.7 Plant Alarm Response Procedure A7 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
l BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT l TEST TITLE: Air: Ejector Failure ~SQT-4.28 1 REQVIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:04/18/90 , GENERAL DESCRIPTION: When the malfunction is activated, a decrease in vacuum is verified as well as the alarm. Operator action -is taken to place the failed air ejector out of service and to place the standby one _in service and note: a .j vacuum increase. 3 AVAILABLE OPTIONS: CND 8A - 1A Air Ejector CND-8B 18 Air Ejector-OPTION TESTED: CND-BA - 1A Air Ejector INITIAL CONDITIONS: 1C 100% PWR. .. CORE AGE - BOL Ensure steam jet air ejector IA is on'line and O LIST IB is OTHER secured. SPECIAL-CONDITIONS: FINAL CONDITIONS TEST-DURATION: 1.5 HRS.~ Failed air ejector out of service, standby air ejector placed in service, vacuum is increasing. BASELINE DATA: Malfunction Description 6.3.4.5.8 Plant Alarm Response Procedure ~A7-03 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A I EXCEPTIONS TAKEN TO ANS. 3.5: None 1
BVP5 1 SIMULATOR CERTIFICATION TEST: ABSTRACT j TEST TITLE: Vacuum breaker Leak. - SQT 4.29:- j REQUIRED BY.ASI/ANS 3.5 SECTION: 4.2.2. DATE-TESTED:ll/29/891 1 GENERAL DESCRIPTION:- The malfunction is activated and the expected vacuum decrease:is verified.- The appropriate alarms are verified as well:as the expected low low vacuum turbine trip. l l 1 AVAILABLE OPTIONS: 0-100% valve. position OPTION TESTED: 50% open i INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE --BOL- -LIST OTHER SPECIAl. CONDITIONS: -None-1 FINAL CONDITIONS . TEST DURATION: .45 HRS. Turbine and reactor tripped due to low low vacuum turbine-trip.- BASELINE. DATA: Malfunction Ot<scription 6.3.4.5.9L Plant- Alarm Response Procedures- A7-03.and A7-04: DEFICIENCIES: None
-CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN-TO ANS. 3.5: None- -
BVPS I SIMULATOR CERTIFICATION TEST, ABSTRACT TEST-TITLE: _ Condenser' Tube Leak
'SQT-4.30-REQUIREDBYASI/ANS3.5SECTION: 4.2.2 DATETESTED:04/17/90- l GENERAL DESCRIPTION: Malfunction leak is activated, increase in hotwell level is_ verified. Expected alarms are verified for *hotwell level- and _* secondary; chemistry. Operator action is _taken to isolate the-fa ited water box and proper effects are noted.
l
- NOTE: Expected alarms don't work on_ Cert? Pack A but work on normally used - !
Trng Pack. , 4 AVAILABLE OPTIONS: Variable Leak 0-I,000 gpm OPTION TESTED: 1,000 gpm INITIAL CONDITIONS: 10-42 . 100% PWR, CORE AGE -'BOL
' LIST OTHER SPECIAL CONDITIONS: None.
b v FINAL CONDITIONS TEST DURATION: L1.25 HRS. Malfunction active, faulty water box is' isolated, condenser vacuum and hotwell-level returning to normal. BASELINE DATA: Malfunction Description 6.3.4.5.101 Plant Alarm Response Procedures A7-02, A6-127-DEFICIENCIES: None. CORRECTIVE ACTION /DATEi Expected alarms da EQEh on normal training pack. EXCEPTIONS TAKEN TO ANS. 3.5: N/A. O
BVPS l' SIMULATOR CERTIFICATION TEST ABSTRACT-l TEST TITLE: Cooling Tower Pump Trip
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SQT 4.31 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:12/19/89 GENERAL DESCRIPTION: The pump is tripped by the malfunction and the amps decrease, breaker position and auto stop alarm are-verified.- Condense vacuum decrease with the resulting electrical generator output decrease are also verified. Cooling _ tower pump discharge temperatures slowly increase, i AVAILABLE OPTIONS: CND-12A - Pump 1A CND 12B - Pump 1B CND-12C - Pump 10 CND-120 - Pump-ID OPTION TESTED' CND-12C Cooling tower pump IC INITIAL CONDITIONS: 1C-42 100% PWR. CORE AGE --BOL , ( LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS . TEST ~ DURATION: =1.'5 HRS. Vacuum decrease has stopped, due to reduction of generator output power. Approximately 20 mwt'. BASELINE DATA: Malfunction Description -6.3.4.5.12: Plant Alarm Response Procedure A6-83 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A P EXCEPTIONS TAKEN TO ANS. 3.5: None d
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. s BVPS I' SIMULATOR CERTIFICATION TEST 1 ABSTRACT-
- TEST TITLE: Cooling-Tower Pump Discharge Valve Failure' .SQT-4.32
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REQUIRED BY ASI/ANE 3 S SECTION: 4.2.2- .DATE-TESTED:11/19/89 GENERAL DESCRIPTION: This test verifies the valve will fail closed-when the malfunction is activated and that the cooling tower pump will; trip when the i valve is closed. i 1
'I AVAILABLE OPTIONS CND-13A - Valve 110A CND-13B - Valve 1108 CND 13C - Valve'110C CND-13D . Valve 110D OPTION TESTED: CND-13B l
10-42 100% PWR, : CORE AGE - 80L' O' is' otata seccia' INITIAL conoittons: "e#e CONDITIONS: FINAL CONDITIONS -TEST DURATION: .25 HRS. Valve 110B closed, B Cooling Tower Pump tripped, -condenser-' vacuum decreasing. BASELINE DATA: Malfunction Description 6.3.4.5.13 Plant Alarm Response' Procedure A6-84 DEFICIENCIES: None , CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
l BVPS I SIMULATOR CERTIFICATION TEST ABSTRACTi Cl l TEST TITLE: Condensate Recirc Valve FailureE SQT-4.33 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 -DATE TESTED:11/19/89- 1 GENERAL DESCRIPTION: The malfunction fails FCV-CNIO1-open. Decreased flow to-the tsain feed pumps is verified. Appropriate alarms associated:with the ! decreased mair, feed water flow activate. The "A";MFW pump-trips and a_Rx trip results. _ i 5 AVAll.ADLE OPTIONS: - Variable 0-100% open OPTION TESTED: 100% open INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL- ! LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: l'.0 HRS. Reactor has tripped on lo level S/G and Stm f_ low > feed : flow. Recire flow has been manually established. BASELINE DATA: Malfunction Description L6.3.4.5.14 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None-a I
v BVPS-I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Hotwell Level Control Valve-Failure SQT-4.34 REQUIRED BY ASI/ANS 3.5 SECTION:. 4.2.2 DATE TESTED:ll/19/89 GENERAL DESCRIPTION: When LCV-102 fails open,-it should iause hotwell level to e increase and secondary demin storage tank to_ decrease. - Av the level in the hotwell increases, the spill valve should open and limit the amount of increase: The operator will then take control to restore levels to normal. F AVAILABLE OPTIONS: Variable 0-100% of full open CND-15A - LCV-101 CND-158 - LCV 102 i l OPTION TESTED: CND-ISB,100*,' open l INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - MOL LIST OTHER SPECIAL CONDITIONS: None l FINAL CONDITIONS TEST-DURATION: .45 HRS. Manual control- of the hotwell level using MOV-CN-105. Plant conditions returning to normal. BASELINE DATA: Malfunction Description 6.3.4.S.15 - DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A 4 - pa EXCEPTIONS TAKEN T0 ANS. 3.5: None
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BVPS I SIMULATOR-CERTIFICATION TEST-ABSTRACT ll TEST TITLE: Vacuum Priming Pump Vacuum Breaker Valve Failure SQT-4.36 REQUIRED BY ASI/ANS 3.3 SECTION: 4.2.2 DATE TESTED:11/19/89 - GENERAL DESCRIPTION: The malfunction-will cause a slow decrease -in condenser vacuum as_ air begins to build up in the circulating water system. _ Cooling .! Tower pumps will eventually cavitate, the auto start- of the second-vacuum ; priming pump will not restore conditions to normal.- ' l l 1 AVAILABLE OPTIONS: CND-17A -_ Valve 102A- ' CND-178 - Valve 102B-OPTION TESTED: CND-17A INITIAL CONDITIONS: IC-42 100%'PWR. . CORE- AGE - MOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .5 HRS. Condenser vacuum oscillating, Cooling Tower pumps cavitating,cvacuum lower than beginning of transient. BASELINE DATA: Malfunction Description 6.3.4.5.17
- Plant Alarm Response Procedure A6-77 DEFICIENCIES: Condenser vacuum oscill'ates CORRECTIVE ACTION /DATE: TR-282 written.
TR-282 has been resolved. -
-EXCEPTIONS TAKEN-TO ANS. 3.5: None
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.. I BVPS I SIMULATOR CERTIFICATION TEST' ABSTRACT TEST TITLE: Vacuum Priming Pump Trip SQT-4.37 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:ll/19/89.~ J GENERAL DESCRIPTION: The operating Priming Pump "A" is tripped. The expected
.- alarm is verified. - As vacuum-decreases the ."B" Vacuum Priming Pump auto : starts, restoring vacuum. , 1 AVAILABLE OPTIONS: CND 18A Pump A CND-18B Pump B OPTION TESTED: CND-18A O INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CCNDITIONS: Ensure A Pump in Run, B Pump in Auto FINAL CONDITIONS TEST DURATION: ~ .25 HRS.
"B" Priming Pump running and restoring vacuum -
BASELINE DATA:- Malfunction Description 6.3.4.5.18 Plant Alarm Response Procedure A6-68 DEFICIENCIES: None r CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Loss of Rod Drive MG Set SQT-4.38 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:10/20/89 GENERAL DESCRIPTION: When the first Rod Drive MG Set is tripped the alarm comes on, but no Rx Trip should occur. Upon trip)ing the second Rod Drive MG Set the CRDM's have no power and rods drop into tie core. AVAILABLE OPTIONS: CRF-1A 1A MG Set Trip CRF-1B 18 MG Set Trip OPTION TESTED: Both of the above O INITIAL CONDITIONS: 1C-42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .25 HRS. Rx Tripped, Both Rod Drive MG Sets Tripped BASELINE DATA: Malfunction Description Alarm Response Procedures A4-99, A4-107, A4-97, A5-14 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS 3.5: None ;
BVPS I SIMULATOR CERTIFICATION TEST-ABSTRACT. TEST TITLE: Failure of Rods to Move - SQT-4.39 REQUIRED BY ASI/ANS 3.5 SECTION: 4. 2. 2. DATE. TESTED:10/20/89 GENERAL DESCRIPTION: The malfunction is activated to prevent both auto and manual rod motion. When turbine load is reduced 10%, failure of auto rod-motion is verified. RCS temperatures & Pzr level will increase. The operator will then take manual control of rods and attempt to move them and they will not move. AVAILABLE-OPTIONS: CRF-2A Auto Motion Failure CRF-2B Manual Motion: Failure OPTION TESTED: CRF-2A, CRF 2B INITIAL CONDITIONS: 10-42 100%-PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS- TEST DURATION: .45 HRS. Power Level = 90%, Tavg higher than Tref due to control- rod failure BASELINE DATA: . Malfunction Description 6.3.4.6.2 DEFICIENCIES: 'None CORRECTIVE ACTION /0 ATE: N/A O EXCEPTIONS TAKEN TO ANS 3.5: None
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1 i. BVPS I SIMULATOR CERTIFICATION TES ABSTRACT t L v TEST TITLE: Improper Bank Overlap SQT-4.40 REQUIRED BY AS!/ANS 3.5 SECTION: '4.2.2 DATE TESTED:10/20/89 GENERAL DESCRIPTION: The malfunction is set to cause Control. Banks.B & C to move at the same time during an Rx Start Up. When this occurs,La Rod Control Urgent Alarm stops rod motion. -The problem is then corrected and normal overlap operation verified. Improper overlap is then verified between Banks A
& B as the Start Up is tried again.
AVAILABLE OPTIONS: CRF-3A Bank A & B-Improper Overlap ' CRF-38 Bank B & C Improper Overlap CRF-3C Bank CL& D Improper Overlap Variable Counter-0-999 steps OPTION TESTED: CRF-3A, CRF-3B 200 steps, 50 steps l' INITIAL CONDITIONS: 10-4B 0%-PWR, CORE AGE.--M0L LIST OTHER SPECIAL CONDITIONS: FINAL'CONDIT1GNS TEST. DURATION: .45 HRS. Plant /Rx Start Up in progress with improper overlap- between Control Banks
-A and B l
. BASELINE DATA:1 -Malfunction Description 6.3.4.6.3 DEFICIENCIES: None
-CORRECTIVE ACTION /DATE: N/A 0: EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Dropped Centrol Rod SQT-4.41 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:10/20/89 GENERAL DESCRIPTlvN: The nialfunction caused Rod F-8 to drop into the core. A negative rate trip should cause a Rx trip. Appropriate alarms indicating rod drop are verified as well as the First Out Rx Trip annunciator. AVAILABLE OPTIONS: Any Control Rcd Stationary or Moveable Coil Failure OPTION TESTED: Rod F-8, Stationary Coil O INITIAL CONDITIONS: 10 42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1 HRS. Rx Tripped, all post Rx trip conditions as expected BASELINE DATA: Malfunction Description 6.3.4.6.4 Plant Alarm Response Procedures A4126, A4 69, A5-14 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None
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'l BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Uncontrolled Rod Motion SQT-4.42 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:10/25/89 GENEPAL DESCRIPTION: Auto outward rod motion is initiated, Tavg increase is verified, change to OP & OT AT setpoints verified, turbine runback verified, reactor trip is verified. AVAILABLE OPTIONS: Rod speed 8-72 steps / min. (CRF 5A or SB) Auto or Manual failure OPTION TESTED: CRF-5A Auto, 8 steps / min. f L INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Mal RCS-21 is used to cause control Band D rods to go into Ril prior to initiating Mal CRF 5 so as to get maximum transient from this test FINAL CONDITIONS TEST DURATION: 1 HRS. Rx tripped due to turbine trip BASELINE DATA: Malfunction Description 6.3.4.7.5 Abnormal Operating Procedure 1.53.04.1.1.3 DEFICIENCIES: None CF;RECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None
j i BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT l TEST TITLE: Automatic Rod Speed failure SQT-4.43 REQUIRED BY ASI/ANS 3.S SECTION: 4.2.2 DATE TESTED:10/20/89 GENERAL DESCRIPTION: The malfunction is activated, then turbine power is 4 reduced, when rods begin to move in auto the immediately move at and remain moving at 72 steps per minute. When switched to manual rod motion stops and demand speed goes to 48 steps per minute. AVAILABLE OPTIONS: Variable Speed 0-72 steps / minute OPTION TESTED: 72 steps / minute lO j INITIAL CONDITIONS: 10 42 100/. PWR. CORE AGE BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .25 HRS. Plant at 85% Power, Rod motion stopped, rods in manual, Tavg = Tref l BASELINE DATA: Malfunction Description 6.3.4.6.6 DEFICIENCIES: None , CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None
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l BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT O V TEST TITLE: Tref failure SQT 4.44 REQUIRED BY ASl/ANS 3.5 SECTION: 4.2.2 DATE TESTED:07/09/90 GENERAL DESCRIPTION: When failure occures rods are verified moving in. Rx Power, Tavg and Pzr Level and Pressure should decrease. Al should decrease, turbine load will decrease when the valve position limit is reached. ' Tavg will reach Tref AVAILABLE OPTIONS: Variable 547'F - 578'F ! OPTION TESTED: 547' l b INITIAL CONDITIONS: IC- 42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None l FINAL CONDITIONS TEST DURATION: 1.5 HRS. Rx Critical, Tavg = 547'F Turbine load reduced due to low steam line pressure BASELINE DATA: Malfunction Description 6.3.4.6.7 Plant Alarm Response Procedure A4-46 Abnormal Operating Procedure 1.53.C.4.1.1.3 DEFICIENCIES: None l l CORRECTIVE ACTION /DATE: NA EXCEPTIONS TAKEN-T0 ANS. 3.5: None
l 1 BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: 1.R.P.I. Loss of Voltage SQT 4.45 REQUIRED BY ASI/ANS 3.5 SECTION: 4 . 2 . ?, DATE TESTED:01/23/90
- GENERAL DESCRIPTION
- When malfunction is activated Rod M 4 should indicate "0" steps and the rod bottom light should activate. Alarms associated with the rod being on the bottom of the core should activate.
AVAILABLE OPTIONS: Rods J 13, G 7, B 10, F 4, M-4, K 6 OPTION TESTED: Rod M-4 INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .5 HRS. Halfunction active, plant at initial conditions except for failed rod position ir,dicator and associated alarms. BASELINE DATA: Malfunction Description 6.3.4.6.8 l DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A C) V EXCEPTIONS TAKEN TO ANS. 3.5: None
l l t BVPS 1 SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Rod Position Step Counter Failure SQT 4.46 i REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:01/23/90 GENERAL DESCRIPTION: A turbine load reduction is performed with rods in auto. Rod motion is verified using IRPI while the failed counter does not move. ; AVAILABLE OPTIONS: Various Counters A1, A2, 81, 82, C1, C2, Dl, D2 Failure Rate 0, 0.5, 2 times normal OPTION TESTED: Dl, 0 O INITIAL CONDITIONS: 1C.42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURA'10N: .5 Hno, Power Reduction stopped, the failed counter has not moved for control bank D while the other has. BASELINE DATA: Malfunction Description 6.3.4.6.10 DEFICIENCIES: None l CORRECTIVE ACTION /DATE: N/A 1 O EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS 1 SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Stuck Rod SQT-4.47 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:01/23/90 GENERAL DESCRIPTION: A load reduction is conducted and as Control Bank C begins to move; Rod M 4 is verified stuck. Power distribution effects are verified as well as appropriate alarms. The Rx is then tripped and rod M 4 is again verified stuck out. AVAILABLE OPTIONS: Mode - Electrical or Mechanical Any rod can be selected OPTION TESTED: Rod M-4, Mechanical INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .9 HRS. l The Rx is tripped with Rod M-4 still stuck out l BASELINE DATA: Malfunction Description 6.3.4.6.11 Abnormal Operating Procedure 1.1.6 Alarm Response Procedure A4-76 l DEFICIENCIES: Power distribution effects of stuck rod not seen CORRECTIVE ACTION /DATE: TR-280 written. To be resolved by December 1992. O EXCEPTIONS TAKEN TO ANS 3.5: None
BVPS ! SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Reactor Trip Failure SQT-4.4B REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:01/23/90 GENERAL DESCRii'iiON: The turbine is tripped via a low condenser vacuum problem which also blocks s: cam dump operation. The Rx does not trip when the turbine trips, various alarmi associated with a Tavg increase are verified, RCS pressure increases and the PORV's open. The Reactor is then tripped using the Rod Drive MG Sets, s AVAILABLE OPTIONS: CRF-12A Auto Trip Failure CRF-128 Manual Trip Failure OPTION TESTED: CRF-12A O-INITIALCONDli10NS: 1C-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Control Rods placed in Manual FINAL CONDITIONS TEST DURATION: 1 HRS. Rx Tripped via rod drive MG Set trips Plant conditions normal for post trip conditions l BASELINE DATA: Malfunction Description 6.3.4.6.12 OM Ch b3A FR-S.1 and Background Document DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Rod Stop Failure SQT 4.49 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:01/31/90 GENERAL DESCRIPTION: Af ter the malfunction is activated with rods in auto, the operator borates to decrease Tavg and cause outward rod motion in auto. Movement past the rod stop is verified, manual control is taken then to stop rod movement. l AVAILABLE OPTIONS: N/A j OPTION TESTED: N/A !
]' INITIAL CONDITIONS: 10 45 25% PWR, CORE AGE MOL i LIST OTHER SPECIAL CONDITIONS:
None l FINAL CONDITIONS TEST DURATION:1.75 HRS. Rx Power - 25%, Control Bank "0" Rods Fully Withdrawn Beyond Rod Stop BASELINE DATA: Malfunction Description 6.3.4.6.16 Plant Alarm Response Procedure A4-125 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None
l 1 ! BVPS I SikAATOR CERTIFICATION TEST ABSTRACT OTESTTITLE: Reactor Trip SQT-4.50 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:01/24/90 ! GENERAL DESCRIPTION: The rods drop in when the "A" Trip Breaker open, then the ! negative rate trip opens the "B" Breaker. Procedures E-0 and ES-0.1 are used
- to verify all expected post trip responses..
i l I 1 i i AVAILABLE OPTIONS: CRF 14A Trip Breaker A CRF-14B Trip Breaker B i ) I i OPTION TESTED: CRF 14A i INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None I FINAL CONDITIONS TEST DURATION: 1 HRS. Rx Tripped, E 0 and ES 0.1 steps pertaining to the. Reactor Trip have been. verified and/or carried out. i BASELINE DATA: Halfunction Description 6.3.4.6.14 OM Ch 53 A.1 E-0 and Background Document L DEFICIENCIES:' None i J CORRECTIVE ACTION /DATE: NA y O EXCEPTIONS TAKEN TO ANS. 3.5: None i
i BVPS 1 SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Letdown Pressure Regulator Valve Failure SQT-4.51 RE0VIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:11/07/89 GENERAL DESCRIPTION: When the valve is failed shut letdown flow is verified to stop. Pressure builds up and the Letdown Relief Valve opens. VCT level should decrease, manual control is taken and should have no effect. AVAILABLE OPTIONS: Failed Position 0 100% Open OPTION TESTED: 0% Open O INITIAL CONDITIONS: 10 42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None , FINAL CONDITIONS TEST DURATION: .25 HRS. Letdown flow stopped, PCV CH145 in manual but will not open. VCT level decreasing. BASELINE DATA: Malfunction Description 6.3.4.4.1 Plant Alarm Response Procedure A3-123 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS 1 SIMULATOR CERTIFICATION TEST ABSTRACT C TEST TITLE: Letdown Relief Valve Failure SQT 4.52 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:ll/07/89 GENERAL DESCRIPTION: When the malfunction activates, Relief Line temperature is verified to increase, letdown flow decrease is verified, VCT level decrease verified and Auto Makeup occurs. l l AVAILABLE OPTIONS: None OPTION TESTED: Valve fails Open O INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .5 HRS. Malfunction Active, Letdown flow low, VCT Level Decreasing, PRT Level increasing l BASELINE DATA: Malfunction Description 6.3.4.4.2 Alarm Response Procedure A3123 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None i
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- BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE
- Letdown Line Leak in Containment SQT 4.53 RE0"! RED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:ll/08/89 GENERAL DESCRIPTION: Letdown Flow decreases, PZR Level and Press. decrease Containment Press. increases, Reactor Trip and S.I. occur. Operator c6rries out E 0 and E 1 and documents steps accomplished.
l AVAILABLE OPTIONS: Variable Leak Rate 0 1000 gpm OPTION TESTED: 350 gpm O INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 2 HRS. Malfunction Active, Rx Tripped, Si and CIA actuation, E 0 and E-1 completed BASELINE DATA: Malfunction Description 6.3.4.4.3 OM Ch S3A E-0, E-1 i DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A 1O EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Plugged Seal Water injection Filter SQT-4.54 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:ll/08/89 GENERAL DESCRIPTION: Seal Injection flow decreases to zero, Low Seal Injection flow alarm actuates, Pressurizer level should decrease. Seal Injection flow is then isolated, and the malfunction cleared which simulates switching filters. AVAILABLE OPTIONS: Variable Flow Rate 0100% OPTION TESTED: 0% O INITIAL CONDITIONS: 1C-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: FINAL CONDITIONS TEST DURATION: 1 HRS. Malfunction Cleared, Seal Header Flow Control Valve rester'.ng seal injection flow to normal BASELINE DATA: Malfunction Description 6.3.4.4.4 Plant Alarm Response Procedures A3 52, A3-78 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A A V EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: V.C.T. Level Control Valve Failure SQT 4.55 REQUIRED BY AS!/ANS 3.5 SECTION: 4.2.2 DATE TESTED:05/25/90 GENERAL DESCRIPTION: Level Control Valve LCV CH ll5A begins to direct 100% of Letdown Flow to the VCT rather than the Degassifier when the malfunction activates. The VCT level is raised using Makeup to verify LCV CH-115A does not return Letdown to ths De'ja s si fier. AVAILAB'.E OPTIONS: 0% - 100% OPTION TESTED: 0% INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE BOL LIST OTHER SPECIAL CONDITIONS: VCT set for continuous Degas FINAL CONDITIONS TEST OVRATION: 1.25 HRS. l Halfunction, Letdown flow going direct to VCT and not the Degassifier. VCT Level and Pressure increasing due to Manual Make Up. 1 ! BASFLINE DATA: Malfunction Description 6.3.4.4.5 Alarm Response Procedure A3-53 DEFICIENCIES: None l CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS 3.5: None
i l BVPS 1 SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: VCT Degass Level Control Valve failure SQT-4.56 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:05/25/90 GENERAL DESCRIPTION: When activated the valve diverts flow to the Coolant i Recovery Tank and VCT level will decrease, VCT level will decrease until l LCV CH ll5A tries to restore level, level will decrease at a slower rate. AVAILABLE OPTIONS: 0 100% Flow to VCT OPTION TESTED: 0% Flow to VCT I INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Set up for 60 gpm continuous Degas flow FINAL CONDITIONS TEST DURATION: 1.5 HRS. VCT level = 12%, LCV-CHil5A is diverting flow to VCT l BASELINE DATA: Malfunction Description 6.3.4.4.6 Alarm Response Procedure A3-53 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANT. 3.5: None
l BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT n U TEST TITLE: Dilution Accident SQT 4.57 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:ll/15/89 GENERAL DESCRIPTION: The dilution flow will change VCT inventory, the variable for RCS Boron concentration XRCSC will decrease, Tavg will increase and control rods will move in to compensate. This test was run twice with the different letdown flows. AVAILABLE OPTIONS: Dilution Leak Rate 0 50 gpm OPTION TESTED: 50 gpm 4 INITI A'. CONDITIONS: 10-42 1005'. PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: For second test run set up for 60 gpm letdown flow FINAL CONDITIONS TEST DURATION: 2.5 HRS. Dilution in progress with rods moving in to reduce Tavg BASELINE DATA: Malfunction Description 6.3.4.4.7 DEFICIENCIES: None CORRECTIVE ACTION /0 ATE: N/A O V EXCEPTIONS TAKEN TO All.. .5: None l 1
BVPS I SIMULATOR CERTiflCATION TEST ABSTRACT TEST TITLE: Boration Accident SQT-4.58 REQV! RED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:ll/15/89 GENERAL DESCRIPTION: The malfunction causes leakage past the Emergency Boration Valve, RCS boron concentration increase (XRCSC) is verified. Tavg begins to drop and control rods move out. 1 AVAILABLE OPTIONS: 0 20 gpm Boration Flow Rate s OPTION TESTED: 20 gpm INITIAL CONDITIONS: 1C-42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Dilute Rods down to RIL prior to test start FINAL CONDITIONS TEST DURATION: .5 HRS. RCS Boron concentration increasing, Tavg decreasing, control rods moving out to restore Tavg BASELINE DATA: Malfunction Description 6.3.4.4.8 DEFICIENCIES: None CORRECTIVE ACTION /0 ATE: N/A EXCEPTIONS TAKEN TO ANS 3.5: None l
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT OTESTTITLE: Boric Acid flow Transmitter Failure SQT 4.59 l REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:05/24/90 GENERAL DESCRIPTION: VCT Level is decreased to the point where make up , indicates. The malfunction is then actuated and Boric Acid Flow decreases with I a corresponding increase in PG Water Flow. l I l AVAILABLE OPTIONS: -100%/4100% % of present value change OPTION TESTED: 1O INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Maximum Letdown Flow is Lined Up To Degassifier and to the Coolant Recovery Tank FINAL CONDITIONS TEST DURATION: 2.5 HRS. i Malfunction Active. Auto Make Up to the VCT is supplying less Boric Acid then set in due to the Flow Transmitter problem. BASELINE DATA: Malfunction Description 6.3.4.4.9 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Blender Flow Transmitter Failure SQT 4.60 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:05/24/90 GENERAL DESCRIPTION: When Auto Make Vp begins, the failed Transmitter will indicate 0 gpm. Actual flow will increase to maximum. The Flow Deviation Alarm will stop all blender flow. VCT level will decrease. AVAILABLE OPTIONS: 0 160 gpm Indication Failure Range OPTION TESTED: 0 gpm INITIAL CONDITIONS: IC-42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Letdown flow diverted to Coolant Recovery Tank to insure Auto Make Up takes place. FINAL CONDITIONS TEST DURATION: 2 HRS. VCT level decreasing, Auto Hake Up Flow stopped l BASELINE DATA: Malfunction Description 6.3.4.4.10 l Alarm Response Procedure A3 32 l DEFICIENCIES: None l l l CORRECTIVE ACTION /DATE: N/A n U t EXCEPTIONS TAKEN TO ANS. 3.5: None l '
l BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Charging Header Leakage SQT 4.61 REQUIRED BY ASI/ANS 3.5 $ECTION: 4.2.2 DATE TESTED:05/03/90 GENERAL DESCRIPTION: When the malfunction activates, charging flow decreases, seal injection flow increases, VCT inventory decreases. Aux Bldg sump and radiation levels should increase. The operator isolates the charging header to isolate the leak and lines up seal injection via the Fill Headen I AVAILABLE OPTIONS: Variable leak Rate 0 500 gpm OPTION TESTED: 200 gpm O INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None l FINAL CONDITIONS TEST DURATION: 2.5 HRS. l Malfunction Active, leak isolated, seal injection supplied via the Fill Header BASELINE DATA: Malfunction Description 6.3.4.4.11 Plant Alarm Response Procedure A3 58 DEFICIENCIES: Leakage had no noticeable effect on sumps or radiation levels ' in the Aux Bldg CORRECTIVE ACTION /DATE: Trouble Report 25; Written, TR 261 has been resolved. EXCEPTIONS TAKEN TO ANS. 3.5: None
l BVPS 1 SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Fill Header Leakage SQT-4.62 RE041 RED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TEST 0:05/25/90 GENERAL DESCRIPTION: Af ter the Fill Header is placed in service the leak malfunction is activated. Fill Header flow and pressure decreases are verified. VCT level and seal injection flow also decrease. Normal charging flow is then restored and the Fill Hender isolated to stop the leak. AVAILABLE OPTIONS: Variable Leak Rate 0 500 gpm OPTION TESTED: 150 gpm INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL O LIST OTHER SPECIAL CONDITIONS: Place fill Header in service prior to beginning test FINAL CONDITIONS TEST DURATION: 1.25 HRS. Malfunction Active, fill Header leak is isolated, normal charging and l seal injection are restored BASELINE DATA: Malfunction Description 6.3.4.4.12 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A i p EXCEPTIONS TAKEN TO ANS 3.5: None v I l
BVPS I SIMULATOR CERTlflCATION TEST ABSTRACT TEST TITLE: RCP Seal Flow Control Valve Failure SQT-4.63 U REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TFSTED:05/04/90 GENERAL DESCRIPTION: As the controller output increases the Seal Inj. FCV goes closed, seni flow decreases and the alarm comes on. When the controller output decreases leal Injection FCV goes open, seal flow increases. AVAILABLE OPTIONS: Variable Controller Output 0100% OPTION TESTED: 100% and 0% q INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL y LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 2 HRS. I For the above mentioned failures the overall plant remains stable, in the first case seal flow remains 0 gpm and for the second case seal flow increases to = 27 gpm. BASELINE DATA: Malfunction Description 6.3.4.4.13 Alarm Response Procedure A3 78 A3-58 DEFICIENCIES: Instructor Console Malfunction Description incorrect CORRECTIVE ACTION /DATE: TR 300 written, TR-300 has been resolved. EXCEPTIONS TAKEN TO ANS. 3.5: None 7
BVPS I SlHULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Excess Letdown Divert ValJe Failure SQT-4.64 RIQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTE0:05/04/89 GENERAL DESCRIPTION: The malfunction will cause full excess letdown flow to divert to the #1 Primary Drains Tank. HCV-CH-389 valve position change is noted as well as an increase in DGTK-1. AVAILABLE OPTIONS: Variable Valve Position 0-100% OPTION TESTED: 0% INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Place Excess Letdown in service FINAL CONDITIONS TEST DURATION: 1 HRS. Excess Letdown in service, diverting to DGTK1 rather than the VCT BASELINE DATA: Malfunction Description 6.3.4.4.14 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None 1 l
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT l \
- {V TEST TITLE: H2 Supply Pressure Regulator Failure SQT 4.65 l
REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:07/26/90 GENERAL DESCRIPTION: When the malfunction activates VCT Press will increase rapidly to supply header pressure. The malfunction is cleared, PCV-CH 109 is closed and the VCT vented to restore pressure to normal. AVAILABLE OPTIONS: Variable Opening 0 100% OPTION TESTED: 100% open % l t
' INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL i LIST OTHER SPECIAL CONDITIONS:
Insure H2 Supply Lined Up To the VCT FINAL CONDITIONS TEST DURATION: 1.5 HRS. Malfunction active but produced no effect on the VCT. Test terminated. BASELIME DATA: Malfunction Description 6.3.4.4.15 \ 9
)
DEFICIENCIES: Malfunction does not work and another problem was fid %-on PCV-CH-108, it did not work properly 1 CORRECTIVE ACTION /0 ATE. i Trouble Reports 270 and 271 written. TR 271 voided, TR-270 has been f] resolved ! v EXCEPTIONS TAKEN TO ANS. 3.5: None t-1 m
BVPS I $1MULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Volume Control Tank Leak SQT-4.66 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:ll/14/89 GENERAL DESCRIPTION: The malfunction is activated, VCT level and pressure are verified decreasing. Low level alarm activates, make up occurs and ultimately charging pump suction switches to the RWST. AVAILABLE OPTIONS: Variable Leak 0-1000 gpm OPTION TESTED: 250 gpm O INITIAL CONDITIONS: 10-42 100% PWR. CORE ACE BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .5 HRS. Malfunction Active, VCT leaking, Charging Pump suction auto switched to the RWST BASELINE DATA: Malfunction Description 6.3.4.4.16 Alarm Response Procedure A3-53, A3-54 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A l O EXCEPTIONS TAKEN TO ANS. 3.5: None i 1 .
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Blender Outlet flow Control Valve Failure SQT-4.67 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:11/17/89 GENERAL DESCRIPTION: A boration is initiated, after the appropriate time the alarm for improper flow activates, and flow is verified to be 0 gpm. AVAILABLE OPTIONS: Variable f ailure, 0100% of Full Open OPTION TESTED: 0% INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1 HRS. VCT level stable, Blender set up for boration but none occurs BASELINE DATA: Malfunction Description 6.3.4.4.17 Alarm Response Procedure A3-40 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A
- O EXCEPTIONS TAKEN TO ANS. 3.5: None i
. _ . _ - .. , ,, .+~
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Boric Acid Transfer Pump Trip SQT-4.68 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:ll/14/89 i GENERAL DESCRIPTION: Letdown flow is diverted to the Degassifier to cause VCT level to initiate Makeup. When the Makeup begins the 2A Boric Acid Pump does not start. AVAILABLE OPTIONS: CHS 19A Pump 2A Trip CHS 198 Pump 2B Trip OPTION TESTED: CHS 19A INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Insure 2A Boric Acid Pump in Auto FINAL CONDITIONS TEST DURATION: .5 HRS. The VCT Makeup demand , present but does not take place as the 2A B.A. Pump is tripped, VCT ievel is decreasing BASELINE DATA: Malfunction Description 6.3.4.4.19 Alarm Response Procedure A3-40 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMVLATOR CERTIFICATION TEST ABSTRACT TEST TITLE:' VCT Level Transmitter Failure SQT-4.69 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:ll/14/89 GENERAL DESCRIPTION: LT-115 indication goes to 0%, auto makeup initiates,--VCT level then rises until LCV-CH-112 diverts water to the Coolant Recovery Tanks. , 1 AVAILABLE OPTIONS: CHS-20A LT-112 Variable 0-100% CHS 208 LT-ll5 OPTION TESTED: 0% CHS-20B INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS .-TEST DURATION: --5 HRS. LT-115 failed low, VCT level-high with LCV-CH-112
- diverting water to the Coolant Recovery Tanks i EASELINE DATA: Malfunction Descripti5n G.3.4.4.20 Alarm Response Procedure A3-53 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A -
O EXCEPTIONS TAKEN-T0 ANS. 3.5: None
l- , 6 BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT' ; 1 TEST TITLE: Letdown Isolation Valve Failure SQT-4.70 REQUIRED BY AS!/ANS 3.5 SECTION: 4.2.2 DATE TESTED:11/14/89-l GENERAL DESCRIPTION: . Valve LCV-460A fails closed. Letdown flow and pressure-decrease. VCT level decreases. -l s AVAILABLE OPTIONS:- Open, Closed CHS-21A = 460A CHS-21B = 460B-OPTION TESTED: CHS- 21A, Closed 1O INITIAL CONDITIONS: 10 -100% PWR. CORE-AGE - BOL i LIST OTHER SPECIAL CONDITIONS: None-l FINAL CONDITIONS ' TEST DURATION: .5 HRS. < [ No Letdown ~ Flow, VCT level decreasing-BASELINE DATA: Malfunction Description 6.3.4.4.21 DEFICIENCIES: Incorrect Letdown Line Temperature Response.
'CORRECTIVEACTION/DATE:
Trouble Report 221 Written, TR-221 has been cleared. EXCEPTIONS TAKEN TO ANS. 3.5:' None
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BVPS I ERTIFICATION TEST ABSTRACT TEST TITLE: Charging Flow control Valve f ailure SQT-4.71 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:ll/17/89 GENERAL DESCRIPTION: FCV-122 Fails open, charging flow increases, VCT level decreases and Pzr. level increases. Seal injection flow decreases. The operator takes manual control of FCV-122 and closes it, FCV-122 is then isolated and the bypass around FCV-122 uscd for further charging control. AVAILABLE OPTIONS: Variable Position 0-100% Open i OPTION TESTED: 100% O INITIAL CONDITIONS: 1C-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1 HRS. Charging flow normal, being controlled with bypass valve around FCV-122. BASELINE DATA: Malfunction Description 6.3.4 Alarm Response Procedure A3-58 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None i
1 BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT , TEST TITLE: Letdown Temp Control Valve Failure SQT-4.72 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:31/17/89 i GENEPAL DESCRIPTION: TCV-CH-143 Fully diverts flow to the VCT. No other effects expected. AVAILABLE OPTIONS: Variable Failed Position 0-100% OPTION TESTED: 0%, Failed to VCT around demins O INITIAL CONDITIONS: IC-42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: - 1_ HRS. TCV-CH-143 diverting to VCT BASELINE DATA: Malfunction Description _6.3.4.4.23 DEFICIENCIES: None CORRECTIVEACTION/DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None I
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Station Blackout SQT-4.73 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:04/20/90 GENERAL DESCRIPTION: Loss of Offsite Power is' verified as malfunction progresses, all non emergency busses ultimately lose power with appropriate 1' alarms. EOG's energize the AE and DF busses, the malfunctien is then cleared and using LOA's offsite power is restored, i AVAILABLE OPTIONS: None OPTION TESTED: NA O INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 3 HRS. Malfunction cleared, Offsite power restored, _ Rx tripped and natural circulation in progress i [ BASELINE DATA: Malfunction Description 6.3.4.7.1 Abnormal Operating Procedure 1.35.2 Alarm Response Procedures A8-31, A8-27, - A8-70, A8_65, A8-66 OM Ch 53 Al Attachment 2-D DEFICIENCIES: None CORRECTIVEACTION/DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None n
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BVPS 1 SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Unit Station Service Transformer failure SQT-4.74 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2- DATETESTED:04/15/90 ! GENERAL DESCRIPTION: When the malfunction activates the IC . transformer undergoes a fault that causes the loads that -it supplies to.de-energize as well ! as the ID to trip and all loads, lA, IB,10, :10 bus auto transfer to the 1A and 18 transformers. AVAILABLE OPTIONS: EPS-2A Transformer IC EPS-28 Transformer ID r OPTION TESTED: EPS-2A O INITIAL CONDITIONS: 10-42 100% PWR, CORE-AGE - BOL LIST OTHER SPECIAL CONDITIONS: i None FINAL CONDITIONS TEST DURATION: 1.25 HRS. Rx tripped, offsite power supplying'onsite 4160 vac busses BASELINE DATA: Malfunction. description 6.3.4.7.2 Alarm Response Procedures A8-75, A8-79, A8-83, AS-87, A8-91 A8-95, A8-99, A8-103 DEFICIENCIES: Some expected alarms did not activate l l CORRECTIVE ACTION /DATE: Trouble. Report 259 written. TR-259 voided upon further investigation. EXCEPTIONS TAKEN TO ANS. 3.5: None ?
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT o TEST TITLE: System Station Service Transformer Failure SQT 4.75 . REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE-TESTED:04/18/90 GENERAL DESCRIPTION: When the malfunction occurs OCB 92 trips the breakers from the 1A transformer to the 1A & IB busses trip, the 1A & IB busses remain de-energized, the.AE bus de-energizes until the #1 Diesel starts and picks up the loads. AVAILABLE OPTIONS: EPS-3A 1A Transformer EPS-3B 18 Transformer OPTION TESTED: EPS-3A O INITIAL CONDITIONS: IC-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Line up 1A & IB Busses to the 1A Transformer-FINAL CONDITIONS TEST DURATION: 1.5 HRS. --
.Rx tripped due to low RCS Flow, all RCP's off, lA & -1B busses de-energized,
#1 Emergency Diesel Generator carrying the AE bus BASELINE DATA: Malfunction _ Description 6.3.4.7.3 Alarm Response Procedures A8-9, A8-76, A8-84, A8-105, A8-106 DEFICIENCIES: None l
CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT A
\~ l TEST TITLE: Loss of 4160 Volt Bus SQT 4.76 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:04/16/90 GENERAL DESCRIPTION: The malfunction trips breaker ACB 41C on Overcurrent. The 1A Bus de-energizes as well as the AE bus which will be picked up by the #1 Emergency Diesel Generator. Proper Breaker action as well as appropriate alarms are verified. The malfunction is cleared, and normal power is supplied to 1A then AE busses.
AVAILABLE OPTIONS: EPS-4A Bus A EPS-4F Bus DF EPS 48 Bus B EPS-4C Bus C EPS-4D Bus D EPS-4E Bus AE OPTION TESTED: EPS-4A , INITIAL CONDITIONS: 1C-42 100% PWR, CORE AGE- BOL ! LIST OTHER SPECIAL CONDITIONS: N one O i FINAL CONDITIONS TEST DURATION: 1.5 HRS. . Halfunction cleared, normal power supply breakers alignment restored to IA l and AE busses BASELINE DATA: Malfunction Description 6.3.4.7.4 Alarm response procedures A8-73, A8-76, A8-105, A8-106, A8-109 A9-26, A9-81, A9-42, A9-87, A9-58 DEFICIENCIES: Some expected alarms did not come in CORRECTIVE ACTION /DATE: Trouble Report 258 written. To be resolved by December, 1991.
/ None Q) EXCEPTIONS TAKEN TO ANS. 3.5:
_ _ _ _ - - .- . . _ . . . . . _ .. . _ . . . _ _ _ _ ,. _ . . .._. _ . ~ ..- _ ._..._ ___ . P BVPS-I SIMULATOR CERTIFICATION-TEST ABSTRACT-TEST TITLE: Loss of 480 Volt Bus - SQT 4.77 REQUIRED BY ASI/ANS 3.5 FECTION: 4.2.2 DATE TESTED:04/16/90' GENERAL DESCRIPTION: The malfunction causes a loss -of the lA 480'vac bus. Expected lost loads are verified, as well as alarms- j q l . --i
' AVAILABLE-0PTIONS: Selectable Busses lA,B,C,0,E,F,G,H,J,K, IN,1N1, IP,lPl. _
OPTION TESTED: 1 A' Bus OINITIALCONDITIONS: 10-42 100%'PWR. CORE AGE - BOL' LIST OTHER SPECIAL CONDITIONS: FINAL CONDITIONS - TEST-- DURATION: . 1.5 HRS. The Rx tripped unexplainably,1B 480 volt-bus de-energized l .! }- BASELINE DATA: Mal _ function Description 6.3.4.7.5 l: Alarm Response Procedure A9-69 L DEFICIENCIES: Unexplained Rx Trip, equipment powered from wrong bus i CORRECTIVE ACTION /DATE: Trouble Report 257- written,-TR-257 will be resolved . - by December 1991 ~. 5 EXCEPTIONS TAKEN TO ANS. 3.5: None-e y , .--re, ,, - .- r r e e-e e-, rwk--,-..-w-- -e~- ,r**w 'M=
=i
^
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Loss of 120 Volt AC Bus Vital Bus SQT-4.78 REQUIRED BY ASI/ANS 3.5 SECT 10N: 4.2.2 DATE TESTED:04/20/90 GENERAL DESCRIPTION: The Vital Bus is deenergized by the malfunction. All expected loads that should be lost are verified de-energized; Expected response of various systems or comments to the loss of #1 Vital Bus are verified using the Alarm Response Procedure. AVAILABLE OPTIONS: EPS-6A Vital Bus 1 EPS 6B Vital Bus 2 EPS-6C Vital Bus 3
. EPS 60 Vital Bus 4 OPTION TESTED: EPS-6A INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS:
None FINAL-CONDITIONS TEST DURATION: 4 HRS. The plant has tripped due to the loss of.the #1 Vital Bus which is still de-energized. BASELINE DATA: Malfunction Description 6.3.4.7.6 Alarm Response Procedures Al-10 DEFICIENCIES: RCP response to loss of Vital bus incorrect O CORRECTIVE ACTION /DATE: Trouble Report 281 written. TR-281 has-been resolved.
.BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT-TEST TITLE: Loss of Inverter SQT-4.79 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:04/19/90 l GENERAL DESCRIPTION: When this malfunction activates the expected alarms are verified indicating the Vital bus is no longer receiving its normal power.
AVAILABLE OPTIONS: EPS-7A = Inverter 1 EPS Inverter 2 EPS-7C - Inverter 3 EPS Inverter 4 OPTION TESTED: .EPS-7A O INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL~ LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS : TEST DURATION: . 75 HRS.. Malfunction Active, expected alarms Al-10 and /. 18 activated BASELINE DATA: Malfunction. Description 6.3.4.7.7 Alarm Response Procedure Al-10, . Al DEFICIENCIES: None-
.C0RRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS -I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Loss of DC Bus SQT-4.80 REQUIRED-BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:05/20/90 GENERAL DESCRIPTION: After the malfunction is activated that deenergizes the
#1 DC Bus, all the expected automatic actions.that are listed-in the ARP for Loss of DC Bus are verified.. It will be necessary several- times to freeze and re-start simulator to check the effects of the accident under various plant conditions, i
AVAILABLE OPTIONS: EPS-8A, B, C, D, E = DC Bus 1, 2, 3, 4, 5 l OPTION TESTED: EPS-8A l INITIAL CONDITIONS: 10-42 100% PWR. ' CORE AGE-- 80L' LIST OTHER SPECIAL CONDITIONS: FINAL CONDITIONS TEST DURATION: 4.5 HRS. DC Bus de-energized,-Rx tripped BASELINE DATA: Malfunction = Description 6.3.4.7.8 Alarm Response-Procedure A9-98 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O ! EXCEPTIONS TAKEN:TO~ANS. 3.5: None a _ . . ,_ , _ , _ .__ _ . . _ . -- _.a_._
~BVPS-I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Grid Voltage Variation SQT 4.Sl
. REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:04/19/90 .l GENERAL DESCRIPTION: The malfunction causes Grid Voltage to decrease, a indicated voltage is verified decreasing components powered by offsite are checked for an increase in current. Generator power factor and VARS are verified changing in the correct direction.
1 I. AVAILABLE OPTIONS: 0 200% Selectable OPTION TESTE0: 95% O INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None i FINAL CONDITIONS TEST DURATION: --5 HRS.; Malfunction Active, Grid Voltage low, Plant remains at 100% power BASELINE DATA: - Malfunction Description 6.3.4.7.9 DEFICIENCIES: None CORRECTIVE ACTION /DATE: NA EXCEPTIONS TAKEN TO ANS. 3'.5: None
i BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Diesel Generator Trip SQT-4.82 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:04/16/90 GENERAL DESCRIPTION: The malfunction is activated with the #1 Diesel Generator paralleled to the AE Bus. When the malfunction is activated the Diesel is verified tripped and expected alarms are verified. Normal current values from the A to the AE bus return. AVAILABLE OPTIONS: EPS-11A #1 Diesel Generator EPS-llB- #2 Diesel Generator i OPTION TESTED: EPS-IIA INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Start and parallel the #1 EDG to the AE Bus prior to beginning of test. FINAL CONDITIONS - --- TEST-DURATION:-- 1.0 HRS. The #1 Diesel Generator is tripped and idling, the remainder of the plant is normal and stable. , BASELINE DATA: Malfunction Description 6.3.4.7.11 Alarm Response Procedures A9-1, A9 97 DEFICIENCIES: None CORRECTIVE _ ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None l l
BVPS I SIMULATOR CER',FICATION TEST ABSTRACT f TEST TITLE: Emergency Diesel Generator Erratic Speed Control SQT-4.83 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:08/03/90 GENERAL DESCRIPTION: The AE bus is de energized using Malfunction EPS 4E. The
#1 EDG starts and picks up the bus, the malfunction is activated causing speed oscillations, it is verified by observing RPM, Frequency and Diesel Generator Watts. The malfunction is not large enough to cause a trip of the diesel generator.
AVAILABLE OPTIONS: EPS-12A =
#1 D/G EPS-128 -
#2 0/G Magnitude 0-1 OPTION TESTED: EPS-12A, .25 INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS:
None FINAL CONDITIONS TEST DURATION: .75 HRS. Malfunction cleared, Plant stable at 100% with the #1 EDG carrying-the A/E Bus. BASELINE DATA: Malfunction Description 6.3.4.7.12 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION-' TEST ABSTRACT-TEST TITLE: Diesel Generator Erratic Voltage Regulation _ .SQT-4.84 1 REQVIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:04/19/90~ GENERAL DESCRIPTION: The diesel is set up to'be carrying the AE bus. The I malfunction is--then activated. -Diesel 1 Generator Volt and Amp meter movement-is-verified correct. The malfunction is then cleared ^ and parameters-are _ verified , to be stable. ! AVAILABLE OPTIONS: EPS-13A #1 Diesel Generator .. EPS-13B #2 Diesel Generator-Variable Range 0-10% OPTION TESTED: EPS-13A, 10% ( O INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE - BOL-LIST OTHER SPECIAL CONDITIONS: EDG #1 paralleled to carry the AE bus. FINAL CONDITIONS TEST DURATION: .75 HRS. -, Malfunction cleared,- plant stable-BASELINE DATA: Malfunction Description 6.3.4.7.13' .- DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None-i e
l l BVPS I S!MULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Diesel Generator Output Breaker. Trip _ .SQT-4.85 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTE0:04/18/90 GENERAL DESCRIPTION: After the diesel generator is carrying the AE bus-the 4 malfunction is activated. The breaker is verified open .and the appropriate L alarms should come on. The loads carried by the AE bus are-verified ' i de-energized. AVAILABLE OPTIONS: EPS 14A #1 Diesel Generator. EPS-14B #2 Diesel Generator . OPTION TESTED: EPS 14A INITIAL CONDITIONS: 1C-42 100% PWR. CORE AGE. BOL: LIST OTHER SPECIAL CONDITIONS: l Diesel Generator paralleled to and carrying the- AE bus de-energized, Pzr. Ievel ciecreasing due to loss of charging FINAL CONDITIONS TEST DURATION: .75 HRS. Plant at 100%, #1 Emergency Diesel Generator tripped, AE bus de-energized, Pzr Level decreasing due to loss of charging. l BASELINE DATA: Malfunction Description 6.3.4.7.14 Alarm Response Procedures, A9-1, A9-3 DEFICIENCIES: None 1
- CORRECTIVE ACTION /DATE: N/A
- O c EXCEPTIONS TAKEN TO ANS. 3.5
- None i
( -- l BVPS-1-SIMULATOR CERTIFICATION TEST ABSTRACT-TEST TITLE: Load Rejection SQT-4.86. REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:04/18/90 GENERAL DESCRIPTION: The malfunction will cause an 85% load rejection. l Electrical Watts, Reactor Power, Turbine Power all-decrease, Reactor Power ' decrease will be slower to decrease due to Steam' Dump operation. Rods will'. step in to control Tavg and without operator action will cause -rods to go below Ril and cause Delta 1 problems. AVAILABLE OPTIONS: Variable 0-95% OPTION TESTED: 85% i INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE - BOL i LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TESTEDURATION:.1.0-HRS.. Plant approaching stable conditions at 15% p'ower, Rods below:RIL4 and Delta-I out of limits BASELINE DATA: Malfunction Description 6.3.4.7.15 Abnormal Operating Procedure 53C4.1.35.2 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O
-EXCEPTIONS TAKEN TO ANS. 3.5: None l
____= - - J
i BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Generator Dutput Breaker Failure SQT-4.87 REQUIRED BY ASI/ANS 3.5 SECTION: A.2.2 DATE TESTED:04/18/90 GENERAL DESCRIPTION: The reactor is tripped. When the turbine and generator trip, PCB 331 is verified to have failed closed. , AVAILABLE OPTIONS: EPS-16A EPS-16B OPTION TESTED: EPS-16A O INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE - MOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .5 HRS. Rx Tripped, Turbine Tripped, Generator Tripped Except for PCB-331 which is still closed BASELINE DATA: Malfunction Description 6.3.4.7.16 OM Ch 53A E-0 Step 4 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None i
BVPS 1 SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Voltage Adjust Setpoint Failure SQT-4.88 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:04/19/90 GENERAL DESCRIPTION: The malfunction activates and tends to cause an increase in MVARS, Generator Volts and causes Power Factor to go more lagging. The base adjuster will sense the problem and then adjust the setpoint to half load value. AVAILABLE OPTIONS: Variable 0 200% OPTION TESTED: 200% O INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1 HRS. Plant stable, power level same as pre event, Generator Volts, MVARS and Exciter Current less than pre event BASELINE DATA: Malfunction Description 6.4.5.7.17 Alarm Response Procedures A7-125, A7-107, A7-111, A7-109 DEFICIENCIES: Expected alarm did not come on CORRECTIVE ACTION /DATE:
^
Trouble Report 284 written. TR-284 to be resolved by December 1991 (V) EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT i TEST TITLE: Main Transformer Failure -SQT-4.89' '! REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 'DATE TESTED:04/19/90 GENERAL DESCRIPTION: When the malfunction activates the main generator trips, various alarms for the transformer problem energize, the turbine-and reactor 'j trips followed by the main generator trip. The 4160 volt A,B,C,D busses _ auto , transfer to offsite power sources. i i AVAILABLE OPTIONS: None - OPTION TESTED: N/A lO INITIAL CONDITIONS:. 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION:'.5 HRS.- Main Generator, Turbine and Reactor tripped, offsite power supplying-l A,B,C,0 busses BASELINE DATA: Malfunction Description 6.3.4.7.18 Alarm Response Procedures AB-6, A8-5, A7-121, A7-106 DEFICIENCIES: None-i CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS 1 SIMULATOR CERTif! CATION TEST ABSTRACT-TEST TITLE: Main Feedwater Pump Trip SQT-4.90. . REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:04/30/90'- i GENERAL DESCRIPTION: The "A" Main Feed Pump is tripped at 100% Power. The- i breakers are verified-tripped open and amps decrease to 0. Feedwater flow will decrease with associated alarms. Steam generator level will decrease and a-reactor trip will result. AVAILABLE OPTIONS: FWM 1A = A Main Feed Pump FWM 1B - B Main Feed Pump . OPTION TESTED: FWM-1A , INITIAL CONDITIONS: 1C 42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL-CONDITIONS -TEST' DURATION: 1.5 HRS.
"A" MFW Pump tripped, Rx tripped due to low steam generator level.
BASELINE DATA: Malfunction Description 6.3.4.8.1 Alarm Response Procedures A7-37, A7-39 DEFICIENCIES: None L CORRECTIVE ACTION /DATE: N/A L O EXCEPTIONS TAKEN TO ANS. 3.5: Ncne l' ! _-. - _ _ , _ . . __m ._ _.__ ._-. .. ,.. . ___. . _ . . - ._ - . -._.._.._ ,, __.._,m. . - , _ . .
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Heater Drain Pump Trip SQT-4.91 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:04/30/90 GENERAL DESCRIPTION: The "B" Heater Drain Pump trips, breaker opens and amps decrease to 0. Initially, feed flow decreases until the."A" Heater Drain Pump auto starts, then feed flow returns to normal. AVAILABLE OPTIONS: FWM 2A = "A" Heater Drain Pump FWM 2B "B" Heater Drain Pump OPTION TESTED: FWM 2B INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE - BOL U LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1 HRS. Plant stable, feed flows back to normal, "A" Heater Drain Pump running, "B" Heater Drain Pump tripped BASELINE DATA: Malfunction Description 6.3.4.8.2-Alarm Response Procedure A6-71, A7-06 DCFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
,i BVPS-I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Feedwater Leak In= Containment SQT-4=.92 l REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE-TESTED: 5/23/90 GENERAL DESCRIPTION: The malfunction will cause the "B" S/G to lose' level and -!
depressurize. Feed flow to the "B" S/G will- indicate an increase,_ with a - resultant decrease to "A" & "C" as header pressure drops. . Containment temp., ' press. and humidity will_ increase. -The reactor will' trip:on Lo Lo S/G: level and subsequently SI on lo Steam Line Pressure due-to the leak. The operator will perform steps to isolate the leak and _ verify-that the; drop in Tavg and-RCS pressure can be stopped.- a l u AVAILABLE OPTIONS: FWM 3A = S/G A - Variable Rate 0-20 x LIO6 lbm/hr. FWM-3B - S/G B , FWM-3C = S/G C OPTION TESTED: FWM-3B 20 x'IO6 lbm/hr. e INITIAL CONDITIONS: -IC-42 100% PWR. CORE AGE - BOL-LIST OTHER-SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: ~2 HRS . -- The Rx has Tripped, SI, FWI, CI "A" and SLI have occurred. The "B" S/G is depressurized;and isolated pe E0P Procedure E-2. Tavg_and ; RCS Press, have stopped decreasing. BASELINE DATA: Malfunction Description 6.3.4.8.3-E0P Background Document For E-2 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Feedwater Leak Outside Containment SQT-4.93 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 5/15/90 GENERAL DESCRIPTION: When the malfunction is activated feed flow increases to: the affected steam generator. Hotwell level and Turbine Plant Demin Storage Tank level decrease. -The Reactor trips due to low S/G levels, Aux Feed Water Pumps start. The operator shuts the isolation valves necessary to isolate the-leak and verifies it isolated. i AVAILABLE OPTIONS: FWM-4A = S/G A FWM-4B = S/G B Variable Rate 0-20 x 106.lbm/hr. FWM-4C = S/G C OPTION TESTED: FWM-4C 12 x 106 lbm/hr. 1 INITIAL CONDITIONS: 10-42 100% PWR.- CORE AGE - BOL O LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST. DURATION: 1.25 HRS. l Rx Tripped,-Leak isolated, AFW supplying the steam generators BASELINE DATA: Malfunction Description 6.3.4.8.4 DEFICIENCIES: tione CORRECTIVE. ACTION /DATE: N/A l EXCEPTIONS TAKEN TO ANS 3.5: None
q
]4 BVPS I-SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Feedwater Recire Control Valve Failure SQT-4.94 REQUIRED BY ASI/ANS 3.5 SECTION: 5.2.2 DATE TESTED:04/30/90 GENERAL DESCRIPTION: As the valve fails open it causes feed flow to decrease, the feed reg. valves wil' open to compensate. The recire valve misoperation alarm is also verified on.
f AVAILABLE OPTIONS: FWM-5A FCV-150A 0,C - Open or Closed FWM-5B FCV-150B OPTION TESTED: FWM-5A, Open O INITIAL CONDITIONS:- 1C-35 75% PWR. ' CORE AGE - MOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1;2 HRS. Reactor stable-at =-76%, main feed reg, valves are open more than originally to compensate for the- open- recire, valve.
-BASELINE DATA: Malfunction Description 6.3.4.8.5 Alarm Response Procedure A6 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O ' EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST. TITLE: High Press. Feedwater Tube Leak SQT-4.95 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 7/3/90 GENERAL DESCRIPTION: When the leak occurs, Feedwater Flow will decrease along with levels on the steam generators. The heater level as-well as heater drain-receiver and level increase. The heater is then isolated and-plant efficiency is verified to decrease. Feed Flows and levels return to normal. AVAILABLE OPTIONS: FWM 6A - FW-E-1A FWM-6B = FW-E-1B Variable Leak 0-10,000 gpm OPTION TESTED: FWM-6A, 3000 gpm ic-42 toos ewa. cone act - Bo' Oi">'ia'co"oir:ans: LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1.0 HRS. Malfunction Active,1A Feedwater Heater isolated and bypassed, plant efficiency decrease-has been noted. BASELINE DATA: Malfunction Description 6.3.4.8.6 ! Procedure OM 1.23A.1.c-Alarm Response Procedure 47.26 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT O TEST-TITLE: Feedwater Reg. Valve Failure SQT-4.96 { REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:05/14/90 GENERAL DESCRIPTION: The malfunction causes the valve to go shut.- Feed flow _ goes to zero. A S/G level decreases to the low level and SF-FF mismatch Rx i trip setpoint. After the trip AFW will supply the steam generators. AVAILABLE OPTIONS: FWM-7A - FCV 478 FWM-7B - FCV 488 Position 0-100% of.open FWM 7C - FCV 498 OPTION TESTED: FWM-7A, 0% , O INITIAL CONDITIONS: IC 42 100% PWR. CORE' AGE - MOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS . TEST DURATION: 1.5 HRS. 4 Reactor tripped, malfunction active, AFW ' supplying the steam generator. BASELINE DATA: Malfunction Description 6.3.4.8.7 Incident Report 1-90-32 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A 0' -EXCEPTIONS TAKEN TO ANS. 3.5: None
)
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT l O TEST TITLE: Feed Reg Bypass Valve f ailure SQT 4.97 ! REqVIRED BY ASI/ANS 3.5 SECTION: 4.? 2 DATE TESTED:05/23/90 j GENERAL DESCRIPTION: "C" Bypass FRV fails full open resulting in increased i feed flow to "C" S/G and momentary reduction in flow to "A" & "B" S/Gs. "C" 1: S/G is cooled by the rapid increase in unpreheated feedwater flow resulting in shrink and a reduction in steam flow. Steam flow from "A" and "B" S/Gs ) increase to corrpensate resulting in level swell,. Nucledr power increases due ! to cooling effect of the over fed "C" S/G. "A" and
- F S/G 1evels are restored !
to program. "C" S/G 1evel continues to increase toward the P 14-setpoint i I i
; AVAILABLE OPTIONS: FWM8A FCV FW 479 Variable ramp 0 9999 sec
- FWM8B FCV FW-489 FWM8C FCV FW 499 Fail position 0 100%
l l OPTION TESTED: FWM8C 100%, O sec ramp l INITIAL CONDITIONS: 10 9 10% PWR.. CORE AGE MOL LIST OTHER SPECIAL CONDITIONS: . Bypass FRVs in Auto , l FINAL CONDITIONS TEST DURATION: 1.5 HRS. Test terminated at 70% in "C" S/G and' rising P14 (Turbine trip, FW isolation) setpoint is 75% BASELINE DATA: Malfunction description 6.3.4.8.8 Alarm Response Procedure A7 61 DEFICIENCIES: None CORRECTIVE ACTION /DATE:'N/A A y U-EXCEPT10N3 TAKEN.TO ANS, 3.5: None-
~. _._. _ _ . _ . . . _ __._ _ . _ _ _ _ _ . _ _ _ - . . . . . . _ _ . , , _ . _ __, , _ , _ _ _ . _ , _ .
- _ _ . _ . - - = . - _ - . . .- . _ . -. - . . -
BVPS I SIMULATOR CERT!FICATION TEST ABSTRACT O TEST TITLE: Erratic feedwater Flow Control SQT 4.98 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:10/17/89 GENERAL DESCRIPTION: "B" S/G MFRV (FCV FW 488) oscillates over a 50% travel causing feed flow and level oscillations. Feed flow / steam flow mismatch and level deviation annunciators are actuated. By placing FCV FW 488 in manual the oscillations are stabilized. AVAILABLF OPTIONS: FWM 9A FCV FW-478 Oscillation range 0 100% FWM-9B FCV FW 488 Oscillation period 0 1000 see FWM 9C FCV FW 498 OPTION TESTED: FWM98, 50%, 120 sec INITIAL CONDITIONS: 1C-42 100% PWR. CORE AGE BOL LIST OTHER SPECIAL CONDITIONS: None l FINAL CONDITIONS TEST DURATION: 5 HRS. S/G 1evels and feedwater flows stable, power at 100% l l BASELINE DATA: Malfunction Description 6.3.4.8.9 Alarm Response Procedure A7 53 A7-50 A7-52 l DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SlHULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: AFW Pump Trip SQT 4.99 REQUIRED BY ASI/ANS 3.S SECTION: 4.2.2 DATE TESTED:10/17/89 GENERAL DESCRIPTION: FW-P 2 is tripped due to closure of its trip throttle valve causing STEAM UNAVAILABLE TURBlhE ORIVEN FEED PP FW P-2 to alarm. Aux feed flow indicates zero on VB-C and S/G levels trend downward. RCS loop AT's decrease as S/G effectiveness as a heat sink decreases. AVAILABLE OPTIONS: FWM llA FW P 3A FWM llB FW P-3B FWM llc FW P 2 OPTION TESTED: FWM llc O INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE -BOL LIST OTHER SPECIAL CONDITIONS: Both MDAFW pump control switches placed in PTL prior to test performance. Reactor is manually tripped to initiate the test (MALF CRFilA) FINAL CONDITIONS TEST DURATION: 1.0 HRS. Rx suberitical with the RCS heating up due to loss of heat sink BASELINE DATA: Malfunction Description 6.3.4.8.11 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A (O LXCEPTIONS TAKEN TO ANS 3.S: None
l BVPS ! SIMULATOR CERTIFICATION TEST ABSTRACT l 4 TEST TITLE: Aux Feedwater Flow Control Valve Failure SQT-4.100 i REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE1ESTED:10/16/89 l ! GENERAL DESCRIPTION: When the malfunction is activated, the valve fails shut. l The pump associated with that valve is started and the auto open feature of i that valve is verified not to work. ' l I AVAILABLE OPT 10NS: FWM 12A F, Valves FWM-151A,151B,1510,1510,151E,151F
-j i
{ OPTION TESTED: FWM 12F j i l , INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: l
- Place FW P 38 in PTL
- Close FW 40 (LOA FWM38)
I FINAL CONDITIONS TEST DURATION:. 1 HRS. FW P 3A running, FWM-151F remains closed. BASELINE DATA: Malfunction Description 6.3.4.8.12 Alarm Response Procedure.A7-51 l DEFICIENCIES: Test SAT, Instructor Sys. Labeling Problem Found-CORRECTIVE ACTION /DATE: i Trouble Report 210 written, T. R. cleared. EXCEPTIONS TAKEN TO ANS. 3.5: None
l i
; BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT I TEST TITLE: AFW Pump Suction Leak SQT-4.101 l REQUIRED BY ASI/ANS 3.5 SECT 10N: 4.2.2 DATE TESTED:10/16/89
! GENERAL DESCRIPTION: Aux feed flows indicated on VB C drop to zero and pump i amps oscillate as FW P-3B cavitates. WT-TK-10 (normal suction supply) drops to the low level alarm set oint. Upon reali backu river water supp y (leak isolated)gnment , AFW flow of tw F-30pump is restored, suction amps to the stabi ize, TK 10 level stabilizes. I AVAILABLE OPTIONS: FWM 13A FW P 3A Leak Rate 0 1000 gpm FWM-13B FW P-3B i FWM 13C FW P 2 i OPTION TESTED: FWM 13B, 1000 gpm O INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE BOL LIST OTHER SPECIAL CONDITIONS: FW P-3B is manually started upon identification of pump cavitation, LOAs are used to isolate the normal suction piping and align backup. river _ water suction. FINAL CONDITIONS TEST DURATION: 1.0 HRS. <- FW P 3B flow restored BASELINE DATA: Malfunction Description 6.3.4.8.13 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS 3.5: None . . . . _ . - . . ~ . _ . _ . . _ _ . - _ _ _ _ _ . . _ _ . - - . . _ _ _ . . - _ - . _ . - _ . . _ . . . _ . _ _ - . _ . _
BVPS 1 SIMULATOR CERTIFICATION TEST ABSTRACT O TEST TITLE: Feedwater Flow Transmitter Failure SQT 4.102 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:10/16/89 GENERAL DESCRIPTION: When activated the indication of the failed transmitter fails high. The feed reg. valve it controls closes, causing an S/G level decrease. Af ter the appropriate alarms activate, the operator takes manual l control of the S/G and selects in the non faulted flow transmitter for auto I control usage, l AVAILABLE OPTIONS: FWM-14A F = FT476, FT477, FT486, FT487, FT496, FT497 Variable 0-5x106 lbm/hr i l p OPTION TESTED: FWM 14E 5x106 lbm/br
%J l INITIAL CONDITIONS: 10-42 100*/. PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS:
None FINAL CONDITIONS TEST DURATION: 2 HRS. S/G Level and flow returning to normal, with the faulted flow transmitter switched out of the control circuit. ! BASELINE DATA: Malfunction Description 6.3.4.8.14 Alarm Response Procedure A7-58 DEFICIENCIES: None l l CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None l
i- j
, I'
- BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT
- l TEST TITLE
- S/G Programmed Level Signal failure SQT 4.103 REQVIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:ll/19/90 j GENERAL DESCRIPTION: When activated the demand signal for the *A" S/G goes to 100%, feed flow to that S/G increases. The level in the "A" S/G increases till j
, the turbine trips on Hi Hi S/G 1evel, following the turbine trip the reactor 1 trips also. T a AVAILABLE OPTIONS: FWM 15A - AH FW 478
- FWM 15B AM FW 488 Variable 0-100% FWM-150 AM fW 498
~
OPTION TESTED: FWM 15A, 100% INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS = TEST DURATION: 1 HRS. The reactor is tripped, feedwater partial isolation has occurred, the "A" S/G 1evel is higher than the others. BASELINE DATA: Malfunction Description 6.3.4.8.15 Alarm Response Procedure A7-45, A5-10 DEFICIENCIES: None-CORRECTIVE ACTION /DATE: N/A- - O EXCEPTIONS TAKEN TO~ANS. 3.5: None
~
Elf 9 =p*Ty-Try Tv = aurop-et.,TNiyr M 7 M = m y + 7 y-ig- tt r-tis y p-et t -wy_- -r-my-eM -- m m
j BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT j
, TEST TITLE: S/G Level Transmitter failure SQT-4.104 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:10/17/89 -l l
GENERAL DESCRIPTION: Channel III of each S/G is the control input to SGWLC. ! Channel 111 of B S/G fails high resulting in a 33% high level error to the { auto FRV control circuitry. - A high-high level alarm is generated and high high !' , channel trip status light is lit. B MFRV closes in response to the level error which in tur:. causes an offsetting flow error signal to SGWLC. 8 S/G level j reduces generating approariate low level alarms. If left unattended,-a reactor trip would be generated )y the unaffected channels on low-low level. The operator places B HFRV in manual to restore B.S/G 1evel to program.
-l AVAILABLE OPTIONS: FWM 16A C A S/G LTs (3 Failed Value 0-100% -
FWM 16D-F B S/G LTs (3 Ramp Time 0-9999 Sec. FWM 16G 1 C S/G LTs (3 i OPTION TESTED: FWM-16F, 100%, O Sec. INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL O' LIST OTHER SPECIAL CONDITIONS: Failed channel inputting to SGWLC (CH III) FINAL CONDITIONS TEST DURATION: 1.0 HRS. l Plant stable at 100%, operator manually controlling B S/G level. i BASELINE DATA: Malfunction Description 6.3.4-8.16 . Alarm Response Procedures A7-53, A7-55 ; DEFICIENCIES: None j l . CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None N u i
BVPS I SIMULATOR CER11FICATION TEST ABSTRACT , ! TLST TITLE: Steam Leak Upstream of MSIV SQT-4.105 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:10/17/89 I i GENERAL DESCRIPTION: Upon initiation of the break in a steamline, steam flow ! l in all S/G's rises rapidly with A S/G exceeding B & C. RCS temperature, PZR l pressure and level drop rapidly. CNMT pressure, temperature, and humidity 1 increase. The rapid drop in steamline pressure results in a rate compensated ! low steamline pressure SI and reactor trip. MSLI isolation occurs due to-high-i CNMT pressure. Steam flow from B & C S/G's is essentially stopned. A S/G i continues to indicate flow until the S/G boils dry.. A CIB and= spray signal is t actuated on Hi Hi CNMT pressure. The operator implements Emergency Operating : Procedures.E 0 and E 2 to verify all automatic actuations have occurred and to l identify and isolate the faulted S/G. [' J AVAILABLE OPTIONS: MSS-1A A S/G Leak Rate 0-1E7 lbm/hr Ramp Time 0-9999 Sec. l MSS-1B B S/G
- MSS-V C S/G OPTION TESTED
- HSS 1A, IE7 lbm/hr., O Sec.
i l 10 42 100% PWR. CORE AGE - BOL is' o'"oa seccia' co"oitions: O'INITIALCONDITIONS: ' None FINAL CONDITIONS TEST DURATION: 1.5 HRS. Plant conditions stabilizing toward Si termination criteric with all
- flow paths to and from A S/G isolated. A S/G blown.has dry. -
BASELINE DATA: Malfunction Description 6.3.4.9.1. . Emergency Operating Procedures E-0, E-2, ESF Check 1ists ; DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
- - - . . . . . . - - . . . . - -- - . - . , . . . . . ,. . -. - ,a .
BVPS 1 SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Steam Leak Downstream of MSIV SQT-4.106 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:10/18/89 GENERAL DESCRIPTION: Increased steam flow results in increased Rx power. OPAT runback activated, but Rx power still reaches the OPAT trip setpoint. Following the Rx trip excessive steam flow continues to cool and depressurize the S/Gs and RCS. Steamline pressure drops-to the SI/STM line isolation setpoint in all S/Gs. Following Isolation RCS and S/G parameters trend toward stable values considering SI has actuated. AVAILABLE OPTIONS: MSS 2A A Steamline Leak Rate 0-12E6 lbm/hr MSS 28 B Steamline Ramp time 0-9999 see MSS 20 C Steamline OPTION TESTE0: MSS-2B,12E6 lbm/hr, 60 sec ramp O INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Control Rods in Auto FINAL CONDITIONS TEST DURATION: 2 HRS. Plant parameters trending toward post trip / spurious SI anticipated valves BASELINE DATA: Malfunction Description 6.3.4.9.2 Alarm Response Procedure A4-50 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.S: None __ - - , - - , , - - - -_.-s-. - _ - - - - - - -
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: MSIV Drifts Shut SQT 4.107 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTE0:10/18/89 GENERAL DESCRIPTION: "A" Mily drifts shut r :ulting in decreased heat removal in the "A" loop and severe level shrink to the Lo Lo Rx trip setpoint. Prior i to the trip 'B" and "C" loops attempt to compensate for the load " drop" of the
" A" loop. Due to the rapid pressure drop in the "B" & "C" steam generators, a Si and MSLI occurs.
4 l AVAILABLE OPTIONS: MSS 3A TV-MS-101A Ramp Time 0 9999 sec MSS-3B TV MS-101B MSS-3C TV-MS-101C OPTION TESTED: MSS 3A, 60 see i l O INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE BOL l LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: . S HRS .~ Plant parameters trending toward anticipated post trip / spurious SI values BASELINE DATA: Malfunction Description- 6.3.4.9.3 Alarm Response Procedure Al-56 DEFICIENCIES: None CORRECTIVE ACTION /DATE: NA _ O EXCEPTIONS TAKEN TO ANS. 3.5: None b
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Non Return Valve to 1st Point Heater Fails SQT-4.108 O REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 7/10/90 l GENERAL DESCRIPTION: Loss of preheat in the 1st point heaters results in introduction of colder feedwater to the S/G's, increased secondary heat -l removal and subsequent RCS temperature reduction causes reactor power to ; increase. Rods receive a withdrawal demand signal, however,:a Bank D full ! withdrawal sto) prevents rod motion. The final reactor power and Tavg will be = dependent on tie magnitude of the power / temperature reactivity coefficients. I a AVAILABLE OPTIONS: Failed Position 0 Open C-Closed-OPTION TESTED: MSS-4, C NRV ES 101 fails closed # INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL !
*O,LISTOTHERSPECIALCONDITIONS:
None FINAL CONDITIONS TEST DURAT10N: .5 HRS-. Reactor power stable above 100% power with a reduced Tavg. BASELINE DATA: Malfunction' Description 6.3.4.9.4 DEFICIENCIES: None. 4 CORRECTIVE ACTION /DATE: !
.N/A j.
.None:
-(]EXCEPTIONSTAKENTOANS.3.5: u
i l BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT 1 i l TEST TITLE: Non-Return Valve to 3rd Point Heaters fails SQT 4.109-I REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:. 7/10/90
- GENERAL DESCRIPTION
- Reduced feedwater preheat results in a reduction in #
overall plant efficiency. (The final ratio of Rx power / turbine power > increases), t 1 i l l AVAILABLE OPTIONS: MSS 5A NRV ES-103A failed Position 0 open, C-closed MSS 5B NRV ES 103B j OPTION TESTED: MSS 5A l INITIAL CONDITIONS: 10 42- 100% PWR. CORE AGE BOL-l s LIST OTHER SPECIAL CONDITIONS: ( Verify rods in AUTO. FINAL-CONDITIONS TEST DURATION: :.75 HRS. Rx power stable above 100% with a reduced Tavg. ; l BASELINE DATA: Malfunction Description 6.3.4.9.5 i DEFICIENCIES: None l CORRECTIVE ACTION /DATE:- N/A 1 EXCEPTIONS TAKEN TO ANS. 3.5: None
I i BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Steam Generator Relief Valve fails SQT-4.110 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTE0:10/20/89 GENERAL DESCRIPTION: Since the RV must initially lift for the malfunction to . work, all normal post-trip steam release paths are locally isolated prior to a ! turbine trip. The turbine is then nanually tripped resulting in an immediate Rx trip due to power above P 9 (49%). S/G pressure increase above 1075 psig causing SV's to lift. The operator c:anually isolates reheat steam IAW E0P's.
- As RCS temperature and S/G pressure
- , decrease, all but the stuck open SV close.
B & C S/G pressures stabilize. A S/G continues to depressurize. The plant will eventually SI on low steamline pressure. 4 AVAILABLE OPTIONS: (MSS 6A thru 0) Selects failed safety valve. Select Leak Rate 01000,000 lbm/hr. OPTION TESTED: MSS 6A,100,000 lbm/hr. INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE - BOL iO LIST OTHER SPECIAL CONDITIONS: ( t i Isolate steam to FW P 2 and S/G atmospheric relief valves using LOA's l to assure S/G safety valves lift during-the test. The condenser steam j dumps are defeated. FINAL CONDITIONS TEST DURATION: 3.0 HRS.: RCS pressure and temperature decreasing, Si has occurred. l l BASELINE DATA: Malfunction Descriptior. 6.3.4.9.6 1 DEFICIENCIES: None j CORRECTIVE ACTION /DATE: N/A l l. O EXCEPTIONS TAKEN TO ANS. 3.5: None
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3 I BVPS I SIMULATOR CERTIFICATION TEST' ABSTRACT > L l
- TEST TITLE
- Steam Dump Valve Fails to Operate SQT-4.111-REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 7/10/90 l
j GENERAL DESCRIPTION: The test is initiated using malfunction TUR-15 to cause a j 40% load rejection. Although the dumps arm with an open demand signal present, s no dumps open. RCS temperature and pressure increase. S/G pressures increase, levels decrease due to shrink. Control rods insert at max. rate to restore-Tavg Tref. An OT Delta-T- and/or OP Delta T rod stop/run back could occur due to excessive RCS Tavg, but did not for this test. Plant oscillations eventually converge. l l I l AVAILABLE OPTIONS: None i OPTION TESTED: N/A . INITIAL CONDITIONS: IC-42 100% PWR. CORE AGE - BOL O LIST OTHER SPECIAL CONDITIONS: None l : FINAL CONDITIONS TEST DURATION: 1.25 HRS. Plant stable at about 77%, Tavg Tref., S/G 1evels return to program. BASELINE DATA: Malfunction Description 6.3.4.9.7-DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A j
/ )EXCEPTIONSTAKENTOANS.3.S: None w- aw N an..e-ww. ~ , , - . - . v a-a,,-se-ee,s--, .w,e- w. r m - -e-w av-+ -or - w ,e- ,,me.-,r-e.ee v. o,-- n en e--,v,-- ,,,m--,-, -- ee r sw . -waww~ r- ,W- -m v. , g er, s we rvn.,e n +
r BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Steam Dump Valve Sticks SQT 4.ll2 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:07/13/90 GENERAL DESCRIPTION: A main turbine trip is manually initiated which in turn results in a Rx tri) due to power > P9. The Rx trip arms the first two banks of steam dumps whici pop open due to the Tavg Tno load mismatch. Tavg reduces to Tno-load and all but the failed valve modulate closed. Tavg reduces below 547'F. The failed dump valve fails to close in response to operator attempts to use the manual controllers or Train A and 8 off switches. Local closure of the dump header manual isolation valves terminates steam dump. Plant conditions stabilize. AVAILABLE OPTIONS: MSS 8A thru R 18 Steam dump valves failed Position 0-100% OPTION TESTED: MSS 8A, 100% s O INITIAL CONDITIONS: 10 42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Main turbine is manually tripped to initiate the transient. Steam dump is selected to STM Press mode af ter recognition of stuck open dump valve. Steam dumps are subsequently selected to Off Steam header manual isolation valve is closed via a LOA to stuck open dump valve FINAL CONDITIONS TEST DURATION: .75 HRS. Plant stable in Hot Siby BASEllNE DATA: Malfunction description 6.3 4.9.8 DEFICIENCIES: None ( 3 CORRECTIVE ACTION /DATE: NA V EXCEPTIONS TAKEN TO ANS. 3.5: None I
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT O TEST TITLE: Erratic Tavg Control SQT-4.ll3 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:07/09/90 GENERAL DESCRIPTION: Control rods move in and out as Tavg signal oscillates. All major primary and secondary system parameters respond as predicted. After placing rod control in manual the primary and secondary system oscillations damper. AVAILABLE OPTIONS: Range 0 10*F Oscillation period 0-1000 sec n OPTION TESTED: 10'F, 300 sec l V INITIAL CONDITIONS: 10 42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: l Rods initially in auto, placed in manual after verifying all parameters oscillating FINAL CONDITIONS TEST DURATION: 1.5 HRS. Power stabilized at 100% i BASELINE DATA: Malfunction description 6.3.4.9.9 DEFICIENCIES: None CORRECTIVE ACTION /DATE: NA EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I $1MULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Tref to Steam Dump Fails SQT 4.114 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 7/24/90 GENERAL DESCRIPTION: The malfunction is activated and a large Tavg Tref error signal exists. The o>erator then initiates a load rejection. to arm the dumps. When the dumps arm, tiey open due to the Tavg Tref error signal. Steam flow 1 increases, Rx Power increases, due to drop in Tavg and outward rod motion. ' AVAILABLE OPTIONS: MSS 10A Turbine Trip Logic Failed Value 540-580*F MSS 10B Load Rejection Logic-- OPTION TESTED: MSS 10A, 540'F INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE =- BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 2.0 HRS. Malfunction active, steam dumps open,-Rx power increasing, Rods moving out to restore Tavg to Tref. BASELINE DATA: Malfunction Description 6.3.4.9.10: DEFICIENCIES: Tref meter and B/S status-light do not work properly.
' CORRECTIVE ACTION /DATE: Trouble Report 304 written. TR 304 to be resolved by December,'1991.
EXCEPTIONS TAKEN TO ANS. 3.5: None
~
i l l BVPS I $1HULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Steam Pressure Signal to Steam Dump Fails SQT 4.ll5 l j REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:07/24/90 i GENERAL DESCRIPTION: In response to the sensed high pressure condition 2 banks-
- of steam dumps modulate full open with Tavg above 543*F. RCS temperature drops as does steamline pressures until the rate sensitive low steamline
- pressure logic li met resulting in a SI and steam line isolation. All steam
! dumps trip closed when Tavg reaches P12 (543'F). The operator attempts to reduce steam dump controller output in MANUAL but the action is ineffective. ! The low low tavg interlock is manually defeated and the three cooldown dump valves are observed to modulate full open. . The dumps are selected to 0FF and the three cooldown valves are observed to trip closed. t AVAILABLE OPTIONS: Failed valve 0 1400 psig l OPTION TESTED: 1400 psig O INITIAL CONDITIONS: IC- 48 0% PWR. CORE AGE - HOL-
- LIST OTHER SPECIAL CONDITIONS
! Steam Dumps selected to STM PRESS mode Steam Dump controller in Auto FINAL CONDITIONS TEST DURATION: . 75 HRS.
Malfunction Description 6.3.4.9.11 BASELINE DATA: Malfunction Description 6.3.4.9.11 DEFICIENCIES: None L CORRECTIVE ACTION /DATE: NA , l EXCEPTIONS TAKEN TO ANS. 3.5: None ym g y tuehsums.w=-q-- -y_,y,?49 w y-puw g ue3t9 y peiy ee- g. e,+=-sg. ,,eg*Fgy-9,re,- ,,n .,w-y-gi --- - yyye--yy-, gmy w y w w - y vgge-W t rg,1Www av4'Wyq-+=W
I DVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Atmospheric Steam Dump Valve Fails SQT-4.ll6 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:07/24/90 GENERAL DESCRIPTION: Controller output increases to 25%, PCV MS-101A opens as indicated by position lights on BB A. Loop A Tavg and auctioneered high Tavg decrease. Operator action to close PCV MS 101A. Altnough controller output can be reduced to zero, the valve remains 25% open. Upon local isolation of i the PCV, Steam Flow is isolated. RCS/ secondary parameters stabilize at no load conditions. AVAILABLE OPTIONS: MSS 12A PCV MS 101A Failed position 0 100% MS$128 PCV MS 101B MSS 12C PCV MS-101C Ramp time 0 9999 sec OPTION TESTED: MSS 12A, 25%, O sec ' O INITIAL CONDITIONS: 10 48 0% PWR. CORE AGE - MOL l LIST OTHER SPECIAL CONDITIONS: Attempt manual control following failure Locally close manual isolatinn valve via LOA FINAL CONDITIONS TEST DURATION: 1.0 HRS. Plant stable in Hot Standby with PCV-MS 101 locally isolated BASELINE DATA: Malfunction description 6.3.4.9.12 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None l I
17
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BVPS 1. SIMULATOR CERTIFICATION TEST. ABSTRACT 1 TEST TITLE: Erratic Control- of Atmospheric Steam Dump-Valve -SQT 4.ll7 O REQUIRED BY ASI/ANS 3.5 SECTION:- 4.2.2 DATE-TESTED: 7/24/90 l GENERAL DESCRIPTION: PCV MS 101A oscillates-open and closed over a 50% range with an oscillation frequency of 100 sec. A S/G pressure and flow oscillate- as expected causing a net cooldown of the RCS (pump and decay heat input only). The operator takes manual control of PCV MS-101A. The oscillations stop. S/G ; parameters stabilize. RCS returns to no-load .Tavg. -!\ l i I AVAILABLE OPTIONS: MSS 13A PCV MS 101A Range 0-100% MSS-138 PCV MS-101B Period 0-1000-sec. MSS 13C PCV MS 101C OPTION TESTED: MSS 13A, 50%, 100 sec. INITIAL CONDITIONS: 10-48 0% PWR, CORE AGE - MOL i O LIST OTHER SPECIAL CONDITIONS: i Selected valve must be in AUTO prior to test initiation FINAL CONDITIONS TEST DURATION: 1.0 HRS. I Plant stable at normal no-load conditions. l BASELINE DATA: Malfunction Description 6,3.4.9.13 ' DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
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4 i BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT i R TEST TITLE: Steam flow Transmitter Failure SQT 4.ll8 O REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 7/31/90 i GENERAL DESCRIPTION: Steam flow indiction to 'A' S/G (FT MS 474) fails high.
'A' MFRV goes open in response to the anticipatory flow error signal generated '
. by SGWLC. 'A' S/G 1evel starts increasing above program resulting in an offsetting level error signal. Upon receipt of a level deviation alarm the' operator places ' A' MFRV in manual, matches feed to steam flow. The alternate
- steam flow channel is selected as the input to SGWLC. 'A' MFRV is then restored to AUTO. Feed flow reduces as 'A' S/G 1evel is restored to program.
Feed flow returns to normal.
- t AVAILABLE OPTIONS: 4 MSS 14A/B FT474/475 'A' S/G Failed Value 0 4.5E6'1bm/hr MSS 14C/D FT484/485 'B' S/G Ramp Time 0 9999 sec.
MSS 14E/F FT494/495 'C' S/G I OPTION TESTED: MSS 14A, 4.5E6 lbm/hr O sec. INITIAL CONDITIONS: 10 42 100% PWR, CORE AGE - BOL Os LIST OTHER SPECIAL CONDITIONS: The failed channel is selected as the controlling channel for SGWLC prior to mt.1 function activation. l FINAL CONDITIONS TEST DURATION: 15 HRS. Plant stable at 100%, all feed reg, valves in AUTO maintaining program level. BASELINE DATA: Malfunction Description 6.3.4.9.14 Alarm Response Procedure A7 45-DEFICIENCIES: None i CORRECTIVE ACTION /DATE:- N/A EXCEPTIONS TAKEN TO ANS. 3.5: None [ L
i BVPS 1 SIMOLATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Steam Pressure Transmitter Failure to Atm Dump Valve SQT-4.119 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 7/24/90 GENERAL DESCRIPTION: 'A' S/G pressure indicators high. PCV MS 101A opens fully resulting in an increased steam demand of approximately 30%. RCS-parameters respond as expected to increased steam demand resulting in an increase of Rx power. An OP Delta T rod stop is actuated on 'A' Loop but- the coincidence of 2/3 is not made. The operator places PCV MS 101A controller in manual and closes the valve. Steam flow returns to the initial 100% value. I I AVAILABLE OPTIONS: MSS ISA PCV MS 101A Failied Value 01200 psig MSS ISB PCV MS 101B Ramp Time 0 9999 sec , MSS ISC PCV-MS 101C- i OPTION TESTED: MSS 15A, 1200 psig, 60 sec. INITIAL CONDITIONS: 10 42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Atmospheric dump valve controller in AUTO prior to test initiation. FINAL CONDITIONS TEST DURATION: 1.5 HRS. Plant stable at initial conditions (100%) i I BASELINE DATA: Malfunction Description 6.3.4.9.15 Alarm Response Procedure A4 66 DEFICIENCIES: None i CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None O 4
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Steam Pressure Transmitter Failure SQT-4.120 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:ll/20/89 l I GENERAL DESCRIPTION: Channel 111 of .'A' S/G steam indicates high. 'A' MFRV opens in res)onse to the steam flow / feed flow mismatch. 'A' S/G 1evel increases. Jpon receipt of the level deviation alarm, the operator places 'A' MFRV in manual then matches feed flow to steam flow (actual). Operator selects . Channel IV steam flow for control then returns 'A' MFRV to AUTO. 'A' 5/G 1evel and flows return to normal. l s AVAILABLE OPTIONS: MSS 16A/B/C PT474/475/476 Failed Value 0 1200 psig MSS-160/E/F PT 484/485/4C6 Ramp Time 0-9999 Sec. MSS 16G/H/I PT494/495/496-OPTION TESTED: MSS-168, 1200 psig, 20 Sec. INITIAL CONDITIONS: 10 42 100% PWR, CORE AGE BOL O LIST OTHER SPECIAL CONDITIONS: Channel to be failed is solocted as the input to.SGWLC FINAL CONDITIONS TEST DURATION: 1.0 HRS.- Plant stable at 100%, all MFRV's in AUTO controlling S/G 1evels on program, i BASELINE DATA: Malfunction Description 6.3.4.9.16 DEFICIENCIES: None CORRECTIVE ACTION /DATE:- N/A l : 1 , EXCEPTIONS TAKEN TO ANS. 3.5: None [
.._ _.__ _. _ _ _ ~ _ . _ _ . _ _ ._ _- . . _ _ _
.] l BVPS 1 SIMULATOR CERTIFICATION TEST A3STRACT TEST TITLE: Steam Leak on AFW Pump Supply.Line SQT-4.121-REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTEDr07/24/90 GENERAL DESCRIPTION: The leak occurs on the common supply header upstream of the isolation mov. Two S/G's are normally aligned to supply FW P-2. The plant ' responds as expected to the increased steam demand with an eventual OP Delta T 1 rodstop/ turbine runback generated. The operator manually trips the reactor after about 5 minutes. The reactor trip coincident with low taug causes a main feedwater isolation. S/G levels and pressures drop until a low steamline pressure 51 is actuated (MSLI also occurs to the low steamline pressure). The operator takes FW P 3A and 3B out of PTL. Both pumps auto start, providing
> 700 gpm AFW flow. Local operator action isolates steam flow to the leak.-
S/G levels bagin to recover. AVAILACLE OPTIONS: Steam Leak Rate 0 100% 1 i' OPTION TESTED: 100% INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE-- BOL O LIST OTHER SPECIAL CONDITIONS: Both MOFW pumps are placed in PTL prior to test performance, i FINAL CONDITIONS TEST DURATION: 1.5 HRS. Reactor tripped with SI in progress. Plant conditions' stabilizing'following steam leak isolation. BASELINE DATA: Malfunction Description 6.3.4.9.17' ' Emergency Operating Procedures E-0. E-2 DEFICIENCIES: None, i CORRECTIVE ACTION /DATE: N/A
- EXCEPTIONS TAKEN TO ANS. 3.5: None.
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t BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT l TEST TITLE: Source Range Channel Failure SQT-4.122-REQVIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:ll/29/89 i GENERAL DESCRIPTION: A failure of on channel of SR high. exceeding 10 5cps l j prior to SR being blocked at P 6 (10'I0 amps) results in a Reactor Trip. i ! i : a I . t L : NIS-1A N31 Failed Value 10 0-10 6cp3 AVAILABLE OPTIONS: j NIS-1B N32 Ramp Time 0 9999 Sec. 4 l l OPTION TESTED: NIS 1A, IE6 cps, 60 Sec. l INITIAL CONDITIONS: 10 48 0 % PWR. CORE AGE - MOL i , e LIST OTHER SPECIAL CONDITIONS: I None l FINAL CONDITIONS TEST DURATION: .5 HRS. Plant in Mode 3, Rx tripped on SR High Flux. ! BASELINE DATA: Malfunction Description 6.3.4.10.1 i DEFICIENCIES: Meter indication was inaccurate low due to meter out of calibration. CORRECTIVE ACTION /DATE: T.R.195 written. T.R.-195-has been resolved. EXCEPTIONS TAKEN T') ANS. 3.5: None l
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT c Intermediate Range Channel failure SQT 4.123 (] TEST TITLE: i'EQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:ll/29/89 GENERAL DESCRIPTION: The malfunction is initiated wnen the plant is below P-10, when activated the channel fails high, SUR increases then decays off, the high level bistable causes a plant reactor trip. AVAILABLE OPTIONS: NIS-2A N 35 Failed Value IE-Il to IE-3 amps NIS 2B N-36 OPTION TESTED: NIS 2A, IE-3 amps m l b INITIAL CONDITIONS: 10 13 0% PWR CORE AGE - HOL LIST OTHER SPECIAL CONDITIONS: None l l FINAL CONDITIONS TEST DURATION: .5 HRS. IR Channel 35 failed high, Px tripped. BASELINE DATA: Malfunction Description 6.3.4.10.2 Plant Alarm Response Procedure AS-1 DEFICIENCIES: None CORRECTIVE ACTION /0 ATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
l BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Power Range Channel Failure SQT 1.124 REQVIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:11/09/89 GENERAL DESCRIPTION: N-44 pegs high at 100%, the positive rate bistable trips. Control rods insert at maximum speed due to power mismatch (rate) circuit. As the Terror signal builds td the power mismatch signal decays, rods slow and eventually stop. Rod withdrawai is demanded but the 1/4 channel over power rod stop prevents motion. Since this malfunction occurs at the output of the summing and level amp detector current comparison and OP/0T delta T circuitry ; remains unaffected. A channel deviation alarm is generated. The operator defeats the overpower rod stop on MC&1 drawer. AVAILABLE OPTIONS: NIS 3A N 41 NIS 3D N 44 NIS-3B N-42 Failed Value 0 200% NIS-3C N 43 Ramp Time 0-9999 Sec. OP110N TESTED: NIS 30, 200%, O Sec. INITIAL CONDITIONS: IC 42 100% PWR. CORE AriE - BOL ~ LIST OTHER SPECIAL CONDITIONS: ! Control Rods in AUTO FINAL CONDITIONS TEST DURATION: .5 HRS. , Power stable slightly below 100%, Tavg low Turbine on the GV limiter due to reduced steam pressure. BASELINE DATA: Malfunction Description 6.3.4.10.3 Abnormal Operating Procedure 1.2.1 DEFICIENCIES: None ! CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS 3.5: None i
I
- BVPS_I: SIMULATOR CERTIFICATION-TEST ABSTRACT - TEST TITLE: Intermediate RangeLCompensating Voltage Failure- - SQT'-4.125:.
l' REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE: TESTED:ll/29/85 GENERAL-DESCRIPTION: N-35 loss of compensating voltage trips thefrawer l bistable and actuates the control board annunciator. The o)erator-inserts rods .; to establich a slightly negative SUR. H35 level indicates ligher than N36 and has a smaller SUR indicated. The operator stabilizes power at 1E-11 amps ; (N36), N35 levels off about SE 8 amps. ! i AVAILABLE OPTIONS: NIS 4A N 35 Current Value -- IE-11 to IE-5, +1E-Il 'to +1E-5 NIS-4B N 36 Ramp Time 0 9999 Sec. OPTION TESTED: NIS4A, +5E-8 amps, O Sec. INITIAL CONDITIGHS: 10-13 10-8 amps 100%-PWR. CORE AGE:- MOL-LIST OTHER SPECIAL CONDITIONS: Slowly in ease power to IC 7 amps and stabilize prior to malfunction ac i,uation. 1 i FINAL CONDITIONS- TEST DURATION: 1.5 HRS. Rx power stable at 2E-ll amps (N36) 6 BNELINE DATA: Malfunction Description .6.'3.4.10.4 Alarm Response Procedure A4-94 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO'ANS. 3.5: None u
e BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT i TEST flTLE: Source Range High Voltage Cutoff Failure SQT-4.126 O REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2- DATETESTED:11/29/89 I GENERAL DESCRIPTION: The malfunction results in failure of one channel of SR to de energize when the SR high flux ~ trips are manually blocked by the operator ! during a Reactor startup. N32 de-energizes normally when the trip is blocked j
-but N31 remains on. The level trip is blocked, Reactor power continues to- i increase above P10 but N31 remains energized. ;
1, AVAILABLE OPTIONS: NIS SA N-31 NIS 5B N-32 ; OPTION TES1ED: NIS-SA
-i INITIAL CONDITIONS: 10-13 100% PWR. CORE AGE.- MOL hLISTOTHERSPECIALCONDITIONS:
Perform a Reactor startup IAW OM 50 FINAL CON 91T'10NS TEST DURATION: -.75 HRS. , Reactor power 2 10% (P-10) BASELINE DATA: Malfunction Description 6.3.4.10.5 DEFICIENCIES: None 6-CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None a
BVPS'l SIMULATOR CERTIFICATION TEST ABSTRACT-TEST TITLE: Source Range Fuse Blown- SQT 4.127 4 .- 2 . 2 i REQVIREDCY.ASI/ANS3.5SECTION: !DATE-TESTED:11/_29/89-GENERAL DESCRIPTION: A reactor trip signal is generated by SSPS due to loss of power to Source Range Channel:1 input relays. Since thel coincidence is 1/2 the reactor trip breakers open. .No drawer bistable lights are lit due to a-loss of power to the lights. 1 AVAILABLE OPTIONS: NIS-6A N31 1 -~ Instrument Power' Fuse NIS-6B N32 -2.4 Control Power fuse l OPTION TESTED: NIS-6A.2 INITIAL CONDITIONS: 10-48 0%-PWR,- CORE AGE - MOL O- LIST OTHER SPECIAL-CONDITIONS: None. FINAL CONDITIONS. TEST DURATION:. -.45 HRS. Rx subcritical, trip breakers open. BASELINE DATA: -Malfunction description 6.3.4.10.6-Abnormal operating -procedure -1.2.1 DEFICIENCIES: Drawer fuseholder lights do not light ~up when the fuse blows.. CORRECTIVE' ACTION /DATE: . Change Request #120 written; to be resolved by-
-December 1992.-
f EXCEPTIONS TAKEN TO ANS. 3.5: None
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT ,73 TEST TITLE: Intermediate Range Blown Fuse SQT-4.128 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:ll/28/89 GENERAL DESCRIPTION: N 35 indication fails low due to loss of detector HV power supply. All drawer bistables trip with appropriate status lights lit (except P6 which goes out when the bistable trips). No trips or rodstops occur due to being blocked when power is raised above 10% (P10). AVAILABLE OPTIONS: NIS-7A N 35 1 - Instrument Power Fuse NIS-7B N-36 2 - Control Power Fuse OPTION TESTED: NIS-7A, 1 fm INITIAL CONDITIONS: 1C-42 100% PWR. CORE AGE - BOL (_)LISTOTHERSPECIALCONDITIONS: None
-FINAL CONDITIONS TEST DURATION: .5 HRS.
Plant stable at 100%. BASELINE DATA: Malfunction Description 6.3.4.10.7 Abnormal Operating Procedure 1.2.1 DEFICIENCIES: Fuse holder light does not light when the fuse blows. CORRECTIVE ACTION /DATE: Change Request #121 written / l'4 EXCEPTIONS TAKEN TO ANS. 3.5: None
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t- i BVPS I SIMULATOR CERTIFICATION: TEST ABSTRACT- - Power Range Fuse Blows SQT-4.129 L aTESI TITLE: REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2- .DATE TESTED:ll/28/89 j GENERAL DESCRIPTION:. N-41 detector currents and channel indication fail low due to loss of detector HV. All. drawer bistnoles-trip with associated status, j lights and alarms generated. Detector.and channel current.comparators -i geparate deviation alarms which subsequently _ clear when the operator defeats- l the failed inputs.at the NIS rack. N 41 provides no control- function inputs., i AVAILABLE OPTIONS: NIS-8A N-41 1 --ins'trument Power Fuse-- . NIS-8B N 2'- Control Power' Fuse ! NIS-8C- N-43. HIS-8D N 44 OPTION TESTED: NIS-8A, 1 INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL L LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION:1 .3 HRS. Plant ' stable at 100% power. BASELINE DATA: . Malfunction Description 6.3.4.10.8 Abnormal Operating Procedure 11.2.1 - DEFICIENCIES: Fuse holder light (s) don't' light when fuse blows. CORRECTIVE ACTION /DATE: Change Request'#122 written. CR-122 to be installed by ' December 1992. EXCEPTIONS TAKEN TO ANS. 3.S:- None
L l BVPS-I SIMULATOR CERTIFICATION TEST ABSTRACT. , d TEST TITLE: CCT Pump-Trip SQT-4.1305 ; REQUIRED BY ASI/ANS- 3.5 SECTION:: 4.2.2: DATE-TESTED:ll/29/89; GENERAL DESCRIPTION: Trip of the running CCT pumps:causes system pressure to drop. Tho. Standby pump auto starts following a 5-second time delay after sensing the in*t-pressure condition or auto stop of the running. pump _-- i 1 AVAILABLE-OPTIONS: CCT-1A' <CC-P-3A' q
- CCT-1B. CC-P-3B i
OPTION TESTED: -CCT-1A 1C-42 100% PWR.- CORE AGE - BOL-O.INITIALCONDITIONS: LIST OTHER SPECIAL CONnITIONS: None FINAL CONDITIONS- TEST DURATION::c.5l HRS. CCP-3A off, CCP-3B running after. an auto start, CCT parameters returning to normal. - ! BASELINE DATA:' Mal function -Description' 6.3.4.3;l
- Alarm Response Procedures A6-57, A6-58,: A8 DEFICIENCIES: None CORRECTIVE ACTION /DATE: . N/A
()' EXCEPTIONS'TAKENT0ANS.3.5: None R f _m E_-___._ _[_._... m .- __._\
BVPS I SIMULATOR CERTIFICATION TEST-ABSTRACT TEST TITLE: TCV-CC-215 Fails SQT-4.131-REQUIRED BY ASI/ANS 3.5 SECTION:- 4.2.2 -DATE TESTED:12/18/89 GENERAL DESCRIPTION: When the TCV fails open, most system flow will: bypass the. CCT heat exchangers. System temperatures will increase until'high temperature alarms activate for various components cooled. 1 l AVAILABLE OPTIONS: Failed Position 0-100% Ramp Time 0-9999 Sec. ; OPTION TESTED: 100%,~10 Sec. INIT1AL CONDITIONS: 10-42 100% PWR. CORE-AGE --BOL. i OLISTOTHERSPECIALCONDITIONS: None FINAL CONDITIONS TEST' DURATION:. 1.0 HRS. Test terminated due to unsatisfactory response. . System temperatures decreasing, pump amps indicate reduced system flow. BASELINE-DATA: Malfunction Description 6.3.4.3.2 .. Alarm Response Procedures A6-59, A6-98, A6-106,- A6-89, A7-127, A7-88, A8-7 DEFICIENCIES: System temperature and flow response incorrect. CORRECTIVE ACTION /DATE: T.R. #283 written. -TR-283 wi1T be resolved by December, 1991. EXCEPTIONS TAKEN TO ANS. 3.5: ~None
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BVPS I- SIMULATOR CERTIFICATION TEST ABSTRACT-~ l q
. . -i g TEST TITLE: -CCT Supply Line Leak- SQT-4.132; q 4.2.2 -- -!
REQUIRED BY ASI/ANS 3.5 SECTION: DATETESTED:12/18/89: GENERAL DESCRIPTION: The leak is of sufficient magnitude to exceed the auto:- 1
-makeup capability of the condensate. system.- System mass drops below the surge -
tank low level alarm setpoint. When the-running pump discharge. pressure drops
- below 60 psig for 5 sec., the standby _ pump _ auto; starts.. System flow drops resulting in insufficient cooling of various-components. When the malfunction '
is cleared, surge tank level increases due.to auto' makeup. a 1 1 AVAILABLE OPTIONS:-CCT-3A CND PP'MTR OIL CLR--CCT3D.150--PHASE DUCT-CCT 3B EH CLR. .CCT3E Hp,.LVAC. PRIME, SAC, CLRS . CCT-3C- TUR OIL CLR . Leak Rate 0-500 gpm- ! Ramp Time 0 9999 sec._ g OPTION TESTED: CCT-3B, 500 gpm,10 sec. INITIAL CONDITIONS: 10-42 '100% PWR. -CORE AGE - BOL-O_ LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1.5 HRS. Surge tank level recovering. BASELINE DATA: Malfunction l Description 6.3.4.3.3 .
. Alarm Response: Procedures A6_-61, . A7-'127, A8-7, A6-57, A6-58.
DEFICIENCIES: None . CORRECTIVE ACTION /DATE: N/A o EXCEPTIONS.TAKEN TO ANS. 3.5:.-None
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACTI ! CCT Suction Header Leak - SQT-4.133, OTESTTITLE: REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2' .-DATE TESTE0:12/18/89 GENERAL DESCRIPTION: The~1eak is of sufficient magnitude;to exceed the auto makeup ca) ability from the' condensate system.- System mass decreases below the- '- surge tans low level alarm setpoint. Continuing loss of mass results in low-- pump discharge pressure. The standby pump auto starts after a 5:sec. time' i del ay. System flow is insufficient to provide cooli'ng resulting-in high temperature alarms and trips (where applicable) of tcomponents' served.. s, , L AVAILABLE OPTIONS: Leak Rate 0-1000 gpm
-Ramp Time 0-9999-sec'.
OPTION TESTED: 1000 gpm, O sec. INITIAL CONDITIONS: .IC-42 100 % PWR. CORE AGE -- BOL O, LIST OTHER SPECIAL CONDITIONS:- None 4 ( '.. FINAL CONDITIONS TEST DURATION: 2.0 HRS. CCT pumps in PTL,.high temperature conditions on-various~ components - served.' - BASELINE DATA: Malfunction Description 6.3.4. 3,4 . - Alarm Response Procedures A6-61, A6-58,~ A6-57,,A6 59, A7-88,
-AS-98, A6-108,- A6-89, A6-127, A8 l DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A' ,
EXCEPTIONS TAKEN TO ANS. 3.5: None e e r -v <- , .- , --
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: PZR Safety Valve Leakage SQT-4.134 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 4/09/90 GENERAL DESCRIPTION: The acoustic monitor and tail pipe temperature provide indication and alarm for the affected valve. PZR level and pressure decrease. PRT conditions indicate RCS leakage. AVAILABLE OPTIONS: PRS-1A RV-RC-551A Leak Size 0-5% PRS-1B RV-RC-551B Ramp Time 0-9999 sec. PRS-lC RV-RC-551C OPTION TESTED: PRS-1A, 5%, 60 sec. p INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL y LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .75 HRS. PZR level and pressure decreasing with PRT level, temperature, anc pressure increasing. BASELINE DATA: Malfunction Dsscriotion 6.3.4.11.1 Alarm Respons! Pro'cedure A4-6 DEFICIENCIES: None CORRECTIVE ACTION /DATE: h/A
/ EXCEPTIONS TAKEN TO ANS. 3.5: None
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'BVPS'I SIMULATOR CERTIFICATION l TEST ABSTRACT:
PZR St'ety Valve: Failure' SQT-4.135-
.O(TEST-TITLE:
REQUIRED ~BY-A'I/ANS 3.5 SECTION:':4.2.2- ;DATE TESTED:J4/09/90 GENERAL CESCRIPTION:. The selected safety valve fails full open with i appropriate indications on acoustic monitor,- tail pipe _ temperature,'and;PRT - conditions. _RCS pressure drops rapidly;resulting in a_ reactor trip-and SI.. :i The PZR goes solid ~in about 8 minutes.- The PRT: eventually ruptures. CNMT- j conditions' degrade' as the RCS continues to blowdown. The operator; trips-all' RCP's IAW Emergency Operating Procedures. - a \. l e l AVAILABLE OPTIONS: PRS-2A RV-RC-551A PRS-28 RV-RC-551B-- ~ PRS-2Ci RV-RC-551C t OPTION TESTED: PRS-28 l INITIAL: CON 0liIONS: 10-42 . 100% PWR.' ' CORE AGE -~ BOLL- . LIST 0THER SPECIAL CONDITIONS: ;[ None , I-FINAL CONDITIONS . TEST DURATION: ..i HRS. . j1
- Rx tripped, SI/ CIA actuated, _HHSI flow and S/G'.s with AFW flow.providing. 3 core cooling, leak path via stuck open safetycvalve.'
BASELINE DATA:- Malfunction Description 6.3.4.11.2 Emergency Operating procedures E-0, E DEFICIENCIES: -None-CORRECTIVE ACTION /DATE: N/A EXCEPTIONS-TAKEN TO ANS. 3.5: None- ,
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: PZR PORY Failure SQT-4.136 O REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 7/12/90 GENERAL DESCRIPTION: When the malfunction is activated, the PORV fails open, acoustic indication and PORV open annunciator are verified. Plant response is verified. The block valve for the failed PORV is closed to verify it will isolate the problem. AVAILABLE OPTIONS: PRS-3A PCV-RC-455C Leak Size 0-5% PRS-3B PCV-RC-455D PRS-3C PCV-RC-456 Ramp Time 0-9999 sec. OPTION TESTED: PRS-3A, 5%, 60 sec. INITIAL CONDITIONS: 1C-42 100% PWR. CORE AGE - BOL O LIST OTHER SPECIAL CONDITIONS: None flNAL CONDITIONS TEST DURATION: 1.0 HRS. Malfunction active, Pressure low but increasing, PORV is failed open but isolated by Block Valve. Power is reduced due to OTAT Runback. BASELINE DATA: Malfunction Description 6.3.4.11.3 Alarm Response Procedures A4-6, A4-25 DEFICIENCIES: Instructor System Description on Console is incorrect 0-5% should be 0-100%. CORRECTIVE ACTION /DATE: Trouble Report 268 written. TR-268 has been resolved. EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST.ABSTPACT 1 g EST T TITLE: PORV Rescat Failure SQT-4.137 REQUIRED BY ASI/ANS 3.5.SECTION: 4.2.2 .DATE TESTED: 7/12/90-GENERAL DESCRIPTION: With all PZR heaters manually energized and the spray valves in manual and closed PZR pressure will increase to the PORY lift setpoint. -Although all PORV's may lif t, only the unisolated- one effects the= RCS reduction. The operator places the spray valve controllers in AUTO. The s aray valves open-to reduce system pressure below'the PORV setpoint,- however, . tie malfunctioning PORV fails to reseat. RCS pressure continues to drop rapidly resulting in a low pressure Rx trip and SI. The PRT eventually ruptures relieving to CNMT. The test is terminated-following manual closure of the open PORV's block M0V. I AVAILABLE OPTIONS: PRS-4A PCV-RC 455C PRS-4B PCV RC 4550 PRS-4C PCV-RC-456 OPTION TESTED: PRS-4B / INITIAL CONDITIONS: 10-42 100% PWR, CORE' AGE - BOL LIST OTHER SPECIAL CONDITIONS: Prior to test open block MOV for affected PORV and close the other two block MOV's. Ensure all PZR heaters are energized,- spray valve controllers in manual with ' valves full closed. - FINAL CONDITIONS TEST. DURATION: 1.5-HRS. Rx tripped with Si actuated. The leaking' PORV is -' isolated. The PZR is solid and the PRT ruptured. BASELINE DATA: Malfunction Description 6. 3. 4.11'. 4 - Emergency Operating Procedures E-0, E-1 Alarm Response Procedures:A4-9, A4-10, A4-5, A4-13, A4-25 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A ( EXCEPTIONS TAKEN TO ANS. 3.5: None
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT 5 TEST TITLE: PZR Steam Space' Leak SQT-4.138:- f REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:13/30/90 [ GENERAL DESCRIPTION: PZR pressure and level -(initially) decrease., Automatic i pressure control energizes all heaters in an: attempt to restore pressure. CNMT temperature, pressure, and humidity begin-to increase.- An OTAT rodstop/ - turaine runback is actuated, the Rx subsequently trips on OTAT then SI's on low RCS pressure. PZR level begins to' recover and would eventually 90 solid. ; RCS pressure stabilizes. CNMT radiation levels (indicated) rise slowly due to inherent lag times in the sample collection system. i AVAILABLE OPTIONS: Leak Rate-0-850 gpm j OPTION TESTED: 850 gpm INITIAL CONDITIONS: 1C-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS- TEST DURATION: 1.0 HRS. Rx tripped and SI in progress. . i BASELINE DATA: Malfunction Description 6.3.4.11.5 . l Emergency Operating Procedures E-0, E-1 DEFICIENCIES: None 1 CORRECTIVEACTION/DATE: N/A . EXCEPTIONS TAKEN T0 ANS. 3.5: None
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\. , 1 l BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT j TEST TITLE: PZR Level Transmitter failure' SQT-4'.1394 ; t' i REQUIRED BY ASI/ANS 3.5 SECTION:- 4.2.2- DATE TESTED: 3/30/90: 1 GENERAL DESCRIPTION: Indicated levels pegs high, PZR level: high alarms
- l actuate. Charging flow decreases due to indicated vs programmed level error.
Actual PZR level and pressure decrease, PZR _ heaters energize. , Regen. Hx high7 temp alarms due to minimal charging flow,. letdown isolates, . heaters de energize l when actual PZR level drops below 14% as sensed by the redundant level channel._. i The operator selects the alternate level for control. Charging flowLincreases, PZR level begins to recover.- l AVAILABLE OPTIONS: PRS 6A LT-RC-459 PRS-6B- LT-RC-460 PRS-6C LT-RC-461 Failed Value 0-100% PRS-6D LT-RC-462 OPTION TESTE0: PRS-6A, 100% INITIAL CONDITIONS: 1C-42 100%-PWR, CORE--AGE - BOL-OLISTOTHERSPECIALCONDITIONS:- - Prior to test initiation ensure affected channel is selected--. for " control" and to the_ recorder. (except PRS 6D) FINAL CONDITIONS TEST DURATION: Ll.0 HRS. Rx plant stable at 100% with PZR level recovering, heaters will restore system pressure once -level increases above the . low level cutoff point (14%). ' BASELINE DATA: Malfunction Description 6.3.4.11.6. t DEFICIENCIES: None
-CORRECTIVE ACTION /DATE: N/A-None D).EXCEPTIONSTAKENTOANS.3.5:
~ i Li b BVPS 1 SIMULATOR CERTIFICATION TEST ABSTRACT- ' j TEST TITLE: Pressurizer Ref. Level Signal Failure SQT4/140 0 REQUIRED BY ASI/ANS 3.5.SECTION: 4.2.2' .DATE TESTED:E3/30/89- , i GENERAL DESCRIPTION: When activated, the malfunction cause the PZR Reference-Level Signal to fail to-54%, since actual:_ level-is -lower than this,1the level' control system o) ens FCV-CH 122 and' increases charging flow and pressurizer-level. Alarms siould activate for PZR-Level Deviation and High; Charging. Flow. The operator -takes manual control- to restore level. AVAILABLE OPTIONS: Range of 530'F - 630'F I o OPTION TESTED: 630*F INITIAL CONDITIONS: 10-35 75% PWR; -CORE? AGE-lBOL.
-- ( LIST OTHER SPECIAL CONDITIONS:
None FINAL CONDITIONS TEST DURATION:l .5'HRSL Malfunction ' active, operator has taken manual control of- FCV-CH-122 returning level to-normal . BASELINE DATA: - Malfunction , Description 6.3d.11.7, BVPS Alarm Response Procedure A3-58l DEFICIENCIES: None= CORRECTIVE ACTION /DATE: -N/A a JEXCEPTIONS TAKEN TO ANS 3.5: None
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Pressurize Pressurer Transmitter Failure SQT-4.141 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 7/31/89 GENERAL DESCRIPTION: When activated, the failed transmitter is verified going 1 s to the failed value selected.-_ Proper response of _the system-is verified i.e., spray valves -open, Heaters go off. -.PORV opens l and PRT- conditions 1
-indicate discharge into it._ The operator takes manual control and returns ;
conditions to normal. i AVAILABLE OPTIONS: PRS-8A PT-455 PRS 80 PT-444 i PRS-8B PT-456 PRS 8E PT-445 PRS-8C PT 457- : Range 1700-2500 psig i OPTION TESTED: PRS-8D, 2350 psig INITIAL-CONDITIONS: IC-42 100% PWR. CORE AGE - BOL O\ LIST OTHER SPECIAL CONDITIONS: f Insure PORV-455C in service. FINAL CONDITIONS TEST DURATION:- .5 HRS. Malfunction active, PT-444 indicates 2350 psig, pressure control-in manual and being-restored to normal.- BASELINE DATA: Malfunction Description 6.3.4.11.8 Plant Alarm Response Procedure A4-10 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
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I i BVPS ~ I SIMULATOR CERTIFICATION TEST . ABSTRACT p TEST TITLE: PZR. Spray Valve Failure SQT-4.142 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTE0:11/16/89 GENERAL DESCRIPTION: When the malfunction activates the: spray valve is verified open. RCS pressure decreases until a Low Press Trip causes an- SI. After SI occurs the operator trips the "C" RCP-to verify stopping it will stop. l the pressure decrease. , 1 d AVAILABLE OPTIONS: PRS-9A 455A PRS-98 455B Range 0 100%_ Open - OPTION TESTED: PRS-9B 100% Open INITIAL CONDITIONS: 10-42 .100% PWR, CORE AGE - BOL-O LIST OTHER SPECIAL CONDITIONS:
-None-FINAL CONDITIONS TEST DURATION:- 1 HRS.
The malfunction is active, the failed spray valve is open, the "C" ; RCP is tripped, RCS pressure: decrease has' stopped. BASELINE DATA: Malfunction Description 6.3.4.11.9 E0P E-0 Background Document DEFICIENCIES: -None 4 CORRECTIVE ACTION /DATE: N/A.
. EXCEPTIONS TAKEN TO ANS. 3,5: None
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT l
- TEST TITLE: PZR, Heater Control Failure SQT-4.143 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 7/12/90 GENERAL DESCRIPTION: When the malfunction activated, the PZR. Control Heaters I came on and a slow pressure increase is verified. Pressure will increase until it is limited by the proper opening of the spray valves.
l' AVAILABLE OPTIONS: 0-100% of Full Heater Output > f I OPTION TESTED: 100% , Q INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL V LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1-HRS. Malfunction Active, Heaters on,_ pressure increase limited by spray valves opening. BASELINE DATA: Malfunction Description 6.3.4.11.10 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A r~s (,,), EXCEPTIONS TAKEN TO ANS. 3.5: None i
BVPS~I SIMULATOR CERTIFICATION TEST' ABSTRACT TEST TITLE: PZR Spray Valve Control Failure. 'SQT-4.144 i O REQUIRED BY ASI/ANS 3.5 SECTION: _4.2.2 DATE, TESTED:ll/09/89 - I GENERAL = DESCRIPTION: When. activated, the output of PCV RC-455A is verified:to a increase-to 100%. PZR pressure decreases, heaters come-on,: loop OTAT 1 setpoints decrease. The operator then takes man _ual control. of thecspray valve - and closes it. PZR pressure begins returning to: normal. AVAILABLE OPTIONS: PRS-IIA-455A 0-100% Controller Output PRS-118-455B-OPTION TESTED: PRS 11A, 100% INITIAL CONDITIONS: IC-42 -100% PWR.-- CORE _ AGE _BOL O+ LIST-OTHER SPECIAL CONDITIONS:
-Ensure PCV-RC-455A-is in AUTO.
FINAL CONDITIONS TEST' DURATION: .5 HRS.- Malfunction Active, Controller- in manual,- spray 1 valve elosed,' pressure returning to normal. BASELINE DATA: Malfunction Description 6.3.4.11.12 P1 ant-Alarm Response Procedure A4-12 DEFICIENCIES: None , CORRECTIVEACTION/DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
j BVPS I SIMULATOR CERTIFICATION-TEST ABSTRACT j 1 f TEST TITLE: PZR Master Pressure Control Failure -SQT-4.145
)
REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2- DATETESTED:11/09/89-GENERAL DESCRIPTION: The controller output goes to zero. Heaters'are verified- 1' on, spray valves are verified shut, the PORV operated by this controller stays shut. Pressure increases until the PORV-456 opens to stop the pressure
. increase. (PCV-RC-456 is controlled by another channel).- ]
t i l AVAILABLE OPTIONS: 0-100% of Controller Output l OPTION TESTED: 0% 1 INITIAL CONDITIONS: IC-42 100%'PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .5 HRS. Malfunction Active, Spray Valves closed,-Heaters on, PORV-456 opening as necessary to ' control pressure increase. BASELINE DATA: Malfunction Description 6.3.4.11.12 Plant Alarm Response Procedures A4-12,- A4-9 DEFICIENCIES: None CORRECTIVE ACTION /DATE: 'N/A O EXCEPTIONS TAKEN T0-ANS. 3.5: None _ . - _ - - - . - - - - - - -)
t BVPS I SIMULATOR-CERTIFICATION TEST ABSTRACT.- , TEST TITLE: Pressurizer Level Controller Failure SQT-4.146 l O REQUIREDBYASI/ANS3.5SECTION: 4.2.2 DATE TESTED: 7/12/_90 -! a GENERAL DESCRIPTION: When the malfunction activates it will cause level ! controller output to go high increasing charging ficw. Charging flow -; increases. PZR level increase and-V.C.T.-level decrease are verified. Level will continue to increase until a High PZR Level Rx Trip occurs. l AVAILABLE OPTIONS: 0-100% Controller Output OPTION TESTED: 100% INITIAL CONDITIONS: 10-42 100%'PWR. CORE AGE - BOL. LIST OTHER SPECIAL CONDITIONS: None ' FINAL-CONDITIONS- TEST-DURATION: '1.5 HRS. Malfunction active, Reactor Tripped due_to High PZR Level. BASELINE. DATA: Malfunction Description 6.3.4.11'.13 - Plant Alarm Response Procedures A4-1, A4-2, A4-20, A5-23 DEFICIENCIES: None-CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None /-
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT 1 TEST TITLE: Surgeline Leak SQT-4.147 0g REQUIRED BY ASI/ANS 3.5 SECTION:- 4.2.2 DATE TESTED: 7/30/90: GENERAL DESCRIPTION: The malfunction is activated, the effects on-RCS level- - and pressure-verified. Contal. ment pressure,: temperature and humidity, should increase as' well as radiation. levels. Auto actuations for ESF Systems are verified and operator actions for E 0,- E-1 and thru step 11b of ES-1.2-are done on the simulator prior to completion- of test. -
)
AVAILABLE OPTIONS: Variable Rate 0-3000 gpm - OPTION TESTED: 3,000 gpm-INITIAL CONDITIONS: 10-42 100% PWR. . CORE AGE - BOLJ O LIST OTHER SPECIAL-CONDITIONS: ; None il FINAL CONDITIONS TEST--0URATION:--l 5 HRS. j Malfunction active, RCS pressure - 350 psig, Rx tripped.. SI, CI "A", CI "B', actuated but treset, cooldown commenced per step :11.b of ES-1.2. BASELINE DATA: Malfunction Description-6.3.4.-12;l E0P E-1-Background-Document-DEFICIENCIES: None
. CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None -
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BVPS I SIMULATOR CERTIFICATION TEST: ABSTRACT j i TEST TITLE: Cold Leg Leak SQT-4.148 l O REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:07/30/90~ a GENERAL DESCRIPTION: When the malfunction is activated the approiate drop in' l RCS pressure and Pzr. level are verified. Approlate low press. -and level alarms are verified. Containment press. and temp. are verified-to increase with expected alarms. Proper auto operation of ESF equipment is also verified.- . 1 q i AVAILABLE OPTIONS: RCS-2A Loop A Leak- RCS-2D - Loop A DBA- .
'RCS-2E - Loop B DBA- .'
RCS-2B Loop:B Leak RCS-2C- Loop C Leak. RCS-2F - Loop C DBA ;
~l OPTION TESTED: RCS-2E DBA
- INITIAL CONDITIONS: 1C-42 100% PWR. CORE. AGE - BOL l J LIST OTHER SPECIAL CONDITIONS:
None. l n TEST-DURITION:<2.5 HRS.- FINAL CONDITIONS- + Rx tripped, SI, CIA, CIB, SLI and FWI have taken place 1 RCS'is depressurized with core cooling being done by E.C.C.S. BASELINE' DATA: Malfunction description 6.3.4;12.2-FSAR Accident Analysis DBA LOCA ; OM53.~E0P Background Document.for E-1 l DEFICIENCIES: None. ! CORRECTIVE ACTION /DATE:: -N/A l EXCEPTIONS TAKEN TO ANS. 3.5: None.
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT p TEST TITLE: Steam Generator Tube Leak SQT-4.149 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 1/18/90 GENERAL DESCRIPTION: The malfunction is activated at 100% power to the "A" S/G at a 400 gpm leak rate. Expected indications and alarms are verified. The operator performs the steps of E-0 and E-3 to the point where the primary to secondary leak is stopped. The ability to perform E-0 and E-3 is verified as part of this test. , i l AVAILABLE OPTIONS: RCS-3A "A" S/G RCS-3B "B" S/G Variable Leak Rate .0-1000 gpm RCS-3C "C" S/G OPTION TESTED: RCS-3A, 400 cpm Leak Rate 10-42 100% PWR, CORE AGE - BOL-(') INITIAL CONDITIONS:
'v LIST OTHER SPECIAL CONDITIONS:
None FINAL CONDITIONS TEST DURATION: 2.25 HRS. Rx Tripped, SI in progress, RCS pressure less than Ruptured -S/G, Malfunction active but leak stopped due to operator actions. BASELINE DATA: BVPS Malfunction Description 6.3.4.12.3 E0P Background Document for Tube Rupture (E-3) DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A o
) EXCEPTIONS TAKEN TO ANS. 3.5: None ,
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_ !\ i BVPS 11 SIMULATOR CERTIFICATION TEST ABSTRACT ! TEST TITLE: Reactor Vestel Flange Leak- SQT-4.150 l O REQUIRED BY ASI/ANS 3.5-SECTION: 4.2i2? DATE TESTED:.1/22/90 , GENERAL DESCRIPT10Ni -When the malfunction is activated, the leak is verified by the leak off temp. increase and the: rising level in DG-.TKl.1 Alarm Response' i Procedure A3-96 is. followed to isolate the reak off .line, j. q AVAILABLE OPTIONS: None-0PTION-TESTED: N/A' O INITIAL CONDITIONS: 1C-42 100%-PWR. CORE-AGE-- BOL V - LIST 0THER SPECIAL CONDITIONS: None l FINAL CONDITIONS LTEST< DURATION:- .75~ HRS.- m Malfunction active, leak still in progress,;1eakt offlline:is'olated so
- other line can-be placed in service for theLother seal.
BASELINE DATA: . Malfunction Description 6.3.4.12.4 . , BVPS Alarm Response -Procedure A3-96 DEFICIENCIES:: -None CORRECTIVE ACTION /DATE: N/A-EXCEPTIONS TAKEN TO ANS.-3.5: None-
BVPS I wlMULATOR CERTIFICATION: TEST ABSTRACT: 1 TEST TITLE: Rx Coolant Pump #1 Seal Failure SQT-4.151 O REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE-. TESTED: 1/18/90 i GENERAL DESCRIPTION: After the malfune',on is activated, expected Seal flow-and temperature indications are verified on the control- board and selected ; parameters- are recorded for later review. Operator actions are taken to -1 isolate seal leak off and verify leak off flow decreases.. ! 1 AVAILABLE OPTIONS: RCS-5A . RCPilA- Range 0-50 gpm- , RCS-5B - RCP-1B RCS-5C - RCP-lC < 3 OPTION TESTED: RCS-5A, 50 gpm
-p INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL Os LIST OTHER SPECIAL CONDITIONS:
Initial values of parameters to be checked, need to be recorded prior to-malfunction activation. FINAL CONDITIONS TEST DURATION:: 1 HRS. Malfunction active, seal leak off' flow isolated, Seal . temperatures are high. BASELINE DATA: Malfunction Description 6.3.4.12.5 BVPS Alarm Response Procedures-A3-B7,;A3-79, A3-B6 DEFICIENCIES: None CORRECTIVEACTION/DATE: N/A
-EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Rx Coolant Pump #2 Seal Failure SQT-4.152 O REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 1/22/90 GENERAL DESCRIPTION: After the malfunction is activated, seal leak off flow is verified decreasing. VCT level decrease is verified, and DG-TK1 level is verified increasing. RCP Leak off flow low and RCP Seal Vert Pot level alarm are verified active. Selected parameters are printed out >or transient verification. AVAILABLE OPTIONS: RCS-6A 1A-RCP RCS-6B 18-RCP 0-5 gpm variable rate RCS-6C IC-RCP OPTION TESTED: RCS-6B, 5 gpm INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL 9 LIST OTHER SPECIAL CONDITIONS: None a FINAL CONDITIONS TEST DURATION: .5 HRS. Malfunction active, IB-RCP seal leak off low, VCT level decreasing, DG-TK1 level increasing. BASELINE DATA: Malfunction Description 6.3.4.12.6 BVPS Alarm Response Procedures A3-79, A3-109 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS 1 SIMULATOR CERTIFICATMN TEST ABSTRACT Rx Coolant Pump $3 Seal f ailure TEST TITLE: SQi 4.153 O REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 1/22/90
& 8/31/90 GENERAL DESCRIPTION: When the malfunction is activated, #3 Seal leak off increases. Seal Vent Pot level is verified decreasing. The operator then adds make up water to the vent pot and level is verified increasing.
AVAll ABLE OPTIONS: RCS-7A - 1A RCP RCS 7B - IB RCP RCS 70 IB RCP OPTION TESTED: RCS-78 INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL ! x LIST OTHER SPECIAL CONDITIONS: Open containment isolation valve for PG Make Up prior to opening MOV RC-5228 FINAL CONDITIONS TEST DURATION: .75 MRS. Malfunction active, #3 Seal Leak Off high, Vent Pot level increasing due to operator providing make up. BASELINE DATA: Malfunction Description 5.3.4.12.7 BVPS Alarm Response Procedure A3-111 DEFICIENC1'ES None l CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
,- 1 l BVPS I SIMULATOR rERYlFICATION TEST ABSTRACT 1
i TEST TITLE: Reactor Coolant Pump Trip SQT 4.154 REQUIRED BY AS!/ANS 3.5 SECTION: 4.2.2 DATETESTED:10/24/89 : l ! GENERAL DESCRIPTION: The malfunction trips the pump, breaker I.isition and pump amps are used to verify it tripped. RCS loop flow decrease is verified as well - as affects on loop temperatures and affected steam generator pressure, level
- l and steam flow. Expected alarms are . "ified and selected data points plotted out for analysis.
i I i I i AVAILABLE OPTIONS: RCS 8A 1A RCP l RCS 8B IB RCP , RCS 8C IC RCP , , OPTiW TESTED: RCS-8A INITIAL CONDITIONS: 10 45 25% PWR. CORE AGE BOL O' LIST OTHER SPEclAL CONDITIONS: l Insure power slightly less than 25% and H.F.R.V.'s are in auto. Set up to plot data using Procedure D. j FINAL CONDITIONS TEST DURATION: 2~ HRS. Halfunction active, RCP's l~ Band 10 operating,_1A Pump Tripped, !
"B" and "C" Steam Generators providing much more steam flow than "A" l Steam Generator, l
BASELINE DATA: Mal function- Description 6.3.4.12.8 BVPS Alarm Response Procedure A3-104 DEFICIENCIES: None r- i CORRECTIVE ACTION /DATE:- N/A i L i . EXCEPTIONS TAKEN TO ANS 3.5: None L
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- BVPS
- SIMULATOR CERTIFICATION TEST ABSTRACT l
q TEST TITLE: RCP Locked Rotor Accident SQT 4.155 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:ll/10/89 GENERAL DESCRIPTION: The malfunction to activate the " Locked Rotor" occurs at 100% power. Plant parameters and alarms are noted, expected flows, pressures , and temperatures are monitored against expected results. Test is stopped when ! RCS temperature and pressure are relatively stable. J i AVAILABLE OPTIONS: RCS 9A RCP-1A RCS-9B RCP-1B RCS 9C RCP lC y t . OPTION TESTED: RCS 98 INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL O LIST OTHER SPECIAL CONDITIONS:- Set up to monitor selected parameters using Procedure D. to place data on the tape. FINAL CONDITIONS TEST DURATION: .45 HRS.. 7 Rx Tripped, RCP's lA and 10 operating, plant stable in Mode:3, BASELINE DATA: BVPS Malfunction Description 6.3.4.12.9 FSAR Accident Analysis " Locked Rotor Accident" 1 DEFICIENCIES: RCS Temp / Press, response to accident.too small. i a CORRECTIVE ACTION /DATE: Trouble Report 287 written. TR 287 will be resolved-by December 1992. ()'EXCEPTIONSTAKENTOANS.3.5:None-1
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Rx Coolant Pump Vibration SQT-4.156 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:10/24/89 GENERAL DESCRIPTION: The malfunction is activated. The indication on the meter behind VB *B" is verified correct and the two expected alarms are verified on. AVAILABLE OPTIONS: RCS 10A - RCP 1A RCS 10B RCP-1B Range 0 30 mils RCS 100 - RCP lC OPTION TESTED: RCS 10C, 30 mils INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE BOL O 1.lST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .25 HRS. Malfunction active, alarms present, vibration indicating 30 mils pump left running. BASELINE DATA: Malfunction Description 6.3.4.12.10 BVPS Alarm Response Procedures A3-126, A3127 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPi10NS TAKEN TO ANS 3.5: None
., t BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT 4
i TEST TITLE: RCS Activity High SQT 4.157 l REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:10/24/89 1 GENERAL DESCRIPTION: When the malfunction is activated, an increase in radiation level is verified on RCS-CH-101A and B. Letdown Radiation Monitor, i and the Hi and Hi Hi alarms are verified on, a i 4 AVAILABLE OPTIONS: Selectable activity 10~7 to 10*I uc/gr. . OPTION TESTED: IE-1 uc/gr ! 1 O INITIAL CONDITIONS: 10 42 100% PWR.. CORE AGE - BOL l' L / LIST OTHER SPECIAL CONDITIONS: None i FINAL CONDITIONS TEST DURATION: .25 HRS. H Malfunction active, Letdown Rad Monitors reading high and in Alarm status, Hi and Hi Hi. BASELINE DATA: Malfunction Description 6.3.4.12.11' ! Alarm Response Procedures-A4-71, A4-72 j ! DEFICIENCIES: -None l 1 CORRECTIVEACTION/DATE: N/A O ExCEeriONS 1AxEN 10 ANS. Neee 3.5: !
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l BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Fuel Handling Accident SQT-4.158 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:10/24/89 GENERAL DESCRIPTION: This malfunction simulates the expected alarms and radiation monitor indications that would occur if a Fuel Assembly dropped in the fuel Bldg. The test verified expected alarms, indications and auto actions caused by the simulated radiation level increase in the fuel Bldg. t , AVAILABLE OPTIONS: None i 1 OPTION TESTED: N/A INITIAL CONDITIONS: IC-42 100% PWR, . CORE AGE --BOL-O LIST OTHER SPECIAL CONDITIONS: Main Filter Bank ventilation on Train A-i i FINAL CONDITIONS TEST DURATION: .5 HRS. Malfunction Active, radiation level high on RIS-VS-103A & B other expected indication did not rise as expected. BASELINE DATA: BVPS Malfunction Description 6.3.4.12.12-Abnormal Operating Procedure i DEFICIENCIES: Fuel Bldg. area monitors did not indicate correctly nor-did the Main Filter _ Dampers work correctly.- CORRECTIVE ACTION /DATE: Trouble Report 285 written, TR-285 has been resolved. EXCEPTIONS TAKEN TO ANS.-3.5: None 1
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, i BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT 4 TEST TITLE: Hot Leg N.R. Temperature Sensor Failure 'SQT-4.159 . O REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:08/03/90 GENERAL DESCRIPTION: After the malfunction is actuated, its affect on Thot meter and recorder instrumentation is verified. Affects on OP Delta-T and OT Delta T circuits are also verified. Expected alarms due to this failure are verified. The plant itself should not be affected as this fault will not feed thru to any control system. AVAILABLE OPTIONS: RES-14A 41281 RCS 140 422B2 RCS-148-412B2 RCS-14E-432B1 Variable 520 660F RCS-150-422B1 RCS-14F-43282 OPTION TESTED: RCS 14A, 660F
<-- INITIAL CONDITIONS: 10-18 100% PWR. CORE AGE BOL
( LIST OTHER SPECIAL CONDITIONS: Vse Pack J; select HSSTR-412 to Loop 1 1 1 i FINAL CONDITIONS TEST DURATION: 1 HRS. , Malfunction active, plant steady state at 100%, no effect on plant other than expected alarms, and indication caused by failed detector. BASELINE DATA: Malfunction Description 6.3.4.12.141 Alarm Response Procedure A4-42. r DEFICIENCIES: None , CORRECTIVE ACTION /DATE: N/A None. ()EXCEPTIONSTAKENTOANS.3.5: L
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< BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Hot Leg W.R. Temp. Sensor Failure SQT-4.160 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:08/03/90 GENERAL DESCRIPTION: Wide range Thot provides indication on a Control-Room recorder, an input to the plant computer, and an input to the ICCM. All of these indications failed to 700F, The only annunciator to actuate is the -
Train A ICC Malfunction due to a failed input. . l l I 1 q
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AVAILABLE OPTIONS: RCS ISA Loop A Failed value 0 - 700'F RCS ISB Loop B RCS ISC Loop C OPTION TESTED: RCS-ISA, 700'F INITIAL CONDITIONS: 10-18 100% PWR. CORE AGE - MOL .;
^
, OLISTOTHERSPECIALCONDITIONS: None FINAL CONDITIONS TEST DURATION: 1.0 HRS. Plant stable at 100% t BASELINE DATA: Malfunction Description 6.3.4.12.15 Alarm Response Procedure A3-63 l 5 DEFICIENCIES: None . CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
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- BVPS I S!MULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Cold Leg Narrow Range Temperature Sensor Failure SQT-4.161 l
' O REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTE0:8/03/90 GENERAL DESCRIPTION: When the malfunction is activated, the appropriate indications and alarms are verified; no automation actions or transient are ! caused by this failure. . Loop 1 Tavg and AT should. increase, affects on OP. ! and AT Trips and Runback circuits are checked. ! J I l ! l I AVAILABLE OPTIONS: RCS 16A = Loop 1 RCS-16B = Loop 2 Variable 510'f 630'F ] RCS-160 Loop 3 i OPTION TESTED: RCS 16A, 510'F INITIAL CONDITIONS: -1C-18 100% PWR, CORE AGE - BOL-O LIST OTHER SPECIAL CONDITIONS: ; i
-Select HSS ITR412 to Loop 1 i
, Run this test on Pack J , FINAL CONDITIONS TEST DURATION: .5 HRS. ! Plant stable at'100%, Malfunction active, all alarms and i indication received due to the failure are still'present, j l l i BASELINE DATA: Malfunction Description 6.3.4.12.16 DEFICIENCIES: None-t CORRECTIVE ACTION /DATE: _ N/A i l EXCEPTIONS TAKEN TO ANS. 3.5: .None l a
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j i BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT l i Otos"tt: ce'o tea a 'e ner tere seeser r 4,ere REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 w so'-4 iez DATE TESTED: 8/03/90- . i ! GENERAL DESCRIPTION: The wide range Tcold provides input to the plant [ computer, vertical board recorder, and Cold Leg loop isolation valves' interlock. When the output of the RTD fails high, all-indications go i high and a status light indicates a >5'F deviation from the other j two loops, a j j i ! AVAILABLE OPTIONS: RCS-17A TE-410 Loop A Failed Value 0-700'F ! RCS-178 TE-420 Loop B RCS 17C TE 430 Loop C (
- OPTION TESTED
- RCS 17A, 700'F O INITIAL CONDITIONS: 10 18 ~
100% PWR. CORE AGE - MOL. ! U LIST OTHER SPECIAL CONDITIONS: None j FINAL CONDITIONS TEST DVRATION: .5 HRS. Plant stable at 100%, Malfunction Active, associated alarm present i 1 l 1 l BASELINE DATA: Malfunction Description 6.3.4.12.17 a DEFICIENCIES: None =i
.l LCORRECTIVE ACTION /DATE: . N/A i
EXCEPTIONS TAKEN.T0 ANS. 3.S: None-- 4
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I BVPS I $1MULATOR CERTIFICATION TEST l ABSTRACT TEST TITLE: Hot Leg Pressure Transmitter Failure SQT 4.163 O ,cQUIRED f BY ASI/ANS 3.5 4.2.2 SECTION: DATE TESTED: 4/27/90 - GENERAL DESCRIPTION: MOV-RH 700 and 720A automatically close to isolate thel RHR System due to exceeding the setpoint of 630 psig. One )ressurizer PORV i opens as a result of a direct inaut.from this transmitter w1en the cold OPPS is in service. Various control soard indicators and annunciators are - actuated. The operator attemats. to manually open the RHR isolation valves, which do not respond due to tie failed transmitter.
.j AVAILABLE OPTIONS: RCS 18A PT 403 LoopB) Failed Value.0 3000_ psig RCS-188 PT-402 Loop C)
OPTION TESTED: RCS18B, 3000 psig, O see i
'NITIAL-CONDITIONS: 10 52 0%'PWR. CORE AGE - MOLE LIST OTHER SPECIAL CONDITIONS:
l Plant S/D, RHR in operation. RCS pressure <350 psig . FINAL CONDITIONS TEST DURATION: 1.0 HRS.. Plant S/D with the RHR System isolated and RCS' l pressure decreasing toward PRT pressure due to the
'open'PORV.
i BASELINE DATA: Malfunction Description 6.3.4.12.18 Alarm Response Procedure A4-15 DEFICIENCIES: None - CORRECTIVE ACTION /DATE: N/A > 1 ; O ExCEe110NS 1AxEN3.5: 10 ANS nene i q
l l ) BVPS 1 SIMULATOR CERTIFICATION TEST ABSTRACT-TEST TITLE: Loop Flow Transmitter Failure SQT 4.164-i . DATE TESTED: 4/27/90 j REQUIREDBYASI/ANS3.5SECTION: 4.2.2 I GENERAL DESCRIPTION: 0% flow is indicated on.one transmitter for Loop 'A'. t A loop 'A' low flow alarm is generated. The affected channel's status light , is lit indicating a tripped condition is seen by SSPS but no protective actions are actuated since the 2/3 coincidence is not satisfied. i r i t i t i AVAILABLE OPTIONS: RCS 19A Loop A Selected Transmitter 414,424,434 Final Value 0130% RCS 19B Loop B 415,425,435 ); RCS 19C Loop C 416,426,436 OPTION TESTED: RCS 19A, Ft-414, 0% l i INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL. r LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .5 HRS. Plant stable at 100% with one Loop A flow channel in a tripped condition. ! BASELINE DATA: Malfunction Description 6.3.4.12.19 Alarm Response Procedure- A3-104 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A , c f EXCEPTIONS TAKEN TO ANS. 3.5: None y 1
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Incore Thermocouple failure SQT-4.165 ( REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 7/27/90 GENERAL DESCRIPTION: The thermocouples input to the plant computer systems , for display only. The P250 reads out 700F and outputs an alarm message to the typewriter. SPDS reads 700F. The Train 'A' ICCM indicates 700F for the failed detector as well as a reduced margin to saturation and an increase in the average for the five hottest thermocouples. AVAILABLE OPTIONS: Select failed thermocouple Failed Value 0 700F , OPTION TESTED: A08, 700F 7 INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL (V LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .75 HRS. Plant stable at 100% ! i BASELINE DATA: Malfunction Description 6.3.4.12.20 DEFICIENCIES: None CORRECTIVEACTION/DATE: N/A t ( ()N EXCEPTIONS TAKEN TO ANS. 3.5: None
4 - BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT RCS Boron Concentration SQT-4.166 ( ) TEST TITLE: REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 7/26/90 l GENERAL DESCRIPTION: RCS boron concentration is increases approximate 1 ppm l which adds about 8 pcm of reactivity to the core. Tavg drops as necessary to affect the reactivity added by the boration (magnitude is a function of the moderator temperature coefficient). Pressurizes and VCT boron concentrations slowly increase toward a new equilibrium-value _ Rods do not move due to the j small change in temperature. l i i AVAILABLE OPTIONS: Final Value 0 2000 ppm Ramp Time 0 9999 sec. i { OPTION TESTED: 975 ppm, 60 sec. i INITIAL CONDITIONS: 10 42 100% PWR. . CORE AGE - BOL O LIST OTHER SPECIAL CONDITIONS: None 1 ! FINAL CONDITIONS TEST DURATION: -.5 HRS. Plant stable at 100% with a slightly reduced Tavg and an increased i boron concentration. BASELINE DATA: Malfunction Description 6.3.4.12.21 DEFICIENCIES: -None CORRECTIVE ACTION /DATE: N/A
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()EXCEPTIONSTAKENTOANS.3.5: None 4
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j l BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: RHR Pump Trip SQT 4.167 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 2/22/90 GENERAL DESCRIPTION: RH-P 1A trips on an overcurrent condition as evidenced by a rapid rise than fall to zero on indicated pump amps and breakers tripped indication. A pump AUT0 STOP alarm is actuated.- . Indicate RHR flow drops and the low flow condition is annunciated. - The auto' flow control valve opens . fully in an attempt to maintain setpoint flow. RHR temperatures slowly' 1 decrease due to ambient losses. RCS cooldown ceases. C i g AVAILABLE OPTIONS: RHR 1A RH P 1A 1 RHR 1B RH P 1B OPTION TESTED: RHR-1A INITIAL CONDITIONS: 10-2 0% PWR. CORE AGE - MOLL LIST OTHER SPECIAL CONDITIONS: , Establish a small cooldown rate on RHR
.5 HRS.-
FINAL CONDITIONS . TEST DURATION: 2 RCS heatup in progress. RHR System no_ longer removing decay heat. 4 . BASELINE DATA: Malfunction Description 6.3.4.13.1 4 Alarm Response Procedures Al-126, Al-127 L DEFICIENCIES:. None' 4 4 CORRECTIVE ACTION /DATE: N/A J - (- (_,,T EXCEPTIONS TAKEN TO ANS. 3.5:None , y f i I i
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BVPS 1 SlHULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: RHR Relief Valve Failure SQT-4.168 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 2/22/90 GENERAL DESCRIPTION: RV 721 fails to the full open position which yields a nominal flow rate of 1133 gpm at 600 psig to the PRT. RHR System flow is maintained constant by auto flow con'- 1 valve closing. PRT c, iitions result in level, pressure, and temperaturs ms. RCS pressure and PZR level drop rapidly. VCT level drops as chargir elow increases to maximum. The operator identifies the leak and isolates the'RHR System. RCS conditions stabilize. Pressure and level begin to recover. AVAILABLE OPTIONS: Failed Position 0 100% Ramp Time 0 9000 sec OPTION TESTED: 100%, O sec
~
INITIAL CONDITIONS: IC 2 0% PWR. CORE AGE - MOL (\ LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .5 HRS. l RCS level and pressure increasing. BASELINE DATA: Malfunction Description 6.3.4.13.2 Alarm Response Procedures A4 36, A4-38 i DEFICIENCIES: None l l CORRECTIVE ACTION /0 ATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: RHR Flow Transmitter Failure- SQT-4.169 i REQUIRED BY AS!/ANS 3.5 SECTION:' 4.2.2 DATE TESTED: 2/22/90 GENERAL DESCRIPTION: FT RH 605 inputs to MOV RH 605 auto control circuit. In response to the high failure, MOV RH 605 closes. Closure of RH-605 results in full RHR System flow through the RHR heat exchangers. RHR return temperature decreases. RCS cooldown rate increases. ] l .i i i r t \
- AVAILABLE OPTIONS
- Failed Value 0 8500 gpm Ramp Time 0 9999 sec 4
i
- OPTION TESTEO
- 8500 gpm, O sec INITIAL CONDITIONS: IC-2 0% PWR. CORE AGE MOL' O LIST OTHER SPECIAL- CONDITIONS:
Verify MOV RH 605 IN AUTO prior to Test initiation. t l j- FINAL CONDITIONS TEST DURATION: .5 HRS. RCS cooldown rate excessive. BASELINE DATA: Malfunction Description 6.3.4.13.3 DEFICIENCIES: None
- I i
CORRECTIVE ACTION /DATE: ' N/A 4
-EXCEPTIONS TAKEN TO'ANS. 3.5:- None m
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t. BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: RHR FCV Failure SQI 4.170 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 2/22/90 I GENERAL DESCRIPTION: Since MOV-RH 758 fails as ist no changes in plant parameters occur. When HIC-RH 758 is adjusted to reposition MOV RH-758, the controller output changes but the valve does not respond. RHR and RCS temperatures do not respond to the control manipulation. AVAILABLE OPTIONS: RHR 4A 758 Cooldown valve) RHR 4B 605 Recire, valve) OPTION TESTED: RHR 4A INITIAL CONDITIONS: IC-2 0'4 PWR. CORE AGE - BOL OLISTOTHERSPECIALCONDITIONS: Plant in Mode 5 on RHR decay heat removal prior to malfunction actuation FINAL CONDITIONS TEST DURATION: .25 HRS. Same as initial conditions BASEllHE DATA: Malfunction Description 6.3.4.13.4 Abnormal Operating Procedure 1.10.1 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None 1
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BVPS 1 SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: RHR Pump Shaft failure SQT-4.171 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 2/22/90 GENERAL DESCRIPTION: When RH P 1A shaf t shears, RHR system flow drops rapidly 1 initiating a low flow alarm. MOV-RH 605 automatically modulates full open in an attempt to maintain RH System total flow constant. Due to reduced total system flow, the RCS will start to heatt.p. Decreased RHR heat removal is amplified by the increased amount of flow by passing the heat exchangers through MOV RH 605. AVAILABLE OPTIONS: RHR SA RH P 1A Ramp Time 0 9999 see RHR 5B RH P 1B OPTION TESTED: RHR A, O see INITIAL CONDITIONS: 10-2 0% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: O Pia #t 4n CSo en RHa deca, heat remeve, nr4or to maifunc14en in414at4en. FINAL CONDITIONS TEST DURATION: .25 HRS. RCS temperature increasing DASELINE DATA: Malfunction Description 6.3.4.13.5 Abnormal Operating Procedure 1.10.1 Alarm Response Procedure Al 126 DEFICIENCIES: None , CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
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BVPS I SlMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: RWST Leak -SQT 4.172 REQUIRED BY ASI/ANS 3.5-SECTION: 4.2.2 DATE TESTED: 2/28/90 GENERAL DESCRIPTION: RWST level drops. Annunciators actuated at appropriate setpoints. The malfunction is then cleared, level reduction stops.. The operator initiates RWST refill IAW procedure Q of OM.1.7. Level is observed to be increasing. 1 1 AVAILABLE OPTIONS: Leak Rate 0 1000 gpm Ramp Time 0 9999 sec-OPTION TESTED: 1000 gpm, O sec INITIAL CONDITIONS: 10 42 100% FWR. CORE AGE - BOL OLISTOTHERSPECIALCONDITIONS: None i FINAL CONDITIONS 1EST DURATION: 3.5 HRS. Plant stable, RWST Level increasing. i BASELINE DATA: Malfunction. Description 6.3.4.14.1- . Alarm Response Procedures A619, A6 20, A6-21, A6 ' DEFICIENCIES: None. CORRECTIVE ACTION /DATE: N/A EXCEPTIONS-TAKEN TO ANS. 3.5:- None J
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i BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT i 1 1 ) TI'.ST TITLE: Quench Spray Pump Failure SQT 4.173 { l RI: QUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: L2/28/90 l
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- NERAL DESCRIPTION: Pump amps peg high and the breaker trips open due to the osercurrent condition. Pump amps and discharge pressure drops to zero. The -l QS-P 1A auto stop alarm is received, !
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l i AVAILABLE OPTIONS: SIS 2A QS P 1A - SIS 2B QS-P 1B- -; I ! i OPTION TESTED: SIS 2A l INITIAL CONDITIONS: 10 42 100% PWR. CC'RE AGE - BOL ; O5 LIST OTHER SPECIAL CONDITIONS: QS P-1A is manually started for this test. !
'I FINAL CONDITIONS . TEST DURATION: .33- HRS. . !
Plant remained stable at 100% inroughout test. i BASEL2NE DATA: ifun tion Des ript on 6 3.4 4.2:
-t DEFICIENCIES: - None i
I CORREC11VE ACTION /DATE: N/A f I
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(}EXCEPTIONSTAKENT0ANS.;3.5: 'None
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l BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT l TEST TITLE: Recirc Spray Pump Failure SQT-4.174 i I REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 2/28/90 GENERAL DESCRIPTION: Following a DBA LOCA, a CIB signal starts the RS pumps after a time delay (-210 sec.). Pump current pegs high and the breaker trips open on the overcurrent condition. Pump amps and discharge pressure drop to zero. The RS P 1A auto-stop alarm stops. AVAILABLE OPTIONS: S!S-3A RS-P-1A SIS-3B RS P-1B SIS 3C RS-P-2A SIS 30 RS-P 2B OPTION TESTED: INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL p/ s LIST OTHER SPECIAL CONDITIONS: A DBA LOCA is act Wated to initiate this test. The malfunction is actuated after the RS pump has auto started. FINAL CONDITIONS TEST DURATION: .5 HRS. Rx tripped, LOCA Pnd CIB in progress. BASELINE DATA: Malfunction Description 6.3.4.14.3 Alarm Response Procedure Al-81 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
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- I BVPS I SIMULATOR CERTiflCATION TEST ABSTRACT ;
l TEST TITLE: Recire Spray Hx Tube Leak SQT-4.175 ) O REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 4/16/90 GENERAL DESCRIPTION: Following a DBA LOCA, a CIB signal generated by High Cnmt Pressure causes all four RS pumps to auto start following a time delay (-225 seconds). When the leak occurs, combine river water flow from the heat exchangers increases. The radiation monitor on the IA Hx outlet increases above its alarm setpoint actuating the common HIGH and HI HI Control Room annunciators. AVAILABLE OPTIONS: SIS-4A RS E-1A SIS 40 RS-E 1B SIS-4C RS E-lc Leak Rate 0 500 gpm SlS 4E RS-E-10 Ramp Time 0-9999 sec. OPTION TESTED: SIS 4A, 500 gpm, O sec. INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL
/N LIST OTHER SPECIAL CONDITIONS:
V A RCS DBA LOCA is activated to start the test. CIB is verified to have actuated prior to activating SIS 4 r FINAL CONDITIONS TEST DURATION: .5 HRS. Rx tripped, DBA LOCA in progress, CIB actuated. BASELINE DATA: Malfunction Description 6.3.4.14.4 Alarm Response Procedures A4-71 and A4-72 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
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A 1 BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: High Head SI Pump Failure SQT-4.176 O REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TE3TED: 2/28/90. ! GENERAL DESCRIPTION: The running charging /HHSI pump trips;_the auto stop altrm actuates. With no charging pump cperating, flow and pressure drop. The charging _ flow control valve modulates open in an attempt to increase flow. Low ' discharge flow and pressure annunciators are actuated. PZR level starts decreasing eventually generating a low level ' deviation alarm. A low . seal inj. flow alarm is actuated. -Regenerative Hx outlet temperature-exceeds its alarm setting due to the loss of charging flow with letdown in-service. The operator , manually starts CH P-1B to restore charging- flow and PZR level. _l t e AVAILABLE OPTIONS: SIS-5A CH-P-1A SIS 5B CH-P-1B j $1S-5C CH-P lC OPTION TESTED: SIS-SA INITIAL CONDITIONS: 10 100% PWR. CORE AGE - BOL . [}LISTOTHERSPECIALCONDITIONS: CH P-1A is aligned as the in-service charging pump. FINAL CONDITIONS- TEST DURATION: .61 HRS.- Plant stable at 100 %, all parameters restored- to normal, CH-P'1B - running
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BASELINE DATA: Malfunction Description 6.3.4.14.5 - ! Alarm Response Procedures A3 49, A3-50, A3-58, A4-4,~A3-78,
-A3-ll5 DEFICIENCIES: None q
CORRECTIVE ACTION /DATE: N/A -{ i
-; ~ EXCEPTIONS TAKEN T0 ANS. 3.5: None
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Low Head SI Pump failure SQT 4.177 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 2/28/90 GENERAL DESCRIPTION: SI P-1A trips generating an AUTO STOP alarm. Low head flow indiction for the 1A pump drops to zero. Pump amps drop to zero. AVAILABLE OPTIONS: SIS 6A SI-P-1A SIS 6B SI-P 1B OPTION TESTED: SIS 6A C)
\> INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS:
A DBA LOCA is activated to initiate the test. SI-P-1A is verified to have auto started. FINAL CONDITIONS TEST DURATION: .55 HRS. DBA LOCA in progress with only one train of low head SI flow indicated. BASELINE DATA: Malfunction Description 6.3.4.14.6 DEFICIENCIES: None 1 CORRECTIVE ACTION /DATE: N/A
/~'s EXCEPTIONS TAKEN TO ANS 3.5: None 1
DVPS I SIMULATOR CERTIFICATION TEST ABSTRACT ! TEST TITLE: Containment In-Leakage SQT-4.178 iO j REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 2/28/90
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GENERAL DESCRIPTION: CNMT air in-leakage quickly exceeds the capacity of the . ! running vacuum pump (-55cfm), pressure increase above the partial, pressure ! ! high-high alarm setpoint. The operator starts the second vacuum pump but the ! l combined capacity of both pumps is about 100 X less than the air inleak rate. 't
- CNMT. pressure stabilizes slightly below atmospheric pressure. The malfunction' .,
j is clear and CNMT pressure is observed to be reducing. : i J i a AVAILABLE OPTIONS: Leak Rate 0 1000 SCFM Ramp Time 0 9999 Sec.
- OPTION TESTED
- 1000 SCFM, O Sec. -
ti ! O CONDITIONS: IC-42 100% PWR. CORE AGE - BOL U LIST OTHER SPECI AL CONDITIONS: i CV P.IA running, CV-P-IB off ; 5 FINAL CONDITIONS TEST DURATION: .5 HRS. Plant stable at 100% with CNMT pressure reducing. ; a
- BASELINE DATA: Malfunction Description 6.3.4.14.7 ,
! Alarm Response Procedures Al-35, Al-36,' Al-43, Al 44 . e i ! DEFICIENCIES: N'one - k l > L LORRECTIVE ACTION /DATE: N/A ,
' EXCEPTIONS TAKEN TO _ ANS. 3.5i None.
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Spurious SI Actuation SQT-4.179 O REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED: 4/25/90 GENERAL DESCRIPTION: Upon receipt of a spurious SI signal the Rx trips and both Trains of SI/ CIA equipment actuate. A FWI signal tri)s the MFP's and 1 closes feedwater isolation valves. Feed is supplied via t1e 2 MDAFW pumps which start as a direet result of the SI signal _and the TDAFW pump which starts due to S/G low-low level caused by the-post trip shrink. PZR drops initially as Tavg reduces then starts to incretse due the HHSI flow. Equipment actuation is verified using E09 Attachments. lne operator resets the SI signal after the j malfunction is cleared. Both trains reset as indicated by status lights on i BB-A. AVAILABLE OPTIONS: None OPTION TESTED: N/A INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1.5 HRS. Rx shutdown, all SI/ CIA equipment actuated, PZR level increasing, SI signal manually reset. SI termination criteria is met. i BASELINE DATA: Malfunction Description Emergency Operating Procedures E-0, Attachments lA, 1B & IC DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.S: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Spurious CIA Actuation SQT-4.180 REQUIRED BY ASI/ANS 3.S SECTION: 4.2.2 DATE TESTED:04/2S/90 GENERAL DESCRIPTION: Verified all CIA actuated components responded as expected in accordance with Emergency Operating Procedures Attachment 1 B. All systems' parameters responded as expected due to isolation of various flow , paths and cooling water supply. AVAILABLE OPTIONS: None OPTION TESTED: N/A INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1.0 HRS. l l Plant stable at 100% with the exception of slowly increasing PZR level due to letdown isolation. BASELINE DATA: Malfunction Description 6.3.4.14.9 , Emergency Operating Procedures Attachment 1-B l DEFICIENCIES: None CCRRECTIVE ACTION /DATE: N/A , O EXCEPTIONS TAKEN TO ANS. 3.S: None-l l i c
I BVPS 1 SIMULATOR" CERTIFICATION TEST ABSTRACT O TEST TITLE: Failure of Auto SIS Actuation SQT-4.181 REQUIRED BY-ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:04/25/90 GENERAL DESCRIPTION: Pressurizer pressure drops to the low pressure Rx trip l setpoint followed quickly by a low pressure SI signal being generated. All Train A components are observed to be in their pre-SI position. If a component' was in its SI position initially, it is placed in the opposite position and i verified not to automatically reposition, Additionally Train A CIA components are verified not to have actuated'as Train A CIA is auto actuated by Train A SI. Finally Train' A SI is manually actuated and all SI/ CIA components carified ! to have actuated. 1 AVAILABLE OPTIONS: SIS-10A Train A SIS-10B Train B OPTION TESTED: SIS-10A INITIAL CONDITIONS: 1C-42 100% PWR. CORE AGE - BOL'- LIST OTHER SPECIAL CONDITIONS: MALF PRS-2A, PZR- Safety Valve Failure open is used to initiate the test l FINAL CONDITIONS TEST DURATION: .75 HRS. LOCA through one stuck open PZR safety valve in progress with both-Trains of Si actuated BASELINE DATA: Malfunction Description 6.3.4.14.10 Emergency Operating Procedures Attachments 1-A_and 1-B-DEFICIENCIES: None CORREh JE ACTION /DATE: N/A e-EXCEPTIONS TAKEN TO ANS. 3.5: None
i t BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT'
- i. i TEST TITLE: SI Accumulator Leak SQT-4.182 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:04/24/90 ,
GENERAL DESCRIPTIONt 'SI-TK-1A level is observed to be decreasing and CNMT sump level increasing. Eventually the low level and low pressure alarms are ' received. MALF SIS-IIA is cleared and SI-TK-1A level is observed to remain constant. The operator implements procedure E of OM 1.11.4 to make up to the : t accumulator and level & pressure are observed to be increasing. I sVf?LABLE OPTIONS: SIS-llA SI-TK-1A Leak Rate 0-200 gpm SIS-llB SI-TK-1B SIS-llc SI-TK-1C Ramp 0-9999 sec OPTION TESTED: SIS-llA, 200 gpm, O sec O INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE --BOL LIST 0THE SPECIAL CONDITIONS: None L FINAL CONDITIONS . TEST ~ DURATION: 1.0: HRS., l l SI-TK-1A level .and pressure . increasing BASELINE DATA: : Malfunction Description 6.3.4.14.11 Normal 0perating Procedure OM 1.11.4.E DEFICIENCIES:- None CORRECTIVE-ACTION /DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: ;None 4 o , .. .,,.~w p.r._,, . , . . . . , , . . _ % ,,_,_,,,,,g, , , , , , , , , . . ,_y,p.,g. , _,_m, y. , ,
BVPS-I SIMULATOR CERTIFICATION TEST ABSTRACT
' O TEST TITLE: SI-Signal Fails To Selected Valves - SQT-4.183-REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE-TESTED:04/24/90 ,
GENERAL DESCRIPTION: Each MOV is tested separately and verified not to reposition-in response to a S1 signal. When the malfunction is cleared with-the SI signal still present the MOV is verified to reposition. l
'h AVAILABLE OPTIONS:
SIS 12A MOV-CH-115B STS-12D MOV CH-ll5E i SIS 128 'MOV-CH-ll5C
. SIS-12C MOV-CH-ll5D r
OPTION TESTED: SIS-12A, 128, 12C, 12D INITIAL CONDITIONS: 1C-42 100% PWR. CORE AGE - BOL LIST OTHER.SPECIAL CONDITIONS: l-SI is manually initiated to start test FINAL CONDITIONS TEST DURATION: . 5 HRS.= Rx tripped-and SI in progress BASELINE DATA: Malfunction Description. 6.3.4.14.12 DEFICIENCIES: None l.
- O l-CORRECTIVE ACTION /DATE
- N/A EXCEPTIONS TAKEN TO ANS. 3.5: None
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i BVPS-1 SIMULATOR CERTIFICATION TEST ABSTRACT O TEST TITLE: Safety Injection Line Leak SQT-4.lB4 REQUIRED BY ASI,'ANS 3.5 SECTION: 4.2.2 DATE TESTED:04/24/90 GENERAL DESCRIPTION: A leak develoas down stream of the BIT outlet isolation MOVs. SI flow through.the BIT is osserved to increase and flow to the cold legs (measured downstream of the leak) is observed to decrease. Because the leak is in the Aux. Bldg., the North Sum)-LEVEL-HIGH alarm comes in. The-operator resets Si to allow closure of tie BIT isolation MOVs. -The leak is isolated. The operator then establishes SI flow via the charging system fill-header. AVAILABLE OPTIONS: Leak rate 0 500 gpm OPTION TESTED: 500 gpm INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE --BOL LIST OTHER SPECIAL CONDITIONS: Si is manually initiated and Si flow stabilized prior to activating the leak malfunction. FINAL CONDITIONS TEST DURATION: 1.25 HRS. SI in progress- with HHSI flow- through the Fill- Header : BASELINE DATA: Malfunction Description 6.3.4.14.13 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None
l l l BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT l O TEST TITLE: RWST Level Transmitter Failure SQT-4.185 REQVIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:04/26/90 l GENERAL DESCRIPTION: Low level alarm: actuated by this transmitter is actuated and level indication is observed to read 5%. l i i l AVAILABLL . 0NS: SIS-14A LT-QS-100A SIS-14D LT-QS-100D SIS-148 LT-QS-100B SIS-14C LT-QS-1000 Failed value 0-100% , OPTION TESTED: SIS-148, 5% INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE - BOL l LIST OTHER SPECIAL CONDITIONS: None l FINAL CONDITIONS , TEST DURATION: 1.0 HRS. Plant stable at 100% I BASELINE DATA: Malfunction Description 6.3.4.14.14 i DEFICIENCIES: PCS did not indicate value observed on VB-C CORRECTIVE ACTION /0 ATE: TR# 302 written, TR-302 has been resolved. l EXCEPTIONS TAKEN TO ANS. 3.5: None
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: LHSI Pump Suction Valve Failure SQT-4.186 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:04/26/90 GENERAL DESCRIPTION: Following a DBA LOCA the RWST inventory is pumped to the RCS resulting in reducing RWST level. When RWST reaches.19 feet-in conjunction-with a SI signal, LHSI pump's suctions are automatically aligned to the containment sump and RWST supply MOVS close. At 19 feet -the B LHSI supply from , the RWST isolates but the CNMT sump suction valve fails-to open resulting in - loss of B train LHSI flow and pump cavitation. a AVAILABLE OPTIONS: SIS-ISA MOV SI-860A SIS-150 MOV-SI 8628
-SIS-ISB MOV SI-860B SIS-ISC MOV-SI-862A Failed Position 0 or C (0 pen / Closed)
OPTION TESTED: SIS-ISB,C Closed ! O. INITIAL CONDITIONS: 10-42 100% PWR. CORE-AGE - BOL ' LIST OTHER SPECIAL CONDITIONS: A DBA LOCA is actuated to initiate the test i FINAL CONDITIONS TEST DURATION: 2.0 HRS. RCS, ECCS, and CNMT;in the recirculation mode of-post-LOCA cooling except , for loss of B Train of LHSI flow RASELINE DATA: Malfunction Description 6.3.4.14.15 DEFICIENCIES: B LHSI pump does not indicate cavitation with both suction valves closed. CORRECTIVE ACTION /DATE: CR #136 written. CR-136 to be installed by Dec.1992. - EXCEPTIONS TAKEN TO ANS. 3.5: -None
BVPS'I SIML'LATOR CERTIFICATION TEST ABSTRACT
~- TEST TITLE: Turbine Trip SQT 4.187 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:02/05/90 GENERAL DESCRIPTION: Upon actuation of malf. all TVs,. GVs,- IVs, & RHSVs close ,
isolating steam flow to the turbine. With a turbine trip signal and Rx Power above P9 (49%) an Rx trip signal is generated and the Rx trips. The Rx trip-arms two banks of steam dumps which trip open due to a large Tavg-Tno load mismatch. RCS temperature, pressure, and PZR level respond as expected to the transient. Main FW isolation occurs when Tavg is reduced to 554*F, AFW provides flow to all S/Gs. After a 30 sec TD the generator output breakers and , exciter breaker open resulting in a fast bus transfer of all in-house buses to- , 4 off-site power. As Tavg decreases to Tno-load the steam dumps modulate . closed. The turbine coasts down, various support lube oil pumps start as the. i shaft driven oil pump discharge pressure drops. AVAILABLE OPTIONS: None l OPTION TESTED: N/A i INITIAL CONDITIONS: IC-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: l None 1 FINAL-CONDITIONS TEST DURATION: 1.0 HRS. l Plant stable in Mode 3, Tavg reducing slowly due to maximum AFW flow being supplied to 3 S/Gs- ' BASELINE DATA: Malfunction Description 6.3.4.15.1 < Abnormal Operating- Procedure 1.26.1 DEFICIENCIES: .None ()CORRECTIVEACTION/DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None l
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT O V TEST TITLE: Turbine-Bearing Vibration High SQT-4.188 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:02/05/90 GENERAL DESCRIPTION: Turbine vibration indication increases to selected value over selected ramp for selected bearing.= Vibration of the two adjacent also 1 increases to a lesser degree. When setpoint is reached, the Turbine . . t Supervisory Trouble alarm comes in. The recorders shift to " jump speed", Alert and Danger LEDs light, and the display flashes. AVAILABLE OPTIONS: TUR-3A-1 Bearings 1 9 Vibration Amplitude -15 to +15 mils Ramp Time 0-9999 sec OPTION TESTED: TUR-3A, +15 mils,180 sec O INITIAL CONDITIONS: IC-42 100% PWR, CORE AGE - BOL-LIST OTHER SPECIAL CONDITIONS:
.None FINAL CONDITIONS TEST DURATION:- 1.0 HRS.'
Power stable at 100% BASELINE DATA: Malfunction Description 6.3.4.15.3 Alarm Response Procedure A7-104
. DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A EXCEPTIONS-TAKEN TO ANS. 3.5:. None l
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BVPS I SIMULATOR-CERTIFICATION TEST ABSTRACT TEST TITLE: Governor Valve Failure SQT-4.-189 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:02/05/90-GENERAL DESCRIPTION:. Steam flow through the turbine drops resulting in a load i rejection. Steam dumps are armed by the drop .in impulse pressure and modulate i open due to the Tavg-Tref mismatch. Control rods-insert to restore Tavg to I Tref and dumps modulate-shut. Feed flow and steam _ flow are reduced and the S/G-levels undergo a shrink transient. EHC modulates GV+1 further open due to Pimp dropping but the GV limiter takes control to.stop any further GV opening. AVAILABLE OPTIONS: TVR 4A GV-1 TUR4D GV-4 TUR-4B GV-2 Failed Position 0-100% TUR-4C GV-3 -Ramp Time 0 9999 sec OPTION TESTED: TVR-48, 0%, 5 sec / INITIAL CONDITIONS: 10-42 100%-PWR. -CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Control Rods in auto EHC in IMP in mode L FINAL CONDITIONS TEST DURATION: 1.0 HRS. Rx plant stabilizes at-about 70%. BASELINE DATA: Malfunction Description 6.3,4.15.4 Abnormal Operating Procedure 1.35.1 DEFICIENCIES: None l' L CORRECTIVE ACTION /DATE: N/A l EXCEPTIONS TAKEN TO ANS. 3.5: None.
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT TEST TITLE: Erratic Govenor Valve Control SQT-4.190 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2 2 . DATETESTED:02/05/90 GENERAL DESCRIPTION: The malfunction causes the No.1 Govenor valve to oscillate. Oscillations in steam flow are verified. ReactorLPower-and Tavg cycle. Compensation by No. 4 Govenor Valve-is verified. AVAILABLE-OPil0NS: iUR-5A - Govenor Valve 1 Oscillation Range 0-50% : TUR-5B - Govenor Valve:2 TUR-5C - Govenor Valve 3. Period 1,000-see TUR-5D - Govenor Valve 4 OPTION TESTED: TUR-1A, 10%, 60 sec INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1.4 HRS. Plant at = 70% Power, No.1 Govenor Valve shut but- periodically _ cycling open. BASELINE DATA: Malfunction Description l DEFICIENCIES: None-CORRECTIVE ACTION /DATE: LN/A O EXCEPTIONS TAKEN TO ANS. 3.5: None
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l BVPS l' SIMULATOR CERTIFICATION TEST ABSTRACT O. TEST TITLE: Throttle Valve Failure SQT-4.191' REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE-TESTED:02/06/90-GENERAL DESCRIPTION: Initially failed TV-1 ful_1 open. Verified correct response for turbine speed increase, steam flow increase, Tavg_ decrease, and .Rx power increase. - OPC actuates to prevent turbine overspeed trip. Next overrode OPC on EHC panel and verified turbine trip actuation at appropriate setpoint and appropriate annunciator actuation. -! i AVAILABLE OPTIONS: TVR-6A TV-1 TUR-60 TV-4 TUR-6B TV-2 Variable position 0-100% TVR-6C TV-3 Variable ramp 0 9999.sec OPTION-TESTED: TUR 6A failed to 100% with 0 sec ramp .a INITIAL CONDITIONo: 10 5% PWR. CORE AGE - MOL LIST OTHER SPECIAL CONDITIONS: 4 Manually overrode OPC to verify turbine trip occurs FINAL CONDIT10NS' TEST DURATION: 2 HRS. Turbine trip)ed Rx plant staale in Mode 2 BASELINE DATA: Malfunction Description ~ 6.3.4.15.6 Alarm Response Procedure A7-100,LA7-0B,.A5 Abnormal Operating Procedure A0P 1.26.1 DEFICIENCIES: None
-CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN [0 ANS. 3.5: None l
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT l TEST TITLE: Erratic Throttle Valve Control _ SQT-4.192 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:00 '06/90 l GENERAL DESCRIPTION: TV1 was selected to oscillate 5% over a 5 second period.: The following secondary plant parameters were observed to oscillate in the expected direction:
- 1) steam flows '
2 feed flows 3 S/G' levels . . . l 4 main generator MW output l-AVAILABLE OPTIONS: TUR-7A TV! TUR-70 TV4 TUR-78 TV2 Oscillation range 0-50%- TUR-7C TV3 Oscillation period 0-1000 sec OPTION TESTED: TUR-7A, 5%, 5 sec period INITIAL CONDITIONS: 10-42 100% PWR, CORE AGE - BOL-LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: . 2 HRS. Plant remains critical with' primary and secondary parameters-oscillating, malfunctions still active , BASELINE DATA: Malfunction Description 6.3.4.15.7 DEFICIENCIES: None i-CORRECTIVE ACTION /DATE: N/A h EXCEPTIONS TAKEN TO ANS. 3.5: None
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1 l BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT i O
'UTEST TITLE: EHC Pump Trip .SQT-4.193 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATETESTED:02/06/90 GENERAL DESCRIPTION: LO-M 9A trips on thermal overload resulting in reducing-EH system pressure. LO M 9B auto starts on. reduced system. pressure and subsequently restores EH pressure to normal.
AVAILABLE OPTIONS:: t TUR-8A Pump A Trip (LO-M 9A) TUR-8B Pump B Trip (LO-M 9B) I. OPTION TESTED:
- TUR-8A l.
INITIAL CONDITIONS: 1C 42 100% PWR. CORE AGE:- BOL LIST'0THFR SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .25 HRS. EH system pressure restored to normal 'by operation of the standby EH fluid-
- pump.
BASELINE DATA: Malfunction Description 6.3.4.I5.8 Alarm:Responso Procedure A7-77 , DEFICIENCIES: None-CORRECTIVE ACTION /DATE: N/A' EXCEPTIONS TAKEN TO ANS. 3.5: -None
BVPS I: SIMULATOR CERTIFICATION _ TEST ABSTRACT TEST TITLE: Turbine Bearing-Lube Oil Pump' Failure SQT-4.194 REQUIRED BY ASI/ANS 3.5 SECTION: 4 .' 2 . 2 DATE. TESTED:02/06/90 GENERAL DESCRIPTION: The turbine was manually tripped and LO M-8 was observed -to fail to-automatically start when turbine speed . reduced below 600 rpm. The _ _ malfunction was subsequently cleared and LO-M 8 was observed to auto start. AVAILABLE OPTIONS: Mode 1 - LO-M-8 falls to auto stop when turbine speed > 600 rpm _ Mode 2 - LO-M-8 fails to auto. start when turbine-speed <.600 rpm OPTION TESTED: Mode 1 , O INITIAL CONDITIONS: 10-42 100% PWR. CORE AGE.- BOL LIST OTHER SPECIAL-CONDITIONS: None FINAL CONDITIONS -TEST DURATIONi ll HRS. Malfunction cleared, LO M-8 running-BASELINE DATA: Malfunction Description 6.3.5.15.10 Abnormal Operating Procedure 1.26.2-. Attachment 1.26.1-1, Instruction'_7.C. DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None (-
]
_ - - _ i
BVPS I SIMULATOR CERTIFICATION TEST-ABSTRACT TEST TITLE: EHC Speed Channel Failure SQT-4.195 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:02/08/90-GENERAL DESCRIPTION: Due to the-sensed difference between actual turbine speed , and 1800 rpm reference speed the governor vd ves open resulting in a megawatt increase turbine control shifts to TURB MAN due to > 150: rpm difference between the main and aux speed channels. SPEED CHAN monitor illuminates. The load swing results in a sensed difference between the lmpulse pressure signal and the load reference signal causing the_ LOAD REF CHnN monitor to illuminate. AVAILABLE OPTIONS: Speed valve selectable 0-1800 rpm Ramp time'0-9999 sec OPTION TESTED: 0 rpm, O sec l INITIAL CONDITIONS: 1C-42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: .3 HRS. Turbine /Rx power -stable in TURB MAN mode of EH control BASELINE DATA: Malfunction Description 6.3.4.15.12 OM 1.26.1 DEFICIENCIES: Emergency Power Supply Status light illuminates. CORRECTIVE ACTION /DATE: TR 301 written 9/25/90, TR-301 has .been resolved. EXCEPTIONS TAKEN T0 ANS. 3.5: None I
, , . . , , ~ , . . , , _ _ . , , , , , - , , , , . _
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT OTESTTi1LE: Turbine Runback Failure SQT-4.196 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2,2 DATE TESTED:02/08/90 , , GENERAL DESCRIPTION: With no runback demand, the turbine runs back at a cyclic rate which prevents the steam dumps from arming. The rods move inward in response to increasing Tavg and Turbine /Rx power mismatch. The Turbine-trips due to anti-motoring at a low enough Rx power-to prevent a Turbine trip. Steam. dumps actuate following the Turbine trip. Taking MANUAL _ Turbine control: does s not stop the runback. , 1 i AVAILABLE OPTIONS: 0 - Open circuit (no runback) C - Closed circuit (runback occurs independent of demand) OPTION TESTED: O C INITIAL CONDITIONS: 10 42 100% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: During the cyclic runback, Turbine control-was placed in MANUAL-FINAL CONDITIONS TEST DURATION: .5 HRS. Rx plant critical at HZP. Turbine' tripped. Decay head removal via condenser-steam dumps i BASELINE DATA:. Malfunction Description 6.3 4.15.14 Alarm Response Procedure A4-50, A4-54 L DEFICIENCIES: None 1 CORRECTIVEACTION/DATE: N/A EXCEPTIONS TAKEN TO ANS. 3.5: None I
- - - - - - - - , , + , . . -- , ,. , . , . . . . - , , , , , , - . , . ~ . , , , , , - . -
. .7 i
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT A [ TEST TITLE: Valve Position Limiter Failure SQT-4.197 REQUIRED BY ASI/ANS 3,5 SECTION: 4.2.2 DATETESTED:04/27/9C GENERAL DESCRIPTION:- A normal turbine startup was-commenced using OM 1.52.4.A. When the turbine was latched, governor valves 2 and 3 travelled 75% open and stopped. Valve position limit indication was verified to indicate 50% and would not respond to the position limit lower control. 1 AVAILABLE OPTIONS: Final limiter _ position 0-100%
' 0PTION TESTED: '
INITIAL CONDITIONS: 'IC-14 5% PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: Operator Auto selected Turbine manually latched ; FINAL CONDITIONS TEST DURATION: 1.0 HRS. l GV #2 and #3 stationary at 50% on the valve position limiter, turbine startup terminated, i BASELINE DATA: Malfunction Description 6.3.4.15.15 , DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O-EXCEPTIONS TAKEN T0 ANS. 3.5: None T ~#
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BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT O TEST TITLE: Failure,1st Stage Pressure Signal to EHC SQT-4.198 REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE-TESTED:02/08/90 GENERAL DESCRIPTION: With EHC selected to IMP In Mode the governor valves modulated shut in response to-Pimp failing high. When the deviation between Pimp and-the Load Ref Channel becomes excessive EHC shifts-to TURB MAN and the-LOAD REF CHANNEL monitor light is lit. Operator AUTO can not be reselected. The turbine trips on reverse power due to insufficient steam supply. AVAILABLE OPTIONS: Final valve in psig 0-600 psig Variable ramp 0-9999 sec
-0PTION TESTED:
600 psig, 180 seconds INITIAL CONDITIONS: 10-42 100% PWR. . CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS: None FINAL CONDITIONS TEST DURATION: 1.0 HRS. Turbine trip results in Rx trip Plant in Mode-3 Rx trip controller modulates steam dumps to reduce Tavg to no-load. BASELINE DATA: Malfunction Description 6.3.4.15.16 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None _______- l
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT-TEST TITLE: MSR Steam Supply-Valve Failure SQT-4.199: REQUIRED BY ASI/ANS 3.5 SECTION: 4.2.2 DATE TESTED:02/19/90' l GENERAL DESCRIPTION: FCV-MS 100A fails closed as indicated by BB-C-position i
-indication. Temperature of the reheat steam to the left side of the LP 1 turbines decreases resulting in decreased LP turbine efficiency. Generator MW ! -loading drops due to reduced turbine efficiency. FCV-MS-100A fails-to respond to manual valve-control.
AVAILABLE OPTIONS: TUR 17A FCV MS-100A Failed Position 0-100%1
-TUR 17B FCV-MS 1008 Ramp-time 0-9999 see-OPTION-TESTED: i TUR-17 0% 0 sec ramp INITIAL CONDITIONS: 1C-42 100%'PWR. CORE AGE - BOL LIST OTHER SPECIAL CONDITIONS:
Attempted operation of FCV in MANVAL Mode FINAL CONDITIONS TEST DURATION: .75 HRS. Power stable with a resultant net loss'of approximately 3 MW : BASELINE DATA: Malfunction Description 6.3.4.15.17
-DEFICIENCIES: 'None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None
BVPS I SIMULATOR CERTIFICATION TEST ABSTRACT O TEST TITLE: 1st Stage-Stm Pressure Transmitter Failure SQT-4.200 REQUIRED BY ASI/ANS 3.5 SECTION:- 4.2.2 DATE TESTED:02/19/90 GENERAL DESCRIPTION: PT-446 fails-to 0 as indicated on VB C.= Tref drops to / 547'F resulting in a deviation alarm and a demand signal to steam dumps % (not armed) and rod control. Rods-insert at maximum rate due to Power-and + Tavg/ Tref mismatch. Actual Tavg decreases. Rod motion eventually stops. Outward rod motion is demanded due to low Tavg but-isl blocked by C-6. S/G levels reduce to no load setpoint. Upon selecting- PT-447 for control, rods withdraw and feed reg. valves opea to restore 100% power conditions. AVAILABLE OPTIONS: TUR-18A PT-446 Variable Range 0-600 pisg TUR-18B PT-447 OPTION TESTED: TUR-18A to O psig O INITIAL CONDITIONS: 10-42 -100% PWR, CORE AGE - BOL 1 LIST OTHER SPECIAL CONDITIONS: PT 446 selected.for-control FINAL CONDITIONS TEST DURATIONi .5 HRS. Power stabilized at 100% BASELINE DATA: ' Malfunction Description 6.3.4.15.18 Alarm Response Procedure A4-46, A3-20,: A7-45, A7-53, A7 DEFICIENCIES: None CORRECTIVE ACTION /DATE: N/A O EXCEPTIONS TAKEN TO ANS. 3.5: None 1
i 3,6 Deficiency list and Correction Schedule Of the deficiencies generataed -, change requests - or trouble reports, as a result of the certification hardware - reviews or testing,- None were considered to cause negative training-with the exception of the NIS -Blown Fuse 1and Reactor Coolant , Pump l.ocked Rotor Malfunctions. These malfunctions will not be used in training until satisfactorily cleared. The blown ~ fuse-malfunctions : are being enchanced by- Change Requesta .120,121 and 122. The locked rotor malfunction deficiency is being tracked by Trouble Repot? 287. i The following 'is a list' of th'e Beaver Valley Power Statio'n-Unit 1-simulator change requests generated as a result of-certification testing - or the hardware comparison between : the Unit 1 J control room and the Beaver Valley Power Station-Unit lLsimulator- . f f L l~ V 1 I
e' I l I BVPS U1 SIMULATOR CERT CR*S DATE:11/12/90
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CR- DESCRIPI' ION , si a 1 0077 CONTROL ROOM NOISE-CREBAPS,PORV 0093 BVPS-1 PROCESS COMPUTER-P250 0120 MAL NIS-6 BLOWN FUSE INDICATION LIGHTS-0121 MAL NIS7 BIDWN FUSE INDICATION LIGHTS - 0122 MAL NIS8 BIDWN FUSE INDICATION LIGHTS 0130 DELETE MAL CHS-15 0131 MAL CND-16 0132 MODEL DIESEL DRIVEN FIRE PUMP 0136 LHSI ' PUMP-IDSS OF SUCTION 0141 LDA*S OR HTR VENTS 0143 CItfT WIDE RANGE H2 ANALYZER 0149 SPING CONSOLE 0150 MAIN GENERATOR UPGRADE 0154 CN RECIRC FANS VIBRATION TRIP-
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Chance Reauest Resolution Schedyle -
- 1. CR-0077-Control Room Noise Generation' for CREBAPS and Safety.
Valve Actuation. Completion scheduled by January 1992.
- 2. CR-0093-Beaver Valley Power Station-Unit 1 Process l Computer-P250. Hardware will be installed and operable within 18 months of acceptance in - the Beaver Valley . Power _ Station-Unit I l
control Room,
- 3. CR-0120, 0121, 0122-NIS Blown Fuse Indication. Training will not be conducted on these malfunctions until proper indication is-provided. Completion scheduled for June 1992.
- 4. CR 130, 131. deletion of Malfunctions CHS-15 and CND-16.
Completed.
- 5. CR 0132-Model Diesel Driven Fire Pump. Completion scheduled for -
June 1992.
- 6. CR-0136-Addition of- ~ LHSI Pump Cavitation. on Loss of Suction.
Completion scheduled for- December 1991.
- 7. CR-0141-Install LOA for Reheater Vent Valves. Completed.
- 8. CR 0143-Install Integrated Response Feature: for CNMT Wide Range H2 Analyzer. . Completion scheduled for June 1992.
- 9. CR-0144-Installation of SPING Consol e. - Completion within - 18 months of authorization to p'rocure the console.-
l 10. CR-0150-Install. Upgraded Main Generator Model. ' Completion scheduled for June 1992.
- 11. CR-0154-Install CTMT Recirculation Fans Vibration Trip- Feature.
Investigation will be performed' to determine if parts are , available. If parts are available, expected- completion within 18 nionths of procurement,. if not LOA feature _-will be added -by-December 1991.
The following is a list of Trouble Reports generated as a result of O cert 4ricet4e# test 4#9 cress-rerereeced ex soT ee ser. l l l l O !O
=l i
REPORT DATE: 11/15/90 - STEADY STATE AND NORMAL OPS -
================================== ===_=== ==_==_====______.______;_==_=..
SQT TITLE' - TR 1TR TR - TR TR TR ' CR - NUMBER #1 #2: #3 #4 #5- #
-_..__ -____ .._____.________.._-__ -___.---_-__.. _-____ _____#6- .--..__ _.
2.1.00 100% STEADY STATE DRIFT TEST 195-2.4.01 PLANT S/D'TO MODE 5-_ __ 197. 198' 199 200-2.4.02 P.R. FUNCTIONAL TEST OST 1.2.1 204 2.4.03 I.R. FUNCTIONAL TEST OST 1.2.2 202 2.4'04 SOURCE RANGE FUNCTIONAL TEST .205-2.4.05 PLANT S/U MODE 5 TO 100% - 207 165 141 2.4.11 _CN ISOL OST-1.47.3A :021 -006 -
- 2.4.12 ^ COLD VLV - EXER OST-1.1.10 __ -323 2.4.15 MOTOR AFW PUMP TEST OST1.24.3' 235 -V_____________
O 2.4.16 TURBINE AFW PUMP TEST _OST1.24, 235 N U
REPORT DATE: 11/15/90 TRANSIZNT TESTS
====================.:=======____===========================================
- SQT TITLE TR TR TR TR TR TR CR I\ NUMBER #1 #2 #3 #4 #5 #6 #
3.001 MANUAL RX TRIP 214 218 220 3.002 IDSS OF ALL FW 306 3.004 RCP'S TRIP 252 307 3.006 TURBINE TRIP RODS-MAN 279 3.007 MAX POWER RAMP 308 3.008 DBA LOCA 309 318 319 320
===========================================================================
1 v i l i m
- . _ - . ,y
i i REPORT DATE : 11/15/90. MALFUNCTION TESTS.
============================================================================ j SQT TITLE TR TR TR CR .
#1 #2 #3 .#
Q NUMBER v ____ _ _____ ___________________ ______________________________ ____________ 4.002 STA AIR-COMP. TRIP 244 4.003 INSTR. AIR LEAK 321 4.008 WASTE GAS EFF. HEADER LEAK- 276 4.019 CCW SUCTION HDR LK 278 4.020- CCW 'IO RCP LEAK . 277 l 4.036 VAC PRIMING PMP,BKR 282 4.047 STUCK ROD -280 ! 4.061- CHARGING HEADER LEAK 267 i 4.063 RCP SEAL INJ FCV FAILURE 300 j - 4.065 H2 SUPPLY PRESS REG FAI WRE
. 270 130-4.070 LETDN ISO.VLV FAIL. 221 4.074 UNIT STA TRANS FAIWRE .307 4.076 IDSS OF 4160 VAC BUS 258 4.077 IDSS 480 VAC BUS ~257 i 4.078 IDSS OF 120 VOLT BUS .
281 4.088 VOLT AIAT SETPOINT FAIWRE 284 4.100 AUX FW FCV 210 4.114 T REF 'IO STM DUMP FAILS 142 304 4.131 TCV-CC-215 FAILS -283 4.136 PZR PORV FAI W RE 268 4.155 RCP IDCKED ROIOR 287 4.158 FUEL HANDING ACC. 285-4.185 RWST LEVEL TRANSHI' ITER FAIL 302
.4.188 TURBINE BEARING VIBRATION 288-0 5"4.195 EHC SPEED CHANNEL FAI W RE- 301
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O
. _ . - _ . . . . . . _ _ . . . . _ - _ _ . . _ . _ - , _ _ . ~ . _ . . _ . . . . _ . . _ _ . . - . . . _ _ _ _ _
0 .. Trouble Report Resolution ~ Schedule The following are -Trouble' Reports .that have. been: resolvid ' and y tested, but. have not yet been cleared. In order-to clear- these trouble reports, the changes must be -incorporated into 'the Simulator Design Basis' Documents. The documentation will . be completed .-by-- March -of' 1991. 165, 197, 198,-199, 200, 202,-204, 205, 207, 210,-214, 216, 218, ; 221, 235,;244,-252, 267, 268, 270, 279;_.278,_281~,.282, 285,l300, - j 301,L302. The following Trouble Reports will' be cleared by December 1991 are: 195, 257, 258,;276,. 277, 283,- 284, 286, 304,'307, 308, 318,- 319,- 320, 321, 323. ! 3 Trouble Reports' that - will -be cleared . by December - 1992.- when1:the .) v : . l advance primary system models are incorporated 11nto the_ simulator' are:-
~
280, 287, 306,L309,-324.. -i i i i
'}
l l l i
- 4. ijnister Trouble Reports (TR's) Rrv ;1ution and Chance Recuests (CR's) Generation Th0 procedures for the resolution of Trouble Reports (TR's) and for the modi'ication or upgrade of the simulator, through the use of Change Requests (CR's), can be found in Appendix 4 and 5 respectively.
II
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i O
i l
- 5. Beaver Valley Power Station Unit i Simulator Safety Limit Check Proaram Limit Check Program General Description As required in Section 4.3 of the staiw a software. program has been
) developed to alert the simulator instructor if the simulator is excceding i ! design limits and/or know operating conditions. The program warns the instructor if pre defined conditions occur by comparing variables such as containment pressure to a limit. If any limits are exceeded, a message will appear on the-instructor's CRT and annunciator Al 08 will flash until acknowledged. Functional Descriotion The following conditions are periodically monitored by the subroutine: <l (1) Containment pressure shall rot exceed 45 psig. (2) Pressurizer pressure shall not exceed -2735 psig. (3) Any one thermocouple shall not exceed 12000 F or fall below h 400F. (4) Core cooling must be superheated, all reactor coolants pumps must be off, any one thermocouple must be greater than -7000 F. and RVLIS full ! range level must be less than 39%. (5) RCS cooldown rate > 4000 0 /hr for 5 minutes (CRll3). l Ooerational Reauirements i The program runs once per second. Inputs from other models are needed for this program to serve any purpose, i
- External Interfaces All variables are located - in datapool and messages dirplayed on the
[ instructor's CRT utilize a call to the subrountine CRT0VT. a O : 1-
,_, m__ . . , _ . . _ . . . . _ . , . . . - . . . . _ , _ - . . , . . - . _ , _ . , _ , . , . . . . , . ,. ...s ... , .s . . _ _ .- .
1 I l Referencri ( Status TREE F-0.5, BVPS Status TREE F 0.2, BVPS Techncial Specifications, BVPS Mathematical Description Data Organization Calling Frmat and Arguments IMTCHK is called by the executive every second. All inputs are located in datapool. If a limit is exceeded, a message to the instructor's CRT utilizing the subrountine CRT0VT is displayed. The argument list for CRT0VT is: ; CALL CRTOUT (MESSAGE,80,1) Where: MESSAGE = character
- 80 variable 80 = length of output 1 = color (red, integer byte)
Input Variables Name Descriptio1/ Size / Format PCNM Containment p essure, psia 1 real word in datapool PPRSSU Prt surizer pressure psia 1 real word in datapool TCFMTC Incore thermocouple temperatures, DEG F 51 reel words in datapool Q v
?
TRVLSMTA Core cooling temperature subeoling margin O i re ' ero 40 eet Poe' NRCPIA,B,C Reactor coolant pump status 1 integer byte in datapool (=off,1 on) BRCSNR RVLIS full range level 1 real word in datapool Outout Variables JLIMIT is a datapool variable used to flash annunciator A1.08 when a limit has been exceeded. Normally it has a value of FALSE; otherwise if a 'simit has been exceeded, its value is TRUE. The messages that may be written to the instructor's CRT are: (1) **** LIMIT EXCEEDED - Containment Pressure >= 45 (2) **** LIMIT EXCEEDED - Pressurizer Pressure >=2735 psig (3) **** LIMIT EXCEEDED Any one T/C Temp <= 400 F or >= 1200 0F (4) **** LIMIT EXCEEDED - RCS RXC00L >= 0 RCPS OFF 0 T/C >= 700 F RVLIS >= 39% 0 (5) **** LIMIT EXCEEDED RCS Cooldown >-4000 F/MR for 5 minutes Internal Variables Name De s c ri pt i er./ $ i z e/ Fo rma t/C on t i gu i ty JLMTEXC Limit exceeded flag Logical byte array of 12 in datapool Array elements are parallel to message JLMTMSG Limit message flag logical byte array of 12 in datapool Array elements are parallel to message
1 i l Constants l NAME Dercription/ Size / Format /Value 1 Message color (red) local integer byte 4
- O O
APPENDIX 1 Beaver Valley Power Station Unit i Simulator Training Initial Conditions Core IC Number Agg_, Description 1 Bol 2000 PPM, 145#, 163, Mode 5, Pzr solid 2 Bol 2000 PPM,110#,162, Mode 5, ready to fill Pzr 3 Bol 2000 PPM, 220#, 209, ready to enter Mode 5 4 Bol 2000 PPM, 360#, 34 , ready for PHR 0.M.I.51.4.0 5 Bol 1229 PPM, Rx S/U 3 hours after 100% power trip 3 l (V 6 Bol 1687 PPM, XE free Rx S/V, 100 steps on CBD 7 Bol 1688 PPM, Tur S/U from 10 6, OM 52.4.A Step 1 8 Bol 1686 PPM, Gen S/U from IC-6, OM 52.4.A l 9 Bol 1681 PPM, MFRV transfer from IC-6, OM 52.4.A 10 Bol 1358 PPM, 63% power, power to 100% from 47% 11 Bol 1386 PPM, 47% power, EQ XE 12 Bol 1226 PPM, 100% power, EQ XE l 13 Mol 1299 PPM, XE free reactor S/U, 100 Steps on CBD , 14 Mol 1305 PPM, 10- 10 A from 1C-13. OM 50.4.0 15 Mol 1305 Gen S/V from 10-13, OM 52.4.A 16 Mol 998 PPM, 47% power, EQ XE 17 Mol 863 PPM, 30% power from 100%, XE
,s - 18 Hol 841 PPM, 100% power, EQ XE i \
l 'O
1 F i Core IC Number agg_ Descriotion j 1 19 Mol 997 PPM 63% power from 47, XE 20 Eo1 265 PPM, 75% power, power from 100%, XE e- 21 Eo1 350 PPM, 63% powe., power from 47% XE i 22 Eo1 700 PPM, XE free' reactor S/U tt 90 steps on CBD 23 Loi 230 PPM, reator S/U 14 hours after reactor trip from 100% power 24 25 4 26 Eo1 311 PPM, 90% power, power to 100% from 47% XE 27 Eo1 379 PPM, 47% power EQ XE 28 Eo1 230 PPM,-100% power, EQ XE O 29 30 . o
~O APPENDIX 2 Enclosed within Appendix 2 is a listing of In-Plant Local Operator l Actions. l l O uO
-.a 4 ~-.--- - , ,. ,,sv., , .- -- - - ,
)
I l LOCAL OPERATOR ACTION LISTING 1 l 1 ( (CCR12,15)
)
CCW1 CCR HX-1A INLET AND OUTLET ISOL VLVS (RCCV12) RANGE O TO 1.0 1=OPEN 0= CLOSED CCW2 CCR HX-1B INLET AND OUTLET ISOL VLVS (CCR13,16) (RCCV13) RANGE O TO 1.0 1=OPEN 0= CLOSED CCW3 CCR HX-1C INLET AND OUTLET ISOL VLVS (CCR14,17) (RCCV14) RANGE O TO 1.0 1=OPEN 0= CLOSED CCW4 CCWS RHR HX-1A & P-1A SEAL COOL INLET ISOL VLV (CCR247) (RCCV247) RANGE O TO 1.0 1=OPEN 0= CLOSED CCW6 RHR HX-1B & P-1B SEAL COOL INLET ISOL VLV (CCR248) (RCCV248) RANGE O TO 1.0 1=OPEN 0= CLOSED CCW7 RHR HX-1A OUTLET ISOL VLV (CCR249) (ROCV249) RANGE O TO 1.0 1=OPEN 0= CLOSED CCWB RHR HX-1B OUTLET ISOL VLV (CCR250) (RCCV250) RANGE O TO 1.0 1=OPEN 0= CLOSED CCW9 CCW10 SEAL WATER HX CH-E-1 OUTLET THROT VLV (CCR113) (RCCV113) RANGE O TO 1.0 1=OPEN 0= CLOSED CCW11 FUEL POOL HX-1A & 1B RETURN HDR ISOL VLV (CCR108) (RCCV108) RANGE O TO 1.0 1=OPEN 0= CLOSED CCW12 10" TO 8" CCR SUPPLY HDRS X-CONN (CCR42) (RCCV42) R ANGE O TO 1.0 1=OPEN 0= CLOSED g-) CCW13 8" TO 10" CCR SUPPLY HDRS X-CONN RANGE O TO 1.0 1=OPEN 0= CLOSED (CCR111) (_j (RCCV111) CCW14 CCR SURGE TANK VENT ISOL VLV (CCR37) (RCCV37) RANGE O TO 1.0 1=OPEN 0= CLOSED CCW15 SG BLOWDOWN DRAIN TK HX OUTLET THROT VLV (CCR66) (RCCV66) RANGE O TO 1.0 1=OPEN 0= CLOSED CCW16 24 INCH HEADER THROTTLE VALVE (CCR18) (RCCW18) RANGE O TO 1.0 1=OPEN 0= CLOSED CRF1 MASTER COUNTER (MCRFOC) RANGE O TO 2000 CRF2 P/A CONVERTER DISCONNECT (XINSPAD) RANGE TRUE OR FALSE CRF0 ROD DRIVE MG SET A OUTPUT BREAKER (JCRFMGAO) RANGE T= TRIP F= CLOSED CRF4 ROD DRIVE MG SET B OUTPUT BREAKER (JCRFMGBO) RANGE T= TRIP F= CLOSED CRF5 P/A CONVERTER CONTROL BANK A (MINSCA2) RANGE O TO 228 CRF6 P/A CONVERTER CONTROL BANK B (MINSCB2) RANGE O TO 228 CRF7 P/A CONVERTER CONTROL BANK C (MINSCC2) RANGE O TO 220 CRF8 P/A CONVERTER CONTROL BANK D (MINSCD2) RANGE O TO 228 CRF9 IRPI POWER SUPPLY NORMAL OR ALTERNATE (JCRFALP >. ) RANGE T= ALT. POWER F=NO ALT POWER I~) k/ CND1 CONDENSER WATERBOX A INLET ISOL VLV (CW106A) (NXCW106A) RANGE O TO 2 0=STOP 1=OPEN 2= CLOSED
k i D3 CAL OPERATOR ACTION LISTINO i I CND2 CONDENSER WATERBOX B INLET ISOL VLV (CW106B) (NXCW106B) RANGE O TO 2 0=STOP 1=OPEN 2= CLOSED !
- CND3 CONDENSER WATERBOX C INLET ISOL VLV (CW106C)
(NXCW106C) RANGE O TO 2 0=STOP 1=OPEN 2= CLOSED ' CND4 CONDENSER WATERBOX D INLET ISOL VLV (CW106D) (NXCW106D) RANGE O TO 2 0=STOP 1=OPEN 2= CLOSED CND5 CONDENSER WATERBOX A OUTLET ISOL VLV (CW100A) (NXCW100A) RANGE O TO 2 0=STOP 1=OPEN 2= CLOSED CND6 CONDENSER WATERBOX B OUTLET ISOL VLV (CW100B) (NXCW100B) RANGE O TO 2 0=STOP 1=OPEN 2= CLOSED CND7 CONDENSER WATERBOX C OUTLET ISOL VLV (CW100C) (NXCW100C) RANGE O TO 2- 0=STOP 1=OPEN 2' CLOSED CND8 CONDENSER WATERBOX D OUTLET ISOL VLV (CW1000) (NXCW100D) RANGE O TO 2 0=STOP 3 OPEN 2= CLOSED CND9 CND10 COND PUMP 1A DISCH ISOL VLV (CNS) (RCNV005) RANGE O TO 1.0 1=OPEN 0= CLOSED CND11 COND PUMP 1B DISCH ISOL VLV (CN6) (RCNV006) RANGE O TO 1.0 1=OPEN 0= CLOSED CND12 COND PUMP 1A MINIMUM FLOW LINE (CN40) (RCNV040) RANGE O TO 1.0 1=OPEN 0= CLOSED CND13 COND PUMP 1B MINIMUM FLOW LINE (CN41) (RCNV041) RANGE O TO 1.0 1=OPEN 0= CLOSED CND14 CND15 LP HTR TRAIN A INLET ISOL VLV (CN18) O (RCNV018) CND16 RANGE O TO 1.0 LP HTR TRAIN B INLET ISOL VLV 1=OPEN 0= CLOSED (CN19) (RCNV019) RANGE O TO 1.0 1=OPEN 0= CLOSED CND17 LP HTR TRAIN A OUTLET ISOL VLV (CN20) (RCNV020) RANGE O TO 1.0 1=OPEN 0= CLOSED CND18 LP HTR TRAIN D OUTLET ISOL VLV (CN21) (RCNV021) RANGE O TO 1.0 1=OPEN 0= CLOSED CND19 CND20 COND RECIRC (FCV-CN-101) MANUAL BYPASS VLV (CN64) (RCNV064) RANGE O TO 1.0 1=OPEN 0= CLOSED CND21 COND RECIRC (FCV-CN-101) MANUAL ISOL VLV (CN65)- (RCNV065) RANGE O TO 1.0 .1=OPEN .0= CLOSED CND22 COND RECIRC (FCV-CN-101) FAIL AIR (JCFWF101) RANGE T/F T=CLOSE F= NORM OP CND23 CND24 EXHAUST HOOD SPRAY MANUAL BYPASS VLV (CN48) (RCNV048) RANGE O TO 1.0 1=OPEN 0= CLOSED CND25 CONDENSATE TO AIR EJECTORS BYPASS VLV (CN11) (RCNV011) RANGE O TO 1.0 1=OPEN 0= CLOSED CND26 COND DRAIN TO-CIRC WATER SYSTEM (CN25) (RCNV025) RANGE O TO 1.0 1=OPEN 0= CLOSED CND27 CND28 COND REJECT TO SG BLOWDOWN DEMINS (CN26) O- (RCNV026) RANGE O TO 1.0 1=OPEN 0= CLOSED l l _ , . _ . . _ _ _ - _ - - _ - - ~ _ _ . . _ . . . _ - . , - , _ _ . , _ _ . , . . . _ . . _ _ . _ - , _ _ . , _ , _ , ,
14 CAL OPERATOR ACTION LISTING CND29 COND MAKEUP FROM SG BLOWDOWN DEMINS (WT858) O (RWTV858) AUX 1 RANGE O TO 1.0 CCT HX-3A OUTLET ISOL VLV 1=OPEN 0= CLOSED (CCT10) (RCCTV010) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 2 CCT HX-3B OUTLET ISOL VLV (CCT11) (RCCTV011) RANGE O TO 1.0 1=OPEN 0=CICSED AUX 3 CCT HX-3C OUTLET ISOL VLV (CCT12) (RCCTV012) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 4 CCT MINIMUM FLOW RECIRC VLV (CCT13) (RCCTV013) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 5 AUX 6 RW TO CCR HX-1A ISOL VLV (RW185) (RRW18 5) RANGE O TO 1.0 1=OPEN 0=CLObED AUX 7 RW TO CCR HX-1B ISOL VLV (RW186) (PRWV186) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 8 RW TO CCR HX-1C ISOL VLV (RW187) (RRWV187) RANGE O TO 1.0 1=OPEN 0=CICSED AUX 9 RW SUPPLY HDR X-CONN CCR HX-1A TO CCR HX-1B (RW183) (RRW183 ) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 10 RW SUPPLY HDR X-CONN CCR HX-1B TO CCR HX-1C (RW184) (RRWV184) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 11 RAW WATER TO CCT HX-1A ISOL VLV (RW30) (RRWV030) RANGE O TO O 1=OPEN 0= CLOSED AUX 12 RAW WATER TO CUT HX-1B ISOL VLV (RW31) (RRWV031) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 13 RAW WATER TO CCT HX-1C ISOL VLV (RW32) g (RRWV032) RINGE O TO 1.0 1=OPEN 0= CLOSED AUX 14 RW TO EDG HX-1A SUPPLY FROM A HDR (RW113A) (RRWV113A) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 15 RW TO EDG HX-1A SUPPLY FROM B HDR (RW113B. (RRWV113B) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 16 RW TO EDG HX-1B SUPPLY FROM A HDR (RW113C) (RRWV113C) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 17 RW TO EDG HX-1B SUPPLY FROM B HDR (RW113 D) (RRWV113D) RANGE O TO 1.0 1=OPEN 0=CICSED AUX 18 RW X-CONN TO RAW WATER (RW61) (RRWV061) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 19 RAW WATER X-CONN TO CIRC WATER AT CCT HXS (RW55) (RRWV055) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 20 AUX 21 STA AIR TO CNM AIR X-CONN (SA90) (RCAV90) RANGE O TO 1.0 1=OPEN 0=CI4SE AUX 22 RESET STATION AIR TRIP VLV TV-105 (JCASRSET) RANGE T OR F T=OPEN F= CLOSED AUX 23 DIESEL DRIVEN AIR COMPRESSOR (NSAC1D) RANGE O TO 1 1=ON 0=OFF AUX 24 AUX 25 CN-EJ-1A 2ND STG STM INLET A SET (AS224) (RASSV224) RANGE O TO 1.0 1=OPEN 0= CLOSED h V AUX 26 (RASSV225) RANGE O TO 1.0 CN-EJ-1B 2ND STG STM INLET A SET 1=OPEN 0= CLOSED (AS225) 1
... - _. _ - = _ , _ _ = _ .- ._ .
LOCAL OPERATOR ACTION LISTING AUX 27 CN-EJ-1A 2ND STG STM INLET B SET (AS226) ( (^T (RASSV226) RANGE O TO 1.0 luoPEN 0= CLOSED ! AUX 28 CN-EJ-1B 2ND STG STM INLET B SET (AS227) l (RASSV227) RANGE O TO 1.0 1=OPEN 0= CLOSED l AUX 29 CN-EJ-1A 1ST STG STM INLET A SET (AS228) J (RASSV228) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 30 CN-EJ-1B iST STG STM INLET A SET (AS229) (RASSV229) RANGE 0 TO 1.0 1=OPEN 0= CLOSED AUX 31 CN-EJ-1A IST STG STM INLET B SET (AS230) (RASSV230) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 32 CN-EJ-1B 1ST STG STM INLET B SET (AS231) (RASSV231) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 33 CN-EJ-1A SUCTION VLV FROM COND A SET (AS261) (RASSV261) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 34 CN-EJ-1B SUCTION VLV FROM COND A SET (AS262) (RASSV262) RANGE O TO 1.0 1=OPEN 0= CLOSED Al". 3 5 CN-EJ-1A SUCTION VLV FROM COND B SET (AS263) ASSV263) RANGE O TO 1.0 1=OPEN 0= CLOSED QX36 CN-EJ-1B SUCTION VLV FROM COND D SET (AS264) (RASSV264) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 37 1 AUX 38 HOGGING EJECTOR 2A STM INLET (AS246) (RASSV246) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 39 HOGGING EJECTOR 2B STM INLET (AS247) (RASSV247) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 40 HOGGING EJECTOR 2A SUCTION VLV FROM COND (AS265) () (RASSV265) AUX 41 RANGE O TO 1.0 1=OPEN 0= CLOSED HOGGING EJECTOR 2B SUCTION VLV FROM COND RANGE O TO 1.0 1=OPEN 0= CLOSED (AS266) (RASSV266) AUX 42 UNIT 2 AUX STM X-CONNECT (AS235) (RASSV235) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 43 AUX BOILER START AND STM HDR ISOL VLV (AS61) (RASSV061) RANGE O TO 1.0 1=OPEN 0=C v ED AUX 44 AUX STM TO TURB GLAND (MS42) (RMSV042) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 45 MAIN STM TO AUX STM PCV (AS100) (XASSSTPT) RANGE O TO 150.PSIG AUX 46 AUX 47 CNM EJECTOR SUCTION ISOL VLV (CV151) (RCVH151) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 48 CNM EJECTOR SUCTION ISOL VLV (CV151-1) (RCVH1511) RANGE O TO 1.0 1cOPEN 0= CLOSED AUX 49 CNM VACUUM BKR VS-D-5-6 (RVSD56) RANGE O TO 1.0 1=OFEN 0= CLOSED AUX 50 AUX 51 RWST TO CHG AND HYDRO TST PP ISOL VLV (SI26) (RSI26) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 52 RWST TO LHSI ISOL VLV (SI30) , (RSI30) RANGE O TO 1.0 1=OPEN 0= CLOSED l
/~ AUX 53 RWST COOLER 1A OUTLET ISOL VLV (QS27)
(_)T RANGE O TO 1.0 1=OPEN 0= CLOSED (RCNSV27) 1
LOCAL OPERATOR ACTION LISTING AUX 54 RWST COOLER 1B OUTLET ISOL VLV (QS28) I O (RCNSV28) AUX 55 RANGE O TO 1.0 RWST REFRIGERATION UNIT 1A OUTLET ISOL VLV RANGE O TO 1.0 1=OPEN 0= CLOSED 1=OPEN 0= CLOSED (QS31) (RCNSV31) AUX 56 RWST RECIRC PUMP QS-P-2A 4 (OVSP1A) RANGE O OR 1 0=OFF 1=ON . AUX 57 SIS ACCUM FILL LINE ISOL VLV . (SI41) l (RSI41) RANGE O TO 1.0- 1=OPEN 0=CicSED AUX 58 H2 TO ACCUM ISOL VLV- (SI66) (RSI66) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 59 OUTSIDE RECIRC SPRAY P-2A TO HHSI (QS157) (RCNSV157) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 60 OUTSIDE RECIRC SPRAY P-2B TO HHSI' (QS159) (RCNSV159) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 61 4 AUX 62 CNM HIGH PRF3S/ LOW PRESS DRAINS X-CONN (DV6) (RRDV6) RANGE O TO 1.0 1=OPEN 0= CLOSED-AUX 63 NORTH SUMP TO HIGH LEVEL WASTE (DV139) (RRDV139) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 64 NORTH SUMP TO LOW LEVEL WASTE (DV140) (RRDV140) RANGE 0 TO 1.0 1=OPEN 0= CLOSED AUX 65 VSLO TO DG-TK (DV260) (RRDV260) RANGE O TO 1.0 1=OPEN 0= CLOSED ~ AUX 66 VSLO TO PRT (DV261) (RRDV261) RANGE.O TO 1.C 1=OPEN 0= CLOSED AUX 67 AUX 68 CHARGING PUMP 1A-AUX LO PUMP (NXCHP1A1) RANGE T OP. F AUX 69 CHARGING PUMP 1B' AUX LO PUMP (NXCHP1B1) RANGE T OR F AUX 70 CHARGING PUMP 1C AUX LO PUMP (NXCHP1C1) RANGE T OR F AUX 71 AUX 72 VS-D-4-4A CHARG PP CUBICLE ALT EXHAUST (NXVSD4 4 A)- RANGE 0=CLOSE-1= NEUTRAL 2=OPEN AUX 73- VS-D-4-4B CHARG PP CUBICLE ALT EXHAUST
- (NXVSD44B) RANGE 0=CLOSE 1= NEUTRAL 2=OPEN-AUX 74 VS-D-A-3A CHARG PP CUBICLE NORM EXHAUST (X43ADMP) RANGE 0= NEUTRAL 1*OPEN 2=CIDSE AUX 75. -VS-D-4-3B CHARG PP CUBICLE - NORM EXHAUST-(X43BDMP) RANGE 0= NEUTRAL 1=OPEN 2=CI4SE AUX 76 VS-D-4-11A SAFEGUARDS PIT EXHAUST (X411ADMP) RANGE 0= NEUTRAL 1=OPEN 2=CLOSE AUX 77 ~VS-D-4-11B SAFEGUARDS PIT EXHAUST (X4118DMP) -RANGE 0= NEUTRAL' 1=OPEN 2=CLOSE AUX 78 VS-F-40A CONT RM HVAC RETURN AIR FAN (NXVSF40A) RANGE 0=OFF' 1= MANUAL- .2= AUTO.
AUX 79 VS-F-40B CONT RM HVAC RETURN AIR FAN -
. (NXVSF408) RANGE 0=OFF 1= MANUAL 2, AUTO AUX 80- VS-P-3A CONT RM HVAC COND WTR CIRC PP
, -O- . (NXVS P3 A) .- RANGE 0=OFF 1=MANU?.L 2= AUTO-R
LOCAL OPERATOR ACTION LISTING AUX 81 VS-P *sB CONT RM HVAC COND WTR CIRC PP Q
\_/
(NXVSP3B) AUX 82 MNGE 0=OFF 1= MANUAL VS-F-42 CONT RM TOILET EXHAUST FAN 2= AUTO (NXVSF42) RANGE 0=STOP 1= START AUX 83 VS-AC-11A AUX BLDG AIR HANDLING UNIT (NXVS11A) RANGE 0=STOP 1= NORM 2= START AUX 84 VS-AC-11B AUX BLDG AIR HANDLING UNIT (NXVS11B) RANGE 0=STOP 1= NORM 2= START AUX 85 VS-D-5-3-C CNM PURGE EXHAUST ISOL (RVSD53C) RANGE O TO 1.0 1=OPEN 0= CLOSED . AUX 86 VS-D-5-5-C CNM PURGE SUPPLY ISOL (RVSD55C) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 87 AUX 88 LOW LEVEL WASTE PP-1A & 1B SUCT X-CONN (LW2) (RLWV2) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 89 LOW LEVEL WASTE DISCH TO HIGH LEVEL WASTE TKS(LW104) (RLWV104) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 90 LIQUID WASTE DISCH FILTER INLET ISOL VLV (LW12) (RLWV12) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 91 LIQUID WASTE DISCH FILTER OUTLET ISOL VLV (LW17) (RLWV17) RANGE O TO 1 , 1=OPEN 0= CLOSED AUX 92 LOW LEVEL WASTE P-1A RECIRC TO LW-TK-3A (LW28) (RLWV28) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 93 LOW LEVEL WASTE P-1B RECIRC TO LW-TK-3A (LW29) (RLWV29) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 94 IDW LEVEL WASTE P-1A RECIRC TO LW-TK-3B (LW30) (RLWV30) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 95 LOW LEVEL WASTE P-1B RECIRC TO LW-TK-3B (LW31) (RLWV31) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 96 LW-TK-3A RECIRC ORIFICE BYPASS (LW32) (RLWV32) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 97 LW-TK-3B RECIRC ORIFICE BYPASS (LW33) (RLWV33) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 98 AUX 99 HI LEV WST LW-TK-2A INLET FROM LO LEV WST (LW43) (RLWV43) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 100 HI LEV WST LW-TK-2B INLET FROM LO LEV WST (LW44) (RLWV44) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 101 HIGH LEVEL WASTE PP-2A & 2B SUCT X-CONN (LW46) (RLWV46) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 102 HIGH LEVEL WASTE DISCH TO WASTE EVAP (LW55) (RLWV55) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 103 HIGH LEVEL WASTE P-2A RECIRC TO LW-TK-2A (LW57) (RLWV57) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 104 HIGH LEVEL WASTE P-2B RECIRC TO LW-TK-2A (LW58) (RLWV58) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 105 HIGH LEVEL WASTE P-2A RECIRC TO LW-TK-2B (LW60) (RLWV60) RANGE O TO 1.0 1=OPEN 0=CLOSLD AUX 106 HIGH LEVEL WASTE P-2B RECIRC TO LW-TK-2B (LW61) l (RLWV61) RANGE O TO 1.0 1=OPEN 0= CLOSED l (~N AUX 107 LW-TK-2A RECIRC ORIFICE BYPASS (LW59) l ( (RLWV59) RANGE O TO 1.0 1=OPEN 0= CLOSED l
14 CAL OPERATOR ACTION LISTING AUX 108 LW-TK-2B RECIRC ORIFICE BYPASS (LW62) O, (RLW62) AUX 109 RANGE O TO 1.0 1=OPEN 0= CLOSED HIGH LEVEL WASTE PP-2A,2B DISCH TO LO LEV WST (LW65) (RLW65) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 110 AUX 111 LNDRY & DRAINS LW-TK-6A INLET ISOL VLV (LW74) (RLWV74) RANGE O TO 1.0 liOPEN 0=CI4 SED AUX 112 LNDRY & DRAINS LW-TK-6B INLET ISOL VLV (LW75) (RLWV75) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 113 DRAINS DISCH FILTER INLET ISOL VLV (LW85) (RLWV85) RANGE O TO 1.0 1=OPEN 0=C14 SED AUX 114 DRAINS P-6A RECIRC TO LW-T*-6A (LW97) (RLWV9 '/ ) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 115 DRAINS P-6B RECIRC TO LW-TK-6A (LW98) (RLW98) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 116 DRAINS P-6A RECIRC TO LW-TK-6B (LW99) (RLWV99) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 117 DRAINS P-6B RECIRC TO LW-TK-6B (LW100) (RLWV100) RANGE O TO 1.0 1=OPEN 0=CI4SE D AUX 118 LW-TK-6A RECIRC ORIFICE BYPASS (LW101) (RLWV101) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 119 LW-TK-6B RECIRC ORIFICE BYPASS (LW102) (RLW102) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 120 AUX 121 EVAP TST TKS LW-TK-5A & SB DISCH TO WST EFFL (LW187) O, (RLWV187) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 122 LW-TK-5A RECIRC LINE DEMIN INLET ISOL VLV (LW198) (RLWV198) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 123 LW-TK-5A RECIRC LINE DEMIN OUTLET ISOL VLV (LW205) (RLWV205) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 124 LW-TK-5A RECIRC LINE DEMIN BYPASS (LW190) (RLWV190) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 125 LW-TK-5A RECIRC ORIFICE BYPASS (LW191) (RLWV191) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 126 LW-TK-5B RECIRC LINE DEMIN INLET ISOL VLV (LW197) (RLWV197) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 127 LW-TK-5B RECIRC LINE DEMIN OUTLET ISOL VLV (LW204) (RLWV204) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 128 LW-TK-5B RECIRC LINE DEMIN BYPASS ( LW'.9 4 ) (RLWV194) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 129 LW-TK-5B PECIRC ORIFICE BYPASS (LW195) (RLWV195). RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 1:0 AUX 131 LIQ WST DEMIN LW-I-1 OUTLET TO LW-TK-7A & 7B (LW408) (RLWV408) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 132 SG DRN TKS LW-TK-7A & 7B DISCH TO WST EFFL (LW305) (RLWV305) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 133 LW-TK-7A RECIRC ORIFICE BYPASS (LW391) (RLWV391) RANGE O TO 1.0 1=OPEN 0= CLOSED O b AUX 134 LW-TK-7B RECIRC ORIFICE BYPASS RANGE O TO 1.0 1*DW 0= CLOSED (LW383) (RLWV383) l
INAL OPERATOR ACTION LISTING AUX 135 SG DRAIM TANK P-12A (NLWP12A) RANGE O OR 1 1= START 0=STOP AUX 136 SG DRAIN TANK P-12B (NLWP12B) RANGE O OR 1 1= START 0=STOP AUX 137 AUX 130 LIQUID WASTE EVAP DRAIN TO NORTH SUMP (LW120) (RLWV120) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 139 LIQUID WASTE EVAP BOTTOMS DISCH TO SOL WST (LW108) (RLWV108) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 140 AUX 141 WASTE GAS CHAR BED GW-TK-3A INLET ISOL VLV (GW7) (RGWV007) RANGE O TO 1.0 1=OPEN OoCLOSED AUX 142 WASTE GAS CHAR BED GW-TK-3B OUTLET ISOL VLV (GW8) (RGWV008) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 143 WASTE GAS CHAR BEDS GW-TK-3A & 3B BYPASS VLV (GW9) (RGWV009) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 144 WASTE GAS CHAR BED GW-TK-3C INLET ISOL VLV (GW10) (RGWV010) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 145 WASTE GAS CHAR BED GW-TK-3D OUTLET ISOL VLV (GW11) (RGWV011) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 146 WASTE GIS CHAR BEDS GW-TK-3C & 3D BYPASS VLV (GW12) (RGWV012) RANG') 0 TO 1.0 1=OPEN 0= CLOSED AUX 147 HLA KO POT DRAIN ISOL VLV (GW35) (RGWV035) RAN(E O TO 1.0 1=OPEN 0= CLOSED AUX 148 OUTDOO1 DILUTION AIR DAMPER O (RGWVSD2) AUX 149 RAN3E O TO 1.0 1=OPEN 0= CLOSED WASTE GAS SWEEP GAS BLOWER GW-F-2A (NGWF2A) RA'lGE O OR 1 0=OFF 1=ON AUX 150 WASTE GAS SWEEP GAS BLOWER GW-F-2B (NGWF2B) RANGE O OR 1 0=OFF '4=ON AUX 151 AUX 152 FUEL POOL PURIF P-4A TO FILTER 1A ISOL VLV (FC18) (RSFV18) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 153 FUEL POOL PURIF P-4A TO FILTER 1B ISOL VLV (FC19) (RSFV19) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 154 FUEL POOL PURIF P-4B TO FILTER 1A ISOL VLV (FC20) (RSFV20) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 155 FUEL PPOL PURIP P-4B TO FILTER 1B ISOL VLV (FC21) (RSFV21) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 156 FILTER 1B OUTLET TO FUEL POOL (FC27) (RSPV27) RANGE 0.TO 1.0 1=OPEN 0= CLOSED AUX 157 FILTER 1A OUTLET TO FUEL POOL (FC28) (RSFV28) RANGE O TC 1.0 1=OPEN 0= CLOSED AUX 158 PURIFICATION RETURN LINE TO FUEL POOL ISOL (FC30) (RSFV30) P?.hGE O TO 1.0. 1=OPEN 0= CLOSED AUX 159 FUEL POOL PURIF-P-4A TO ION EXCH ISOL VLV (FC40) (RSFV40) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 160 FUEL POOL PURIP P-4B TO ION EXCH ISOL VLV (FC41) (RSPV41) RANGE O TO 1.0 1=OPEN 0= CLOS ED I~) AUX 161 ION EXCH TO FILTER 1A ISOL VLV (FC44)
-k/ (RSFV44) RANGE O TO 1.0 1=OPEN 0= CLOSED ~ --
LOCAL OPERATOR ACTION LISTING
- AUX 162 ION EXCH TO FILTER 1B ISOL VLV (FC45) l I~3 (RSPV45) RANGE O TO 1.0 1=OPEN 0= CLOSED
> AUX 163 FUEL POOL TO RWST ISOL VLV (FC47)
(RSFV47) RANGE.0 TO 1.0 1=OPEN 0= CLOSED j AUX 164 PG WATER SUPPLY TO FUEL POOL (FC118) i- (RSFV118) RANGE O TO 1.0 1=OPEN- 0= CLOSED AUX 165 AUX 166 H2 RECOMBINER A STATUS (NYRCIA) RANGE O OR 1 0=OFF 1=ON AUX 167 H2 RECOMBINER B STATUS (NYRC1B) RANGE O OR 1 0=OFF 1=ON AUX 168 H2 ANALYZER A STATUS (NHY100A) RANGE O OR 1 0=OFF 1=ON l AUX 169 H2 ANALYZER B STATUS (NHY100B) RANGE O OR 1 0=OFF 1=ON AUX 170 NARROW RANGE H2 ANALYZER A STATUS (NHY101A) RANGE O OR 1 0=OFF 1=ON AUX 171 NARROW RANGE H2 ANALYZER B STATUS (NHY101B) RANGE O OR 1 0=OFF 1=ON AUX 172 AUX 173 RMS FUSE K16 (JRMSK16) RANGE T OR F AUX 174 RMS FUSE K12 (JRMSK12) RANGE T OR F AUX 175 RMS FUSE K33 (JRMSK13) RANGE T OR F AUX 176 AUX 177 AUX RIVER WATER SCREENWASH BOOSTER PUMP- ^ (XWRP10) RANGE O TO 2 0=STOP 1= START 2= AUTO AUX 178 AUX RIVER WATER TRAVELING SCREEN MOTOR (XWRS3) RANGE O TO 2 0=STOP 1= START 2= AUTO AUX 179 AUX 180 CCR SAMPLE VLV . (SS90) (RNSSV090) RANGE O TO 1.0 1=OPEN 0= CLOSED AUX 181 CHILLED WATER SYSTEM FILL PUMP VS-P-6 (OVSP6) RANGE-0 OR 1 0=OFF 1=ON' AUX 182 COOLING TOWER PUMPS SEAL INJ PRESS 1 (PCWS117) RANGE 10 TO 20 PSIA (NORM =14.8) AUX 183 AUX 184 RIVER WATER THROTTLE VALVE RECIRC SPRAY HX (RW200) (RRWV200)- RANGE O TO 1 0= CLOSED 1=OPEN-RHR1 RHR HX-1A INLET ISOL VLV (RH7) (RRHV007) RANGE O TO 1 0= CLOSED 1=OPEN RHR2 RHR HX-1B INLET ISOL VLV (RH8) (RRHV008) RANGE 0-TO 1 0= CLOSED' 1=OPEN-RHR3 RHR HX-1A OUTLET ISOL VLV (RH9) (RRHV009) RANGE O TO 1- 0=CI4S ED 1=OPEN RHR4 RHR HX-1B OUTLET .ISOL VLV (RH10)
\~ (RRHV010) RANGE O TO 1 0= CLOSED 1=OPEN l
. , - - , -, . - - - . - . . _ . - . . , , . . - . - - - . - - . - - . - . - . - . . ~ . - ,
l LOCAL OPERATOR ACTION LISTING RHR5 RHR6 RHR RETURN TO RWST (RH15) (RRHV015) RANGE O TO 1 0= CLOSED 1=OPEN RHR7 RHR8 RHR PUMP DISCH FLOW LOW ALARM SETPOINT (IRHR605) RANGE 1 OR 2 1=3200 GPM 2=7300 GPM PRS 1 PZR SPRAY BYPASS FLOW 140P 1 (PCV-455A) (RC51) (RRCV51) RANGE 0. TO 1.0 0.=CICSED 1.=OPEN PRS 2 PZR SPRAY BYPASS FLOW LOOP 3 (PCV-455B) (RC52) (RRCV52) RANGE 0. TO 1.0 0.= CLOSED 1.=OPEN l PRS 3 l PRS 4 PRT VENT TO CONTAINMENT (RC292) (RRCV292) RANGE O TO 1.0 1=OPEN 0= CLOSED PRS 5 PRT N2 SUPPLY PRESSURE (PPRTPN2) RANGE 0. TO 100. O.5(PSIG)= NORMAL PRS 6 PRS 7 N2 SUPPLY TO PORV ACCUMULATORS (JPRSN2SP) RANGE T OR F T = FILL HEADER F = STOP SUPPLY PRS 8 PRS 9 ACCOUSTIC VALVE MONITORING SYSTEM ALARM RESET (JPRSRSET) RANGE T OR F T = RESET F = NORMAL PRS 10 ACOUSTIC MONITOR POWER SUPPLY Os (JPRSAMPR) RANGE T OR F T= NORMAL F= ALTERNATE PRS 11 ACCUMULATION RATE OF NON-CONDENSABLES IN PZR (LB/HR) (WPRSN2) RANGE 0. TO 1000. O.= NORMAL PRS 12 KNIFE SW ANNUN A407 (PZR PWR RLF VLV N2 SUP LO PRESS) (JPRSA4 07) RANGE T OR F T= CLOSED F=OPEN NIS1 HIGH FLUX AT SHUTDOWN SETPOINT N31 (LOG) (ZNISSRS1) LtNGE O TO 10. NIS2 HIGH FLUX AT SHUTDOWN SETPOINT N32 (LOG) (ZNISSRS2) RANGE O TO 10. MSS 1 SG A BLOWDOWN THROTTLE VALVE (BD101A) (RBDV101A) RANGE O TO 1.0 1=OPEN 0= CLOSED MSS 2 SG B BLOWDOWN THROTTLE VALVE (BD101B) l (RBDV101D) RANGE O TO 1.0 1=OPEN 0=CICSED
- MSS 3 SG C BLOWDOWN THROTTLE VALVE (BD101C) l (RBDV101C) RANGE O TO 1.0 1=OPEN 0= CLOSED l MSS 4 SG BLOWDOWN DISCH TO AUX BLDG NORTH SUMP (BD36) l (RBDV36) RANGE O TO 1.0 1=OPEN 0= CLOSED l MSS 5 SG BLOWDOWN DISCH TO SG DRAIN TANKS (BD56) l (RBDV56) RANGE O TO 1.0 1=OPEN 0= CLOSED
, MSS 6 MSS 7 SG A ATMOS DUMP VLV ISOL VLV (MS23) (RMSV23) RANGE O To-1.0 1=OPEN 0= CLOSED MSS 8 SG B ATMOS DUMP VLV ISOL VLV (MS24) (RMSV24) RANGE O TO 1.0 1=OPEN 0= CLOSED
; MSS 9 SG C ATMOS DUMP VLV ISOL VLV (MS25)
L (RMSV25) RANGE O TO 1.0 1=OPEN 0= CLOSED
_ _._._ _ _ . . . _ . _ _ _ _ _ _ . ___ _. _ .__ ._ ._. . _ _ . . _ . _ _ _ = _ __ _ . _ _ 4 i LOCAL OPERATOR ACTION LISTING ! MSS 10 COND DUMP VLYS TO A COND ISOL VLV (MS1) (RMSV1) RANGE O TO 1.0 1=OPEN 0= CLOSED l (- MSS 11 COND DUMP VLVS TO B COND ISOL VLV (MS2) l (RMSV2) RANGE O TO 1.0 1=OPEN 0= CLOSED i MSS 12 RESIDUAL HEAT RELEASE VLV ISOL VLV (MS26) (RMSV26) RANGE O TO 1.0 1=OPEN 0= CLOSED MSS 13 MSS 14 SG A BLOWDOWN THROTTLE (NEW B14WDOWN) (RSGB102A) RANGE O TO 1.0 1=OPEN 0= CLOSED MSS 15 SG B BLOWDOWN THROTTLE (NEW BLOWDOWN) (RSGB102B) RANGE O TO 1.0 1=OPEN 0= CLOSED MSS 16 SG C BLOWDOWN THROTTLE (NEW BI4WDOWN) (RSGB102C) RANGE O TO 1.0 1=OPEN- 0= CLOSED MSS 17 BD-P1A,B SUCTION ISOL (NEW BLOWDOWN) (RBD281) RANGE O TO 1.0 1=OPEN 0= CLOSED MSSIB BD-P1A,B DISCH ISOL (NEW BLOWDOWN) (RBD291) RANGE O TO 1.0 1=OPEN 0= CLOSED l MSS 19 TV-BD-108A,B TRIP RESET (NEW-BLOWDOWN) T= RESET (JSGB100R) RANGE T OR F EPS1 AUX RIVER WATER PUMP 9A BKR (JBRK1E2) RANGE T OR F 4 EPS2 AUX RIVER WATER PUMP 9B BKR i 4 (JBRK1F2) RANGE T OR F 1 EPS3 RIVER WATER PUMP 1A BKR (JB3K1E10) RANGE T OR F EPS4 RIVER WATER PUMP 1B BKR ( (JBRK1F10) RANGE T OR F EPS5 RIVER WATER PUMP 1C BKR CONNECT (JRWPCONN) RANGE O TO 2 0=DISCON 1=BUSAE 2=BUSDF-EPS6 EPS7 CCR PUMP 1A BKR (JBRK1E4 ) RANGE T OR F EPS8 CCR PUMP 1B BKR (JBRK1F4) RANGE T OR F EPS9 CCR-PUMP 1C BKR CONNECT (JCCPCONN) RANGE O TO 2 0=DISCON 1=BUSAE 2=BUSDF-EPS10 EPS11 CCT PUMP 3A BKR (JBRK1A9) RANGE T OR F , EPS12 COT PUMP 3B BKR > (JBRK1D12) RANGE T OR. F EPS13 . EPS14 HTR DRAIN PUMP 1A BKR RANGE T OR F . I (JBRK1C9) EPS15 HTR DRAIN PUMP 1B BKR (JBRK1D9) RANGE T OR' F EPS16 l [] EPS17 CRDM SHROUD FAN 2A BKR ! v (JBRK8N18) RANGE T OR F [ 9 p e- ,-yy- - r%.---i.r--y.-,,e-, ,,w.-p 3 ,g ,,.,w, - y-~,. . , . , - - - ,.sv,e-- +.w.c. -s,,ge. , s. - . - ar- ---~
- e- w w- .w w wvy-
. . . - - - . - ..- -- . - - _ .. - ~ _ - - - . - . - _.~. - . - . - - ---- --- -- - ..
i
)
i LOCAL OPERATOR ACTION LISTING i EPS10 CRDM SHROUD FAN 2B BKR (JBRK9P19) RANGE T OR F O- EPS19 CRDM SHROUD FAN 2C BKR CONNECT (JVSF2 CON) RANGE O TO 2 0=DISCON 1=BUSAE 2=BUSDF I EPS20 CNM AIR RECIRC FAN 1A BKR (JBRK8N19) RANGE T OR F-
- EPS21 CNM AIR RECIRC FAN 1B BKR l (JBRK9P18) RANGE T OR F EPS22 CNM AIR RECIRC FAN IC BKR CONNECT l (JVSFICON) RANGE O TO 2 0=DISCON 1=BUSAE 2=BUSDF
! EPS23 CNM PURGE EXHAUST FAN BKR l (JBRK4G9) RANGE T OR F EPS24 LEAK COLL EXHAUST FAN 4A BKR
- (JBRK8NS) RANGE T OR F EPS25 LEAK COLL EXHAUST FAN 48 BKR 4
(JBRK9P6) RANGE T- OR F EPS26 PURGE SUPPLY DAMPER VS-D-5-3-A BKR (JINSD53A) RANGE T OR F EPS27 PURGE SUPPLY DAMPER VS-D-5-3-B BKR (JLVSD53 B) RANGE.T OR F 1' EPS28 PURGE EXHAUST DAMPER VS-D-5-5-A BKR. (JLVSD55A) RANGE T OR_F-EPS29 PURGE EXHAUST DAMPER VS-D-5-5-B BKR (JLVSD55B) RANGE T OR F EPS30 CONTROL ROOM AIR COND CONDENSER 4A BKR (JBRKCUAX) RANGE T OR F EPS31 CONTROL ROOM AIR COND CONDENSER 4B BKR O (JBRKCUBX) RANGE T OR F EPS32 CONTROL ROOM AHU SUMP FAN 1A BKR (JBRK8N10) RANGE T OR F , EPS33 CONTROL ROOM AHU SUMi &AN 1B BKR (JBRK9P10)- RANGE T OR F EPS34 EPS35 LHSI PUMP 1A BKR (JBRK1EB) RANGE T OR F EPS36 LHSI PUMP 1B BKR (JBRK1F8) RANGE T OR F EPS37 EPS38 OUTSIDE RECIRC SPRAY PUMP 2A BKR-(JBRK1E13) RANGE T OR F EPS39- OUTSIDE RECIRC SPRAY PITMP 2B BKR (JBRK1F13) RANGE- T. OR_ F EPS40 __INSIDE RECIRC SPRAY PUMP 1A BKR i (JBRK8N3) RANGE T OR F EPS41 INSIDE RECIRC SPRAY PUMP 1B BKR (JBRK9P4 ) RANGE TL OR F EPS42 QUENCH SPRAY PUMP 1A BKR (JBRK8N4) RANGE T OR F . EPS43 QUENCH-SPRAY PUMP 1B BKR (JBRK9PS) -RANGE T OR F-
- EPS44 QUENCH SPRAY CHEM ADD PUMP 4A BKR ;
' O. . (JBRKE5BT) RANGE T OR F i
)
l I
. _ > , . . _,_ _ -_, __._.,_.;__.._,,..,., . _ , _ _ _ _ . , _ , _ . , _ , , , _ _ , _ . , _ l
IDCAL OPERATOR ACTION LISTING EPS45 QUENCH SPRAY CHEM ADD PUMP 4B BKR 4 O (JBRKE6VA) RANGE T OR F EPS46 QUENCH SPRAY CHEM ADD PUMP 4C BKR (JBRKE5BU) RANGE T OR F EPS47 QUENCH SPRAY CHEM ADD PUMP 4D BKR (JBRKE6VB) RANGE T OR F EPS48 EPS49 CHARGING PUMP 1A BKR ) (JBRK1E11) RANGE T OR P i EPS50 CHARGING PUMP 1B BKR ' (JBRK1F11) RANGE - T OR F EPS51- -CHARGING PUMP 1C-BKR CONNECT (JCHPCONN) . RANGE O TO 2 OuDISCON 1=BUSAE 2=BUSDF EPS52 HYDRO TEST PUMP BKR (JBRK1A4) RANGE T OR F EPS53 EPS54 RHR PUMP 1A BKR (JBRK1E3) RANGE T OR F EPS55 RHR PUMP 1B BKR (JBRK1F3) RANGE T OR F EPS56 EPS57 MOV-RH-758 BKR (JLRH758) RANGE T OR F EPS58 MOV-RH-605 BKR ' O (JLRH605) RANGE T OR F EPS59 MOV-CH-142-BKR (JLCH142) RANGE T OR F , EPS60 MOV-RH-700 BKR (JLRH700) RANGE T OR F EPS61 MOV-RH-701 BKR (JLRH701) RANGE T OR F EPS62 MOV-RH-720A BKR (JLRH720A) RANGE T OR F EPS63 MOV-RH-720B BKR (JLRH720B) RANGE T OR F EPS64 EPS65 MOV-FW-151A BKR (JLFW151A) RANGE T- OR F EPS66 MOV-FW-151B BKR (JLFW151B) RANGE T OR F ! EPS67 MOV-FW-151C BKR (JLFW151C) RANGE T OR F EPS68 MOV-FW-151D BKR (JLFW151D) RANGE T OR F EPS69 MOV-FW-151E BKR (JLFW151E) RANGE T .OR F EPS70 MOV-FW-151F BKR (JLFW151F) RANGE T OR F EPS71- MOV-FW-156A BKR-O. (JLFW156A) RANGE T OR F-
g._.___._.__.__..__ . . _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ . _ . . _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . 1 } LOCAL OPERATOR ACTION LISTING l i EPS72 MOV-FW-156B BKR j - (JLFW156B) RANGE T OR F , EPS73 MOV-FW-156C BKR , I (JLFW156C) RANGE T OR F r EPS74 l EPS75 MOV-SI-860A BKR , (JLSIB 60A) RANGE.T OR F EPS76 MOV-SI-860B BKR-(JISIB 60B) RANGE T OR F J EPS77 MOV-SI-862A BKR. ( l' (JLSI862A) RANGE T OR F EPS78 MOV-SI-662B BKR (JLSIS62B) RANGE T OR F EPS79 MOV-SI-863A BKR (JLSI863A) RANGE T OR F EPS80 MOV-SI-863B BKR (JLSI863B) RANGE T OR F EPS81 MOV-FI-867A BKR (JLSI867A) RANGE T OR F j EPS82 MOV-SI-867B BKR (JLSI867B) - RANGE T OR F a EPS83 MOV-SI-867C BKR 1 (JLSIB670) RANCE T OR F EPS84 MOV-SI-867D BKR i (JLSIB 67D) RANGE T OR F EPS85 MOV-SI-890C BKR l i O (JLSIB 90C) RANGE T OR F EPC86 MOV-SI-885A BKR
-(JLDIB 85A) RANGE T ~OR F EPS87 MOV-SI-885B BKR (JLSIC85B) RANGE -T OR F
- EPS88 MOV-SI-885C BKR l (JLSIBBSC) RANGE T OR F l
EPS89 MOV-SI-885D BKR (JLSI885D) RANGE T OR F EPS90 EPS91 MOV-CH-115B BKR (JLCH115B) -RANGE T - ~ OR F EPS92 MOV-CH-115D BKR (JLCH1150) RANGE T OR F EPS93 EPS94 MOV-RC-557A BKR-(JLRC557A) RANGE T OR -F EPS95 MOV-RC-557B BKR (JLRC557 B) RANGE T OR F EPS96 MOV-RC-557C BKR
-(JLRC557C) RANGE T OR F .
EPS97 O EPS98 (KRCS590)
.MOV-RC-590 BKR RANGE T OR F- T= POWER ON F= POWER OFF
LOCAL OPERATOR ACTION LISTING EPS99 MOV-RC-592 BKR O (KRCS592) EPS100 RANGE T OR F MOV-RC-594 BKR RANGE T OR
- T= POWER ON T= POWER ON F= POWER OFF F= POWER OFF (KRCS594)
EPS101 MOV-RC-591 B.as (KRCS591) RANGE T OR F T= POWER ON F= POWER OFF EPS102 MOV-RC-593 BKR (KRCS593) RANGE T OR F T= POWER ON F= POWER OFF EPS %3 MOV-RC-595 BKR (KRJ8595) RANGE T OR F T= POWER ON F= POWER OFF EPS10) EPS105 PZR B/U HTR GROUP 2A (JBRK8N12) RANGE T OR F
- EPS106 PZR B/U HTR GROUP 2B (JBRK9 P12) RANGE T OR F EPS107 PZR B/U HTR GROUP 2D (JBRK8N13) RANGE T OR F EPS108 PZR B/U HTR GROUP 2E (JBRK9P13) RANGE T OR F EPS109 PZR CONTROL HTR GROUP 2C (JBRK1B7) RANGE T OR F EPS110 EPS111 4160V BUS 1A TO 480V BUS 1J (ACD-A2)
(LBKA2) RANGL T OR F T= CLOSED F=OPEN EPS112 4160V BUS 1A TO 480V BUS 1A & 1E (ACB-A3) O.
. (LBKA3)
EPS113 RANGE T OR F T= CLOSED 4160V BUS 1B TO 480V BUS 1C & 1G F=OPEN (ACB-83) (LBKB3) RANGE T OR F T= CLOSED F=OPEN EPS114 4160V BUS 1C TO 480V BUS 1K (ACB-C2) (LBKC2) RANGE T OR F T= CLOSED F=OPEN EPS115 4160V BUS 1C TO 480V BUS 1B & 1F (ACB-C3) (LBKC3) RANGE T OR F T= CLOSED F=OPEN EPS116 4160V BUS 1D TO 480V BUS 1D & 1H (ACB-D3) (LBKD3) RANGE T OR F T= CLOSED F=OPEN EPS117 EPS110 480V BUS 1A FEEDER (ACB-1A1) (LBK1A1) RANGE T OR F T= CLOSED F=OPEN EPS119 480V BUS 1B FEEDER (ACB-1B1) (LBK1B1) RANGE T OR F T= CLOSED F=OPEN EPS120 480V BUS 1A TO 1B X-TIE (ACB-1A10) (LBK1A10) RANGE T OR F T= CLOSED F=OPEN EPS121 480V BUS 1C FEEDER (ACB-2C1) (LBK2C1) RANGE T OR F T= CLOSED F=OPEN EPS122 480V BUS 1D FEEDER (ACB 201) (LPK2D1) RANGE T OR F T= CLOSED F=OPEN EPS123 480V BUS 1C TO 1D X-TIE (ACB-2C10) (LBK2C10) RANGE T OR F T= CLOSED F=OPEN EPS124 480V BUS 1E FEEDER (ACB-3E1) l (LBK3E1) RANGE T OR F T= CLOSED ?=OPEN ! EPS125= 480V BUS 1F FEEDER (ACB-3F1) k (LBK3F1) RANGE T OR F T= CLOSED _F=OPEN
LOCAL OPERATOR ACTION LISTING EPS126 480V BUS 1E TO 1F X-TIE (ACB-3E10) O (LBK3E10) EPS127 RANGE T OR F 480V BUS 1G FEEDER RANGE T OR F T= CLOSED T= CLOSED F=OPEN F=OPEN (ACB-4G1) (LBK4G1) EPS128 480V BUS 1H FEEDER (ACB-4H1) (LBK4H1) RANGE T OR F T= CLOSED F=OPEN EPS129 480V BUS 1G TO 1H X-TIE (ACB-4G10) (LBK4G10) RANGE T OR F T= CLOSED F=OPEN EPS130 480V BUS 1J FEEDER (ACB-5J1) (LBK5J1) RANGE T OR F T= CLOSED F=OPEN EPS131 480V BUS 1K FEEDER (ACB-5K1) (LBKSK1) RANGE T OR F T= CLOSED F=OPEN EPS132 480V BUS IJ TO 1K X-TIE (ACB-5J9) (LBK5J9) RANGE T OR F T= CLOSED F=OPEN EPS133 EPS134 4160V BUS 1AE TO 480V BUS IN & IN1 (ACB-E12) (LBKE12) RANGE T OR F T= CLOSED F=OPEN EPS135 4160V BUS 1DF TO 480V BUS IP & 1P1 (ACB-F12) (LBKF12) RANGE T OR F T= CLOSED F=OPEN EPS136 EPS137 480V BUS IN FEEDER (ACB-8N1) (LBK8N1) RANGE T OR F T= CLOSED F=OPEN EPS136 480V BUS 1N1 PEEDER (ACB-8N16) (LBK8N16) RANGE T OR F T= CLOSED F=OPEN , EPS139 480V BUS 1P FEEDER (ACB-9P1) O (LBK9P1) EPS140 RANGE T OR F 480V BUS 1P1 FEEDER T= CLOSED F=OPEN (ACB-9P16) (LBK9P16) RANGE T OR F T= CLOSED F=OPEN EPS141 EPS142 480V BUS 1A TO MCC1-1 (ACB-1A3) (LMCC1A3) RANGE T OR F T= CLOSED F=OPEN EPS143 480V BUS 1A TO MCC1-3 (ACB-1A6) (LMCC1A6) RANGE T OR F T= CLOSED F=OPEN EPS144 480V BUS 1A TO MCC1-21 (ACB-1A8) (LMCC1A8) RANGE T OR F T= CLOSED F=OPEN EPS145 480V BUS 1B TO MCC1-2 (ACB-1B6) (LMCC1B6) RANGE T OR F T= CLOSED F=OPEN EPS146 480V BUS 1B TO MCC1-4 (ACB-1BS) (LMCC1BS) RANGE T OR F T= CLOSED F=OPEN EPS147 480V BUS 1B TO MCC1-20 (ACB-183) (LMCC1B3) RANGE T OR F T= CLOSED FrOPEN EPS148 480V BUS 1C TO MCC1-5 (ACB-2C3) (LMCC2C3) RANGE T OR F T= CLOSED F=OPEN EPS149 480V BUS 1C TO MCC1-7 (ACB-2C4) (LMCO2C4) RANGE T OR F T= CLOSED F=OPEN EPS150 480V BUS 1C TO MCC1-29 (ACB-2C2) (LMCC2C2) RANGE T OR F T= CLOSED F=OPEN EPS151 480V BUS 1D TO MCC1-6 (ACB-2D6) (LMCC2D6) RANGE T OR F T= CLOSED F=OPEN 480V BUS 1D TO MCC1-8 O EPS152 (LMCC2D5) RANGE T OR F T= CLOSED F=OPEN (ACB-2DS) l
LOCAL OPERATOR ACTION LISTING EPS153 480V BUS 1E TO McCl-9 (ACB-3E3) (' (LMCC3E3) RANGE T OR F T= CLOSED F=OPEN EPS154 480V BUS 1E TO MCC1-11 (ACB-3E4) (LMCC3E4) RANGE T OR F T= CLOSED F=OPEN EPS155 480V BUS 1E TO MCC1-19 (ACB-3E7) (LMCC3E7) RANGE T OR F T= CLOSED F=OPEN EPS156 480V BUS 1F TO McCl-10 (ACB-3F6) (LMCC3F6) RANGE T OR F T= CLOSED F=OPEN EPS157 480V BUS 1F TO MCC1-12 (ACB-3FS) (LMCC3FS) RANGE T OR F T= CLOSED F=OPEN EPS158 480V BUS 1F TO MCC1-18 (ACB-3F3) (LMCC3F3) RANGE T OR F T= CLOSED F=OPEN EPS159 480V BUS 1F TO MCC1-28 (ACB-3F9) (LMCC3F9) RANGE T OR F T= CLOSED F=OPEN EPS160 480V BUS 1G TO MCC1-13 (ACB-4G3) (LMCC4G3) RANGE T OR F T= CLOSED F=OPEN EPS161 480V BUS 1G TO MCC1-15 (ACB-4G4) (LMCC4G4) RANGE T OR F T= CLOSED F=OPEN EPS162 4L9V BUS 1G TO McCl-17 (ACB-4GB) (LMCC4G8) RANGE T OR F T= CLOSED F=OPEN EPS163 48CV BUS 1H TO McCl-14 (ACB-4H7) (LMCC4H7) RnNGE T OR F T= CLOSED F=OPEN EPS164 480V BUS 1H TO MCC1-16 (ACB-4H6) (LMCC4H6) RANGE T OR F T= CLOSED F=OPEN EPS165 480V BUS 1J TO McCl-23 (ACB-5J5) (LMCC5J5) RANGE T OR F T= CLOSED F=OFEN EPS166 400V BUS IJ TO MCC1-25 (ACB-5J4) g (LMCC5J4) AANGE T OR F T= CLOSED F=OPEN EPS167 480V BUS 1K TO MCC1-22 (ACB-5K5) (LMCCSK5) RANGE T OR F T= CLOSED F=OPEN EPS168 480V BUS 1K TO MCC1-24 (ACB-5K4) (LMCCSK4) RANGE T PR F T= CLOSED F=OPEN EPS169 EPS170 480V BUS IN TO MCCE-1 (ACB-8N7) (LMCC8N7) RANGE T OR F T= CLOSED F=OPEN EPS171 480V BUS IN TO MCCE-3 (ACB-8N8) (LMCC8N8) RANGE T OR F T= CLOSED F=OPEN EPS172 480V BUS IN TO MCCE-5 (ACB-8N6) (LMCCBN6) RANGE T OR F TaCLOSED F=OPEN EPS173 480V BUS IN TO MCCE-7 (ACB-8N14) (LMCC8N14) RANGE T OR F T= CLOSED F=OPEN EPS174 480V BUS IN TO MCCE-9 (ACB-8N11) (LMCC8N11) RANGE T OR F T= CLOSED F=OPEN EPS175 480V BUS IN TO MCCE-13 (ACB-8N15) (LMCC8N15) RANGE T OR F T= CLOSED F=OPEN EPS176 480V BUS IN1 TO MCCE-11 (ACB-8N22) (LMCCBN22) RANGE T OR F T= CLOSED F=OPEN EPS177 480V BUS 1P TO MCCE-2 (ACB-9PB) (LMCC9P8) RANGE T OR F T= CLOSED F=OPEN EPS178 480V BUS 1P TO MCCE-4 (ACB-9P9) (LMCC9P9) RANGE T OR F T= CLOSED F=OPEN O) g
\/
EPS179 480V BUS 1P TO MCCE-6 (ACB-9P14) (LMCC9P14) RANGE T OR F T= CLOSED F=OPEN l
- _. .- . . - . - - - - . ~ . _ - .- . ..- . ._ - - . . - . _ - - .-
LOCAL OPERATOR ACTION LISTING EPS180 480V BUS 1P TO MCCE-8 (ACB-9P7) i (LMCC9P7) RANGE T OR F T= CLOSED F=OPEN EPS181 480V BUS 1P TO MCCE-10 (ACB-9P11) (LMCC9P11) RANGE T OR F T= CLOSED F=OPEN EPS182 480V BUS 1P To MCCE-14 (ACB-9P15) (LMCC9P15) RAGE T OR F T= CLOSED F=OPEN EPS183 480V BUS 1P1 TO MCCE-12 (ACB-9P21) (LMCC9P21) RANGE T OR F- T= CLOSED F=OPEN EPS184 EPS185 VITAL BUS 1 SUPPLY (INVERTER OR MCCE-13)
- (LBKVBil) RANGE T OR F T= INVERT F=E-13
! EPS186 VITAL BUS 2 SUPPLY (INVERTER OR MCCE-14) (LBKVB 2) RANGE T OR F T= INVERT F=E-14 EPS187 VITAL BUS 3 SUPPLY (INVERTER OR MCCE-13) i i (LBKVBt3) RANGE T OR F T= INVERT F=E-13 EPS188 VITAL BUS 4 SUPPLY (INVERTER OR MCCE-14)
; (LBKVBt4) RANGE T OR F T= INVERT F=E-14 EPS189 EPS190 DC DIST PNL 1 SUPPLY (NORM OR ALTERNATE)
(IEPSDCP1) RANGE T OR F T= BUS 5 FaBUS 1A EPS191 DC DIST PNL 4 SUPPLY (NORM OR ALTERNATE) (IEPSDCP4) RANGE T OR F T= BUS 5 F= BUS 2A EPS192 DC DIST PNL 5 SUPPLY (NORM OR ALTERNATE) (IEPSDCPS) RANGE T OR F T= BUS 5 F= BUS 1A
~
EPS193 EPS194 DC CONTROL POWER 4KV BUS 1A (NORM OR ALT) (IEPSDCXA) RANGE T OR F T= BUS 5 F= BUS 1A EPS195 DC CONTROL POWER 4KV BUS 1B (NORM OR ALT) (IEPSDCXB) RANGE T OR F T= BUS 5 F= BUS 1A EPS196 DC CONTROL POWER 4KV BUS 1C (NORM OR ALT) (IEPSDCXC) RANGE T OR F T= BUS 5 F= BUS 2A EPS197 DC CONTROL POWER 4KV BUS 1D (NORM OR ALT) (IEPSDCXD) RANGE T OR F .T= BUS 5 F= BUS 2A EPS198 DC CONT PWR 480V BUS 1A & 1B (NORM OR ALT)- (IEPSDCX1) RANGE T OR F T= BUS 5 F= BUS 1A EPS199 DC CONT PWR 480V BUS 1C & 10 (NORM OR ALT) (IEPSDCX2) RANGE T OR F T= BUS 5 .F= BUS 1A EPS200 DC CONT PWR 480V BUS 1E & 1F (NORM OR ALT) (IEPSDCX3) RANGE T OR F T= BUS 5 F= BUS 1A EPS201 DC CONT PWR 480V BUS 1G & 1H (NORM OR ALT) (IEPSDCX4) RANGE T OR F T= BUS 5 F= BUS 1A EPS202 DC CONT PWR 480V-BUS 1J & 1K (NORM OR ALT) (IEPSDCX5) RANGE T OR F T= BUS S F= BUS 2A EPS203 EPS204 ELEC SYS PROT TRIP RESET (GEN, EPS, EDG)
-(JGENRST) RANGE T OR F T = RESET F = NORMAL EPS205 l
EPS206. 480V BKR ACB-1A1 AFTERCLOSE O- (LBK1A1AC) RANGE.T OR F T= CLOSED F=OPEN
LOCAL OPERATOR ACTION LISTING EPS207 480V BKR ACB-1B1 AFTERCLOSE (LBK1B1AC) RANGE T OR F T= CLOSED F=OPEN O- EPS208 480V BKR ACB-2C1 AFTERCLOSE (LBK2CIAC) RANGE T OR F T= CLOSED F=OPEN EPS209 480V BKR ACB-2D1 AFTERCLOSE (LBK2D1AC) RANGE T OR F T= CLOSED F=OPEN EPS210 480V BKR ACB-3E1 AFTERCLOSE (LBK3E1AC) RANGE T OR F T= CLOSED F=OPEN EPS211 480V BKR ACB-3F1 AFTERCLOSE (LBK3F1AC) RANGE T OR F T= CLOSED F=OPEN EPS212 480V BKR ACB-4G1 AFTERCLOSE (LBK4G1AC) RANGE T OR F T= CLOSED F=OPEN EPS213 480V BKR ACB-4H1 AFTERCLOSE (LBK4H1AC) RANGE T OR F T=C..OSED F=OPEN EPS214 480V BKR ACB-5J1 AFTERCLOSE (LBK5J1AC) RANGE T OR F T= CLOSED F=OPEN EPS215 480V BKR ACB-5K1 AFTERCLOSE (LBK5K1AC) RANGE T OR F T= CLOSED F=OPEN EPS216 I EPS217 BLACK DIESEL STATUS l (JEPSBLDG) RANGE T OR F T=ONLINE F=OFFLINE EPS218 EPS219 BATTERY #1 TO BUS 1 (LBAT1:1) RANGE T OR F T=C LOSED F=OPEN gg EPS220 BATTERY #2 TO BUS 2 l (_j (LBAT1:2) RANGE T OR F T= CLOSED F=OPEN EPS221 BATTERY #3 TO BUS 3 (LBAT1:3) RANGE T OR F T= CLOSED F=OPEN EPS222 BATTERY #4 TO BUS 4 (LBAT1:4) RANGE T OR F T= CLOSED F=OPEN EPS223 BATTERY #5 TO BUS 5 (LBAT1:5) RANGE T OR F T= CLOSED F=OPEN EPS224 EPS225 4160 41A BKR FAST BUS XFR RELAY SWITCH (JEPS41A) RANGE T OR F T= CLOSED F=OPEN EPS226 4160 141A BKR FAST BUS XFR RELAY SWITCH (JEPS141A) RANGE T OR F T= CLOSED F=OPEN EPS227 4160 241B BKR FAST BUS XFR RELAY SWITCH (JEPS241B) RANGE T OR F T= CLOSED F=OPEN EPS228 4160 341B BKR FAST BUS XFR RELAY SWITCH (JEPS341B) RANGE T OR F T= CLOSED F=OPEN EPS229 4160 41C BKR FAST BUS XFR RELAY SWITCH (JEPS41C) RANGE T OR F T= CLOSED F=OPEN EPS230 4160 141C BKR FAST BUS XFR RELAY SWITCH (JEPS141C) RANGE T OR F T= CLOSED F=OPEN EPS231 4160 241D BKR FAST BUS XFR RELAY SWITCH (JEPS241D) RANGE T OR F T= CLOSED F=OPEN EPS232 4160 341D BKR FAST BUS XFR RELAY SWITCH (JEPS341D) RANGE T OR F T= CLOSED F=OPEN EPS233 t (]) l
, _ . - - - - - - . - . _ _ . - . . . - . _ ~ . - . - - ~ . - . . - . - - LOCAL OPERATOR ACTION LISTING EPS234 BATTERY CHARGER #1 AC INPUT BREAKER O (JEPSCHG1) EPS235 RANGE T OR F BATTERY CHARGER 42 AC INPUT BREAKER T= CLOSED F=OPEN (JEPSCHG2) RANGE T OR F T= CLOSED F=OPEN EPS236 BATTERY CHARGER #3 AC INPUT BREAKER (JEPSCHG3) RANGE T OR F T= CLOSED F=OPEN , EPS237 BATTERY CHARGER #4 AC INPUT BREAKER l (JEPSCHG4) RANGE T OR F T= CLOSED F=OPEN EPS238 BATTERY CHARGER #5 AC INPUT BREAKER l (JEPSCHGS) RANGE T OR F T= CLOSED F=OPEN EPS239 EPS240 MOV-SI-865A LINE STARTER (JLSI865A) RANGE T OR F EPS241 MOV-SI-865B LINE STARTER (JLSI8653) RANGE T OR F EPS242 MOV-SI-865C LINE STARTER (JLSIB65C) RANGE T OR F EPS243 EPS244 MOV-FW-150A LINE STARTER (JLFW150A) RANGE T OR F EPS245 MOV-FW-150B LINE STARTER (JLFW150B) RANGE T OR F FWM1 FW HTR 1A EXTRACTION STM ISOL VLV (ES2) (RESV002) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM2 FW HTR 1B EXTRACTION STM ISOL VLV (ES3) O (RESV003) FWM3 RANGE O TO 1.0 FW HTR 2A EXTRACTION STM ISOL VLV 1=OPEN 0= CLOSED (ES21) (RESV021) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM4 FW HTR 2B EXTRACTION STM ISOL VLV (ES22) (RESV022) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM5 FW HTR 3A EXTRACTION STM ISOL VLV (ES40) (RESV040) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM6 FW HTR 3B EXTRACTION STM ISOL VLV (ES41) (RESV041) RANGE O TO 1.0 1=OPEN 0= CLOSED' FWM7 FW HTR 4A EXTRACTION STM ISOL VLV- (ES67) (RESV067) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM8 FW HTR 4B EXTRACTION STM ISOL-VLN (ES68) (RESV068) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM9 FW HTR SA EXTRACTION STM-ISOL VLV (ES97) (RESV097) RANGE 0 TO 1.0 1=OPEN 0= CLOSED FWM10 FW HTR SA EXTRACTION. STM ISOL VLV ( E199 )_ (RESV099). RANGE O TO 1.0 1=OPEN- 0= CLOSED FWM11 FW HTR SB EXTRACTION STM ISOL VLV (ES98) (RESV098) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM12 FW HTR SB EXTRACTION- STM ISOL VLV (ES100) (RESV100) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM13 FWM14 LP HTR TRAIN A INLETEISOL VLV (CN18) !
' (RHDV018) RANGE O TO 1.0 1=OPEN 0= CLOSED l
FWM15 .LP HTR TRAIN B INLET-ISOL VLV (CN19) L- (RHDV019) RANGE O TO 1.0= 1=OPEN- 0= CLOSED _ -
LOCAL OPERATOR AC" ION LISTING FWM16 LP HTR TRAIN A OUTLET ISOL VLV (CN20) (RHDV020) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM17 LP HTR TRAIN B OUTLET ISOL VLV (CH21) (RHDV021) RANGE O TO 1.0 1=OPEN 0= CLOSED , FWM18 FWM19 FW HTR 1A INLET ISOL VLV (FW11) (RFWV011) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM20 FW HTR 1B INLET :. SOL VLV (FW12) (RFWV012) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM21 FW HTR 1A OUTLET ISOL VLV (FW17) (RFWV017) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM22 FW HTR 1B OUTLET ISOL VLV (FW18) (RFWV018) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM23 FW HTR 1A BYPASS VLV (FW15) (RFWV015) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM24 FW HTR 1B BYPASS VLV (FW16) (RFWV016) RANGE O TO 1.0 1=OPEN 0= CLOSED , FWM25 % FWM26 MAIN FW P-1A RECIRC ISOL VLV (FW19) (RFWV019) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM27 MAIN FW P-1B RECIRC ISOL VLV (FW20) (RFWV020) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM28 MAIN FW P-1A LO PUMP SWITCH + RANGE T OR F (NXLOP3AM) (N FWM29 MAIN FW P-1B LO PUMP SWITCH () (NXLOP3BM) FWM30 RANGE T OR F FWM31 MGv-FW-150A BYPASS VLV (FW214) (RFWV214) RAFJE O TO 1.0 1=OPEN 0= CLOSED FWM32 MOV-FW-150B BYPASS VLV (FW215) (RFWV215) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM33 FWM34 STM SUPPLY TO FW-P-2 FROM SG A (MS15) (RAFV015) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM35 STM SUPPLY TO FW-P-2 FROM SG B (MS16) j (RAFV016) RANGE O TO 1.0 1=0?EN 0= CLOSED f FWM36 STM SUPPLY TO FW-P-2 FROM SG C (MS17) (RAFV017) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM37 FWM38 FW-P-3A B HDR DISCH ISOL VLV (FW40) s (RAFV040) RANGE O TO 1.0 1=OPEN 0=CTOSED FWM39 FW-P-3A A HDR DISCH ISOL VLV (FW37) (RAFV037) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM40 FW-P-3B A HDR DISCH ISOL VLV (FW38) (RAFV038) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM41 FW-P-3B B HDR DISCH ISOL VLV (FW41) (RAFV041) RANGE O TO 1.0 1=OPEN 0-CLOJED [] V FWM42 FW-P-2 A HDR DIGCH ISOL VLV (FK36) (RAFV036) RANGE O TO 1.0 1=OPEN 0= CLOSED 5 l l
LOCAL OPERATOR ACTION LISTING 1"WM43 FW-P-2 B HDR DISCH ISOL VLV (FW39) IO
\/ (RAFV039) RANGE O TO 1.0 1=OPEN 0=CIhSED FWM44 FWM45 AUX FEED TO SG A CNM ISOL VLV (FW158A)
(RAFV158A) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM46 AUX FEED TO SG - B CNM ISOL VLV (FW158B) (RAFV W:P) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM4" AUX FEED TO SG C CNM ISOL VLV (FW158C) (RAFV158C) RANGE O TO 1.0 1=OPEN 0= CLOSED FWMiB FWM49 FW-P-3B SUCTION ISOL FROM WT-TK-10 (WT227) (RAFV227) RANGE O TO 1.0 1-OPEN 0= CLOSED FWM50 FW-P-3A SUCTION ISOL FROM WT-TK-10 (WT226) (RAFV226) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM51 FW-P-2 SUCTION ISOL FROM.WT-TK-10 'W1225) (RAFV225) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM52 FWM53 FW-P-3B SUCTION ISOL FROM RIVER WATER (RW210) (RAFV210) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM54 FW-P-3A SUCTION ISOL 3 ROM RIVER WATER (RW109) (RAFV209) FANGE O TTO 1.0 '
-^VEN 0= CLOSED FWM55 FW-P-2 SUC'" ION ISOL Fut RIVER WATER (RW208)
(RAFV208) RANGE 0 TO 1.0 .1=Oi'En 0= CLOSED FWM56 FWM57 RT-TK-10 ISOL TO FW-P-3B (WT222) (RAFV2" . RANGE O TO 1.0 1=OPEN 0=COSED FWM58 WT-TK-10 ISOL TO FW-P-3A (WT223)- (RAFV222) RANGE O TO 1.G 1=OPEN 0= CLOSED FWM59 WT-TK-10 ISOL TO FW-P-2 (WT221) (RAFV221) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM60
-FWM61 FW-P-2 LATCH /RELAT,'H (JFWALACH)- RANGE T OR F T= LATCHED F= UNLATCHED FWM62 TURBINE TRIP VALVE (RFWATRIP) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM63 HTR DRN TANK SD-TK-2 LCV-SL 106A ISOL VLV (SDB7)
(PSDV087) RANGE O TO 1.0 1=OPEN 0= CLOSED TdM64 WT-TK26 SUPPLY ISOL TO WTP33 AND FWP4 (WT1031) (RWTS1031) RANGE O TO 1.0 l'OPEN 0= CLOSED FWM65 WT-TK26 SUPPLY ISOL TO FWP4 (FW643) (RFWH643) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM66 WT-TK11 SUPPLY ISOL TO FWP4 (FW639) (RFWH639) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM67 FWP4 DISCH ISOL (FW160) -1 (RFWH160) 'GNGE O TO 1. 0 1=OPEN 0=CLOSLD FWM68 FWP4 RECIRC ISOL TO WT-TK26- (FW660)
-(RFWH660)- RANGE O TC 1.0 1=OPEN 0=CIDSED O. FWM69 (RFWH663 ).'
FWP4 RECIRC ISOL TO WT-TK11 RANGE 0.TO 1.0 1=OPEN 0= CLOSED (FW663)
LOCAL OPERATOR ACTION LISTING FWM70 DEDICATED APW PUMP (FWP4) [) k/ (NFWP4) RANGE O OR 1 1=ON 0=OFF FWM71 WT-P33 DISCH SUPPLY TO TK-10 (WT2610) (RWTS2610) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM72 WT-P33 DISCH SUPPLY TO TK-11 (WT2611) (RWTS2611) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM73 WT-P33 DISCH SUPPLY TO PG WATER (WT26PG) (RWTS26PG) RANGE O TO 1.0 1=OPEN 0= CLOSED FWM74 WT-P33A AND WT-P33B (WTP33) ) (NWTSP33) RANGE 0,1,2 0=OFF 1=1 PUMP sN 2=BOTH ON FWM75 FWM76 SD PUMP 1A DISCH RELIEF GAG (SD101A) (RSDV101A) RANGE O TO 1.0 0= GAGGED 1=NOT GAGGED FWM77 SD PUMP 1B DITJH RELIEF GAG (SD101B) (RSDV103 B) RANGE O TO 1.0 0= GAGGED 1=NOT GAGGED FWM78 FWM79 SD-105A,B,C,D COMBINED POSITION (SD-105A,B,C,D) (RSDV105) RANGE O TO 1.0 0= CLOSED 1=OPEN SWD1 345KV BU" 4 TO AUTO TRANSFORMER (PCB342) (LBK342) RANGm T OR F T= CLOSED F=OPEN SWD2 345KV BUS 3 TO AUTO TRANSFORMER (PCB332) (LBK332) RANGE T OR F T= CLOSED F=OPEN SWD3 fg SWD4 345KV BUS 4 TO COLLIER LINE (PCB346) ('~) (LBK346) RANGE T OR F T= CLOSED F=OPEN SWD5 345KV BUS 3 TO COLLIER LINE (PCB336) a (LBK3?6) RANGE T OR F T= CLOSED F=OPEN SWD6 SWD7 345KV BUS 4 TO SAMMIS LINE (PCB344) (LBK344) RANGE T OR F T= CLOSED F=OPEN SWD8 345KV BUS 3 TO SAMMIS LINE (PCB334) (LBK334) RANGE T OR F T= CLOSED FaOPEN SWD9 SWD10 345KV BUS 6 TO MANSFIELD LINE (PCB366) (LBK366) RANGE T OR F T= CLOSED F=OPEN SWD11 345KV BUS 5 TO MANSFIELD LINE (PCB355) (LBK355) RANGE T OR F T= CLOSED F=OPEN SWD12 SWD13 138KV BUS 2 TO AUTO TRANSFORMER (OCB82) (LBK82) RANGE T OR F T= CLOSED Fa0 PEN < SWD14 138KV BUG 1 TO AUTO TRANSFORMER (OCB91) (LBK91) RANGE T OR F T= CLOSED F=OPEN SWD15 SWD16 7.38KV BUS 1 TO CRESCENT LINE (OCBo7) (LBK97) RANGE T OR F T= CLOSED F=OPEN [' SUD17 128KV BUS 1 TO CRUCIBLE LINE (OCB95) x- (LBK95) RANGE T OR F T= CLOSED F=OPEN
. ~ .. .. .
LOCAL OPERATOR ACTION LISTING
~ SWD18 N' SWD19 138KV BUS 2 TO SHIPPINGPORT RESERVE XFMR (OCB80)
(LBK80) RANGE T OR F T= CLOSED F=OPEN SWD20 138KV BUS 1 TO SHIPPINGPORT RESERVE XFMR (OCB90) (LBK90) RANGE T OR F T= CLOSED F=OPEN SWD21 SWD22 138KV BUS 2 TO VALLEY LINE (OCB88) (LBK88) RANGE T OR F T= CLOS ED F=CPEN SWD23 138KV BUS 2 TO CRESCENT LINE (OCB84) (LBK84) RANGE T OR F T= CLOSED P=-OPEN SWD24 138KV BUS 2 TO MIDLAND LINE (OCB85) (LBK65) RANGE T OR F T= CLOSED F=OPEN SWD25 138KV BUS 2 TO SHIPPINGPORT XFMM (OCB81) (LBK81) RANGE T OR F T= CLOSED F=OPEN SWD26 SWD27 138KV TO BUS 7 (OCB87) (LBK87) RANGE T OR F T=CLOShu F=OPEN SWD28 138KV BUS 7 TO CRUCIBLE (OCB89) (LBK89) RANGE T OR F T=C LOSED F=OPEN SWD29 SWD30 138KV TO BUS 8 (OCB93) (LBK93) RANGE T OR F T= CLOSED F=OPEN fw SWD31 138KV BUS 8 TO CRUCIBLE (OCB98) ( (LBK98) RANGE T OR F T= CLOSED F=OPEN SWD32 SWD33 138KV BUS 7 TO BUS 8 X-TIE (OCB180) 3 (LBK180) RANGE T OR F T = CLOSED F=OPEN SWD34 345KV BUS 3 TO 138KV BUS 8 (OCB333) (LBK333) RANGE T OR F T= CLOSED F=OPEN . SWD35 SWD36 SWITCHYARD BREAKER RESET FOR MALF EPS-1 (JSWDRST) RANGE T OR F T=TRUE F=FALS E SWD37 SWD38 MAIN XFMR TO 345KV BUS 3 DISCONNECT (LDISGENA) RANGE T OR F T= CLOSED F=OPEN SWD39 MAIN XFMR TO 345KV BUS 4 DISCONNECT (LDISGENB) RANGE T OR F T= CLOSED F=OF1N SWD40 MAIN XFMR TO 345KV BUS 3 DISCONNECT-(LDISGENC) RANGE T OR F T= CLOSED F=OPEN SWD41- MAIN XFMR TO 345KV BUS 4 DISCONNECT (LDISGEND) RANGE T OR F T= CLOSED F=OPEN GEN 1 USST 1C DISCONNECT (JGENUA1) RANGE T OR F T= CLOSED PnOPEN GEN 2 USST 1D DISCONNECT (JGENUA2) RANGE T OR F TmCLOSED FnOPEN b' I CHS1 (RCHV4) PCV-145 MANUAL BYPAS3 RANGE O TO 1.0 1=OPEN 0= CLOSED (CH4)
LOCAL OPERATOR ACTION LISTING CHS2 PCV-145 ISOL VLV (CH5)
/) (RCHVS) RANGE O TO 1.0 1=OPEN 0= CLOSED \~/ CHS3 CHS4 BORONOMET5R OUTLET ISOL VLV (CH58)
(RCHV58) RANGE O TO 1.0 1=OPEN 0=CIOSED CHSS BORONOMETER INLET ISOL VLV (CH57) (RCHV57) RANGE O TO 1.0 1=OPEN 0= CLOSED CilS 6 CHS7 MIXED BED DEMIN 1A ISOL VLV (CH7) (RCHV7) RANGE O TO 1,0 1=OPEN 0= CLOSED CHS8 MIXED BED DEMIN 2B ISOL VLV (CH8) (RCHV8) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS9 CATION BED DEMIN ISOL VLV (CH46) (RCHV46) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS10 CATION BED DEMIN BYPASS VLV (CHil) (RCHV11) RANGE O TO 1.0 l a'.
- W 0= CLOSED CHS11 DEBOR DEMIN 3A ISOL VLV (CH49)
(RCHV49) RANGE O TO 1.0 1=OPEN 0=r!OSED CHS12 DEBOR DEMIN 3B ISOL VLV (CH50) (RCHV50) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS13 CHS14 VCT DRAIN (CH247) (RCHV247) RANGE O TO 1.0 1=OPEN 0= CLOSED
~. CHS15 CHS16 BORIC ACID TO CHARG PP (BLENDER BYPASS) f(CH135)
(RCHV135) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS17 PG WATER TO CHARG PP (BLENDER BYPASS) (CH138) (RCRV138) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS18 CHS19 RWST FILL FROM BLENDER (CH89) (RCHV89) RANGE O TO 1.0 1=OPEN 0= CLOSED
'CHS20 CHS21 CHARGING PUMP 1A. SUCTION FROM VCT/RWST (CH19)
(RCHV19) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS22 CHARGING PUMP 1B SUCTION FROM VCT/RWST (CH2O) (RCHV20) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS23 CHARGING PUMP 1C SUCTION FROM VCT/RWST (CH21) (RCHV21) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS24 CHARGING PUMP 1A SUCTION FROM SIS (CH146) (RCHV146) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS25 CHARGING PUMP 1B SUCTION FROM SIS (CH147) (RCHV147) RANGE O TO 1.0 1=OPEN O= CLOSED CHS26 CHARGING PUMP 1C SUCTION FROM SIS (CH148) - (RCHV148) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS27 CHARGING PUMP 1A DISCH ISOL (CH25) (RCHV25) RANGE O TO 1.0 1=OPEN 'O= CLOSED
/3 CHS28 CHARGING PUMP 1B DISCli ISOL (CH26)
L/ (RCHV26) RANGE O TO 1.0 1=OPEN 0= CLOSED
LOCAL OPERATOR ACTION LISTING CHS29 CHARGING PUMP 1C DISCH ISOL (CH27) t,.'T (RCHV27) RANGE O TO 1.0 1=OPEN 0=CLCsBD kl CHS30 CHARGING PUMP 1A DISCH To FILL HDR (CH158) (RCHV158) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS31 CHARGING PUMP 1B DISCH TO FILL HDR (CH159) (RCHV159) RANGE O TO-1.0 1=OPEN 0= CLOSED CHS32 CHARGING PUMP 1C DISCH TO FILL HDR (CH161) (RCHV161) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS33 CHS34 FCV-122 MANUAL BYPASS VLV (CH29) (RCHV29) RANGE O TO 1.0 1=OPEN 0= CLOSED . CHS35 FCV-122 ISOL VLV (CH30) (RCHV30) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS36 REGEN HX ISOL VLV (CH289) (RCHH289) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS37 CHS38 HCV-186 ISOL VLV (CH171) (RCHV171) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS39 FILL MDR TO SEAL INJECTION (CH172) (RCHV172) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS40 SEAL INJ FILTER 1A INLET ISOL VLV (CH174) (RCHV174) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS41 SEAL INJ FILTER 1A OCTLET ISOL VLV (CH176) (RCHV176) RANGE O TO 1.0 1=OPEN 0=C LOSED ( CHS42 SEAL INJ FILTER 1B INLET ISOL VLV gS (CH175) l ('~j (RCHV175) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS43 SEAL INJ FILTER 1B OUTLET ISOL VLV (CH177) , (RCHV177) RANGE O TO 1.0 1=OPEN 0= CLOSED l CHS44 SEAL INJ FILTER BYPASS VLV (CH173) l (RCHV173) RANGE O TO 1.0 1=OPEN 0= CLOSED l CHS45 SEAL INJ TO RCP 1A ISOL VLV (CH308A) (RCHH308A) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS46 SEAL INJ TO RCP 1B ISOL VLV (CH308B) (RCHH308B) RANGE O TO 1.0 1=OPEN 0= CLOSED l CHS47 SEAL'INJ TO RCP 1C ISOL VLV (CH308C) (RCHH308C) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS48 SEbL INJ TO RCP 1A THROT VLV (CH179) (RCHV179(1)) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS49 SEAL INJ TO RCP 1B THROT VLV (CH178) (RCHV179(2)) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS50 SEAL INJ TO RCP 1C THROT VLV (CH180) (RCHV179(3)) RANGE O TO 1.0 1=OPEN 0= CLOSED ( CHSS1 RCP 1A #1 SEAL PRESS XMTR ISOL VLV (CH343) (RCHV34 3 (1) ) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS52 RCP 1B #1 SEAL PRESS XMTR ISOL VLV (CH344) (RCHV343(2)) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS53 RCP 1C #1 SEAL PRESS XMTR ISOL VLV .(CH345) (RCHV343(3)) RANGE O TO 1.0 1=OPEN 0= CLOSED CHSS4 SEAL WATER HX INLET ISOL VLV (CH218) (RCHV218) RANGE O TO 1.0 1=OPEN 0= CLOSED I'N CHS55 SEAL WATER HX OUTLET ISOL VLV (CH219)
\_) (RCHV219) RANGE O TO 1.0 1=OPEN 0= CLOSED ;
LOCAL OPERATOR ACTION LISTING CHS56 SEAL WATER HX BYPASS VLV (CH217) ['T \- (RCHV217) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS57 CHS58 H2 SUPPLY PRESS TO VCT (PCV-CH-118) (PCVC118) RANGE O TO 114.7 CHS59- N2 SUPPLY-PRESS TO VCT (PCV-CH-119) (PCVC119) RANGE O TO 114.7 CHS60 CHS61 BA TANK 1A OUTLET ISOL VLV (CH71)
'(RCHV71(1)) RANGE'O TO 1.0 1=OPEN 0= CLOSED CHS62 BA TANK 1B OUTLET ISOL VLV (CH72)
(RCHV71(2)) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS63 BA TANK 1A RECIRC ISOL VLV (CH77) (RCHV77 (1) ) RANGE O TO 1.0- 1=OPEN 0= CLOSED CHSd4 BA TANK 1B RECIRC ISOL VLV (CH78) (RCHV77 (2 ) )- RANGE O TO 1.0 1=OPEN 0= CLOSED CHS65 BA TANK 1A RECIRC ORIFICE ISOL VLV (CH107) (RCHV107(1)) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS66 BA TANK 1B RECIRC ORIFICE ISOL'VLV (CH108) (RCHV107(2)) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS67 BA TRANS PUMP 2A DISCH TO BA FILTER (CH79) (RCRV79(1)) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS68 BA TRANS PUMP 2B DISCH TO BA FILTER (CH80)~ (RCHV79(2)) -RANGE O TO 1.0 1=OPEN 0= CLOSED CHS69 BA TANK 1A BA FILTER RETURN ISOL VLV (CH104) O- (RCHV104(1)) RANGE 0 TO 1.0 -1=OPEN 0= CLOSED CHS70 BA TANK 1B BA' FILTER RETURN ISOL VLV (CH106) (RCHV104(2)) RANGE O TO 1.0 1=OPEN- 0= CLOSED CHS71 CHS72 BA TANK 1A FILL FROM BORIC ACID HOLD TANK (CH127) (RCHV127(1)) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS73 BA TANK 1B FILL FROM BORIC ACID HOLD. TANK (CH128) (RCHV127(2)) RANGE 0 TO 1.0 1=OPEN 0= CLOSED
.CHS74 .
CHS75 PG WATER:TO BA TANK 1A (CH129) (RCHV129(1)) RANGE O TO l'.0 1=OPEN 0= CLOSED CHS76 PG WATER TO BA TANK 1B - (CH130) (RCHV129(2)) RANGE 0-TO 1.0 1=OPEN 0= CLOSED CHS77 CHS78 BA BATCn TANK FILL FROM PG WATER (CH120) (RCHV120) RANGE O TO 1.0 'l=OPEN 0= CLOSED CHS79 . BA D:.TCH TANK OUTLET ISOL VLV (CH116) (RCHV116) RANGr: 0 TO 1.0 1=OPEN 0= CLOSED CHS80 BA BATCL TANK TO BA TRANS PUMP 2A _ (Chill) 1 1=OPEN 0= CLOSED ; (RCHV111(1)) PANJE O TO 1.0 CHS81 BA BATCH TANK TO BA TRANS PUMP 2B (CH112) i (RCHV111;2)) RANGP 0.TO 1.0 1=OPEN 0= CLOSED l CHS82 l ,{
LOCAL OPERATOR ACTION LISTING :
.CHS83 NON-AERATED VENT HDR TO DEGAS 2A .ISOL VLV (BR16)
( (RBRV16) RANGE O TO 1.0 1=OPEN 0=CLOSE CHS84= NON-AERATED 1 VENT HDR TO DEGAS 2B ISOL VLV (BR17)- (RBRV17) RANGE O-TO 1.0 1=OPEN 0=CLOSE CHS85 DEGAS-2B INLET ISOL VLV- (BRS60)- (RBRV560) RANGE 0 TO 1.0-- 1=OPEN 0=CLOSE-CHS86- DEGAS 2A STM PRESS -CONT. VLV - (PCV-BR-103A): (RBR103 AP) - RANGE O TO 1.0 1=OPEN 0=CLOSE, CHS87. - DEGAS 2B STM PRESS CONT VLV (PCV-b3-103B) (RBR103BP) RANGE O TO 1.0 1=OPEN 0=CLOSE
-CHS88 CHS89 COOL RECOV TANK 4 A INLET & OUTLET ISOL 'VLVS (BR22,29)
(RBRV22) RANGE O TO 1.0 1=OPEN 0=CLOSE CHS90- - COOL RECOV TANK 4B INLET : & OUTLET ISOL VLVS (BR23,30) (RBRV23). RANGE O TO 1.0 1=OPEN 0=CLOSE CHS91 CHS92 BR EVAP 1A REFLUX FLOW CONTROL. VLV - (BR102A) (RBRV102A) RANGE O TO 1.0 11=OPEN. 0=CLOSE CHS93 BR EVAP 1B RDFLUX FLOW : CONTROL: VLV (BR102B)' (RBRV102B) RANGE 0 TO 1.0 1=OPEN 0=CLOSE CHS94 CHS95 TEST TANK PUMP SA DISCH-VLV- (BR365) (RBRV365) . RANGE'O TO 2.0- -1=OPEN- 0= CLOSED _ _CHS96 TEST TANK PUMP 53 DISCH VLV (BR366) (RBRV366) RANGE O TO 1.0 1=OPEN, 0= CLOSED CHS97 TEST TANK PUMP SB RECIRC TO TEST TANKL2B, (BR368) (RBRV368) RANGE =0 TO 1.0 -1=OPEN 0=CICSED CHS98 = TEST-TANK PUMP 5A RECIRC TOLTEST TANK 2A (BR370)- (RBRV370) RANGE O TO 1.0: 1=OPEN 0=CLOSE CHS99
-CHS100 CLEANUP FILTER RECIRC TO TEST TANK 2A -(BR400)
.(RBRV400) RANGE O TO 1.0 1=OPEN' 0=CLOSE' CHS101 CLEANUP FILTER RECIRC.TO' TEST TANK 2B (BR401).
(RBRV401) RANGE O TO 1.0- 1=OPEN: 0=CLOSEc CHS102 CHS103 CLEAMUP FILTER BYPASS TO PG WATEh THXS _ (BR389)
-(RBRV389) RANGE 0:TO 1.0 1=OPEN.'0- f 4S E --
CHS104 CLEANUP FILTER DISCHLTO PG V'.-tR SANKS (BR397) (RBRV397) RANGE O TO 1.0 1=OPEN 6=CLOSE CHS105 CHS106 LVAP BOTTOMS" HOLD ~ TANK BYPASS ( BR284.) 3 (RBRV284). RANGE-0 TO l'.0 1=OPEN: 0=CLOSE CHS107 -EVAP BOTTOMS PUMP DISCH TO BA HOLD TANK. (BR344)
.(RBRV344) RANGE 0 TO 1.0- 1=OPEN--0=CLOSE.
CHS108 EVAP BOTTOMS. PUMP DISCH TO BA TANKS 17.& 1B (BR764)
.(RBRV764) ; RANGE O TO 1.0- 11=OPEN 0=CLOSE, f'T CHS109 (m/ '
1 _ - = _ - - A
LOCAL OPERATOR ACTION LISTING
,s CHS110 PG WATER MAKEUP FROM WATER TREATMENT (BR439)
( (RRMWV439) RANGE O TO 1.0 1=OPEN 0= CLOSED \ /) CHS111 PG WATER TANK 6A INLET ISOL VLV (BR115A) 1 (RPRWV15A) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS112 PG WATER TANK 6B INLET ISOL VLV (BR115B) (RRMWV15B) RANGE O TO 1.0 1=OPEN 0= CLOSED l CHS113 PG WATER PUMP 10A SUCTION FROM TANK 6A (BR406) l (RRMWV406) RANGE O TO 1.0 1=OPEN 0= CLOSED l CHS114 PG PATER PUMP 10A SUCTION FROM TANK 6B (BR408) (RRMWV408) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS115 PG WATEL PUMP 10B SUCTION FROM TANK 6B (BR409) (RRMWV409) RANGE r. TO 1.0 1=OPEN 0= CLOSED CHS116 PG WATER PUMP 10B SUCTION FROM TANK 6A (BR407) (RRMWV407) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS117 PG WATER PUMP 10A DISCH TO PG WATER HDR (BR415) (RRMWV415) RANGE O TO 1.0 1=OPEN 0= CLOSED CMS 118 PG WATER PUNP JOB DISCH TO PG WATER HDR (BR416)
~ : WV416) C 'R s 0 Tt 1.0 1=OPEN 0= CLOSED iT19 PG W4.iER HDR RECIRC TO TANK 6A ISOL VLV (BR693)
(,OMWV693) RANGE O TO 1.0 1=OPEN 0= CLOSED CMS 120 PG WATER HDR RECIRC TO TANK 6B ISOL VLV (BR694) (RRMWV694) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS121 FCV-PG-101 BYPASS TO TAHK 6A (BR410)
'n.RMWV410 ) RANGE O TO 1.0 1=OPEN 0= CLOSED CL3122 FCV-PG-101 BYPASS TO TANK 6B (BR411)
(RRMWV411) RANGE O TO 1.0 1=OPEN 0= CLOSED (~~ CHS133 PCV-PG-117 & FCV-PG-101 BYPASS (BR697) (RR1!WV697 ) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS124 PG WATER PUMP 10A DISCH TO CLEANUP FILTER (BR417) (RRMWV417) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS125 PG WATER PUMP 10B DISCH TO CLEANUP FILTER (DR418) (RRMWV418) RANGE O TO 1.0 1=OPEN 0= CLOSED CHS126 CLEANUP FILTER INLET FROM PG WATER PUMPS (BR421) (PRMWV421) RANGE O TO 1.0 1=OPEN 0= CLOSED RCS1 RCS LOW FLOW LOOP 1 BS-414 PROT CHAN I ($JFB414) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS2 RCS LOW FLOW LOOP 1 BS-415 PROT CHAN II ($JFB415) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS3 RCS LOW FLOW LOOP 1 BS-416 PROT CHAN III ($JFB416) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS4 RCS LOW FLOW LOOP 2 BS-424 PROT CHAN I ($JFB424) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCSS RCS LOW FLOW LOOP 2 BS-425 PROT CHAN II ($JFB425) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS6 RCS LOW FLOW LOOP 2 BS-426 PROT CHAN III ($JFB426) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS7 RCS LOW FLOW LOOP 3 BS-434 PROT CHAN I ($JFB434) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS8 RCS LOW FLOW LOOP'3 BS-435 PROT CHAN II ($JFB435) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS9 RCS LOW FLOW LOOP 3 BS-436 PROT CHAN III ($JFB436) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS /,_) RCS10 \_J
1 LOCAL OPERATOR ACTION LISTING RCS11 OVERPOWER DELTA T LOOP 1 BS-412B-1 PROT CHAN I ( ($JTB412B1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS12 OVERTEMP DELTA T LOOP 1 BS-412C-1 PROT CHAN I ($JTB412C1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS13 ICW TAVG LOOP 1 BS-412D-1 PROT CHAN I ($JTB412D1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS14 HIGH TAVG LOOP 1 BS-412D-2 PROT CHAN I ($JTB412D2) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS15 LOW-LOW TAVG LOOP 1 BS-412E PROT CHAN I ($JTB412E) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS16 OPDT ROD STOP LOOP 1 BS-412B-2 PROT CHAN I ($JTB412B2) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS17 OTDT ROD STOP LOOP 1 BS-412C-2 PROT CHAN I ($JTB412C2) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS18 RCS19 OVERPOWER DELTA T LOOP 2 BS-422B-1 PROT CHAN II ($JTB422B1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS20 OVERTEMP DELTA T LOOP 2 BS-422C-1 PROT CHAN II ($JTB422C1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS21 LOW TAVG LOOP 2 BS-422D-1 PROT CHAN II ($JTB422D1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS22 HIGH TAVG LOOP 2 BS-422D-2 PROT CHAN II ($JTB422D2) O= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS23 LOW-LOW TAVG LOOP 2 BS-422E PROT CHAN II ($JTB422E) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS 3 RCS24 OPDT ROD STOP LOOP 2 BS-422B-2 PROT CHAN II y~) ($JTB422B2) 0=NCRMAL, 1= TRIP, 2= RESET, 3=AS IS RCS25 OTDT ROD STOP ICOP 2 BS-422C-2 PROT CHAN II (6JTB422C2) C= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS26 RCS27 OVERPOWER DELTA T LOOP 3 BS-432B-1 PROT CHAN III ($JTB432B1) 0= NORMAL, 1= l'RI P , 2= RESET, 3=AS IS RCS28 OVERTEMP DELTA T LOOP 3 BS-432C-1 PROT CHAN III ($JTB432C1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS PCS29 LOJ TAVG LOOP 3 BS-432D-1 PROT CHAN III ($JTB432D1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS30 HIGH TM1G LOOP 3 BS-432D-2 PROT CHAN III ($JTB432D2) 0=Noai!AL, 1= TRIP, 2= RESET, 3=AS IS RCS31 LOW-LOW TAVG LOOP 3 BS-432E PROT CHAN III ($JTB432E) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS32 OPDT RCD STOP LOOP 3 BS-432B-2 PROT CHAN III ($JTB432B2) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS33 OTDT ROD STOP- LOOP 3 BS-432C-2 PROT CHAN III ($JTB432C2) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS34 RCS35 PZR HIGH LEVEL BS-450A-1 PROT CHAN I (QJLB459A1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS36 PZR HIGH LEVEL BS-460-1 PROT CHAN II ($JLB460A1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS (-) RCC37 PZR HIGH LEVEL BS-461-1 ($JLB461A1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS PROT CHAN III l
.. l
-l LOCAL OPERATOR ACTION LISTEMG O RCS38 RCS39 PZR HIGH PRESS BS-455A PROT CHAN I (SJPB455A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS40 PZR LO PRESS RX TRIP BS-455C PROT CHAN I
($JPB455C) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS41 PZR LO PRESS SI BS-455D PROT CHAN I ($JPB455E) O= NORMAL, 1= TRIP, 2= RESET, 3=AS IS' RCS42 P-11 BS-455B PROT CHAN I ($JPB455B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS43 RCS44 PZR HIGH PRESS BS-456A PROT CHAN:II ($JPB456A) O= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS45 PZR LO PRESS RX TRIP BS-456C PROT CHAN II ($JPB456C) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS46 PZR LO PRESS SI BS-456D PROT CHAN II ($JPB456D) 0= NORMAL, 1= TRIP, 2= RESET,-3=AS IS RCS47 P-11 BS-456B PROT CHAN II ($JPB456B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS48 x RCS49 PZR HIGH PRESS BS-457A PROT CHAN III ($JPB457A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS50 PZR LO PRESS RX TRIP BS-457C' PROT CHAN III O s ($JPB457C) RCS51 0= NORMAL, 1= TRIP, PZR LO PRESS SI 2= RESET, 3=AS IS BS-457D PROT CHAN III ($JPB457D) 0= NORMAL, 1= TRIP, 2= RESET,-3=AS IS RCS52 P-11 BS-457B PROT CHAN III ($JPB457B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS
-RCSE3 RCS54 STM/FD MIS STM>FD ~ LOOP 1' BS-478B PROT.CHAN III-($JFB478B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS55 STM/FD MIS STM>FD LOOP:1 BS-478A PROT CHAN IV [
($JFB478A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS g RCS56 STM/FD MIS STM>FD LOOP 2 BS-488B PROT CHAN III 5 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS
~
-($JFB4 88B)
RCS57 STM/FD MIS STM>FD' LOOP 2- BS-488A PROT CHAN IV ($JFB488A) O= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS58 STM/FD MIS STM>FD LOOP 3 BS-498B PROT CHAN III ($JFB498B) 0= NORMAL,-1= TRIP, 2= RESET, 3 RAS IS RCS59 STM/FD MIS STM>FD IcOP 3 BS-498A PROT CHAN IV ($JFB498h) 0= NORMAL, 1= TRIP,.2= RESET, 3=AS IS RCS60 RCS61 SG LOW-LOW LEVEL LOOP 1 BS-474A-1 PROT CHAN I ($JLB474A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS62 SG LOW LEVEL LOOP 1 BS-474B-3 PROT CHAN I ($JLB474B) -0=NORMLL, 1= TRIP, 2= RESET, 3=AS IS I_ RCS63 SG HI-HI LEVEL LOOP 1 BS-474-1 PROT CHAN I ($JLB474C) 0= NORMAL, 1= TRIP., 2= RESET, 3=AS IS
N LOCAL OPERATOR ACTION LISTING RCS64 SG LOW-LOW LEVEL LOOP 1 BS-475A-1 PROT CHAN II O ($JLB475A) RCS65 0= NORMAL, SG LOW LEVEL 1= TRIP, 2= RESET, 3=AS IS LOOP 1 BS-475B-1 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS PROT CHAN II ; ($JLB475B) RCS66 SG HI-HI LEVEL LOOP 1 BS-475-1 PROT CHAN II (SJLB475C) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS67 SG LOW-LOW LEVEL LOOP 1 BS-476-A PROT CHAN III ($JLB476A) 0= NORMAL, 1= TRIP, 2= RESET,.3=AS IS RCS68 SG HI-HI-LEVEL LOOP 1 BS-476 PROT CHAN III ($JLB476C) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS69 RCS70 SG LOW-LOW LEVEL LOOP 2 BS-484A-1 PROT CHAN I ($JLB484A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS71 SG LOW LEVEL LOOP 2 BS-484B-3 PROT CHAN I ( $JLB4 84 B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS72 SG HI-HI LEVEL LOOP 2 BS 484-1 PROT CHAN I ($JLB484C) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS73 SG LOW-LOW LEVEL LOOP-2 BS-485A-1 PROT CHAN II ($JLB485A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS74 SG LOW LEVEL LOOP 2 BS-485B-1 PROT CHAN II ($JLB485B) 0= NORMAL, 1= TRIP, 2=RESLT, 3=AS IS RCS75 SG HI-HI LEVEL LOOP 2 BS-485-1 PROT CHAN II ($JLB485C) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS76 SG LOW-LOW LEVEL LOOP 2 BS-486-A PROT CHAN III ($JLB486A) 0= NORMAL, laTRIP, 2= RESET, 3=AS IS RCS77 SG HI-HI LEVEL LOOP 2 BS-486 PROT CHAN III O ($JLB486C) RCS78 0= NORMAL, i='rRI P , 2= RESET, 3=AS IS RCS79 SG LOW-LOW LEVEL LOOP 3 BS-494A-1 PROT CHAN I ($JLB494A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS80 SG LOW LEVEL LOOP 3 BS-494B-1 PROT'CHAN I ( $JLB494 B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS81 SG HI-HI LEVEL LOOP 3 BS-494-1 PROT CHAN I ($3LB494C) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCSB2 -SG LOW-LOW LEVEL LOOP 3 BS-495A-1 PROT CHAN II ($JLB495A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS83 SG LOW LEVEL LOOP 3 BS-495B-1 PROT CHAN II c ($JLB495B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS84 SG HI-HI LEVEL LOOP 3 BS-495-1 PROT CHAN II
-( $JLB495C) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS85 SG' LOW-LOW LEVEL LOOP 3 BS-496-A PROT CHAN III
($JLB496A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS86- - SG HI-HI LEVEL LOOP 3 BS-496 PROT CHAN III - ($JLB496C) 0= NORMAL, 3= TRIP, 2= RESET, 3=AS IS RCS87 RCS88 10 STM LINE PRESS LOOP 1 PS-474A PROT CHAN II ($JPB474 h) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS89 LO STM LINE PRESS LOOP 1 PS-475A PROT CHAN III ($JPB475A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS
,O RCS90 LO STM LINE PRESS LOOP 1 PS-476A PROT CHAN IV (SJPB476h) 0= NORMAL, 1= TRIP,-2= RESET, 3=AS IS i
LOCAL OPERATOR ACTION LISTING RCS91 LO STM LINE PRESS LOOP 2 PS-484A PROT CHAN II , ($JPB484A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS [_s')
's RCS92 LO STM LINE PRESS LOOP 2 PS-485A PROT CHAN III i
($JPB485A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS93 LO STM LINE PRESS LOOP 2 PS-486A PROT CHAN IV
. ($3PB486A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS94 LO STM LINE PRESS LOOP 3 PS-494A PROT CHAN II
($JPB494A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS l RCS95 LO STM LINE PRESS LOOP 3 PS-495A PROT CHAN III ) ($JPB495A) 3= NORMAL, 1, TRIP, 2= RESET, 3=AS IS RCS96 LC STM LINE PRESS LOOP 3 PS-496A PROT CHAN IV ($JPB496A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS97 RCS98 HI STM PRESS RATE LOOP 1 PS-474B PROT CHAN II ( $JPB474 B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS99 HI STM PRESS RATE LOOP 1. PS-475B PROT CHAN III ($JPB475B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS100 HI STM PRESS RATE LOOP 1 FS-476B PROT CHAN IV ($JPB476B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS101 HI STM PRESS RATE LOOP 2 PS-484B PROT CHAN II ( $JPB484 B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS102 HI STM PRESS RATE LOOP 2 PS-485B PROT CHAN III ($JPB4858) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS , RCS103 HI STM PRESS RATE LOOP 2 PS-486B PROT CHAN IV l ( $JPB4 86B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS104 HI STM PRESS RATE LOOP 3 PS-494B PROT CHAN II i () ($JPB494B) RCS105 0= NORMAL, 1= TRIP, 2= RESET, 3=AS HI STM PRESS RATE LOOP 3 PS-495B 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS IS PROT'CHAN III ($JPB495B) RCS106 HI STM PRESS RATE LOOP 3 PS-496B PROT CHAN IV ($JPB496B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS107 R CS .'.0 8 CNM PRESS HI BS-LM100B-1 PROT CHAN II ($JPB934B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS109 CNM PRESS HI BS-LM100C-1 PROT CHAN III ($JPB935B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS110 CNM PRESS HI BS-LM100D-1 PROT CHAN IV ($JPB936B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS111 CNM PRESS INT HI BS-LM100B-3 " ROT CHAN II ($JPB934C) G= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS112 CNM PRESS INT HI BS-LM100C-3 FRJT CHAN III ($JPB935C) 0=lORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS113 CNM PRESS ICT HI BS-LM100D-3 PROT CHAN IV ($JPB936C) 0=h0RMAL, 1= TRIP, 2= RESET, 3=AS IS RCS114 CNM PRESS HI-HI BS-LM100A-2 PROT CHAN I ($JPB934A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS115 CNM PRESS HI-HI BS-LM100B-2 PROT CHAN II ($JPB935A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS116 CNM PRESS HI-HI BS-LM100C-2 PROT CHAN III ($JPB936A) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS117 CNM PRESS HI-HI BS-LM100D-2 PROT CnAN IV [])
\_ ($JPB937Af 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS
i LOCAL OPERJ. TOR ACTION LISTING
~ RCS118
\~- RCS119 CNM PRESS HI-HI CHA3 I BYPASS (XPPLTB(1)) RANGE T OR F F = NORMAL RCS120 CNM PRESS HI-HI CHAN II BYPASS (XPPLTB(2)) RANCE T OR F F = NORMAL RCS121 CNM PRESS HI-HI CHAN III BYPASS (XPPLTB(3)) RANGE T OR F F = NORMAL RCS122 CNM PRESS HI-HI CHAN IV BYPASS (XPPLTB(4)) RANGE T OR F F = NORMAL RCS123 RCS124 P-7 BS-446A-1 PROT CHAN III ($JPB446A1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS125 .P-7 BS-447E-1 PROT CHAN IV ($JPB447E1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS126 RCS127 TAVG DEV (LOW) LOOP 1 BS-408A-1 ($JTB408A1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS128 TAVG DEV (HIGH) LOOP 1 BS-408A-2 ($JTB408A2) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS129 TAVG DEV (LOW) LOOP 2 BS-408B-1 ($JTB408B1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS130 TAVG DEV (HIGH) LOOP 2 BS-408B-2 ($JTB408B2) O= NORMAL, 1= TRIP, 2= RESET, 3=AS IS g-s RCS131 LOOP 3 BS-408C-1 () ($JTB408C1) RCS132 TAVG DEV (LOW) 0= NORMAL, TAVG DEV (HIGH) 1= TRIP, LOOP 2= 3 RESET, 3=AS IS BS-408C-2 ($JTb408C2) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS133 DELTA T DEV (LOW) LOOP 1 BS-409A-1 ($JTB409A1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS134 DELTA T DEV (HIGH) LOOP 1 BS-409A-2 ($JTB409A2) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS135 DELTA T DEV (LOW) LOOP 2 BS-409B-1 ($JTB409B1) 0= NORMAL, 1= TRIP, 2'= R E S E T , 3=AS IS RCS136 DELTA T DEV (HIGH) LOOP 2 BS-409B-2 ($JTB409B2) 0= NORMAL, 1= TRIP, 2= RESET,-3=AS Ib RCS137 DELTA T DEV (LGW) LOOP 3 BS-4090-1 ($JTB409C1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS138 DELTA T DEV (HIGH) LOOP 3 BS-409C-2 ($JTB409C2) 0= NORMAL, 1= TRIP, 2= RESET, 3=i.S IS RCS139 RCS140 PZR LOW LEVEL (HTRS & LCV-459) ($JLB45PC) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS141 PZR LOW LEVEL (HTRS & LCV-460) ($JLB460C2) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS142 PZR HIGH LEVEL DEV (B/U HTRS ON) ($JLB459D). 0= NORMAL, 1= TRIP, 2" RESET, 3=AS IS RCS143 PZR LOW LEVEL DEV ($JLB459E) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS
+
RCS144 PZR HIGH LEVEL (u ($JLB4 60C1) O= NORMAL, 1= TRIP, 2= RESET, 3=AS IS
LOCAL OPERATOR ACTION LISTING RCS145 RCS146 PZR LOW PRESS DEV_(B/U HTRS ON) ($JPB444F) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS147 PZR LOW PRESS ($JPB445B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS148 PZR HIGH PRESS ($JPB445C) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS149 PZR HIGH PRESS (PCV-4550, PCV-456) , ($JPB445A) 0=NCRMAL, 1= TRIP, 2= RESET, 3=AS IS RCS150 PZR HIGH PRESS (PCV-455C) ($JPB444B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS151 PZR HIGH PRESS DEV. ($JPB444E) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS152 PCV~455C OVER PRESS. PROT. ($JPB403H) 0=HORMAL, 1='fRI ? , 2= RESET, 3=AS IS RCS153 PCV-455D OVER PRFCS PROT ($JPB402H) 0= NORMAL, 1=TR1P, 2= RESET, 3=AS IS RCS154 RCS155 STM/FD MIS F0>STM LOOP 1 BC 478C ($JFB478C) 0= NORMAL, 1= TRIP, 2=DESE:, 3=AS IS RCS156 STM/FD MIS STM>FD LOOP 1 BS-478D ($JFB478D) 0= NORMAL, 1= TRIP, 2= RESET, 3=AG TS RCS157- STM/FD MIS FD>STM LOOP 2 BS-488C ($JFB488C) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS158 STM/FD MIS STM>FD LOOP 2 BS-488D ($JFB488D) _0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS159 STM/FD MIS FD>STM LOOP 3 BS-498C ($JFB498C) 0= NORMAL,-1= TRIP, 2= RESET, 3=AS IS RCS160 STM/FD MIS STM>FD LOOP 3 BS-498D ($JFB498D) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS161 RCS162 SG LOW LEVEL DEV LOOP 1 ($JLB478D1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS163 SG HIGH LEVEL DEV LOOP 1 ($JLB478D2) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS164 SG LOW LEVEL DEV LOOP 2 ($JLB488D1)- 0= NORMAL, 1= TRIP, 2= RESET,-3=AS IS RCS165 SG HIGH LEVEL DEV LOOP 2 ($JLB488D2) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS166- SG IDW LEVEL DEV LOOP 3 ($JLB498D1) 0= NORMAL,_1= TRIP, 2= RESET, 3=AS IS RCS167 SG HIGH LEVEL DEV LOOP-3 ($JLB498D2) 0= NORMAL, 1= TRIP, 3= RESET, 4=AS IS RCS168 RCS169 15% LOAD REJECTION BS-447A ($JPB447A) 0= NORMAL, 1= TRIP, 3rRESET, 4=AS IS RCS170 50% LOAD REJECTION- BS-447B-($JPB447B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS [ RCS171 LOAD REJ 20NT T"IP OPEN BANK 1 ($JTD408F1) 0= NORMAL, leTRIP, 2= RESET, 3=AS IS
._ _ _. _. . ~ _ _ - _ _ _ _ _ _
LOCAL OPERATOR ACTION LISTING , g RCS172 LOAD REJ CONT TRIP OPEN BANK 2 ($JTB408F2) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RX TRIP CONT TRIP OPEN BANK 1 RCS173 ($JTB408J1) OrNORMAL, leTRIP, 2= RESET, 3=AS IS RCS174 RX TRIP CONT TRIP OPEN BANK 2 ($JTB408J2) 0= NORMAL, 1= TRIP, 2= RESET,-3=AS IS , RCS175 RCS176 IR HIGH FLUX ROD STOP NI 35 ($JBSNC35E(1)) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS177 IR HIGH' FLUX ROD STOP NI 36 ($JBSNC35E(2)) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS178 CONT BANK D WITHDRAWAL LIMIT ROD STOP- , ($JZB409K) 0= NORMAL,.1= TRIP, 2= RESET, 3=AS IS RCS179 BLOCK AUTO ROD WITHDRAWAL-(C-5) ($JPB446B) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS180 - ROD IN MOTION (AUTO ONLY) ($JSB408C1) -0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS181 ROD OUT MOTION (AUTO ONLY) ($JSB408C2) 0= NORMAL,'l= TRIP, 2= RESET, 3=AS IS RCS182 RCS183 CONT BANK A LOW LIMIT ($JZB409A1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS104 CONT BANK A LOW-LOW LIMIT ($JZB409A2) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS RCS185 CONT BANK E LOW LIMIT ' O ($JZB409B1) 0= NORMAL; 1= TRIP, 2= RESET, RCS186 CONT BANK B LOW-LOW LIMIT 3=AS IS ($JZB409B2) 0= NORMAL, 1= TRIP,:2= RESET, 3=AS IS RCS187 CONT ~ BANK C LOW LIMIT ($JZB409C1) 0= NORMAL, 1= TRIP,-2= RESET ,3=AS IS RCS188 CONT BANK C LOW-LOW LIMIT ($JZB409C2) 0= NORMAL,_1= TRIP, 2= RESET,'3=AS:IS RCS189 CONT BANK D LOW LIMIT ($JZB409D1) 0= NORMAL, 1= TRIP, 2= RESET, 3=AS IS , RCS190 CONT BANK D LOW-LOW LIMIT ($JZB409D2) 0= NORMAL, 1= TRIP, 2= RESET, 3eAS IS r RCS191 RCS192 RX BYPASS BKR A~ RACKED IN (X52BYAX) T= RACKED IN, F= RACKED OUT RCS193 RX BYPASS BKR B-RACKED IN- ' p (X52BYBX) T= RACKED IN, F= RACKED-OUT RCS194 RX BYPASS'BKRS CLOSE l (XPPLBYPC) 1=BYA, 2=BYB, 3=NEITHER RCS195 L RCS196 POWER MISMATCH' DEFEAT SWITCH (KPCSPMDF) RANGE T= DEFEAT F= NORMAL , RCS197
- RCS198-L O' (RRCV55)
REACTOR VESSEL FLANGE OUTER CHAMBER STOP RANGE 0= CLOSED-1=OPEN (RCSSS) k e -4uw.~, , - . . + - . , , , , , -
,.+.*p w y a ,, 3
LOCAL OPERATOR ACTION LISTING RCS199 REACTOR' VESSEL FLANGE INNER CHAMBER STOP (RCS56) 7_ 5 4 (RRCV56) RANGE 0=CLCSED 1=OPEN
\> RCS200 RCS201 AMSAC BYPASS SWITCH (JRCSAMSC) RANGE T OR F T= CLOSED F=OPEN RCS202 RCS203 RWST LO-LO LVL CHAN I BYPASS (LT-QS-1000)
(JCSRWSTB(1)) RANGE T OR F F = NORMAL RCS204 RWST LO-LO LVL CHAN II BYPASS (LT-QS-100D) (JCSRWSTB(2)) RANGE T OR F F = NORMAL RCS205 RWST LO-LO LVL CHAN III BYPASS (LT-QS-100A) (JCSRWSTB(3)) RANGE T OR 7 F = NORMAL RCS206 RWST LO-Lo LVL CHAN IV BYPASS (LT-QS-100B) (JCSRWSTD(4)) RANGE T OR F F = NORMA' RCS207 RCS208 1/3 CONTROL RM CHLORINE DETECTION SIGNAL (A11-L4) (JCB001) RANGE T OR F F = NO SIGNAL RCS209 2/3 CNTL RM CHLORINE DET,CNTL RM VENT ISO INIT.(A11-53) (JCB003) RANGE T OR F F = NO SIGNAL RCS210 RCS211 NARROW RANGE TH RTD BIAS (LOOP 1) (JPCSBIAS (1) ) RANGE T OR F T = BIAS INSERTED fs RCS212 NAR'OW
? RANGE TH RTD DIAS (IDOP 2)
(~) (JPCSBIAS(2)) RANGE T OR F T = BIAS INSERTED RCS213 NARROW RANGE TH RTD BIAS (LOOP 3) (JPCSBIAS(3)) RANGE T OR F T = BAIS INSERTED
O APPENDIX 3 BVPS UNIT I SIMVLATOR CERTIFICATION TEST SCHEDULE The test schedule presented in this attachment meets or exceeds the requirements of ANSI /ANS 3.5-1985. This schedule provides the testing to be accomplished during the four year cycle following the initial submittal of this report. o s._/ I 4 i
BVPS UI SIMULAMR TEST SCHEDULE SQT TEST TEST DESCRIPTION YEAR E BE TESTED NUMBER 1991 1992 1993 1994 SQT-1.0 SIMULATION REAL TIME TEST XXXX XXXX XXXX XXXX S7 -2.0 STEADY STATE, DRIFT & NORMAL OPS. SERIES SQT-2.1 STEADY STATE DRIFT TEST AT 100% PWR. XXXX XXXX XXXX XXXX SQI-2,2 STEADY STATE TEST AT 75% PWR. XXXX XXXX XXXX XXXX SQT-2.3 STEADY STATE TEST AT 30% WR. XXXX XXXX XXXX XXXX SQT-2.4 NORMAL OPERATIONS SQT-2.4.1 PLANT SHUTDOWN 100% TO MODE 5 XXXX XXXX XXXX XXXX SQT-2.4.2 NIS POWER RANGE OST-1.2.1 XXXX XXXX XXXX XXXX SQT-2.4.3 NIS INTERMEDIATE RANGE OST-1.2.2 XXXX XXXX XXXX XXXX SQT-2,4.4 NIS SOURCE RANGE OST-1.2.3 XXXX XXXX 'XXXX XXXX SQT-2.4.5 PLANT STARTUP MODE 5 TO 100% XXXX XXXX XXXX XXXX SQT-2.4.6 1001 OP CHECK OST-1.6.7 XXXX XXXX XXXX XXXX SQT-2.4.7 RCS INVENTORY BALANCE OST-1.6.2 XXXX XXXX XXXX XXXX SQT-2.4.8 BA PUMP TEST OST-1.7.1/2 XXXX XXXX XXXX XXXX SQT-2.4.9 EDG #1 OST-1.36.1 XXXX XXXX XXXX XXXX SQT-2.4.10 EDG #2 OST-1.36.2 XXXX XXXX XXXX XXXX SQT-2.4.11 CONTAINMENT ISOLATION VALVE OST XXXX XXXX XXXX XXXX CGT-?.4.12 COLD VALVE EXERCISE OST-1.1.10 XXXX X.VX XXXX XXXX SQT-2.4.13 MSIV CWSURE TEST OST XXXX XXXX XXXX XXXX v SQT-2.4.14 AW DISCHARGE VALVE STROKE TEST XXXX XXXX XXXX XXXX SQT-2.4.15 MOTOR A W PUMP OST-1.24.2/3' XXXX XXXX XXXX XXXX SQT-2.4.16 TURBINE A W PUMP OST-1.24.4 XXXX XXXX XXXX XXXX SQT-2.4.17 RX STARTUP AFTER A TRIP XXXX XXXX XXXX XXXX SQT-3.0 TRANSIENT TESTS YEAR TO BE -TESTED SERIES 1991 1992 1993 1994 SQT-3.1 MANUAL REACIOR TRIP XXXX XXXX XXXX XXXX SQT-3.2 COMPLETE WSS OF ALL FEEDWATER XXXX XXXX XXXX XXXX SQT-3.3 SIMUTANIOUS CWSURE OF ALL MSIV'S XXXX XXXX XXXX XXXX SQT-3.4 SIMUTANIOUS TRIP OF ALL RCP'S XXXX XXXX XXXX XXXX SQT-3.5 TRIP OF ONE RX COOLANT PUMP XXXX XXXX XXXX XXXX SQT-3.6 MAIN TURBINE TRIP (RODS IN MANUAL) XXXX XXXX XXXX XXXX SQT-3.7 MAXIUM POWER RAMP (100%-75%-100%) XXXX XXXX XXXX XXXX SQT-3.8 DBA WCA WITH MSS OF 0FF SITE POWER XXXX XXXX XXXX XXXX SQT-3.9 MAXIUM STEAM BREAK IN CONTAINMENT XXXX XXXX XXXX XXXX SQT-3.10 PZR SAFETY VALVE LEAK WITH NO HHSI XXXX XXXX XXXX XXXX SQT-3.11 MAIN TURBINE TRIP (ROD 3 IN AUT0) XXXX XXXX XXXX XXXX l i v Page 1
BVPS UI SIMULAMR TEST SCHEDULE , SQT TEST TEST DESCRIPTION YEAR 'IO BE TESTED NUMBER 1991 1992 1993 1994 SQT-4.0 MALFUNCTION TESTS YEAR 'IO BE TESTED SERIES 1991 1992 1993 1994 AUX-1 THRU AUX-14 SQT-4.1 CONTAINMENT INST AIR 00t1 PRESSOR TRIP XXXX SQT-4.2 STATION AIR COMPRESSOR TRIP XXXX SQT-4.3 INSTRUMENT AIR LEAK XXXX
- SQT-4.4 CONTAINMENT INSTRUMENT AIR LEAK XXXX I
SQT-4.5 STATION AIR HEADER ISO VALVE FAIWRE XXXX SQT-4.6 AUXILIARY STEAM HEADER LEAK XXXX SQT-4.7 GASEOUS WASTE TANK EFFWENT. LEAK XXXX SQT-4.8 GASEOUS WASTE DECAY TANK HEADER LEAK XXXX-SQT-4.9 RIVER WATER PUMP TRIP XXXX SQT-4.10 RAW WATER PUMP TRIP XXXX SQT-4.11 AUXILIARY RIVER WATER PUMP TRIP XXXX SQT-4.12 CONTAINMENT VENTILATION FAN FAILURE XXXX SQT-4.13 RADIATION MONITOR FAIWRE XXXX CCW-1 THRU CCW-9 4 SQT-4.14 NON-REGENERATIVE HX TUBE LEAK XXXX SQT-4.15 RCP THERMAL BARRIER HX TUBE LEAK XXXX ! SQT-4.16 CCW PUMP TRIP XXXX l[ l SQT-4.17 CCW TEMP CONTROL VALVE FAILURE SQT-4.18 NON-REGENERATIVE HX TCV FAILURE XXXX XXXX l SQ"-4.19 COi PUMP SUCTION HEADER LEAK XXXX Sr6-4.20 CCW SUPPLY LINE TO RCP LEAK XXXX SQT 4.21 RCP SEAL WATER HX TUBE LEAK. XXXX CND-1 THRU CND-18 SQT-4.22 CONDENSATE PUMP TRIP XXXX SQT-4.23 FEEDWATER HEATER BYPASS VALVE FAI WRE' .XXXX SW-4.24 CONDENSATE PUMP DISCHARGE-HEADER LEAK XXXX SQT-4.25 FEEDWATER HEATER TUBE LEAK (2ND PI ) XXXX , SQT-4.26 FOURTH POINT HEATER WV FAIWRE XXXX SQT-4.27 - FIFTH POINT HEATER.LCV OSCILLATION - XXXX SQT-4.28 AIR EJECIOR FAIWRE XXXX SQT-4.29 VACUUM BREAKER LEAK XXXX SQT-4.30 CONDENSER TUBE LEAK- XXXX SQT-4.31 COOLING 'IDWER PUMP TRIP XXXX XXXX SQT-4.32 COOLING TOWER PUMP DISCH VALVE FAILS SQT-4.33 CONDD! SATE RECIRC CONTROL VALVE FAILS XXXX l SQT-4.34 H0'IWELL LCV FAILURE XiXX SQT-4.35 DELETED SQT-4.36 PRIMING PUMP VAC BREAKER VALVE FAILS XXXX SQT-4.37 VACUUM PRIMING PUMP TRIP XXXX CRF-1 THRU CRF-14 SW-4.38 IDSS OF ROD DRIVE MG SET XXXX SQT-4.39 FAILURE OF RODS TO MOVE XXXX SW-4.40 IMPROPER BANK OVERLAP XXXX SW-4.41 DROPPED R0D XXXX 1
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BVPS UI SIMULATOR TEST SCHEDULE-SQT TEST TEST DESCRIPTION YEAR TO BE TESTED NUMBER 1991 1952 1993 1994 SQT-4.42 UNCONTROLLED ROD MOTION XXXX SQT-4.43 AUTOMATIC ROD CONTROL SPEED FAILURE XXXX SQT-4.44 T REF FAIWRE XXXX SQT-4.45 IRPI IDSS OF VOLTAGE XXXX SQT-4.46 ROD POSITION STEP COUNTER FAILURE XXXX SQT-4.47 STUCK ROD XXXX SQT-4.48 REACTOR TRIP FAIWRE XXXX SQT-4.49 ROD STOP FAILURE XXXX SQT-4.50 react 0R TRIP XXXX CHS-1 THRU CHS-24
- SQT-4.51 LETDOWN BACK PRESS REGUIATOR FAILURE XXXX SQT-4.52 LETDOWN RELIEF VALVE FAILURE XXXX SQT-4,53 LETDOWN LINE LEAK IN CONTAINMENT XXXX SQT-4.54 PWGGED SEAL WATER INJ FILTER XXXX SQT-4,55 VCr LEVEL CONTROL VALV3 FAILURE XXXX SQT-4.56 - VCr DEGASS LCV FAILURE XXXX SQR-4.57 RCS DILUTION ACCIDENT XXXX SQT-4.58 RCS BORATION ACCIDENT XXXX SQT-4.59 BA TO BLENDER FLOW TRANSMITTER FAILS XXXX SQT-4.60 BLENDER OUTLET FIDW TRANSMITTER FAILS XXXX SQT-4.61 CHARGING HEADER LEAKAGE XXXX SQT-4.62 RCS FILL HEADER LEAKAGE XXXX SQT-4.63 RCP SEAL HEADER FCV FAIWRE XXXX SQT-4.64 EXCESS LETDOWN DIVERT VALVE FAIWRE XXXX SQT-4.65 DELETED SQT-4.66 VOLUMN CONTROL TANK LEAK XXXX SQT-4.67 BLENDER FWW VCT BYPASS VALVE FAIWRE XXXX SQT-4.68 BORIC ACID TRANSFER PUMP TRIP XXXX SQT-4.69 VCr LEVEL TRANSMITIER FAILURE XXXX SQI-4.70 LETDOWN INLET ISOLATION VALVE FAILURE XXXX SQT-4.71 CHARGING FCV FAIWRE XXXX SQT-4.72 LETDOWN HIGH TEMP DIVERT VALV FAILS XXXX EPS-1 THRU EPS-18 SQT-4.73 STATION BLACKOUT XXXX SQT-4.74 UNIT STATION SERVICE TRANS FAIWRE XXXX SQr-4.75 SYSTEM STATION SERVICE TRANS FAI WRE XXXX SQT-4.76 IDSS OF 4160 VOLT BUS XXXX SQT-4.77 LDSS OF 480 VOLT BUS XXXX SQT-4.78 LDSS OF 120 VOLT BUS XXXX SQT-4.79 IDSS OF INVERTER XXXX SQT-4.80 IDSS OF DC BUS XXXX SQT-4.81 GRID VOLTAGE VARIATION XXXX SQT-4.82 DIESEL GENERATOR TRIP XXXX SQT-4.83 DIESEL GEN ERRATIC SPEED CONTROL XXXX G SQT-4.84 DIESEL GEN ERRATIC VOLTAGE REGULATION SQT-4.85 DIESEL GEN OUTPUT BREAKER TRIP XXXX XXXX SQT-4.86 IDAD REJECTION XXXX SQT-4.87 MAIN GEN OUTPUT BREAKER FAILURE XXXX Page 3 j
_.. _ .. _ _ _ _ )
BVPS UI SIMULAM R TEST SCHEDULE (] SQT TEST TEST DESCRIPTION YEAR M BE TESTED NUMBER 1991 1992 1993 1994 SQT-4.88 VOLTAGE ADJUSTER SETPOINT FAILURE XXXX SQT-4.89 MAIN TRANSFORMER FAILURE XXXX WM-1 THRU FWM-16 SQT-4.90 MAIN FEEDWATER PUMP TRIP XXXX SQT-4.91 HEATER DRAIN PUMP TRIP XXXX SQT-4.92 FEEDWATER LEAK IN CONTAINMENT XXXX SQT-4.93 FEEDWATER LEAK OUT OF CONTAINMENT XXXX SQT-4.94 FEEDWATER RECIRC CONTROL VALVE FAILS XXXX SQT-4.95 HP FEEDWATER TUBE LEAK XXXX SQT-4.96 FEED REG VALVE FAILURE XXXX SQT-4.97 FEED REG BYPASS VALVE FAILURE XXXX SQT-4.98 ERRATIC FEEDWATER FIDW CONTROL XXXX SQT-4.99 AUX FEEDWATER PUMP TRIP XXXX SQT-4.100 AUX FEEDWATER FCV FAILURE XXXX SQT-4.101 AUX FEEDWATER PUMP SUCTION LEAK XXXX SQT-4.102 FEEDWATER FIDW TRANSMITTER FAILURE XXXX SQT-4.103 SW GEN PROGRAMMED LEVEL SIG FAILURE XXXX SQT-4.104 SW GEN LEVEL TRANSMITTER FAILURE XXXX MSS-1 THRU MSS-17 !,e) SQT-4.105 STEAM LEAK UPSTREAM MbfV XXXX U XXXX SQT-4.106 STEAM LEAK DOWNSTREAM MSIV SQT-4.107 MSIV DRIFIS SHUT XXXX SQT-4.108 NRV TO IST POINT HEATER STICKS XXXX SQT-4.109 NRV W 3RD POINT HEATER STICKS XXXX SQT-4.110 SG SAFETY FAILS E RESEAT XXXX SQT-4.111 Sm DUMP VALVE FAILS TO OPERATE XXXX SQT-4.112 STEAM DUMP VALVE STICKS XXXX SQT-4.113 ERRATIC T-AVG CONTROL XXXX SQT-4.114 REF TEMP 'ID SE DUMP FAILS XXXX SQT-4.115 SW PRESS SIGNAL M STM DUMP FAILS XXXX SQT-4.116 ATMOSPHERIC Sm DUMP VALVE FAILS XXXX SQT-4.117 ERRATIC CONTROL OF ATH STM DUMP VALVE XXXX' SQT-4.118 STEAM FLOW TRANSMI'1TER FAILURE XXXX SQT-4.119 STM PRESS TRANS FAILS (CONTROL) XXXX SQT-4.120 SW PRESS TRANS FAILS (PROTECTION) XXXX SQT-4.121 STEAM LEAK M AFW PUMP SUPPLY LINE XXXX NIS-1 THRU NIS-8 SQT-4.122 SOURCE RANGE CHANNEL FAILURE XXXX SQr-4.123 INTERMEDITE RANGE CHANNEL FAILURE XXXX SQT-4.124 POWER RANGE CHANNEL FAILURE XXXX XXXX SQT-4.125 INTERMEDIATE RANGE COMP VOLTS FAILURE SQT-4.126 SOURCE RANGE HI VOLT CUTOFF FAILURE XXXX SQT-4.127 SOURCE RANGE FUSE BIDWN XXXX c XXXX SQT-4.128 INTERMEDIATE RANGE FUSE BIDWN SQT-4.129 EOWER RANGE FUSE BIDWN XXXX CCT-1 THRU CCI-4 Page 4
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EVPS UI SIMULATOR TEST SCHEDULE v SQT TEST TEST DESCRIPTION YEAR TO BE TESTED IMMBER 1991 1992 1993 1994 SOT-4.130 CCW PUMP TRIP XXXX SQT-4.131 CCW TCV FAILURE XXXX SQT-4.132 SUPPLY LINE LEAK XXXX SQT-4.133 SUCTION HEADER LEAK XXXX PRS-1 THRU PRS-13 SQT-4.134 PZR SAFETY VALVE LEAKAGE XXXX SQT-4.135 PZR SAFETY VALVE FAIWRE XXXX SQT-4.136 PZR PORV LEAKAGE XXXX SQT-4.137 PZR MRV RESEAT FAI WRE XXXX SQT-4.138 PZR STEAM SPACE LEAK XXXX SQT-4.139 PZR LEVEL TRANSMITTER FAILURE .00(X SQT-4.140 PZR REF LEVEL SIGNAL FAILURE XXXX SQT-4.141 PZR PRESS TRANSMITTER FAILURE XXXX SQT-4.142 PZR SPRAY VALVE FAILURE XXXX SQT-4.143 PZR HEATER CONTROL FAILURE XXXX SQT-4.144 PZR SPRAY VALVE CONTROLLER' FAILS XXXX SQT-4.145 PZR MASTER PRESS CONTROLLER FAILURE XXXX SQT-4.146 PZR LEVEL C0tifROL FAILURE XXXX S RCS-1 THRU RCS-21 (d SQT-4.147 SURGE LINE LEAK SQT-4.148 COLD LEG LEAK XXXX XXXX SQT-4.149 STEAM GENERATOR TUBE LEAK XXXX SQT-4.150 RX VESSEL HEAD FLANGE LEAK XXXX SQT-4.151 RCP SEAL #1 FAILURE XXXX SQT-4.152 RCP SEAL #2 FAILURE XXXX SQT-4.153 RCP SEAL #3 FAILURE XXXX SQT-4.154 REACIOR COOLANT PUMP TRIP XXXX SQT-4.155 REACIOR COOLANT PUMP IDCKED ROIOR XXXX SQT-4.156 REACIOR COOLANT PUMP HIGH VIBRATION XXXX SQT-4.157 REACIOR COOLANT HIGH ACTIVITY XXXX SQT-4.158 FUEL HANDLING ACCIDENT XXXX SQT-4.159 DELETED SQT-4.160 HOT LEG TEMP SENSOR FAILURE XXXX SQT-4.161 DELETED SQT-4.162 COLD LEG TEMP SENSOR FAILURE XXXX SQT-4.153 HOT LEG PRESS TRANSMITTER FAILS XXXX SQT-4.164 IDOP FIDW TRANSHITIEP FAILS XXXX SQT-4.165 INCORE T/C FAILURE XXXX SQT-4.166 RCE BORON CONCENTRAfION XXXX RHR-1 THRU RHR-5 SQT-4.167 RHR PUMP TRIP XXXX SQT-4.168 RHR RELIEF VALVE LEAK XXXX . l SQr-4.169 RHR FILW TRANSMITTER FAILS XXXX SQT-4.170 RHR FILW CONTROL VALVE FAILURE XXXX 'I ' XXXX SQT-4.171 RHR PUMP SHAFT SEIZURE SIS-1 THRU SIS-15 l l
I O& BVPS UI SIMULAMR TEST SCHEDULE SQT TEST TEST DESCRIPTION YEAR E BE TESTED NUMBER 1991 1992 1993 1994 SQT-4.172 REFUELING WATER SE RAGE TANK LEAK XXXX SQT-4.173 QUENCH SPRAY PUMP FAILURE XXXX SQT-4.174 RECIRC SPRAY PUMP FAI WRE XXXX SQT-4.175 RECIRC SPRAY RX TUBE LEAK XXXX SQT-4.176 HHSI PUMP FAIWRE XXXX SQT-4.177 WSI PUMP FAILURE XXXX SQT-4.178 CONTAINMENT IN-LEAKAGE XXXX SQT-4.179 SPURIOUS SI SIGNAL XXXX SQT-4.180 SPURIOUS CI"A" SIGNAL XXXX SQT-4,181 AUTO SI ACTUATION FAILURE XXXX SQT-4.182 ACCUMULAMR LEAK XXXX SQT-4.183 SI SIGNAL FAILS TO SELECTED VALVES XXXX SQT-4.184 SAFETY INJECIION LINE LEAK XXXX SQT-4.185 RWST LEVEL TRANSMITTER FAILURE XXXX SQY-4.186 MSI PUMP SUCTION VALVE FAILURE XXXX TUR-1 THRU TUR-18 SQT-4.187 TURBINE TRIP XXXX SQT-4.188 7 %BINE BEARING HIGH VIBRATION XXXX SQT-4.189 GOVENOR VALVE FAILURE XXXX p) s SQT-4.190 ERRATIC GOVENOR VALVE CONTROL SQT-4.191 THROTTLE (TRIP) VALVE FAIWRE XXXX XXXX SQT-4.192 ERRATIC THROTTLE VALVE CONTROL XXXX l SQT-4.193 EHC PUMP FAILURE XXXX SQT-4.194 TURBINE BEARING LIFT OIL PUMP FAILURE XXXX SQT-4.195 EHC SPEED CONTROL CHANNEL FAILURE XXXX , SQT-4.198 TURBINE RUNBACK FAILURE XXXX SQT-4.197 VALVE POSITION LIMITER FAILURE XXXX SQT-4.198 FIRST STAGE PRESS SIGNAL IDSS TO EHC XXXX SQT-4.199 MSR STEAM SUPPLY VALVE FAILURE XXXX SQT-4.200 FIRST STAGE STM PRESS TRANS. FAI WRE XXXX d 4 l O l Pace 2
APPENDIX 4 DUQUESNE LIGHT COMPANY Volume 2 Nuclear-Group Chapter 12 g) t As Training Administrative Manual Section 12.1 Appendix C APPENDIX C SIMULATOR DISCREPANCY REPORTING AND RESOLUTION A. PURPOSE This instruction outlines the methods to be used to report discrep-ancies between simulator and actual plant response or control room configuration, and identifies the mechanism by which these disc, rep-ancies will be resolved. This instruction should only be used for discrepancies which fall within the defined scope fo simulation and for which resolution will not affect the simulator design data base. Those changes affecting the design data base will be tracked and implemented using Appendix B of this Section. B. PROCEDURE A Trouble Report (TR) Log will be maintained by the simulator staff I in the Simulator Office. Although any staff member observing a q discrepancy may initiate a Trouble Report, TR forms (Figure 12.1.12) Q will be filled out by the Simulator Engineer or the on-shift simulator instructor. The name of the staff member filling out the' form must be included in the ' originator' block. The TR form should be submitted to another member of the Simulator staff for evaluation. If the TR is valid, then it should be logged, numbered, and placed in the Trouble Report System. The TR Index is included as Figure 12.1.14. Active TRs will be reviewed by the Simulator Coordinator and the Supervisor, Simulator Training, on a regular basis for completeness and accuracy. It will be the responsibility of the Supervisor, Simulator Training, to resolve active TRs. Once the problem has been resolved, testing will be performed by a Simulator Staff member. Testing responsibility will normally belong to the simulator staff member who wrote the TR, but may be reassigned to an alternate by the Simulator Coordinator or the Supervisor, Simulator Training. If the TR fails its test, it will be noted on Revision 5 Page 12.14 O O
DUQUESNE LIGHT COMPANY Volume 2 Nuclear Group Chapter 12 O Training Administrative Manual Section 12.1 Appendix C the TR and given to the Simulator- Engineer for corrective action. Once the TR 10 retested satisfactorily, it will be signed off by the responsible. staff member and either the Simulator Supervisor or the Coordinator, Simulator Training. The Index wi:1 be updated by the responsible individual completing the cleared initial /date section of the Index log sheet. O Revision 5 Page 12.15 O
l DUQUESNE LIGHT. COMPANY Volums 2 Nuclear Group Chapter 12 Training Administrative Manual Figure 12.1.12 Page 1-of 2 O SIMULATOR TROUBLE REPORT (TR) l TR No. l TITLE: DATE: ORIGINATOR: PRIORITY: SYSTEM: ; i IC No. PACK: DESCRIPTION OF PROBLEM: O PROPER PERFORMANCE & SUPPORTING DOCUMENTATION: Reviewed by: .. Assigned to: (See back for checklist) Post-fix Testing: Sat U Unsat Instructor Date CLEARED: Simulator Coordinator Supervisor, Date O Simulator Training Revision 5 Page 12.113 l
DUQUESNE LIGHT OOMPANY Volum3 2 Nuclear Group Chnpter 12 Training Administrative Manual Figare 12.1.12 Page 2 of 2 Initial Review:
- 1. Redundancy X or H
- 2. Valid X or H (Person reviewing TR should test the TR.
If it is found a change is needed to the . Data Base, a CR should be written, noted on TR and TR closed out.)
- 3. Clarity - Problem defined completely X or H Supporting documentation lisced
- 4. Update simulator documentation X or E
- 5. Update training material X or E
- 6. Rejected X or H FINAL ACTION l
1 %J l l t l Logbook Date Engineer Date Completed
$O
(/ Revision 5 Page 12.114
APPENDIX 5 DUQUESNE LIGHT COMPANY Volume 2 Nuclear Group Chapter 12
/ ,)
Training Administrative Manual Section 12.1 C' Appendix B APPENDIX B SIMULATOR DATA BASE TRACKING CHANGES AND MODIFICATIONS A ." PURPOSE This instruction outlines the methodology to be used in tracking the design data base of the Beaver Valley Simulator. The intent of the instruction is to ensure consistent logging, routine and modification decisions based on changes to the reference review,t.or plan training requirements. The instruction is based on the requirements of ANS 3.5 (1985) and USNRC Regulatory Guide 1.149. B. PROCEDURE This instruction is divided into two (2) major areas based on the method by which a change to the simulator and its data base is initiated. These two methods are: gm 1. A change to the reference plant configuration which l (j requires a corresponding change or modification to the existing simulator data base.
- 2. A change to the simulator and its data base requested by a member of the Simulator Trianing Center staff, Nuclear Training Department, etc., which has no corresponding l
reference plant change. Examples of this type of change would be the addition of malfunctions or LOAs, changes to the instructor console or instructor's system, etc. For each of the above 21sted methods, the data - base tracking proce-l dure is divided into three (3) action areas: 1) the receipt and l logging of the reference plant changes or a change request from the simulator users (CHANGE INITIATION) ; 2) an evaluation of the infor-mation received (CHANGE EVALUATION); and 3) the implementation and documentation of the change after its completion (CHANGE COMPLE-TION). Each of thest action areas will be tracked and documented using the Simulator Data Base Tracking Form (Figure ' 12.1. 7 ) , which will be maintained as part of the data base. Revision 5 Page 12.9 (3
l DUQUESNE LIGHT COMPANY Volume 2 l Nuclear Group Chapter 12 l lO Training Administrative Manual Section 12.1 l V Appendix B. C. PLANT CHANGES The accomplishment of simulator modifications necessitated by changes to the. reference plant will be performed in- accordance with Flow Chart No. 1 (Figure 12.1.8). Notification of changes to the plant will normally be accomplished through Design Concept Notices (DCNs). The Simulator Training Center is on the distribution list for all DCNs for Beaver Valley.
- 1. Receiot and Locaina (CHANGE INITIATION) l As soon as practicable following the receipt of a DCN or ,
l other initiating document, the Simulator Coordinator, or l his designated Simulator Training Center staff member, will log the following information on the Simulator Data Base Tracking Form:
- a. Document Type
- b. Document Number (If applicable.)
O 2. Evaluation (CHANGE EVALUATION) Each logged document will be reviewed by the Supervisor, Simulator Training, and the Simula:or Coordinator or his/her designee, for potential action based upon license training requirements, ANS 3.5 (1985), and Regulatory ; i Guide 1.149. This review. will include a decision as to whether or not a change to the simulator and/or simulator training materials- is required. The review will be doc _-
- umented using the Review and Evaluation Form (Figure l 12.1.9). If no modificaiton to the simulator is required,
! the Supervisor, Simulator Training, - will inform the Engineering Section, the'DCN and_its associated Review and Evaluation Form will be filed, and the t.ppropriate entries will be made on the Simulator Data Base Tracking Form.
- If it appears that changes to the simulator will be required, the Supervisor, Simulator Training, and the Simulator coordinator or his/her designee, will fill out the Review and Evaluation Form, initiate and ~1og -- a Simu-lator Change Request (Figure 12.1.10), and make the appro- ,
1 Revision 5 Page 12.10 l l l l
l l DUQUESNE LIGHT COMPANY '/M ume 2 ('T Nuclear Group Cha; e 12 ; Gi Training Administrative Manual Section 12.1 Appendix B l 1 priate entries on the Data Base Tracking Form. The DCN, Review and Evaluation Form and Simulator Change Request will then be forwarded to the Simulator Engineer. If a change to the simulator training materials is required, the appropriate entry will be made on the Data Base l Tracking Form, and a copy of the Review and Evaluation Form will be forwarded to the Lead Instructor. It will be the responsibility of the Lead Instructor to enScre that the training materials are modified to reflect the change. Upon receipt of the DCN, Review and Evaluation Form, and Simulator Change Request, the Simulator Engineer will review the material to determine if: 1) additional infor-mation will be required to implement the change; 2) if assistance is required to develop the software associated with the change; and 3) if procurement of the associated hardware is to be perfortred by Engineering. He will then inform the Supervisor, Simulator Training, of the results of the review. The Supervisor, Simulator Training will consult with the Engineering Section to obtain the necessary hardware and/or support. U When all additional information has been received, the Simulator coordinator, and the Supervisor, Simulator Training will make a final evaluation (if required), and establish the scope of the change on the Simulator Change Request.
- 3. Imolementation and Documentation (CHANGE COMPLETION)
Following the completion of the actions outlined above, further actions will be guided using Figure 12.1.8. Following implementation, satisfactory testing of the change, and required data base updating to the Simulator copy of the documentation, the appropriate Data Base Tracking Form entries shall be made, the Simulator Change Request cleared, and the change submitted to the Simulator coordinator for review and approval. The approved change package, including the DCN, supplemental information, Simulator Change Request, and Review and Evaluation Sheet will be filed. Copies of the documentation change (s) will be sent to NERU in accordance with the guidelines in the configuration management program. Revision 5 Page 12.11 m l 1 l l
1 l DUQUESNE LIGHT COMPANY Volume 2 l Nuclear Group Chapter 12 O Training Administrative Manual Section 12.1 Appendix B D. SIMULATOR CHANGES Periodic changes may be required to the simulator which have no corresponding plant change. - Changes of this type normally will be initiated by members of the Simulator Training Center staff or members of the Nuclear Training Department. Changes of this type will be accomplished in accordance with Flow Chart No. 2 (Figure 12.1.11).
- 1. Receint and Loacina (CHANGE INITIATION) .
The person requesting a change to the simulator will fill out a Simulator Change Request and forward it to the Simulator Coordinator. The Simulator Coordinator = or his/her designated Simulator Training Center staff - member will ensure that the Simulator Change Request is logged on the Data Base Tracking Form as an initiating document -by entering:
- a. Document Type (Change Request)
- b. Document Number (Change Request Number)
- c. Date Received
- 2. '
Evaluation (CHANGE EVALUATION) The Simulator coordinator will review each change request, then forward it to the Simulator Engineer. The Simulator Engineer will review the Simulator Change Request to determine if: 1) additional information is requred - to implement the change; 2) if software assistance will be required; and 3) if assistance will be required in procuring hardware. The Simulator change Request will then be returned to the Simulator Coordinator' for resolution of 1), 2), or 3) above. After resolution, the Simulator Coordinator, the Supervisor, Simulator Training, and the Simulator Engineer will set the final scope of the change. The Simulator Engineer will begin implementation of the change. Revision 5 Page 12.12 I
_ _ _ . _ _ _ -.____ _ . ._.. ._._._ _ . ...._ _,. . . . ~ . . _ . _ _ _ _ _ i DUQUESNE LIGHT _ COMPANY ~ Volume 2-Nuclear Group Chapter'12 Section-12.1
~
Training Administrative Manual i Appendix B y
- 3. Imolementation and Documentation Following completion of the actions outlined 'above, further actions will be - guided.: using . Figure 12.1.11.-
Following implementation, satisf actory testing of the , change and required data ~ base updating to the simulator : copy of the documentation, the appropriate Data .-- Base
-Tracking Form i entries will be made, the simulator Change ,
Request - cleared, and the - change package - submitted to_; the' Simulator coordinator"for review and approval. . The change t package, including the- change request ane -any supplemental-information, will be- filed. Copies of - thei documentation change (s) will _ be sent to NERU in accordance with .the guidelines in the configuration management program. LO.
-Revision 5 Page 12.13
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DUQUESNE LIGfT Ca@M1Y Vclume 2 Nuclear Group Qupter 12 p Trainirg 1&dnistrative Ihnual Figare 12.1.9 REVIEW M7D EV/dL%TIQ1 FOIN TITII: REFERDICE DOCUMDTT: THE AIOVE Ptru<u1CED QiMJGE 70 BEAVER VAllIY UNIT #1 WIIL WILLim BE D4CDRPORATED INIO THE BEAVER \%LLEY SDiTLA70R. THE AIDVE i<truiNCED CHMiGE WILL WIII Im RILUIRE QW1GES 70 THE SDULA70R TRADID1G 1RTERIAIS. EVALIJATION: O O l FINAL EVAI11ATION (IF RD7JIRED): i CDORDDR70R - SDUUiIOR TRAINING :IFULA70R SUPERVISOR DATE I t
,a Revision 4 Page 12.118 m
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DUQUESNE LIGfr CIMPANY Voltme 2 Nuclear Group Chapter 12 Training Administrative Ma.M Figure 12.1.10 Page 1 of 2 O SDETLAER OWM RDJUEST OIANGE REQUEST NJ. TITLE: IATE: ORIGINA2tR: PRIORITY: SYSTEM: REVIEWED BY: DATE: l (See checklist on back) DESCRIPTION OF ONGE: 1 O i T J d 7 J t ( m PIETED: . _ _ _ . SDEATOR DGINEER SDEATOR INSTRUCIOR DATE
- O Revision 5 Page 12.110 g
-_--_____-__-<m---J'_-, ,w--- - ~ - - - -, ' + - -
DLQUESNE LIGrr CIMPANY Volume 2 Nuclear Group . Chapter 12-Training Administrative Manual Figure 12.1.10 Page 2 of 2 f INITIAL REVIEW:
- 1. Redurdan:y X or E
- 2. Valid Y or B i
- 3. Clarity - Prublem defined ocmpletely X or U 1
Supporting @ =antation listed
- 4. Update sin 11ator M =antation X or N 4 5. Update training material X or H 6.- Rejected Y or H 4
l l 4
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i FINAL ACTION O i i i 1 d + L W k Date Engineer LO Revision 5 Page 12.111
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3 BVPS TRANSIENT REVIEW COMMITTEE EXPERIENCED SUMMARIES O John Kido Current Position: Simulator Instructor for 7 years. Education / License / Certification: Business College 3 years for Computer Science. SRO certifica - tion Beaver Valley.- Technical Experience: U.S. Nuclear. Navy 6 years, NSSS Instructor for Westinghouse 9
- years, Beaver Valley Simulator
. Instructor 7 years.
Thomas Kuhar Current Position: License Operator Training Supervisor 1 year. Education / License / Certification: College 2 years for Engineering, i' SR0 License Beaver Valley. Technical- Experience: Operatiu.s Instructor 8 years, License Operations Training:2 i O years, License Operations Training Supervisor 1 year. Beaver Valley Operations Experience: Reactor Operator 5 years. Allen J. Lind9rtB Current Position: Simulator Coordinator 4 years, . Education / License / Certification: ' College 6 years for Electrical Engineering and Management,'.SR0 License Zion Power Station, SR0 Certification Beaver-' Valley, R0' License Suton Nuclear Facility. U.S. Nuclear Navy-6 years; Reactor Technical Experience: l Operator Training Saxton Nuclear Facility 9 months, Simulator Instructor for Westinghouse Nuclear Training Center 9' years, Supervisor NVSLSimulator Projects 5 years,~ Simulator Coordinator-and Instructor. Beaver Valley .6 years.
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, EXPERIENCE SUMMARIES i l 1
Lawrence Schad 1 Current Position: Simulator Supervisor 4 years. Education / License / Certification: SR0 Certification Shippingport Atomic Power Station, SR0 License Beaver Valley. Technical Experience: U.S. Nuclear Navy 6 years, Simulator Coordinator 4 years. Beaver Valley Operations Experience: Nuclear Shift Foreman 5 years, Nuclear Shift Supervisor 4 years, Nuclear Station Operations: Supervisor 7 years. James V. Vassello Current Position:- Director Licensing 5 years. Ed uc a ti on/L i cen s e/Ce rt i fi c a t i on : SRO License Beaver _ Valley Unit-I, SR0 License Beaver Valley Unit II, Engineer Training Penn State.- Technical Experience: U.S. Nuclear Navy 7 years, Instructor Shippingport Atomic Power Station 2 years . Director Nuclear Training Beaver _ Valley-11-years. Beaver Valley Operations Experience: Unit I Shift Foreman 2 years, Shift Start-up. Coordinator Unit-I 1 year,'(Assignment) Nuclear Shift Supervisor Unit II 2 years.
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