ML20082K764
| ML20082K764 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/22/1991 |
| From: | Bettinger S COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20082K763 | List: |
| References | |
| NUDOCS 9109030002 | |
| Download: ML20082K764 (900) | |
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{{#Wiki_filter:- ________- - --__---- _ _ _ - _ _ - _ _ - _ - _ _ _ . _ _ _ - . - _ _ _ _ - _ _ - _ - - _ _ - - - _ _ _ _ - _ - - _ _ l t O : 1 t BYRON SIMULATOR l ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT SEPTEMBER,1991 b
'l Subaltted: (M ~~ M hKIL Simulator Fidelity /Cerfification Coordinator Reviewtd: A #8 Byron Simulator Training Supervisor !
M Reviewed: ,Cfrecior of Operations Program Reviewed: // SigatorReviewJoardChairman Approved: bd Production Training Manager
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l BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 TABLE Of CONTENTS SECII0ff 111LE EAGE ; A.I. Simulator Information 4 A.1.1 General 4 : A.I.2.1 Control Room Physical Arrangement 5 A.I.2.2 Panels /fquipment 6 A.I.2.3 Systems 13 ; A.1.2.4 Simulator Control Room Environment 14 - A.I.3 Instructor Interface 15 A.1.3.1 Initial Conditions 15 A.I.3.2 Halfunctions 15 A.I.3.3 Controls Provided for Items Outside of Control Room 18 : A.I.3.4 Additional Special Instructor / 19 f Training features Available . A.I.4 Operating Pro:edures for Reference Plant 21
/~S A.1.5 Changes Since Initial Delivery 22 A.2 Simulator Design Data Base 23 A.3 .
Simulator Tests 24 l A.3.1 Computer Real Time Test 24 i A.3.2 Steady State & Normal Operations Tests 25 , A.3.3 Transient Tests 26 A.3.4 Halfunction Tests 29 A.4 Simulator Discrepancy Resolution and Upgrading Program 32 APPENDIX 1 List of Initial Conditions 33 APPENDIX 2 8.ist of Remote functions 37 APPENDIX 3 List of Acronyms / Abbreviations 38 APPENDIX 4 Byron Simulator Transient Test Review Board Qualifications 42 APPENDIX 5 ANSI /ANS-3.5-1985-Certification Report Cross 45 Reference Matrix APPENDIX 6 Simulator Test Procedure and Halfunction Testing Schedule 48 (BYRONSIM 113/2 08/22/91) . r _, , . , - , - , . .. _- ,.-. - -,-,.,..., _~ . , ,
BYRON SIMULATOR ANS!/ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT SEPTEMBER, 1991
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TABLE OF CONTENTS SECIl0N 111LE EAGE ATTACHMENT 1 Reg. Guide 1.149 Requirements for Dual Plant 49 Simulation Facility ATTACHMENT 2 Steady State / Normal Operations /Real Time / 54 Transient Test Abstracts i ATTACHMENT 3 Simulator _Related Work Request Procedure 69 l ATTACHMENT 4 Simulator Review Board Procedure 70 l ATTACHMENT 5 Simulator and Control: Room Layouts 71 l ATTACHMENT 6- Malfunction Cause and Effects . 72 _ i I h O l
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i l BYRON SIMULATOR ! ANSI /ANS-3.'i-1985 CERTIFICATION REPORT l INITIAL REPORT. SEPTEMBER, 1991 i i A.1 Simulator Information A.I.1 General l l This report is being submitted as the initial certification report i as prescribed in Reg Guide 1.149. The Commonwealth Edison owned I Hestinghouse PWR 4-loop, 3411 MH power plant simulator is used for i i 1 training the Byron plant operators. 3ecause of the near exact i duplication between the two units. It is considered a plant l specific simulator for both Byron Units I and 2, hereafter referred I to as the Byron Simulator. The Dyron Simulator is modeled after ; Byron Unit 1, with Byron Unit I being considered the reference
-l plant. The st_mulator was constructed by Simulation, Systems and 1 Services Technologies (S3 Technologies), between November, 1988 and.
-April, 1991 and declared " Ready for Training" in June, 1991. '
i- Appendix 5 of this report lists a cross reference of sections that- ! satisfy ANSI /ANS-3.5-1985 requirements. O ; ! l
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(BYRONSIH- 113/4 08/22/91) 1
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BYRON SIMULATOR I ANSI /ANS-3.5-1985 CERT!f! CATION REPORT INITIAL REPORT. SEPTEMBER, 1991 i s-l A.I.2.1 Control Room Physical Arrangement i l
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The ohysical arrangement of the simulator's control room duplicates Byron Station with the following exceptions
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- 6. Instructors station is raised 27" off of the floor (13 1/2" higher '
than center desk) and occupies the space that would be center desk l in the reference plant.
- b. IPM11J (back panel) right edge is aligned 2 1/2 feet right of IPM07J right edge (reference plant right edges align). '
- c. OPM033, OPM01J (front panels) left edy' is 6 inches to the left of ;
IPM09] left edge to enhance instructor's view of the IPM01] panel. (reference plant left edges align).
- d. Location of doors and equipment outside of the "at the controls ;
s/ area" (behind the control panele) are different from the reference l plant. ;
- e. U-2 control boards / area is not modeled. ,
These exceptions are considered minor and the requirements of ANSI /ANS-3.5 - 1985 Section 3.2.3, Control Room Environment, have been - met. , P
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(BYRONSIM 113/5 08/22/91)
BYRON S!MULATOR l ANSI /ANS-3.5-1985 CERTIFICATION REPORT i INITIAL REPORT. SEPTEMBER, 1991 O' A.I.2.2 Panels / Equipment i The Byron Simulator contains sufficient operational panels to provide the controls, instrumentation, alarms, and other man-machine interfaces to conduct normal plant evolutions of ANSI /ANS-3.5-1985, section 3.1.1 and respond to the malfunctions of section 3.1.2 for each of the Byron Units to the extent identified in the Certification Report. Attachment i 6 1s the control room layouts of Byron Units 1/2 and the simulator. The i following panels are simulated:
- a. IPM01J Auxiliary Power *
- 1. IPM09J Fire Protection I
- b. IPM02J Main Turbine
- j. IPM11J Containment ,
- c. IPM03J Condensate Isolation
- d. IPM04J Feedwater k. OPH01J General Services
- e. IPH05J Reactor /CVCS 1. OPM02J Ventilation O f. IPM06J Safeguard Systems m. OPM03J Switchyard
- g. **
IPM07J Excorf Nuclear Detectors n. IPM14J RM-11/ESD/SER
- h. IPM08J Incore Nucitar Detectors o. ICX05J Plant Computer
- Host of the Unit 2 components located on these panels are visually simulated only. The Unit 2 switches are present but do not function.
The normal Itghts for Unit 2 components are lit. The Unit 2 Service Air Compressor and Aux Steam Valves are fully simulated.
** The-In Plant Process Computer (PPC) and associated Equipment Status Display (ESD) are currently not totally functional. The hardware for these components is in place and Work Request 08-91-0002 has been written. T.v estimated completion date for this-Hork Request-is 2/92.
The data necessary for normal, abnormal, and emergency evolutions
- required by ANSI /ANS-3.5-1985 is available to the operators by contacting the Simulator Operator (acting as Shift Engineer or Technical Staff Engineer).
(BYRONSIM .113/6 08/22/91)
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BYRON SIMULATOR l ANSI /ANS-3.5-1985 CERTIFICATION REPORT i INITIAL REPORT, SEPTEMBER, 1991 l' n A.I.2.2 Panels / Equipment (Cont.)
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i The Byron Simulator is partially modeled for IPH12J and OPH05J. The following components are modeled: l IPM12J j
- a. Llft Coll Disconnect Switch Box !
- b. Containment Drains (sump) Flow Recorder !
- c. 'RIL vs. Bank Position (8-pen) Chart Recorder f
- d. Boric Acid Storage Tank Level Recorder !
- e. RC (loop) 1A & ID Pressure Recorder !
- f. RC (loop) IB & IC Pressure Recorder
- g. SJAE/GS Condenser flow and Dew Point Recorder !
- h. (N41 and N43) Overpower Recorder {
- 1. (N42 and N44) Overpower Recorder i OPMOSJ Center Desk
-a. GSEP Phones b.- Plant Fire and Evacuation Alarm Pushbuttons The Byron Simulator does not model the following panels / equipment:
IPM10J - Radiation Monitoring and Turbine Supervisory Panel
- a. RM23's Instrumentation not installed (functions provided on RH-ll on IPH14J with use of'a' remote function).
- b. Main Turbine and Feedwater Pump Turbine Supervisory Equipment (instrumentation on back panel not installed - software simulated to extent necessary to drive front panel indications and alarms).
- c. Containment Hydrogen Honitors (instrumentation on back panel-not installed - software simulated to extent necessary to drive front panel indications and alarms).
IPM08J Incore Nuclear Detectors Panel
- a. DC supply to HIDS (installed not modeled).
HIDS picoammeter panel (installed not modeled). b. (BYRONSIM' 113/7 08/22/91) c
t I BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT i INITIAL REPORT, SEPTEMBER, 1991 l r v A.I.2.2 Panels / Equipment (Cont.)- The panels / equipment that are not modeled do not detract from training. ! The tasks related to these panels / equipment are handled administratively l to ensure procedural compliance is maintained. The Turbine-Generator : i Temperature Monitoring System and Radiation Monitors (RM-23's) are f located outside the normal operating area.- In addition, these i r non-modeled panels / equipment do not impact on the ability to perform the ! - normal. plant evolutions in ANSI /ANS-3.5-1985 Section 3.1.1 or respond ; to th'e malfunctions in Section 3.1.2. -I i I 3 O : [
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.( BYRONSIM 113/8 -08/22/91) I
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l BYRON S! HULA 10R ! ANSI /ANS-3.5-1985 CERTIFICATION REPORT [ INITIAL REPORT, SEPTEMBER, 1991 l A.I.2.2 Panels / Equipment (Cont.) Differences between the Byron Simulator and Byron Unit I are: I RYR0lLU:1 SHMAIOR EXEl.AM110ll ! GSEP telephones located on GSEP telephones located on Does not impact training. [
' Center Desk facing OPH02J. Center Desk facing Unit 1. Center desk is not fully -!
simulated. Radio jacks are installed in Radio jacks are not Does not impact training, j control boards. . Installed in control Radio jacks not used by [ boards, station operators. f i Backplates for AF005 valve Backplates for AF005 valve Does not impact training. ! and PZR safety valve and PZR safety valve I
-: Indications installed. Indications are not :
installed. f P Color banding located on Color banding located on Does not impact training. i meter cover. meter face. ! r Manufacturer'slname is on Manufacturer's name may be Does not impact training. I control board components. . missing on control board Due to availability of ! components or may be components (ex. H2 ; different, switches have ! ELECTRO-SWITCH instead of HESTINGHOUSE on backplate). i F
. Screws are-used on name tags Screws are not used on Does not impact training..
f 4 and mimics. nam (: tags and mimics. i a O ! 1 (BYRONSIM 113/9 08/22/91) : i
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BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT. SEPTEM6ER, 1991 O A.I.2.2 Penels/ Equipment (Cont.) Differences between the Byron Simulator and Byron Unit I are: H180tLU2.1 SIWLA10B IXEULMM10tl Calibration stickers are Calibration stickers are Does not impact training. used on name tags, not used on name tags. Bypass-permissive panel. Bypass-permissive panel Does not impact training. Top aligned with rod out located - 1/2" too low. Ilght.. Digital Rod Position Digital Rod Position Does not impact training. Indication panel located
- Indications panel located 1 1/8" abovs NI meters. ~ 1/4" too low.
Annunciator acknowledge Annunciator acknowledge Does not impact training. keyswitch/pushbutton is ~ 1 keyswitch/pushbutton is The switch used on Unit 1
& 1/2" tall with black boot. ~ 3/4" tall with no boot. is no longer available.
The Simulator switch matches that on Unit 2 and ; operates much like'the l Unit 1 switch. CH Blowdown' Totalizer has CH Blowdown Tota 11zer has Does not impact training. l silver cover.- black cover. ! CRT 1 & 2 are 25" monitors CRT 1 & 2 are 27" monitors Does not impact training, j mounted in IPM05J with black mounted in IPM05J with ' plastic' borders. - black metal borders ! des 1gned to provide [ similar. front panel 3-appearance. [
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(BYRONSIM 113/10 08/22/91)
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i BYRON SIMULATOR I ANSI /ANS-3.5-1985 CERTIFICATION REPORT ! INITIAL REPORT. SEPTEMBER, 1991 [ 4 O A.I.2.2 Panels / Equipment (Cont.) i Differences between the Byron Simulator and Byron Unit I t.re: . ERQiLU .1 SIMlLA10R EXELAElloll , 1TR-TS001_is an ITR-TS001 is a Leeds & Does not impact training. l Ester 11ne-Angus recorder Northrup recorder with E-A recorder is obsolete, with'iock and latch on front latch on side and no Front panel appearance is ! cover. Recorder has lock'. Recorder has $1milar. Control Room is mechanical point display, digital point display, pursuing a replacement as a Hod and Simulator will 1 follow, f i t ITR-TS002-1s an 1TR-TS002 ts a Leeds & Does not impact training. ; Ester 11ne-Angus recorder Northrup recorder with E-A recorder is obsolete. I with lock and latch on front latch on side and no Front panel appearance is O cover. : Recorder has lock. Recorder has . similar. Control Room is-l mechanical point display, digital point display. pursuing a replacement as l I a Hod and Simuletor will i follow. .} f HH recorder is a Leed & Frequency Recorder Is a Does not impact training. l
-Northrup 250. Leed & Northrup 2500 and
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-is - 1/2" wider and taller, f t
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Frequency-Recorder is a Leed Frequency Recorder is a Does not impact training.
& Northrup 250. .Leed & Northrup-2500 and l is ~ 1/2" wider and taller. !
Aux Thermocouple panel is Aux Thermocouple panel is Does not impact training. ! installed, not installed. No longer used at Stattor. [ l O ! (BYRONSIN 113/11- 08/22/91) ; i _. ..,._._ _ ..._.__ _ ___.~. ,_._ _.._..__..-._..__ _ _ __- . _ _ -
BYRON S!HULATOR ANSI /ANS-3.5 1985 CERTIFICATION REPORT INITIAL REPORT SEPTEMBER, 1991 (D's / A.I.2.2 Panels / Equipment (Cont.) Differences between the Byron Simulator and Byron Unit I are: BYR0 FLU _1 SIMULAIDH EXPLAMI!ON , Aux building ventilation DP Aux building ventilation Does not impact training. recorder is an DP recorder is a Leeds & E-A recorder is obsolete. ; Esterline-Angus recorder Northrup recorder with Front panel appearance is : with lock and latch on front latch on side and no similar, cover. Recorder has lock. Recorder has mechanical point display, digital point display. Blank cover plates are used Blank cover plates may be Does not impact training. to cover switch and used to cover future holes l Indication cutouts not used. left in panels. Simulator . fx panel cutouts that were ! kJ not required were filled tid smoothed. In addition, these differences do not impact on the ability to perform the normal plant evolutions in ANSI /ANS-3.5-1985. Section 3.1.1 or respond to the malfunctions in Section 3.1.2. These differences are minor in nature and do not detract from training. e i s (BYRONSIM 113/12 08/22/91)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICA110N REPORT INITIAL REPORT,_ SEPTEMBER, 1991 _, t l A.I.2.3 Systems-i The Byron Simulator models most of the plant's control room operated i systems. Systems not modeled by the simulator are: I l a.. Turbine-Generator lemperature Monitoring System (TGIMS). J- l
- b. -Radiation Monitors (RH-23). :
i lhe systems that are.not modeled do not detract from training. The l
-tdsk$ related to these systems are handled administratlVely to ensure !
I procedural compliance is maintained. The, Turbine-Generator Temperature ! Monitoring System and Radiation Monitors (RM-23's) are located outside i
-the normal operating area. In addition, these non-modeled systems do not impact on the ability to perfois the normal plant evoletions in
- j ANS!/ANS-3.5-1985, Section 3.1.1 or_ respond to the malfunt.tions in !
Section 3.1.2. [ i O l I i I f [ O ; 1 s (BYRONSIM 113/13 _08/22/91)
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BYRON $1HULATOR ANSI /ANS-3.5-1985 CERTIf! CATION REPORT INITIAL REPORT, SEPTEMBER, 1991 A.I.2.4 Simulator Control Room Environment The Byron Simui.ator simulates the Byron Unit I control room environment to a high degree. The plant's communication systems are present in the simulator. These include the PA system and GSEP phones, and plant's radio system. The simulator room lighting was constructed to closely match the Byron Unit 1 Control Room. The simulator also has the same type ceiling tiles , to ensure the 11ghtf.3 of the simulator is similar to the Byron Unit 1 - Control Room. The Simulator room lighting intensity will be compared with the Byron Unit 1 Control Room and adjusted as necessary, this is being-tracked under Work Request 08-91-0001. The estimated completion date for this work request is 7/92. j The annunciators in the simulator are the same as those used in the Byron-Unit 1 Control Room (Beta Tone III). The Beta Tone III ; annunciators are adjustable in volume, frequency and tone, and have been-tuned to match these re' .ce plant otsign specs. Presently the ! reference plant has - .onal harmonic background noise. The simulator and reference pit working closely to resolve this slight discrepancy. This n being tracked by Hork Request 08-91-0010. Since the resolution to this work request is dependent oa a ')roposed plant modification, an estimated completion date will be provided when the " Str.tlon determines the status of this modification. The requirements of ANSI /ANS-3.5-1985, Section 3.2.3, Control Room Environment, have been met. - LO (BYRONSIM .113/14= 08/22/91)
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BYRON SIMULATOR j ANSI /ANS-3.5-1985 CERTIFICATION REPORT ! INITIAL REPORT SEPTEMBER, 1991 i O A.1.3 Instructor Interface j I A.1;3.1 Initial Conditions ! The Dyron Simulator has 39 predetermined inttial condttions wtth the i capacity for an additional 61 initial conditions to be used by the instructor when appropriate to store non-protected initial conditions. Additionally, the simulator has 60 backtrack steps to backup the simulator from 10 seconds to I hour. The requirsments of-ANSI /ANS-3.5-1985, section 3.4.1 have been met. All initial conditions can be found in Appendix 1. A.I.3.2 Halfunctions The current malfunction description sheets which serve as the malfunction test abstracts can be found in Attachment 6. O- The Byron Simulator malfunction assessment process utilizes LER's.-plant J -
- spectfic operating expertences (DVR's).-NRC bulletins and circulars and *
- other industry events for determining additions / deletions to the existing simulator malfunctions.
Each accident analyzed in the Byron Updated Final Safety Analysis Report that results in observable indications on Control Room instrumentation is simulated. 4 J O (BYRONSIM 113/15 - 08/22/91)- es ---+m we Em- er, 1..-e-s-e.-w, -w+- ,w-s~..,,-,*
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i i BYRON S!HULATOR i ANSI /ANS-3.5-1985 CERT!rICATION REPORT [ INITIAL REPORT, SEPTEMBER, 1991 ! O' l A.I.3 Instrurtor Interface (Con't) ; The appilcable Attachment 6 malfunctions are cross-referenced to the f ANSI /ANS-3.5-1985, Section 3.1.2 required malfunctions as follows: I i Simulator Halfunctions ! ANSI /ANS-3.5-1985 corresponding to the ANSI f StI11on 3.1.2 tenuirement ! (1) Loss of coolant:- (1) ! (a) - Significant PHR S/G tube leaks (a) TH03 ! (b) -Inside/outside primary (b) CV22, CV24, CV25, t containment TH01. TH07. TH13 l (c) Large/small'Ry coolant (c) TH04 THOS, TH06 - breaks (including demonstration i of saturation condition) i (d) Failure of safety / relief valves (d) THil, TH12
-(2) Loss of instrument air.to the extent (2) IA01, IA02, IA03, IA04.. 1 that the whole system or individual- IA05, IA06 IA07 IA08, .
headers can-lose pressure and affect the IA09 r plant's static ur dynamic performance. (3)- Loss or degraded electrical power to (3) ED01, E002, E003, ED04, the-station, including loss of (ffsjte ED05, E006, E007, ED08, i power, loss of emergency power, loss of ED09 EDIO, ED11, ED12, i emergency ganerators, loss of power to the ED13. EDI4, EDIS, EDI6, ; plant's electrical distribution buses and ED17, EG02, EG03, EG04, q loss of power to the individual instru-- EG06, EG07, EG08. EG09 ! mentation buses (AC as well as DC) that provide power'to control room indicatton or plant control functions affecting. [ the plant's response. ! (4) Loss of forced core-coolant flow due to (4) TH16.- TH17, TH18 i single or multiple pump failure. ;
'(5)- Loss of condenser vacuum including (5) FH36, FH37, FH38, FH39, :
loss of condenser level control. FH40 ! I 1 O ' (BYRONSIM 113/16 08/22/91) i I
l 1 BYRON SIMULATOR ; ANSI /ANS-3.5-1985 CERTIFICATION REPORT i INITIAL REPORT, SEPTEMBER, 1991 ,.~ ( A.I.3 Instructor Interface (Cont.) Simulator Halfunctions . ANSI /ANS-3.5-1985 corresponding to the ANSI l St.clion_.L 1. 2 tenairement (6) Loss of service water or cooling to (6) SH01, SH02, SH03, 3H04, individual components 5H05 (7) Loss of shutdown cooling (7) RH01, RH02 (8) Loss of component cooling system (8) CC04, CC05, CC06, CC07, or cooling to individual components CC08 CC09 (9) Loss of normal feedwater or (9) FH01, FH02, FH03, FH04, normal feedwater system failure FH05. FH06, FH07, FH08, FH09, FH10, FH11, FH12, FH13, FH14, FHIS, FH16 FH17 FH18, FH22, FH23, FH24, TH25, FH26 FH27 FH28, FH29, FH30, FH31, FH32, FH33, FH34, FH35 N (10) Loss of all feedwater (normal and (10) FH41, FH42, FH43, FH44, (V emergency) FH45 (11) Loss of protective system channel (11) RPO4, RP14, RX01, RX06, RX13, RX18, RX21, RX22, RX23, RX24 (12) Control rod failure including stuck (12) RD02, RD03, RD04 rods, uncoupled rods, drifting rods, rod drops, and misaligned rods. (13) Inability to drive control rods (13) RDOS, RD06 (14) Fuel cladding failure resulting in (14) TH08 high activity in reactor coolant or off gas and the associated high radiation alarms (15) Turbine trip (15) TCO2 (16) Generator trip (16) EG01, EGOS (17) Failure in automatic control system (s) (17) RD07, RD09, RD10, RD11, that affect reactivity and core heat RD12, RX17 removal (' (18) Fallure of reactor coolant pressure (18) CV01, CV04, CV05, CV06, and volume control systems (PHR) CV07, CV10, CV11, CV12, CV14, CV15, CV19, CV21, CV23, CV26, CV27, CV28 (BYRONSIM 113/17 08/22/91) 2
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BYRON S!HULATOR ANSI /ANS-3,5-1985 CERTIFICATION REPOR1 INITI AL REPORT , 'u driBCR,1991 A.I.3 Instructor Interface (Cont.) Simulator Halfunctions ANSI /ANS-3.5-1985 corresponding to the ANSI 5t11101J.1,2 tequire m it-(19) Reactor trip (19) RD01 (20) Hain steam line as well as main feed (20) FH19 FW20. FH21, H507, ilne break (both inside and outside M508, MSO9 containment) (21) Nuclear instrumentation failure (s) (21) NIO), NIO2, N103, NIO4, NIO5, NIO6, N107, NIOB, NIO9, nil 0, N111, HI12 ( e) Process instrumentation, alarms, and (22) ANO), AN02, CCO2, CC03, control system failures CV08, CV09. CV16, CV17 CV18, CV20. RX02, RXO3, RXO4, RX05, RXO7, RX08 RXO9, RX10, RX11, RX12, RX14. RX15. RX16, RX19. RX20. RX25, RX26, RX27 RX28, TH14, THIS (23) Passive malfunctions in systems, such (23) FH46, RH06, RH07, RH08, as engineered safety features, emergency RH09. RH10. RH11. 5103, feedwater syster, S104. 5105, 5106, 5107, 5108, S109, S110, 5111 (24) Failure of the automatic reactor trip (24) RPO), RP02, RP03 system (25) Reactor pressure control system failure (25) N/A - BHR including turbine bypass failure (BHR) A.I.3.3 Controls Provided For Items Outside Control Room Appendix 2 is a listing of remote functions (RF) for the simulator. The appropriate RF's exist for systems that are operated outside of the Control Room and that are needed to perform normal plant evolutions and/or the malfunctions required by ANSI /ANS-3.5-1985, section 3.1.1/3.1.2. O (BYRONSIM 113/18 08/22/91) __ _ _ _ _ . _ - _ _ _ _ . _ _ ~_ _ _-___-___.
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BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT. SEPTEiiBER, 1991 A.I.3 Instructor Interface (Cont.) A.1.3.4 Additional Special Instructor / Training features Available
- a. Backtrack As previously mentioned, the Byron Simulator has the capabillty of backtracking. Normally, the students can be backtracked anywhere-from 1 to 60 minutes. However, the time frame for tracking the backtrack snapshots is adjustable so that, if the instructor desires, ht can offer _a backtrack-capability of 60 discrete steps with the amount of
. time between each step ranging from 2 seconds several hours,
- b. Freezing The Byron Simulator has the capability to freeze the dynamic simulation.
- c. Simulator Speed The Byron Simulator has the capabillty to vary the speed of.'*mulation._ The most useful portion of this fe N re is slowing down the simulation to allow the students and instructor to observe and discuss all parameters.- The simulator also has the capability to go into fast time at least 10 times normal speed for RCS and pressurizer Heatup, Xenon, decay heat, condenser evacuation, turbine coastdown, and turbine metal temperatures.
- d. Override The Byron Simulator has the capabillty of falling any control board panel control switch or light-either in the on or off position. In addition, each control board meter can be overridden to-various positions.
O (BYRONSIM 113/19 08/22/91)
i BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT SEPTEMBER, 1991 s N- A.1.3 Instructor Interface (Cont.)
- e. Annunciator The Byron Simulator has the capability of falling any point on the sequence of event recorder (SER) eithei on or off causing the associated annuncistor to either alarm or reset. l
- f. Auxillary The Byron Simulator has an aux 111ary I Instructor instructor's console which can be used when the Console instructor wishes to interact to a large degree with the students. This console is a full scope i instructor's station identical to the main instructor console. ;
- g. Plant Ne Byron Simulator also uses Plant Parameters Parameters wntch give the instructor the flexibility to
('N modify' parameters which are outside the operating staff's control. Examples include atmospheric conditions and electrical grid parameters I r r I (~]) s_ ; i (BYRONSlH 113/20 08/22/91) :
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIf! CATION REPORT INITIAL REPORT, SEPTEMBER, 1991 , O' x- A.I.4 Operating Procedures for Reference Plant r l The procedures used on the Byron Simulator are the station's controlled procedures. Controlled procedures are also available for Instructor use. When required (changes made to plant but not yet incorporated into f simulator) temporary procedure changes are used to accommodate differences in I the simulator and the plant operations. The simulator uses locally generated ; BOL, HOL and FOL axial flux difference curves since the plant's axial flux i difference curves are based on the plant's core age. In addition, only one i set of annunciator response procedures (Byron Unit 1) are utilized during i simulator training, i O , t
/
t
.(BYRONSIM 113/21 08/22/91) ;
~
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 A.I.5 Changes Since Last Report This is the initial certification report, therefore, this section is not appitcable. O 4 L' ) (BYRONSIM 113/22 08/22/91)
BYRON SIHULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT , INITIAL REPORT, SEPTEHDER,1991 ,
~~ !
A.2. Simulator Design Data Base i i
The simulator design database for the Byron $1mulator is Dyron Unit I data with the exception of the core load data. This data was obtained from Unit 2 cycle 2 and was chosen because it was the most recent core load data available at the time of construction. This database includes the data from : which the simulator was designed and built, and on which upgrades and modifications are based. The data base includes design documents, performance data, records, assumptions, simpitfications, derivations and other definable data on which the current design of the simulator hardward and software is based. These documents can be.found in the General Files Pattern Simulator (SIM) file. i f^., t (BYRONSIM 113/23 08/22/91)
BYRON S!HULATOR ANSI /ANS-3.5-1985 CERT!f! CATION REPORT INITIAL REPORI. SEPTEMBER, 1991 f
\
A.3. Simulator Tests A.3.1 Computer Real 111ae Test , Real time test was performed per Appendix A of ANS!/ANS-3.5-1985. The l results of the test are acceptable with the test abstract, being located , in Attachment 2. ! u
?
I i i l l r k l ! l O ! (BYRONSIM 113/24 08/22/91)
- ,, .~~ , , -
,.' , , , - a- , . . - -
BYRON S!HULATOR ANSI /ANS-3.5-1985 CERilf! CATION REPORT INITIAL REPORT, SEPTEMBER, 1991 A.3 Simulator Tests A.3.2 Steady Stats 490 Normal Operations Tests Steady state tests were conducted as part of the Byron Simulator Acceptance Test Procedure (Section 7.1, Steady State Testing) in accordance with ANS!/ANS-3.5-1985. The test results are located in Attachment 2. Normal operations tests were conducted as part of the Byron Simulator Acceptance Test Procedure (Section 3. Power Plant Performance Testing) and the Normal Operations Test in accordance with ANSI /ANS-3.5-1985. The tests results are located in Attachment 2.
- ore performance tests were conducted as part of the Byron Simulator Acceptance Test Procedure (Section 6, Core Physics Testing) i n
(~') accordance with ANSI /ANS-3.5-1985. The test results are located in
\~ > Attachment 2.
Operator performed survelliance tests (Periodic Tests) were conducted as part of the Byron Simulator Acceptance Test Procedure (Section 5, Surveillance Testing) and the Surveillance Test in accordance with ANSI /ANS-3.5-1985. The tests results are located in Attachment 2. t L) (BYRONSIM 113/25 08/22/91)
~ - + ~~r~-
. i BYR0d SlHULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 A.3.3 Transient Tests Transient tests (ATP Sec+1on 7.2) were performed per Appendix B of ANSI /ANS-3.5-1985. Appendix 4 contains the transient Test Review Board Members and Qualifications that are used for transient test comparison.
The results of those tests are as follows with the test abstracts being located in Attachment 2:
- a. Manual reactor trip (7.2.1) Acceptable
- b. , Simultaneous trip of all Acceptable feedwater pumps (7.2.7)
- c. Simultaneous closure of Acceptable main steam isolation valves (7.2.8)
- d. Simultaneous trip of all Acceptable reactor coolant pumps (7.2.4)
- e. Trip of any single Acceptable reactor coolant pump (7.2.3)
O~ f. Main turbine trip Acceptable
- (Maximum power level which does r.,t result in immediate reacter trip) (7.2.2) 9 Maximum rate power . Acceptable ramp (100% down to approximately 90% and back up to 1004) (7.2.9 & 7.2.9A)
- h. Maximum size reactor Acceptable coolant system rupture combined with loss of all offsite power (7.2.5)
- 1. Maximum size unisolable Acceptable main steam line rupture (7.2.10)
- j. Slow primary system depressurization Acceptable to raturated condition using pressurizer relief or
{'E
'- safety valve :ter.k open (inhibited actuation of high baad SI) (7.2.11)
(BYRONSIM 113/26 08/22/91) l
_m...... . , BYRON SIMULATOR l ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 () n
\ A.3 Simulator Tests (Con't)
Comparison data for 7.2.1, 7.2.3, 7.2.7 and 7.2.8 was obtained from Braidwood and Byron Stations Prime Computer System. The Prime's data gathering capability is limited to a once per minute interval. The data for the so .aMr was gathered en a twice per second interval. The differere e 5 .ean rates was taken into account during the comparison piotess. Operator action was permitted during the course of the Transient test when such action was required to be aerformed by the Station's emergency procedures to prevent further degradation. These actions included throttling AF flow (and isolating AF to a faulted S/G) to prevent excessive cooldown and tripping the Reactor Coolant pumps when the appropriata trip criteria was reached. The times that these actions ware performed were recorded on the appropriate test. These actions also enable a more realistic' transient and aid in comparison of actual O plant data. During the ' 'nsient Review Board four minor areas were identified that required investigation and/or corrective action. Work Requests were written for these areas. These work requests were determir.ed to be minor and do not detract from training nor affect the acceptable response of the Transient test. These work requests are as follows: O (BYRONSIM 113/27 08/22/91) l
I BYRON SIHULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O A.3 Simulator Tests (Con't) ESTIMATED COMPLETION _HRl_ DESCRIEllON DATE 08-91-0006 Tave, Tcold, and S/G Pressure were 2/92 higher on the simulator than the plant. 08-91-0007 Stm flow showed a slight spike at 2/92 time of RX trip, 08-91-0008 Zero out power mismatch input of NI's 2/92 to FH Regulating Bypass valves. 08-91-0009 S/G HR level response on the 2/92 simulator was incorrect on power O changes and was less than the Station's on RX trip. O i l (BYRONSIM 113/28 08/22/91)
BYRON SIMULATOR I ANSI /ANS-3.5-1985 CERTIFICATION REPORT l INITIAL REPORT, SEPTEMBER, 1991 C) A.3.. saifenc11en 1est, Malfunctions have been tested in accordance with ANSI /ANS-3.5-1985. The Malfunction Cause and Effect book which serves as the malfunction test abstracts can be found in Attachment 6. Approximately 25% of the malfunctions identifled in Attachment 6 are tested annually as per the testing schedule in Appendix 6. The malfunction tests are located in General Files under file SIM-B-9El. The malfunction test results were satisfartory. In the event that a malfunction fails its test, a Hork Request is written to correct the problem. In the interim, any malfunctions that are unavailable for training are documented on a "Not Authorized for Use" letter which is kept in the Malfunction Description Book. This letter informs each instructor as to which malfunctions are currently unavailable for training. O .e order to avoid negative training which can result when the simulator progresset beyond design limits, the instructor 'y +am computer console displays a message +n the instructor. This message alerts the instructor when selected parameters approach values indicative of events beyono the implemented model or known plant behavior. The requirements of ANSI /ANS-3.5-1985, Section 4.3, Simulator Operating Limits, have been met. A Licensee Event Report (LER) review of Byron events !s performed as part of the plant malfunction assessment process. A summary of the 1989-1990 Byron Unit i LER's that were determined to effect simulation follow: O (BYRONSIM 113/29 08/22/91)
t j BYRON SIMULATOR . ANSI /ANS-3.5-1985 CERTIFICATION-REPORT- '! INITIAL-REPORT, SEPTEMBER, 1991 ;
.f A.3.4 Malfunction Tests (con't) }
LEB - DESCRIPTION C01010115 ) i 8'9-002 Rx Trip Due to 1FH530 Failing Open Tested Satisfactorily l Added to MF-FH09 C & E [ t 89-003; VC & VA ESF Actuations Due to Rad -Tested Satisfactorily with ; Monttors & Loss of 345KV LER 89-006, LER 89-007 , Added to MF-RM03 C & E !
~
89-004 .1A DG Failed to' Start Tested Satisfactorily I Added to MF-EG08 C & E ] !
-3 89-005 DG Inop Due to Deficient Tested Satisfactorily i Post-Maintenance Testing No Specific MF !
k- 89-006 ESF. Actuation Due to 345KV Lcss Tested Satisfactorily f See U-1 LER 89-003
]
89-007 VC Actuation Due to Voltage Transient Tested Satisfactorily . from Lightening See U-1 LER 89-003 i 89-008- AF Suct Press Switch:,s Out of Cal -- Not Tested - Setpoint Failure to Correct for Head Calculation Error - MF-FH24 for= l Xmitter Failure' Tested per MF f Test [ o l
)
l . (BYRONSIM 113/30 . 08/22/91) ;
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. . ~ , . . . . . . . . . . . . . . . . _ . . _ . _ . _ . . . . , _ . , _ . . _ , . . _ . . . . . . . . , _ . _ _ _ . _ , - . . . . . . _ . . . . . , , . . . . , , , , _ - - , . _ . . . . _ , . . . --. -, . . - . - -
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 A,3,4 -Malfunction Tests (con't)
- LER DESCRIfl10N C0tMENTS 90-002- Rx'OTAT RTD Fhiled with I Channel in Tested Satisfactorily Test- Added to MF-RX18 C & E 90-005 Auto Start of 0A FHB Booster Fan Tested Satisfactorily During Calibration Added to MF-RH01 C & E-90-006- Rx Trip on Low-2 S/G Level During DEH Tested Satisfactortly Trouble Shooting Added to MF-TC01 C&E 90-008 Plant S/D Due to Excessive Cnmt Temp Tested Satisfactorily No Specific MF 90-010' 'AF PP Auto Start Due to AMS Failure Tested Satisfactorily No Specific HF 90-011 Rx-Negative Flux _ Rate - Rod Cabinet -Tested-Sa.tisfactorily Power: Loss from Lightening Added to MF-NIO9 C & E Tested Satisfactorily 90-013- Both;SX M/V PPs Inoperable Due to-Personnel Error No Specific flF 904014 FHI-During Safeguards Testing Tested Satisfactorily Added to MF-RP09 C & E
~
T (BYRONSIM 113/31 '08/22/91)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991-- !
; x.-
- b -- A.4 Simulator Discrepancy Resolution and Upgrading
- 1. Identifying logging, correcting _and testing simulator discrepancie*.
Administrative Procedure PTAO-103, Simulator Related Work Request Procedure, describes how an identified simulator discrepancy is resolved. See. Attachment-3 for a copy of PTAD-103, Simulator Related Hork Request Procedure.
- 2. Tracking of. design changes incorporated into the reference plant but not yet incorporated into the simulator.
Production Training Department receives modifications from Byron
-Station. Modifications are reviewed and if a modification is deemed appropriate to change simulation, a Work Request is written in accordance with PTAO-103, Simulator Related Work Request Procedure.-
In q addition .all modifications that require simulator work are approved and tracked by the Simulator Review Board in accordance with PTAO-104, Simitlator Review Board Procedure. See Attachment 4 for a copy of PTAO-104, Simulator ~ Review Board Procedure. I
~
i t f s (BYRONSIM- 113/32 08/22/91)
. .. - _. __ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ . W
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEM8ER,-1991 O APPENDIX 1 LIST OF INITIAL CONDITIONS t 'm 1 (BYRONSIM 113/33 08/22/91) '
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 b V APPENDIX 1 LIST OF INITIAL CONDITIONS (IC's) 1C DESSRIE110ll 1 BOC, COLD SHUTDOWN, ALL RODS IN, RCS TEMP 140', PZR SOLID, XENON FREE, ZERO DECAY HEAT, RH IN S/D L/U, RCPs STOPPED, PZR RELIEFS IN " ARM LOW TEMP", SX & CC IN OPER, CV OPER H/ SEAL INJ, (BGP 100-1, Step 20 & 25) 2 BOC, COLD SHUTDOHN, RCS SOLID, ALL RODS IN, RCS TEMP 110*F, RCS PRESS 330 PSIG, PZR SOLID, BORON 1500 PPH, 10 RCP RUNNING, (BGP 100-1 Step 27) 3* BOC, COLD SHUTDOHN, BUBBLE IN PZR, ALL RODS IN, RCS TEMP 150*F RCS PRESS 325-375 PSIG, PZR LVL 28%, PZR TEMP 430*F, BORON 1500 PPH, STARTING RCPs, (BGP 100-1, Step 27) 4* BOC, HOT SHUTDOHN, PZR SOLID, ALL RODS IN, RCS TEMP 200*F, RCS PRESS 325-375 PSIG, BORON 1500 PPH, RCPs ON, CS PUMPS 003, SX001s IN SERVICE, AF006 & AF017s 005, DRAHING PZR BUBBLE, (BGP 100-1, Steps 29-33) 5 BOC, HOT STANDBY, PLANT HEATUP, ALL RODS IN, RCS TEMP 330*F, RCS PRESS 325-375 PSIG, PZR LVL 28%, BORON 1500 PPM, RCPs ON, SI PUMP 005, I CCP 005, PDP 005, AF0135 CLOSED, REMOVING RH L/U, (BGP 100-1 Step 38) c 6 HOC, HOT STANDBY, PLANT HEATUP, ALL RODS IN, RCS TEMP 495'F, RCS PRESS (' 1118 PSIG, PZR LVL 28%, BORON 1000 PPM, P-11 BLOCKED, RAISING RCS PRESS TO CLEAR P-11, (BGP 100-1, Step 48) , 7' BOC, HOT STANDBY, PLANT STARTUP, ALL RODS IN, RCS NOT NOP, S/G LVLs 61% ON FRBVs, STM DUMPS IN " STEAM PRESS H0DE", RD L EH SYSTEMS S/0, BDPS NOT BLOCKED, PRIOR TO PULLING S/D BANKS, (BGP 100-1, Steps 4-14) 8* EOC, HOT STANDBY, PLANT STARTUP, ALL RODS IN, RCS NOT NOP, S/G LVLs 61% ON FRBVs, STM DUMPS IN " STEAM PRESS H0DE", HSIVs CLOSED & EQUILIZING ON BYPASS (BGP 100-2, Step 3) 9 BOC, RE!.CTOR STARTUP, S/D BANK RODS HITHDRAHN, RCS NOT NOP, STM DUMPS IN
" STEAM PRESS MODE", CRITICAL BORON CONC, HI FLUX AT S/D ALRM NOT BLOCKED, (BGP 100-2, Steps 16-23) 10 MOC, REACTOR STARTUP, S/D BANK RODS WITHDRAHN, RCS NOT NOP, STM DUMPS IN
" STEAM PRESS HODE", CRITICAL BORON CONC, HI FLUX AT S/D ALRM NOT BLOCKED, (BGP 100-2, Steps 15-23) 11 EOC, REACTOR STARTUP, S/D BANK RODS WITHDRAWN, RCS NOT NOP, STH DUMPS IN
" STEAM PRESS MODE", CRITICAL BORON CONC, HI FLUX AT S/D ALRM NOT BLOCKED, (BGP 100-2, Steps 16-23) 12 BOC, 3% POWER, RCS TEMP 560*F, RCS PRESS 2235 PSIG, STM DUMPS IN " STEAM PRESS H0DE", PRIOR TO TURBINE STARTUP, (BGP 100-3, Step 3) b (BYRONSIM 113/34 08/22/91)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT , INITIAL REPORT, SEPTEMBER, 1991 k' APPENCIX 1 LIST OF INITIAL LONDITIONS (IC's) (continued) IC QESCRIPTION 13 HOC, 10% PONER, RCS TEMP 562*F, RCS PRESS 2235 PSIG, STM DdHPS IN " STEAM PRESS H0DE", TURBINE SPEED 1800 RPH, XENON SLOHLY INC, HAIN GEN SYNCHRONIZATION, (BGP 100-3, Steps 14-20) 14' EOC, 15% POWER, RCS NOT NOP, XENON SLOHLY INC, HAIN GEN AT 60 MW, STM DUMPS IN " STEAM PRESS H0DE", HDPs S/D, S/U FHP OPER, R00 CONTROL IN MANUAL, PLACING TDFHP IN OPER, (BGP 100-3, Steps 21-35) 15 BOC, 20% POWER, RCS NOT NOP, XENON SLOHLY INC,, HAIN GEN AT 235 MW, 1 - TDFHP IN OPER, PLACING FRVs IN OPER, PLACING ELECT PLANT IN AT POWER L/U, - (BGP 100-3, Steps 35-39) 16 MOC, 50% P0HER, RCS NOT NOP, HAIN GEN AT 550 MH, XENON EQ'JILIBRIUM, . STEADY STATE POWER, (BGP 100-3, Step 54) 17 HOC, 64% POWER, 12-3-5-3 LOAD FOLLOH FOR 5 HOURS, XEN0h INCREASING
-18 H0C, 77% P0HER, RCS NOT N0P, STEADY STATE POWER, (BGP 100-3, Step 56)
() 19 BOC, 100% POWER, RCS NOT NOP, XENON INC, JUST COMPLETED POWER PAMP, ; (BGP 100-3, Step 59) ; 20 EOC, 100% P0HER, RCS NOT NOP, XENCN EQUILIBRIUM, JUST COMPLETED P0HER RAMP,-(BGP 100-3, Step 59) . 21 BOC, 100% POWER, RCS NOT NOP, XENON EQUILIBRIUH, STEADY STATE FULL BASE LOAD, (BGP 100-3, Step 59) 22 HOC, 100% POWER, RCS NOT NOP, XENON EQUILIBRIUM, JUST COMPLETED POWER RAMP, (BGP 100-3, Step 59) 23 H0C, 30% P0HER, RCS NOT NOP, XENON DEC, 3CD.CBPs OPER, SHAPPING FH TO l UPPER N0ZZLES, ELECT PLANT AT POWER L/U, STEADY STATE P0HER, (BGP 100-4, Steps 11-15) 24* E0C, 15% P0HER, RCS NOT NOP, XENON INC, FH CONTROL ON FRVs, STM DUMPS IN t~
"TAVG H0DE" . ROD CONTROL IN AUTO, 1 TDFHP IN OPER, DOHNP0HER FROM 100%,
SHUTTING DOHN THE TURBINE, (BGP 100-4, Steps 18-30) . L 25* HOC, HOT STANDBY, RCS NOT NOP, MSIVs OPEN, HAINTAINING NOT NOP 4 HOURS AFTER SHUTDOHN FROM 100% POWER l l 26 BOC, COOLDOHN, RCS TEMP 350*F, RCS PRESS 400 PSIG, PZR PORVs IN AUTO, I PRIOR TO RH L/U, (BGP 100-5, Steps 56-57) , I a (BYRONSIM 113/35 08/22/91)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT. SEPTEMBER, 1991 v APPENDIX 1 LIST OF INITIAL CONDITIONS (IC's) (continued) 1C EESCRIEIl08 27 BOC, C00LDOWN TO COLD SHUTDOWN, RCS TEMP 205'F, RCS PRESS 325-375 PSIG, RCPs C & D RUNNING, PLACING PZR SOLID, STOPPING RCPs, DEPRESSURIZING, (BGP 100-5, Steps 56-57) 28 BOC, TRIP RECOVERY, RCS NOT N0P, XENON INC, S/D BANKS h THDRAHN, RX STARTUP 8 HOURS AFTER A TRIP 29* BOL LOOPS PARTIALLY DRAINED 30 Mu , 501 P0HER, XENON 50% EQUILIBRIUM 31 BOC, 90% POWER, XENON EQUILIBRIUM 32' BOC, 100% POWER, SGTR TRANSFER FROM BEP-3, 600 GPM BREAK, (BEP-3, last step) 33' REACTOR CAVITY EMPTY, ALL FUEL ASSEMBLIES IN PLACE, VESSEL HEAD READY TO BE REMOVED 34* REACTOR CAVITY FILLED, READY TO BEGIN REFUELING, ALL FUEL ASSEMBLIES IN PLACE 35* 1/3 0F CORE REFUELED, LAST 10 ASSEMBLIES ARE NOT LOADED 36* SPARE 37 BOC, 23% POWER, RAMP FROM 100% XENON INCREASING (BGP 100-4, step 17) 38 HOC, 100% POWER, 12-3-6-3 LOAD FOLLOH AFTER RAMP UP, XENON DEC 39 HOC RX STARTUP INCORRECT ECC BANK C 0 100 STEPS CRITICALITY These Initial Conditions currently not authorized for use. These IC's are scheduled to be ready for training no later than July, 1, 1992. (BYRONSIM 113/36 08/22/91)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 r I APPENDIX 2 i i REMOTE FUNCTION LISTINGS (LIST OF IN-PLANT LOCAL OPERATOR ACTIONS)
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i b U [ P
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r h O . f (BYRONSIH 113/37 08/22/91)
BYRON SINULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
- APPENDIX 2 REMOTE FUNCTION LISTINGS CC01 CC SUCT HDR XTIE 1CC9459A (0-100%)
100% CCO2 CC SUCT HDR XTIE 1CC9459B (0-100%) 100%- CCO3 RCP A UP BRNG CLR 1CC9493A (0-100%) 50% - 176 gpm CC04. RCP B UP BRNG CLR 1CC9493B (0-100%) 50% - 176 gpm CC05- RCP C UP BRNG CLR 1CC9493C (0-100%) 50%:- 176 gpm CCOE RCP D UP BRNG CLR 1CC94930 (0-100%) 50%'- 176 gpm CC07 CC PP O CONNECT BUS 142 (RI/RO) RO CC08' CC PP O DISCH ISOL OCC9465 (0-100%) 100% CC09 CC PP 1A DISCH ?.CC9466A (0-100%)
- 100%
- ~ T- CC10 CC PP 1B DISCH 1CC9466B ' (0-100%)
\ 100%
CC11 CC DISCH HDR XTIE 1CC9458 (0-100%)' 100%- , CC12 CC HX X-TIE 1CC9467C (0-100%) 100% CC13 U2 SUP/RTN-2CC9473A/B,59B (0-100%) 0% CC14 CC-HDR MAN XTIE OCC9509 (0-100%) 100% CC15 CC SURGE TK DRN:1CC2020B (0-100%)
'0%
CC16 CC SURGE TK DRN 1CC2020A (0-100%) 0% CC17 WM M/U AOV IA 1CC183 (ON/OFF) ON CC18 WM M/U AOV POS 1CC183 (0-100%) 0% CC19 PW M/U AOV IA 1CC182 - (ON/OFF) ON CC20 PW M/U-AOV'POS 1CC182 (0-100%) 0% CC21 CC HX 1 INLET 1CC94708 (0-100%) 100% 1 Mt M ,7 *e1ew--we ' w- > s- c-er
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 \'~) APPENDIX 2 REMOTE FUNCTION LISTINGS C22 CC HX 0 INLET OCC9471B (0-100%) 100% CC23 CC HX 1 INLET 1CC9470A (0-100%) 100% CC24 CC HX 0 OUTLET OCC9471A (0-100%) 100% CC25 TRAIN A CC ISOL 1CC9467A (0-100%) 100% CC26 TRAIN B CC ISOL 1CC9467B (0-100%) 100% ; CC27 RH HX B CC INLET 1CC9504B (0-100%) 100% CC28 RH HX A CC INLET 1CC9504A (0-100%) 100% CC29 RCP A LO BRNG CLR 1CC9494A (0-100%) 50% - 5 gpm CC30 RCP B LO BRNG CLR 1CC9494B (0 100%) 50% - 5 gpm (~'s CC31 RCP C LO BRNG CLR 1CC9494C' (0-100%) \_) 50% - 5 gpm CC32 RCP D LO BRNG CLR 1CC9494D (0-100%) 50% - 5 gpm CC33 RH HX B CC OUTLT 1CC9507B (0-100%) 40% - 5000 gpm ' CC34 RH HX A CC DISCH 1CC9507A (0-100%) 40% - 5000 gpm CC35 EX LTDN HX B CC OUT 1CC9411B (0-100%) 50% - 250 gpm CC36 EX LTDN EX A CC OUT 1CC9411A (0-100%) 50% - 250 gpm CC37 LTDN HX A CC INLET 1CC9452A (0-100%) 100% CC38 SL WTR HX CC INLET 1CC9449A (0-100%) 100% CC39 5TDN HX B INLET 1CC9452C (0-100%) 0% CC40 LTON HX A DISCH 1CC9152B (0-100%) 100% CC41 SL WTR HX OUT 1CC9449B (0-100%) 50% - 230 gpm CC42 CC PP O CONNECT - BUS 141 (RI/RO) RI CC1
,s 2
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT i INITIAL REPORT, SEPTEMBER, 1991 O APPENDIX 2 REMOTE FUNCTION LISTINGS CC43 LTDN HX B CC DISCH 1CC9452D (0-100%) 100% CC44 RCP A THERM BARR 1CC9496A (0-100%) 50% - 40 gpm CC45 RCP B THERM BARR 1CC9496B (0-100%) 50% - 40 gpm CC46 C THERM BARR 1CC9496C (0-100%) 50% - 40 gpm CC47 RLJ D THERM BARR 1CC9496D (0-100%) 50% - 40 gpm CC48 CC TO SFP HX 1CC9503 (0-100%) 15% - 1200 gpm CC49 1CC685 VALVE MANUAL OPERATION (0-100%) 0% O O 3
-i I
BYRON SIMULATOR. ; ANSI /ANS-3.5-1985 CERTIFICATION REPORT ! INITIAL _ REPORT, SEPTEMBER, 1991 j fr T i l APPENDIX 2 REMOTE FUNCTION LISTINGS i i
' I Chol H2 ANALYZER PS-343 STATUS (OFF/ LOW /HIGH) $
OFF i CH02. H2 RECOMBINER CONTROL (OFF/ON) I OFF- ! CH03 RX CAVITY DRN V RE9152A & RE152B (CLOSE/OPEN)' t CLOSE i
- CH04 EMERG HATCH (CNMT INTEGRITY) (0-100%) .';
0% ! CH05 REACTOR HEAD (REINSTALL / REMOVE) [ REINSTALL ' CH06 H2 ANNALYZER PS-344 STATUS (OFF/ LOW /HIGH) ; OFF' j
~ CH07- .XFER CANAL GATE VALVE -(CLOSE/OPEN) ;
' CIOSE -;
CH08- EFUEL BUNDLE IN REFUELING MACHINE (OUT/IN) j OUT- i CH09- CNMT-CHIL 1A CONDENSER PS RESET ' (RESET /HI) ' RESET O. .CH10 CNMT CHIL-la CONDENSER PS RESET
-RESET:
(RESET /HI) O . . > ! . ) i ! I l~ $ k L l 1 4 f , 4 Y
, _ _ . ~ . , - . . ~ ~ - - - _ - . . - ~ . - . . . - - - . . - _ . _.- -
BYRON-SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT
. INITIAL REPORT,-SEPTEMBER, 1991 O APPENDIX 2-RFMOTE FUNCTION LISTINGS-
'CRO1 QUADRANT 1 REFUELING (NO.CHG/DE-FUEL /RE-FUEL)
NO.CHG CR02 QUADRANT 2 REFUELING (NO CHG/DE-FUEL /RE-FUEL) NO'CHG' CR03 QUADRANT 3 REFUELING (NO CHG/DE-FUEL /RE-FUEL) NO CHG
'CR04 QUADRANT 4-REFUELING . (NO CHG/DE-FUEL /RE-FUEL)
NO CHG CROS: l FUEL = ASSEMBLY G-15 REFUELING (OUT/IN) oUT CR06 . FUEL ASSEMBLY J-03 REFUELING (OUT/IN)
= oUT -
CR07- FUEL 1ASSEM3LY H-03-REFUELING (OUT/IN) OUT CR08 FUEL ASSEMBLY G-03 REFUELING (OUT/IN) ;
-OUT -!
CR09 FUEL ASSEMBLY J-02 REFUELING (OUT/IN) OUT-
- /' O . CR10 FUEL' ASSEMBLY-H-02-REFUELING (OUT/IN)
\ OUT CR11' FUEL ASSEMBLY G-02 REFUELING (OUT/IN) i OUT
- i
-CR13 FUEL ASSEMBLY.J-01 REFUELING (OUT/IN) ,
-- OUT :
- CR13 FUEL ASSEMBLY H-01 REFUELING (OUT/IN)
OUT
- CR14 FUEL ASSEMBLY G-01 REFUELING- (OUT/IN)
OUT-I 5 i.
. . _ _ . - . . - - . . - . = . - - . - .
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
.(--
~~
APPENDIX 2 REMOTE FUNCTION L.P. STINGS CS01 1CS022 SPRAY ADD TX DRN (0-100%) 0% CSO2 1CSO40B SAT TO EDUC TRN B (0-100%) 100% CSO3 1CSO40A SAT TO EDUC TRN A (0-100%) 100%
. ?
,e N~/ '
6
. . . . .. .~ .- . . - . - - - - . - - . . - . - - . . . . _ . . - ~ . .
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT,g SEPTEMBER, 1991 APPENDIX 2
-REMOTE FUNCTION LISTINGS CV01 CV8408A PCV-CV131 ISCL- (0-100%)
100%
-CV02 CV8409 PCV-CV131 BYPAGS (0-100%)
0% Cv03- Cv8421 RC FILTER BYPASS (0-100%) 0% CV04 CV8107A-LD RH HX BYPASS ISOL (0-100%) 100% CVOS. CV8108 LD RH-HX MAN BYPASS (0-100%) 0 % -- ,
*CV06 CV8387A 1A'CV PP DISCH BYP (0-100%)
- 0%
CV07- CV8387B 1B-CV PP DISCH BYP (0-100%)- 0% CV08 CV8322A REGEN HX LTDWN (0-100%)
,100% ;
'CV09 :CV8322B-REGEN HX LTDWN (0-100%)
100%: p CV10 CV8402B CV182 MAN ISOL 100% (0-100%) V- . CV11. CV8403 CV182 BYPASS ISOL (0-100%) 0% , CV12- CV8439 MAN EMER ' Bort ISOL (0-100%) 0% l' CV13 .CV8441-PW TO AB FLUSH ISOL~ (0-100%)
.0%-
- CV14 CV8'479A-1A-CV PP RECIRC. (0-100%)
11004' CV15- CV8479B-1B:CV"PP.RECIRC -(0-100%) - 100% i- ~CV16 CV8346-L' FILL CV184-:ISOL (0-100%) L . .
- CV17 .'CV8100 Su RTN ISOL POS (0-100%)
0% CV18 CV8396A SL WTR FILTER _ISOL (0-100%)
'100%4
- CV19. CV8398A SL HX INLET ISOL (0-100%)
100% CV20 .CV8398BISL HX OUTLET ISOL (0-100%) 100% 7
. ~ ~ - - - . , - .- , . , ,
l BYRON SIMULATOR l ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS CV21 CV8399 SL FILTER BYPASS (0-100%) 0% CV22 CV8400 SL RTN HX BYPASS (0-100%) 0% CV23 CVB376 N2 SUPPLY REG STPT (0-50 PSIG) 15 PSIG CV24 CV8410 H2 SUPPLY REGULATOR STPT (0-50 PSIG) O PSIG CV25 CV8419 VCT DRAIN (0-100%) 0% CV26 CV8482 SL RTN-VCT INLET (0-100%) 0% CV27 CV8484 SL RTN-VCT OUTLET ( 0-100-% ) 100% CV28 AB8461 BA TANK SUCT ISOL (0-100%) 100% CV29 AB8459 BAT PP RECIRC (0-100%) 100% ("N CV30 AB8478 AB RECIRC ORIFI BYP (0-100%) ( 0% CV31 AB8457 AB RECIRC ORIFI ISO (0-100%) 100% CV32 AB8465 BAT 2 ISOL (0-100%) 0% CV33 AB8460 BAT PP 1 DISCH (0-100%) 100% CV34 AB8458 AB FILT BYPASS (0-100%) 0% CV35 ABB469 BAT PP O DISCH (0-100%) 0% CV36 AB8468 U2 MINIFLOW ISOL (0-100%) 0% CV37 AB8476 BATCH TK TO PP SUCT (0-100%) 0% CV38 AB8494 MAKEUP TO BATCH TK (0-100%) 0% CV39 BAT PUMP 0/1 CONNECTED (PMP1/PMPO) PMP 1 CV40 CV8104 EMER BOR POS (0-100%) 0% CV41 CV8384A SL INJ FILT A ISOL (0/100%) 100% O 8
BYRON SIMULATOR ANSI,ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS CV42 CV83848 SL INJ FILT B ISOL (0/100%) 0% CV43 1CV012 SL INJ FILT BYP (0/100%) 04 CV44 CV8369A SL INJ ISOL 1A (0/100%) 10% - 10 gpm CV45 CV8369B SL INJ ISOL 1B (0/100%) 10% ~ 10 gpr CV46 CV8369C SL INJ ISOL 1C (0/100%) 10% - 10 gpm CV47 CV8369D SL INJ ISOL ID (0/100%) 10% - 10 gpm CV48 CV8514 CATION BYPASS (0/100%) 100% CV49 CV8516 CATION ISOL (0/100%) 0% CV50 CV8524A MB DEMIN 1A ISOL (0/100%) 100% CV51 CV8524B MB DEMIN 1B ISOL (0/100%) CV52 CV8542 BTRS BYPASS (0/100%)
- 100%
CV53 BTRS DEMIN A STATUS (NORM /BOR/UNBOR) UNBOR CV54 BTRS DEMIN 0 STATUS (NORM /BOR/UNDOR) UNBOR CV55 BTRS DEMIN C STATUS (NORM / DOR /UNBOR) UNBOR CV56 BTRS DENIN D STATUS (NORM /BOR/UNBOR) UNDOR CV57 BTRS DEMIN E STATUS (NORM /BOR/UNBOR) UNBOR CV58 CHILLER PP 0/1 CONNECTED (PUMP 1/PUMPO) PUMP 1 CV59 AB8465 BAT PP O SUCTION (0-100%) 0% CV60 AB8468 BAT PP O DISCH (0-100%) 0% CV61 CV8455 PW TO CV M/U (0-100%) 0% CV62 CV8464A PW ORIFI TO CV M/U (0-100%) 100% O o 1
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT ! INITIAL REPORT, SEPTEMBER, 1991 ' 6 r
^"' J-APPENDIX 2 :
REMOTE FUNCTION LISTINGS i l t CV63 CV8467A LTDN HX 1A OUTLET (0-100%) [ 300% ! CV64- CV8467B LTDN HX 1B OUTLET (0-100%) i 100% '
, CV65 CV8432 MAKEUP TO RWST (0-100%)
0% l' CV66- CV8350 LP DRN HDR TO RCDT (0-100%) 0% , CV67 8486A SL INJ FILT 1A DRN (0-100%) : 0% CV68 CV8486B SL.INJ FILT 1B DRN (0-100%) 0% ' CV69 RAD MUNITOR BYPASS 1FI132 (0-100%) , 30% - 3 gpm ; CV70 CV112B CV PP VCT SUCT POS (0-100%) 100% , CV71 - CV112C CV.PP VCT SUCT POS (0-100%) ! 100% !
/~'y CV72- CV112D CV PP VCT SUCT POS (0-100%)
v 0% , CV73 CV112E CV PP VCT SUCT.POS (0-100%) ,
-0% ;
CV7 4 - CV8804A CV PP RH SUCT POS (0-100%) ! 0% CV75 1A CV PP AUX L.O. PP (OFF/ON) OFF 1 CV76 1B CV PP AUX L.O. PP (OFF/ON) ., OFF ! CV77 CV8321A/8392A REGEN HX CHG (CLOSE/OPEN) ; OPEN ' CV78 CV8321D/8392B REGEN HX CHG (CLOSE/OPEN) OPEN CV79 BORON CONC MASTER RESET (0-2100 PPM) - 2000 PPM , CV80 OPWO2PA PUMP CONTACT 3-4 ON MUX 4 LOW (NORMAL /OPEN) - VCT LEVEL ! NORMAL CV81 1CV8355A/D VALVE MANUAL OPERATION (0-100%) , (CONTROLS ALL 4 VALVES) 04 CV82 1AB03P PUMP CONTACT 3-4 ON MUX 5 LOW (NORMAL /OPEN) NORMAL , i A 10 t
BYRON SIMULATOR f ANSI /ANS-3.5-1985 CERTIFICATION REPORT
- INITIAL REPORT, SEPTEMBER, 1991
.r'] -
APPENDIX 2 i REMOTE FUNCTION LISTINGS l CWO1 CW M/U PPS RECIRC CNTRL (0-100%) , 20% t b g 9 h
?
I I r t b e O i 11 l -
BYRON SIMULATOR , ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
.g .
APPENDIX 2 REMOTE FUNCTION LISTINGS i l ED001 0621 LINE DISCONNECT (CLOSE/OPEN) . CLOSE l ED002 15501 LINE DISCONNECT (CLOSE/OPEN) , CLOSE ! ED003 U-1 MAIN-XFMR DISCONNECT (CLOSE/OPEN) r OPEN ! ED004 U-2 MAIN XFMR DISCONNECT (CLOSE/OPEN) CLOSE . ED005 UNIT 1 SAT. DISCONNECT (CLOSE/OPEN) I CLOSE + ED006' BUS 241 AVAIL TO BUS 141 (CLOSE/OPEN) ; OPEN , ED007 BUS 242 AVAIL TO BUS 142 (CLOSE/OPEN) i OPEN i' ED008 BUS 133U1 FEED BREAKER (CLOSE/OPEA) CLOSE-ED009 BUS 134U1 FEED-BREAKER (CLOSE/OPEN) I CLOSE
={ '. ED010 U-1 FEED TO BUS 033Z1 (CLOSE/OPEN) l
[ CLOSE ED011 U-2 FEED.TO BUS 033Z1 (CLOSE/OPEN) , OPEN ED012 U-2 FEED TO BUS-033W (CLOSE/OPEN) e OPEN ED013 U-2 FEED TO BUS 034W (CLOSE/OPEN) 'l OPEN ED014 CHARGER 123 FROM BUS 134Z (CLOSE/OPEN) : CLOSE:
- ED015 DC SUS 123 FEED BREAKER (CLOSE/OPEN) l CLOSE~ !
ED016 IC BUS 111A FEED BREAKER (NORM /OPEN/ RESERVE). ,' NORM ED017 IC BUS 112A FEED BREAKER (NORM /OPEN/ RESERVE) < NORM : ED018 IC BUS 113A FEED BREAKER (NORM /OPEN/ RESERVE) [ NORM ED019 IC BUS 114A FEED BREAKER (NORM /OPEN/ RESERVE) ; NORM. ED020 CHARGER 111 FEED BREAKER (CLOSE/OPEN) CLOSE ; f u : 12 i
. . . - . - - _. ____________-_--______-__-___-____5
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT l INITIAL REPORT, SEPTEMBER, 1991 O APPENDIX 2 REMOTE FUNCTION LISTINGS ED021 CHARGER 112 FEED BREAKER (CLOSE/OPEN) CLOSE ED022 DC BUS 113 SUPPLY FUSE (INSTALLED / REMOVED) INSTALLED ED023 DC BUS 114 SUPPLY FUSE (INSTALLED / REMOVED) INSTALLED ED024 DC BUS 111 TO INV 111 (CLOSE/OPEN) CLOSE ED025 DC BUS 111 TO INV 113 (CLOSE/OPEN) CLOSE ED026 DC BUS 112 TO INV 112 (CLOSE/OPEN) CLOSE ED027 DC BUS 112 TO INV 114 (CLOSE/OPEN) CLOSE ED028 BUS 156 LOCKOUT RELAYS (NORM / RESET) NORM ED029 BUS 157 LOCKOUT RELAYS (NORM / RESET) NORM ED030 BUS 158 LOCKOUT RELAYS (~ x HORM (NORM / RESET) ED031 BUS 159 LOCKOUT RELAYS (NORM / RESET) NORM , ED032 BUS 141 LOCKOUT RELAYS (NORM / RESET) NORM ED033 BUS 142 LOCKOUT RELAYS (NORM / RESET) NORM ED034 BUS 143 LOCKOUT RELAYS (NORM / RESET) NORM ED035 BUS 144 LOCKOUT RELAYS (NORM / RESET) NORM ED036A AC BUS 111A:01:1PM07J (CLOSE/OPEN) CLOSE ED036B AC EUS 111A:02:1PA09J (CLOSE/OPEN) CLOSE ED036C AC-BUS 111A:03:1PA01J (CLOSE/OPEN) CLOSE ED036D AC BUS 111A:05:1PA27J (CLOSE/OPEN) CLOSE ED036E AC BUS 111A:06:1PA11J (CLOSE/OPEN) CLOSE ED036F AC BUS 111A:07:1PA07J (CLOSE/OPEN) CLOSE O l 13
1 BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS ED036G AC BUS 111A:08:1PA10J (CLOSE/OPEN) CLOSE ED036H AC BUS 111A:09:1PA13J (CLOSE/OPEN) CLOSE ED036I AC BUS 111A:10:1PM06J (CLOSE/OPEN) CLOSE ED036J AC BUS 111A:11:1PA45J (CIASE/OPEN) CLOSE ED036K AC BUS 111A:12:1PA09J (CLOSE/OPEN) CLOSE ED036L AC BUS 111A:16:1PA05J (CLOSE/OPEN) CLOSE ED036M AC BUS 111A:18:1PM06J (CLOSE/OPEN) CLOSE ED037A AC BUS 112A:01:1PM01J (CLOSE/OPEN) CLOSE ED037B AC BUS 112A:02:1PA09J (CLOSE/OPEN) CLOSE (] ED037C AC BUS 112A:03:1PA02J (CLOSE/OPEN) V CLOSE ED037D AC BUS 112A:06:1PA16J (CLOSE/OPEN) CLOSE ED037E AC BUS 112A:07:1PM07J (CLOSE/OPEN) CLOSE ED037F AC BUS 112A:08:1PM10J (CLOSE/OPEN) CLOSE ED037G AC BUS 112A:11:1PA45J (CLOSEl 7EN) CLOSE ED037H AC BUS 112A:16:1PA06J (CLOSE/OPEN) CLOSE ED037I AC BUS 112A:18:1PM06J (CLOSE/OPEN) E CLOSE ED03BA AC BUS 113A:01:1PM07J (CLOSE/OPEN) CLOSE ED038B AC BUS 113A:02:1PA09J (CLOSE/OPEN) CICSE ED038C AC BUS 113A:03:1PA03J (CLOSE/OPEN) CLOSE ED03BD AC BUS 113A:06:1PA15J (CLOSE/OPEN) CLOSE ED038E AC BUS 113A:07:1PM07J (CLOSE/OPEN) CLOSE O 14
BYRON SIMULATOR ANSI /ANS-3.5-191'. ERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 y \~/ APPENDIX 2 REMOTE FUNCTION LISTINGS ED038F AC BUS 113A:08:1PA10J (CLOSE/OPEN) CLOSE : ED038G AC BUS 113A:1631PA07J (CLOSE/OPEN) CLOSE ED038H AC BUS 113A318:1PM05J (CLOSE/OPEN) CLOSE ED039A AC BUS 114A:01:1PM07J (CLOSE/OPEN) CLOSE ED039B AC BUS 114A:02:1PA09J (CLOSE/OPEN) CLOSE ED039C AC BUS 114A:03:1PA04J (CLOSE/OPEN) CLOSE , ED039D AC BUS 114A:05:1PA28J (CLOSE/OPEN) CLOSE ED039E AC BUS 114A:r6:1PA12J (CLOSE/OPEN) CLOSE ED039F AC-BUS 114A:07:1PM07J (CLOSE/OPEN) . CLOSE ('T ED039G AC BUS 114A:08:1PA10J (CLOSE/OPEN) (_) CLOSE ED039H AC BUS 114A:09:1PA14J (CLOSE/OPEN)
+ CLOSE -ED039I AC BUS 114A:10:1PM06J (CICSE/OPEN)
CLOSE ED039J AC BUS 114A:11:1PA34J (CLOSE/OPEN) CLOSE ED039K AC BUS 114A:12:1PA10J (CLOSE/OPEN) CLOSE ED039L AC BUS 114A:16:1PA08J (CLOSE/OPEN) CLOSE ED039M AC BUS 114A:18:1PM05J (CLOSE/OPEN) CLOSE ED040A DC MCC 123:CG1:1WG046 (CLOSE/OPEN) CLOSE ED040B DC MCC 123:DG2:1CX08J (CLOSE/OPEN) CLOSE ED041A DC BUS 111:BF1-01:1IP05E (CLOSE/OPEN) CLOSE ED041B DC BUS 111:BF1-12:1RD05E (CLOSE/OPEN) CLOSE ED041C DC BUS 111:BF1-14:1PM11J (CLOSE/OPEN) CLOSE (3 ' V 15
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT ' INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS ED041D DC BUS 111:BF1-16:1PLO7J (CLOSE/OPEN) CLOSE ED041E DC BUS 111:BR1-01:1IP07E (CLOSE/OPEN) CLOSE ED041F DC BUS 111 BR1-05:1DC10J (CLOSE/OPEN) , CLOSE ED041G DC BUS 111:BR1-11:1PLO7J (CLOSE/OPEN) CLOSE ED041H DC BUS 111:BR1-12:1AF004A (CLOSE/OPEN) CLOSE ED041I DC BUS 111:BR1 13:1PA27J (CLOSE/OPEN) CLOSE ED041J DC BUS 111:BR1-14:1FA13J (CLOSE/OPEN) CLOSE ED041K DC BUS 111:BR1-15:1PM02J (CLOSE/OPEN) CLOSE ED041L DC BUS 111:BR1-17:1PLO7J (CLOSE/OPEN) CLOSE ' (g ED041M DC BUS 111:BR1-18:1PA31J (CLOSE/OPEN) (_) CLOSE ED042A DC BUS 112:BF1-01:1IP06E (CLOSE/OPEN) 1 CLOSE ' l ED042B DC BUS 112:BF1-13:1RD05E (CLOSE/OPEN) , CLOSE ED042C DC BUS 112:BF1-14:1PM11J (CLOSE/OPEN) CLOSE ED042D DC BUS 112:BF1-16:1PLOBJ (CLOSE/OPEN) CLOSE ' ED042E DC BUS 112:BF1-19:1PJ08J (CLOSE/OPEN) CLOSE ' ED042F DC BUS 112:BR1-01:11P08E (CLOSE/OPEN) t CLOSE ED042G DC BUS 112:BR1-03:1DC11J (CLOSE/OPEN) CLOSE-ED042H DC BUS 112:BR1-13:1PLOBJ (CLOSE/OPEN) , CLOSE ED042I DC BUS 112:BR1-14:1PA14J (CLOSE/OPEN) CLOSE , l ED042J DC BUS 112:BR1-15:1PA32J (CLOSE/OPEN) CLOSE ED042K DC BUS 112:BR1-16:0PM02J (CLOSE/OPEN) CLOSE t P 16 ,
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 g-APPENDIX 2 REMOTE FUNCTION LISTINGS ED042L DC SUS 112 BR1-19:1AF004B (CLOSE/OPEN) CLOSE ED042M DC BU4 112 BR1-20:1PA28J (CLOSE/OPEN) CLOSE ED043A LC BUS 113 EF1-03:1PA31J (CLOSE/OPEN) CLOSE ED043B DC BUS 113 EF1-10:1ED03E (CLOSE/OPEN) CLOSE ED043C DC BUS 113 EF1-148'A>7J (CLOSE/OPEN) CLOSE ED0430 DC BUS _113 EF1-16:1PMG2J (CLOSE/OPEN) CLOSE EDDS3E DC BUS 113*EF1-17:1PM04J D1 LOSE /OPEN) CLOSE ED0430 DC BUS 11?tEPP.-18:1PM01J (CLOSE/OPEN) CLOSF. ED043G LF. BUS 113:ER1-02:1DC12J (CLOSE/OPEN) l CLOSE ED043H DC DUS 113 ER1-03:1PM02J L (_,
/} CLOSE (CLOSE/OPEN)
ED043I DC BUS 113:ER1-09:1PM11J (CLOSE/OPEN) CLOSE
- ED043J DC BUS 113 ER1-13:0PM03J (CLOSE/OPEN)
CLOSE ED043K DC BUS 113 ER1-18:0PM02J (CLOSE/OPEN) CLOSE ED043L DC BUS 113:ER1-19:1PA26J (CLOSE/OPEN) CLOSE ED043M DC BUS 113 ER1-20:0PM01J (CLOSE/OPEN) CLOSE i ED044A DC BUS 114 EF1-05:1PA42J (CLOSE/OPEN) CLOSE ( E0044B DC BUS 114 EF1'12:1RD03E (CLOSE/OPEN) l CLOSE ED044C DC BUS 114:EF1-17:1PM04J (L(GrE/OPEN) CLOSE ED044D DC BUS 114 EF1-18:1PM02J (CLOSE/OPEN) CLOSE l ED044E DC BUS 114 EF1-20:1TGC7JB (CLOSE/OPEN) CLOSE l ED044F DC BUS 114 ER1-07:1DC13J (CLOSE/OPEN) l CLOSE U 17
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS ED044G DC BUS 114tER1-10:1PM11J (CLOSE/OPEN) CLOSE ED044H DC BUS 114 ER1-14:0PM03J (CLOSE/OPEN) CLOSE ED044I DC BUS 114 ER1-16:1PA2AJ (CLOSE/OPEN) CLOSE ED044J DC BUS 114 ER1-17:0PA01J (CLOSE/OPEN) CLOSE ED045A BUS 156:02:1RC01PB (NORM /CLOSE/OPEN) OPEN ED045B BUS 156:03:1HD01PR (NORM /CLOSE/OPEN) OPEN ED045C BUS 156 04:1FWO1PA (NORM /CLOSE/OPEN) OPEN ED046A BUS 157 01:1RC01PA (NORM /CLOSE/OPEN) OPEN ED046B BUS 157:03:1HD01PA (NORM /CLOSE/OPEN) OPEN
- b. SC BUS 157:04:RSH (NORM /CLOSE/OPEN)
(~)N (_ CLOSE ED046D BUS 157:05:1HD01PC (NORM /CLOSE/OPEN) OPEN ED047A BUS 158:01;1CD05PB (NORM /CLOSE/OPEN) OPEN ED047B BUS 158:03:1CD05PD (NORM /CLOSE/OPEN) OPEN ED047C BUS 158:05:1RC01PC (NORM /CLOSE/OPEN) OPEN l ED048A BUS 159:02:1CD05PA (NORM /CLOSE/OPEN) l OPEN l ED048D BUS 159:03:1CD05PC (NORM /CLOSE/OPEN) OPEN ED048C BUS 159:04:1FWO2P (NORM /CLOSE/OPEN) OPEN ED04ED BUS 159:05:1RC01PD (NORM /CLOSL/OPEN) OPEN ED049A BUS 141:02:1SX01PA (NORM /CLOSE/OPEN) CLOSE ED049B BUS 141:03:1SIO1PA (NORM /CLOSE/OPEN) OPEN
$7049C BUS 141:04:1RH01PA (NORM /CLOSE/OPEN)
CLOSE (~h y 18
4 BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT : INITIAL REPORT, SEPTEMBER, 1991
/) l APPENDIX 2 REMOTE TUNCTION LISTINGS !
ED049D BUS 141 06 DG1A (NORM /CLOSE/OPEN) OPEN ' ED049E BUS 141:08:1AF01PA (NORM /CLOSE/OPEN) j OPEN i ED049F BUS 141:09:1CS01PA (NORM /CLOSE/OPEN) : OPEN ED049G BUS 141:11:1CV01PA (NORM /CLOSE/OPEN) CLOSE ED049H BUS 141:12:1CC01PA (NORM /CLOSE/OPEN) t CLOSE ED049I BUS 141:18:0CC01P (NORM /CLOSE/OPEN) OPEN ED050A BUS 142:02:1SX01PB (NORM /CLOSE/OPEN) , OPEN , ED050B BUS 142:03:1SIO1PB (NORM /CLO9E/OPEN) OPEN ED050C BUF 142:04:1RH01PB (NORM /CLOSE/OPEN) ' OPEN
/~ ED050D BUS 142 06 DG1B (NORM /CLOSE/OPEN)
OPEN ED050E BUS 142:08:1(J01PB (NORM /CLOSE/OPEN) OPEN , t ED050F BUS 142:09:1CC01Po (NORM /CLOSE/OPEN) CLOSE ED050G EUS 142:10:1CV01PB (NORM /CLOSE/OPEN) OPEN ED050H BUS 142:12:0CC01P (NORM /CLOSE/OPEN) , OPEN ED051A BUS 143:03:1HTRA&D (NORM /CLOSE/OPEN) OPEN ED051B BUS 143:08:0WS01PA (NORM /CLOSE/OPEN) CLOSE l ED051C BUS 143:09:1CWO1PA (NORM /CLOSE/OPEN) l OPEN ED051D BUS 143:12:1CH01PC (NORM /CLOSE/OPEN) 3 OPEN ED051E BUS 143:15:0SA01C (NORM /CLOSE/OPEN) i OPEN ED052A BUS 144:03 HTRB&C (NORM /CLOSE/OPEN) OPEN ED0523 BUS 144:04:1SA03C (NORM /CLOSE/OPEN) ! CLOSE , i 19
y.. _... _. . _ . _ _.. _ ..- ._ _ _ _ _. _. _ _ - - _ . . _ _ - - _ _ _ _ t -- BYRON SIMULATOR , ANSI /ANS-3.5-1985 CERTIFICATION REPORT ! INITIAL REPORT, SEPTEMBER, 1991 l 1 l APPENDIX 2 l REMOTE FUNCTION LISTINGS f i l ED052C BUS 144 07:OWS01PB (NORM /CLOSE/OPEN) OPEN ! ED052D-BUS 144* lit 1CWO1PB (NORM /CLOSE/OPEN) l OPEN { ED053A 131X1:B4 1CS001A (CLOSE/OPEN) {
-CLOSE ;
ED053B 131X18C1 1CS009A (CLOSE/OPEN) CLOSE ED053C 131X1tD4:1AF013A (CLOSE/OPEN) , CLOSE j ED053D 131X1tE1:1AF013B (CLOSE/OPEN) ; CLOSE t ED053E 131X1tE2:1AF013C (CLOSE/OPEN) l CLOSE i ED053F 131X1:E321AF013D (CLOSE/OPEN) I CLOSE [ ED053G 131X1:F2 1RH610 (CLOSE/OPEN) l CLOSE ED053H 131X1:F3 1RH8716A (CLOSE/OPEN) CLOSE ; ED053I 131X1:F4 1SI8801A- (CLOSE/OPEN) CLOSE ,: ED053J 131X1:G4 ISI8807A. (CLOSE/OPEN)- f CLOSE j ED053K-131X1tH4:1SI8821A (CLOSE/OPEN) ! CLOSE { ED053L 131X1tK1:1CV8106 (CLOSE/OPEN) ! CLOSE- l ED053M 131X1:K2:ICS019A (CLOSE/OPEN) - CLOSE ! ED053N 131X1:K3:ICC9412A -(CLOSE/OPEN) -! CLOSE .! ED0530 131X1tK4:1CV112D (CLOSE/OPEN)- l CLOSE l ED053P 131X1 M3:1SI8811A (CLOSE/OPEN) ! OPEN i ED054A 131X1:L208 (120) : OPM02J (CLOSE/OPEN) l CLOSE i ED054D 131X1 L216 (120) :1PA51J (CLOSE/OPEN) ! CLOSE ! ED054C 131X1:L218 (120):OPR31132 (CLOSE/OPEN) j CLOSE , v 1 0 9 20 4 i I
.. _. _- . . . - _ . _ . . _ . . _ . . _ _ ,_ . _ . _ _ - - . , _ . . , _ . _ . _ _ . _ . _ - _ _ , - ~ , _ .._-a -.._ . _ a. _ J
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 (3 APPENDIX 2 REMOTE FUNCTION LISTINGS ED054D 131X1 L221 (120) : 1PA03J (CLOSE/OPEN) CLOSE ED054E 131X1 L224 (120) :1PA33J (CLOSE/OPEN) CLOSE ED055A 131X1AIN1:1SI8920 (CLOSE/OPEN) CLOSE ED055B 131X1AIN2:1SI8814 (CLOSE/OPEN) CLOSE F.0055C 131X1A P1:1 SIB 802A (CLOSE/OPEN) OPEN ED055D 131X1A P2:1SI8809A (CLOSE/OPEN) CLOSE ED055E 131X1A P3:1SI8806 (CLOSE/OPEN) OPEN ED055F 131X1A P4:1SI8835 (CLOSE/OPEN) OPEN ED055G 131X1A Q1:1SI8812A (CLOSE/OPEN) CLOSE ' ( ED055H 131X1A Q2:1SI8840 (CLOSE/OPEN) l
's OPEN ED056A 131X2 B1:1RII701A (CLOSE/OPEN)
. .CLOSE ED056B 131X2 B4:1RH8702A (CLOSE/OPEN)
OPEN ED056C 131X2:C3:1VQ001A (CLOSE/OPEN) OPEN ED056D 131X2:C41RC8003D (CLOSE/OPEN) OPEN ED056E 131X2:C5:1RC8003A (CLOSE/OPEM) OPEN ED056F 131X2:F1:1VQOO2A (CLOSE/OPEN) OPEN ED056G 131X2 G1:1RC8001A (CLOSE/OPEN) OPEN' Er056H 131X2 G2:1RC8001B (CLOSE/OPEN) OPEN ED056I 131X2 G3 1RC8001C (CLOSE/OPEN) OPEN ED056J 131X2:04:1RC8001D (CLOSE/OPEN) OPEN ED057A 131X2 F220 (120):1PA33J (CLOSE/OPEN) CLOSE O 21
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS ED057B 131X2 F221 i..0):1PA01J (CLOSE/ OPE!Q CLOSE ED057C 131X2 F212 (120):1PM06J (CLOSE/OPEN) CLOSE ED058A 131X2A A2: SIB 808D (CLOSE/OPEN) OPEN ED058B 131X2A A3:SI8808A (CLOSE/OPEN) OPEN ED058C 131X2B A5 RY8000A (CLOSE/OPEN) CLOSE . ED058D 131X2B:B1A31MS018A (CLOSE/OPEN) CLOSE ED058E 131X2B B1B:1MS0180 (CLOSE/OPEN) CLOSE ED059A 131X3 B4:1AF006A (CLOSE/OPEN) OPEN ED059B 131X3 B5:1AF017A (CLOSE/OPEN) OPEN (} ED059C 131X3 D5t1CC9473A (CLOSE/OPEN) 's ./ CLOSE ED059D 131X3:E4:1SX001A (CLOSE/OPEN) OPEN ED060A 131X3 C205 (120):1PA45J (CLOSE/OPEN) CLOSE ED060B 131X3:C210 (120):1PM01J (CLOSE/OPEN) CLOSE ED060C 131X3:C220 (120) 31PA31J (CLOSE/OPEN) CLOSE ED061 131X4 A5:1CV8100 (CLOSE/OPEN) CLOSE 20062A 131X5:A4:1CS007A (CLOSE/OPEN) CLOSE ED062B 131X5 AS:1CV112B (CLOSE/OPEN) - CLOSE ED062C 131X5 C4:1SX016A (CLOSE/OPEN) CLOSE ! ED062D 131X5 C5:1SX027A (CLOSE/OPEN) CLOSE
-ED063A 132X1:C1:1SX001B (CLOSE/OPEN)
OPEN
- ED063B 132X1 C2:1SI8924 (CLOSE/OPEN)
CLOSE , i 22
BYRON SIMULATOR ANS1/ANS-3.5-1985 CERTIFICATION REPORT ; INITIAL REPORT, SEPTEMBER, 1991 , N APPENDIX 2 ; REMOTE FUNCTION LISTINGS
.f ED063C 132X1:C4 1RH611 (CLOSE/OPEN) !
CLOSE : ED063D 132X11D4:ICC9412B (CLOSE/OPEN) l CLOSE j ED063E 132X1tD5:1CC9473B (CLOSE/OPEN) ! CLOSE ' ED063F 132X1tE4Bt1MS018B (CLOSE/OPEN) i CLOSE ED063G 132X1tG1:1C8009B (CLOSE/OPEN) i CLOSE ED063H 132X1tG2:1CS009B (CLOSE/OPEN) CLOSE i ED063I 132X1tG3:1S18807B (CLOSE/OPEN) ! CLOSE i ED064A 132X1:J209 (120) 1PA32J (CLOSE/OPEN) ! CLOSE ! ED064B 132X1 J211 (120) 1AR031 (CLOSE/OPEN)- ! CLOSE i C ED064C 132X1 J219 (120):1PA04J (CLOSE/OPEN) ( CLOSE r ED064D 132X1tJ221 (120) 1PA34J (CLOSE/OPEN) CLOSE - ED065A 132X2:B1 1RH8702B (CLOSE/OPEN) ! CLOSE ' ED065B 132X2:B3 1RH8701B (CLOSE/OPEN) , OPEN ED065C 132X21B4:1CV8112 (CLOSE/OPEN) , CLOSE ED065D 132X2:04:1RY8000B (CLOSE/OPEN) i CLOSE i ED065E 132X2 D411RC8003B (CLOSE/OPEN) ' OPEN ED065F 132X2:D5 1RC8003C (CLnSE/OPEN) OPEN ED065G 132X2:G1 1RC8002A (CLOSE/OPEN) l OPEN l ED065H 132X2tG2:1RC8002B (CLOSE/OPEN) OPEli , l ED0651 132X2:G311RC8002C I (CLOSE/OPEN)- OPEN [ ED065J 132X2tG4:1RC8002D (CLOSE/OPEN) : OPEN ' O e 23
. ~. _ . _ . _ _ . . _ , . , _ . _
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS ED066A 132X2:F214 (120):1PM09J (CLOSE/OPEN) CLOSE ED006B 132X2 F216 (120):0/1AR056/12 (CLOSE/OPEN) CLOSE ED066C 132X2 F219 (120) : 1PA02J (CLOSE/OPEN) C74SE ED066D 132X2 F208 (120) : 1PM06J (CLOSE/OPEN) CIASE ED067A 132X2A A2:1 SIB 808C (CLOSE/OPEN) OPEN ED067B 132X2AIA3:1 SIB 800B (CLOSE/OPEN) OPEN ED068A 132X3 A4:1AF006B (CLOSE/OPEN) OPEN ED068B 132X3 A511AF017B (CLOSE/OPEN) OPEN ED069A 132X3 B207 (120 #1) :1PM01J (CLOSE/OPEN) CLOSE ps ED069B 132X3 B220 (120 #1) 0PM02J (CLOSE/OPEN) V CLOSE ED070A 132X3 F209 (120 #2) 0PR033J (CLOSE/OPEN) CLOSE l ED070B 132X3 F211 (120 #2):0PR54J (CIASE/OPEN) CLOSE ED072A 132X4 A1:1SX016B (CLOSE/OPEN) CLOSE ED071B 132X4 A2:1SX027B (CLOSE/OPEN) CLOSE ED071C 132X4 A3:1CS5001B (CLOSE/OPEN) CLOSE j ED071D 132X4 A4:1RH8716B (CLOSE/OPEN) CLOSE I ED071E 132X4 B1:1AF013F (CLOSE/OPEN) l- CLOSE l ED071F 132X4:B2:1AF013E (CLOSE/OPEN) CLOSE ED071G 132X4:B3 iCS007B (CLOSE/OPEN) CLOSE ED071H 132X4:B4:1AF013H (CLOSE/OPEN) CLOSE ED071I 132X4:C1:1AF013G (CLOSE/OPEN) CLOSE l O l- 24
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT IN!TIAL REPORT, SEPTEMBER, 1991
/ \
APPENDIX 2 REMOTE FUNCTION LISTINGS ED071J 132X4tC2:1CV112E (CLOSE/OPEN) CLOSE ED071K 132X4 C3 1CV8105 (CLOSE/OPEN) CLOSE ED071L 132X4tD4:1CC685 (CLOSE/OPEN) CLOSZ ED071M 132X4tF1:1SI8821B (CLOSE/OPEN) CLOSE ; ED071H 132X4tHit1SI6811B (CLOSE/OPEN) ; OPEN ED0710 132X4tH3:1VQ001B (CLOSE/OPEN) l OPEN ED071P 132X4tH4:1VQOO2B (CLOSE/OPEN) OPEN ED072A 132X4AtL2 1SI8802B (CLOSE/OPEN) ! OPEN ED072B 132X4A L3:1 SIB 813 (CLOSE/OPEN) OPEN ;
/ ED072C 132X4AtM1:1 SIB 809B (CLOSE/OPEN) j \ CLOSE ED072D 132X4 AIM 2:1SI8812B (CLOSE/OPEN) o CLOSE ,
ED073A 132X5 A4:1S18801B (CLOSE/OPEN) ' CLOSE ED073B 132X5tBitCV8104 (CLOSE/OPEN) CLOSE ED073C 132X5tC2Bt1MS018C ( (CLOSE/OPEN) l CLOSE
- ED073D 132X5tC4 1CV112C (CLOSE/OPEN)
CLOSE ED074 133Yt3Ct1RD01E (CLOSE/OPEN) ) CLOSE ED075A 133U1tB1:1CWO1JA (CLOSE/OPEN) CLOSE ED075B 133U1:C3:1CW001C (CLOSE/OPEN) l CLOSE ED075C 13301tC4:1CWOO1A (CLOSE/OPEN) ! l CLOSE ED075D 133U1 E3:1CWO1JC (CLOSE/OPEN) CLOSE i
,f 1 \~J t i
25 L
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 < Os'
'~'
APPENDIX 2 REMOTE FUNCTION LISTINGS ED076 133U1:D203 (120): OFT-CWO40 (CLOSE/OPEN) CLOSE ED077A 133V2:B202 (120):1PA27J (CLOSE/OPEN) : CLOSE l ED077B 133V2:B204 (120):1PA26J (CLOSE/OPEN) , CLOSE ' ED077C 133V2:B205 (120):1PA22J (CLOSE/OPEN) , CLOSE ED077D 133V2:B206 (120):1PA24J (CLOSE/OPEN) CLOSE [ ED077E 133V2:B208 (120):1PM05J (CLOSE/OPEN) CLOSE ED077F 133V2:B215 (120):1PA32J (CLOSE/OPEN) CLOSE ED077G 133V2:B216 (120):1PA38J (CLOSE/OPEN) { CLOSE : ED077H 133V2:B218 (120):1PA19J (CLOSE/OPEN) I CLOSE (T ED077I 133V2:B224 (120) : 0PM02J (CLOSE/OPEN) i \j CLOSE ED078A 133V3 C5:1CW018 (CLOSE/OPEN) ,l~ CLOSE ED078B 133V3:F2A:0PR05J (CLOSE/CPEN) , CLOSE ; ED079A 133V4:A1A:1PR09J (CLOSE/OPEN) i CLO3E ED079B 133V4:A2A:0PR09J (CLOSE/OPEN) CLOSE - ED079C 133V4:E2:1FWO1PB-A (CLOSE/OPEN) CLOSE ED079D 133V4:E4:1FWO59 (CLOSE/OPEN) CLOSE ED080A 133V4:C203 (120):1PA35J (CLOSE/OPEN) CLOSE ED080B 133V4:C207 (120):1MS01JG (CLOSE/OPEN) CLOSE ED080C 133V4:C212 (120):1CB039A-M (CLOSE/OPEN) CLOSE ED081A 133X1A:C204 (120):1TS-00671A (CLOSE/OPEN) CLOSE D .U 26 _ _ _ m
i BYRON SIMULA'10R ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O APPENDIX 2 - REMOTE FUNCTION L1 STINGS J ED081B 133X1A C206 (120):1PR11J (CLOSE/OPEN) CLOSE , ED081C 133X1A:C208 (120) : 1 TIS-CV129 (CLOSE/OPEN) [ CLOSE a ED081D 133X1AIC224 (120) : 1PA05J (CLOSE/OPEN) i CLOSE i ED082A 133X1BtB201 (120) :1FA36J (CLOSE/OPEN) ! CLOSE l ED082B 133X1B B203 (120) :1PA37J (CLOSE/OPEN) i CLOSE. . [ ED082C 133X1B:B204 - (120) :1PM12J (CLOSE/OPEF' t CLOSE ED082D 133X1B:B219 (120):1PA20JA (CLOSE/OPEN) l CLOSE ED082E 133X1B B220 (120) :1PA50J (CLOSE/OPEN) 'j CLOSE- # ED082F 133X18 B221 (120) :1PA20JB (CLOSE/OPEN) CLOSE ED082G 133X1B B222 (120):1PA075 ,f') (CLOSE/OPEN) \m/ ' CLOSE ED082H 133X18:B223 (120):1PA20JC (CLOSE/OPEN) ;
. . CLOSE ED083 133X1B:C18:1PIO3EA (CLOSE/OPEN)
CLOSE- , ED084A 133X3 A1B:1CV06J (CLOSE/OPEN) CLOSE ; ED084B 133X3 E(A:1PR02J (CLOSE/OPEN) ; CLOSE _ ED085A 133X3:C202 (120 #1):1CV06J (CLOSE/OPEN) i CLOSE i ED085B 133X3:C203_(120'#1):1PM04J (CLOSE/OPEN) i CLOSE , ED085C 133X3 C205 (120 #1):1PM04J (CLOSE/OPEN) CLOSE ; ED085D'133X3 C207 (120 #1):1PM03J (CLOSE/OPEN) , CLOSE ! ED085E 133X3 C209 (120 #1):1PM02J _(CLOSE/OPEN) j CLOSE i ED085F 133X3:C211 (120 #1):1PM02J (CLOSE/OPEN) ; CLOSE- ) ED085G 133X3:C213 (120 #1) 0PM01J (CLOSE/OPEN) l CLOSE ;
'l 27 r
~
, - - _ - - . , - . _ _ _ _ . , - - _ . , _ _ ~ _ , _ . _ _ , , , - . . . - _ . _ . . , . , . . - . _ , . . ~ , . . , _ . -
t BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS 4 ED085H 133X3:C215 (120 #1):1PM01J (CLOSE/OPEN) CLOSE ED086A 133X3:G204 (120 #2):1PA17J (CLOSE/OPEN) CLOSE ED086B 133X3:G212 PR21/28)XS1PA17J (CLOSE/OPEN) , CLOSE ED086C 133X3:G224 (120 #2):1PR28J (CLOSE/OPEN) CLOSE ED087A 133X4:J204 (120):1PA21J (CLOSE/OPEN) CLOSE A ED087B 133X4:J209 (120):1PM06J (CLOSE/OPEN)
'CLOSE ED088A 133Y1:A4:1CB01PC-A (CLOSE/OPEN)
CLOSE , ED088B 133Y1:A5:1CB01PA-A (CLOSE/OPEN) CLOSE ED088C 133Y1:A6:1CD05PA-B (CLOSE/OPEN) CLOSE ,
/~ ED088D 133Y1 B1:1CD05PC-B '
(CLOSE/OPEN) V) CLOSE ED088E 133Y1 E4:1CWOO2A (CLOSE/OPEN) CLOSE ED088F 133Y1 ES:1CWOO3A (CLOSE/OPEN) I CLOSE ED088G 133Y1:G4:1CWOO2D (CLOSE/OPEN) CLOSE ED088H 133Y1:GS:1CWOO3D (CLOSE/OPEN) CLOSE ED089A 133Y1:D203 (120):1CD05PC-B (CLOSE/OPEN) CLOSE ED089B 133Y1:D205 (120):1CD05PA-B (CLOSE/OPEN) , CLOSE ED089C 133Y1:D221 (120):CD210/211 (CLOSE/OPEN) * , CLOSE l' ED090A 133Z2:C202 (120):1PM11/12J (CLOSE/OPEN) - l CLOSE ; ED090B 133Z2:C205 (120):1FWO1PC-J (CLOSE/OPEN) CLOSE ED090C 133Z2:C208 (120):MSRVLVS (CLOSE/OPEN) CLOSE ED091A 133Z2:D3:1rWOO5 (CLOSE/OPEN) ! CLOSE ( 28 I
BYROH SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATTS'l REPORT 4 INITIAL REPORT, SEPTEMBEh, 1991 APPENDIX 2 ; REMOTE FUNCTION LISTINGS ED091B 133Z2 E4:1FWO4A (CLOSE/OPEN) ! CLOSE
- ED091C 13322 G3:1FWOO2A (CLOSE/OPEN) .
CLOSE ED091D 133Z2 G4:1FWO2P-B (CLOSE/OPEN)
- CLOSE
- ED091E 133Z2:H2:1T008PA (CLOSE/OPEN) '
CLOSE ED091F 133Z2 H3:1T008PP (CLOSE/OPEN) CLOSE ED091G 133Z2:H4:1T008PC (CLOSE/OPEN) CLOS ~: ED091H 13327tH5:1FWOO2C (CLOSE/OPEF) CLOS 2-
' ED092 134Y 2A:1RD02E (CLOSE/OPEN) .
CLOSE ED093A 134U1 B3:1CWO1JB (CLOSE/OPEN) CLOSE O ED093B 134U1:B4:1CWOO1B
- ED094 134V1:A1A 1PIO3EB CLOSE (CLOSE/OPEN)
(CLOSE/OPEN) CLCSE - s
- ED095A 134V1 C202-(120):1CC9415 (CLOSE/OPEN)
CLOSE ED095B 134V1:C204 (120):1 TIS-CC672 (CLOSE/OPEN) CLOSE ED095C 134V1:C207 (120):1PM12J (CLOSE/OPEN) CLOSE ED095D 134V1:C208 (120):1PA38J (CLOSE/OPEN) CLOSE ED095E 134V1:C210 (120):1PA43J (CLOSE/OPEN) CLOSE ED095F-134V1:C211 (120):1PA35J (CLOSE/OPEN)- CLOSE t
,ED095G 134V1 C212 (120):1PA22J (CLOSE/OPEN)
CLOSE
- ED095H 134V1 C214 (120):1PA36J (CLOSE/OPEN)
CLOSE-ED095I L134V1:C216,(120):1PA37J (CLOSE/OPEN)
= CLOSE ED095J 134V1:C218-(120):1PA50J (CLOSE/OPEN)
CLOSE 29 u ,-xa- a c.,,,a --+,,w.--,<s+t.-rae-r ,m - s e w_--v,vme,,,m,nmw+w w w.,e s wr e ~w g -w= w, e _ wo m y - y m w r ,--pe,
,w re n g-- <we ,y y 9-re,w,,~,-g-,,g y +e -
. __ _ _ _ _ _ _ . _ . . _ _ _ _ _ ~ _ . . . _ . _ . _ _ _ _ _ . _ _ _ . . .
i I BYRON SIMULATOR l ANSI /ANS-3.5-1985 CERTIFICATION REPORT ! INITIAL REPORT, SEPTEMBER, 1991 ! O APPENDIX 2 REMOTE FUNCTION LISTINGS ED095K 134V1 C219 (120) : IPA 20JA (CLOSE/OPEN) ! CLOSE l ED095L 134V1:C220 (120) :1PM10J (CLOSE/OPEN) ; CICSE l ED095M 134V1 C221 (120) : 1PA20JB (CLOSE/OPEN) l CLOSU ! ED095N 134V1 C223 (120):1PA20JC (CLOSE/OPEN) l CLOSE ! ED096A 134V2: F201 ' (120) 2 0PA01J (CLOSE/OPEN) f CLOSE . ED0968 134V2 F217 (120) .PA08J (CLOSE/OPEN) i CLOSE-ED097 134V3 A1A31PR03J (CLOSE/OPEN) [ CLOSE '
}
ED098 134V3:C208 (120) : TIS-684 / 6 (CLOSE/OPEN) ! CLOSE i ED099A 134V4 D202 (120):1PA28J_ (CLOSE/OPEN) j CLOSE - O ED099B 134V4:D204 (120) :1PA35J ED099C.134V4:D206 (120):1PM03J CLOSE (CLOSE/OPEN) (CLOSE/OPEN) CLOSE , ED099D 134V4:D207 (120) : 3 PM01J (CLOSE/OPEN) :
-CLOSE !
EDM9E 134V4 D209 (120) : 1PM04J (CLOEE/OPEN) -! CLOSE j ED099F 134V4 D210 (120) : 1PM027 (CLOSE/OPEN) j CLOSE '; ED099G 134V4:D211 (120) :1PM04J (CLOSE/OPEN) ! CLOSE t ED099H 134V4:D212 (120):0PM01J (CLOSE/OPEN) ; CLOSE ED099I_134V4 D218 (120):1PM08J (CLOSE/OPEN) I CLOSE ,
- ED099J 134V4:D220 (120):1PA30/32J (CLOSE/OPEN) l
, CLOSE ,
ED099K 134V4:D222 (120) :1PA06J (CLOSE/OPEN) [ CLOSE .! ED099L 134V4 D223 (120):1PA42J (CLOSE/OPEN) l CLOSE i ED099M 134V4:D224 (120) :1PM08J (CLOSE/OPEN) .! CLOSE ' I i 30 } i
% <= c +v sy w + t- er N e r-i.m - - e v' i -~,---rwe,m, -= i<w ---+-,ww-w - ---'r*-- -vv,,-e- e-, r,-e-re- e-e*----s- .----,----*-wr---e------ - = -- - *-Cie-7--*
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT , INITIAL REPORT, SEPTEMBER, 1991
/^}
APPENDIX 2 REMOTE FUNCTION LISTINGS ' i ED100 134V6 C210 (120) : 1FWO1PB-J (CLOSE/OPEN) CLOSE ED101A 134X5:J202 (120) :1PA4 4J (CLOSE/OPEN) CLOSE ED101B 134X5 J216 (120):1PA27J (CLOSE/OPEN) : CLOSE ED101C 134X5:J218 (120) : 1PM09J (CLOSE/OPEN) CLOSE ED102A 134Y1 A4:1CD01PD-A (CLOSE/OPEN) CLOSE ED102B 134Y1 A5:1CD01PB-A (CLOSE/OPEN) CLOSE ED102C 134Y1 A6:1CD05PB-B (CLOSE/OPEN) CLOSE ED102D 134Y1sB1:1CD05PD-B (CLOSE/OPEN) . CLOSE ED103A 134Y2 A4:1CWOO2B (CLOSE/OPEN)
- CLOSE ,
(~} ED103B 134Y2 A5:1CW003B ' (CLOSE/OPEN) id CLOSE ED103C 134Y2:D4:1CWOO2C (CLOSE/OPEN) CLOSE , ED103D 134Y2:05:1CWOO3C (CLOSE/OPEN) 1 CLOSE ED104A 134Y2:C203 (120)s1CD05PB-B (CLOSE/OPEN) CLOSE , ED1048 134Y2:C205 (120):1CD05PD-B (CLOSE/OPEN) CLOSE ED105 134Y3 E1:1FWO1PB-B (CLOSE/OPEN) ; CLOSE ED106A 134Z2 D3:1T007P (CLOSE/OPEN) CLOSE ; ED1068 134Z2:E3:1FWOO2B (CLOSE/OPEN) CLOSE ED106C 134Z2 F1:1FWO1PA-B (CLOSE/OPEN) CLOSE ED106D 134Z2:G1:1FWO1PC-B (CLOSE/OPEN) . CLOSE I ED107A 134Z4 C1:1T008PD (CLOSE/OPEN) CLOSE ED107B 134Z4 C2:1T008PE (CLOSE/OPEN) CLOSE i 31 , i l l
DYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
% APPENDIX 2 REMOTE FUNCTION LISTINGS ED107C 134Z4tC3:1T008PF (CLOSE/OPEN)
CLOSE ED108 SAT LOCKOUT RESET (NORM / RESET) NORM ED109 SYSTEM VOLTAGE (300-370 KV) 345 KV ED110 CROSS-TIE BUSES 35-1/35-2 (CLOSE/OPEN) OPEN ED111 CROSS-TIE UNIT 2 BKR 211 (CLOSE/OPEN) OPEN . ED112 CROSS-TIE UNIT 2 BKR 212 (CLOSE/OPEN) OPEN EDi13 JUMPER AT CONTACTS 5-6 FOR ACB 1411 (NORMAL / BYPASS) NORMAL ED114 JUMPER AT CONTACTS 5-6 FOR ACB 1421 (NORMAL / BYPASS) NORMAL O V 32
[ BYRON SIMULATOR , ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 0 APPENDIX 2 REMOTE FUNCTION LISTINGS 3 r EG01 GEN LOCKOUT RELAY 86GIA (NORM / RESET) NORM EG02 GEN LOCKOUT RELAY 800.'.D (NORM / RESET) ! HORM ! EG03 DG1A CONTROL MODE SELECT (LOCAL / REMOTE /MAINT_O) REMOTE i EG04 D01A UNIT PARALLdL SWITCH (DROOP /ISOCH) I DROOP : EGOS DG1A LOCAT. START /STOP (STOP/ NORM / START) NORM EG06 DG1A LOCAL RESET (NORM / RESET) NORM EG07 DG1A VOLTAGE RAISE / LOWER (LOWER / NORM / RAISE) , NORM ' EG08 DG1A SPEED RAISE / LOWER (LOWER / NORM / RAISE) NORM - EG09 DG1B CONTROL MODE SELECT (LOCAL / REMOTE /MAINT_0) ; p REMOTE U EG10 DG1B UNIT PARALLEL SWITCH (DROOP /ISOCH) , DROOP EG11 DG1B LOCAL ST15tT/STOP (STOP/ NORM / START) NORM EG12 DG1B LOCAL RESET (NC tM/ RESET)
- NORM EG13 DG1B VOLTAGE RAISE / LOWER (LOWER / NORM / RAISE)
- HORM EG14 DG1B SPEED RAISE / LOWER (LOWER / NORM / RAISE)
NORM ; EG15 BRKR 41M TRIP (NORM / TRIP) NORM ; EG16 GEN TRIP TB TEST SW J (CLOSE/0 PEN) CLOSE P
?
33
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS
-EPol RIVER WATER LEVEL (660'-680')
672' EP02 RIVER TEMPERATURE ( 3 2-100'F) 65'F EP03 ATMOSPHERIC WIND SPEED (0-100 MPH) 10 MPH EPO4 - ATMOSPHERIC WIND DIRECTION ( 0-3 6 0') 270' EPOS ATMOSPHERE WET BULB TEMPERATURE ( 0-100'F) 63'F EP06 ATHOSPHERIC DRY BULB TEMPERATUPE ( e2 0-+100'F) 7 5'T EP07 ATMOSPHERIC PRFSSURE (12-17 PSIA)
~
14.7 PSIA EPOS) EXTERNAL GRID FREQUENCY (58-62 Hz) 60 Hz-EP09 EXTERNAL GRID VOLTAGE (300-370 KV) 345 KV ~ EP10 EXTERNAL GRID EQUIVALENT REACTANCE (0-100%)
\
50% 9 t-1 0 34
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFIC;tTION REPORT I INITIAL REPORT, SEPTEMBER, 1991 O v APPENDIX 2 REMOTE FUNCTION LISTINGS l FP01 MPT 1E FP DELUGE RESET (NORMAL / RESET) NORMAL FP02 .1PT 1W FP DELUGr RESET (NORMAL / RESET) : NORMAL , PP03 UAT 141-1 FP DELUGE RESET (NORMAL / RESET) : NO3 MAL FPO4 UAT 141-2 FP DELUGE RESET (NORMAL /1TSET) FORMAL FPOS SAT 142-1 FP DELUGE RESET (NORMAL / RESET) l NORMAL FP06 SAT 142-2 FP DELUGE RESET (NORMAL / RESET) NORMAL FP07 FP/WS CROSSTIE FP5055 (SAC) VLV POS (0-100%) , 0% F208 FP/WS CROSSTIE PP507 VLV Poa (0-100%) 0% , FP09 MOTOR DRIVEN FP LOCAL CONTROL (STOP'\UT0/ START) AUTO-OFF i FP10 DIESEL DRIVEN 1. OCAL CONTROL (STOP/AUT0/ START) O, - AUTO-OFF y a P
+ 5
() : t 35 ,
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS , FWOO1 S1H DUMP SPRAY ISO 1CB038A (0-1004) 100% FWOO2 STM DUMP SPRAY ISO ICB038B (0-100%) > 100% FWOO3 STM DUMP SPRAY ISO 1CB030C (0-1004) 100% FWOO4 STM DUMP SPRAY ISO 1CB038D (0-100%) 100% FWOO5 S1H DUMP SPRAY ISO 1CB038E (0-100%) t 100% FWOO6 STM DUMP SPRAY ISO 1CB038F (0-100%) 100% FWOO7 STM DUMP SPRAY ISO 1CB038G (0-100%) 100% FWOO8 STM DUMP SPRAY ISO 1CD038H (0-100%) ' 100% FWOO9 STM DUMP SPRAY ISO 1CE038J (0-100%) < 100% - FWO10 STM DUMP SPRAY ISO 1CB038K () (0-200%) I 100% , FWO11 STM DUMP SPRAY ISO 1CD038L (0-100%) 100% FWC12 STM DUMP SPRAY ISO 1CB038M (0-100%) 100% } FWO13 CD PP RECIRC BYP 1CD159 (0-100%) i 100% , FWO14 CD PP 1A DIS ISO ICD 041A (0-100%) 100% FWO15 CD PP 1B DIS ISO ICD 04:? (0-100%) l' 100% FWU16 CD PP IC DIS ISO 1CD04b' (0-100%) 100% i FWO17 CD PP 1D DIS ISO 1CD041D (0-100%) 100% FWO18 CP DEMIN ISO VLV 1CD189 (0-100%) 0% FWO19 CP DEMIN ISO VLV 1CD190 (0-1004) 100% FWO20 CB PP A DIS VLV 1CB002A (0-100%) 100% FWO21 CB PP B DIS VLV 1CB002B (0-100%) 100% 36 l
- _ _ _ _ _. .__ _ .__._ -- . _ . - . _ _ _ _ . = _ _ _ _ _ _ _ . _ . _ . _
i BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT,' SEPTEMBER, 1991 O APPENDIX 2 i REMOTE FUi4CTION LISTINGS ! l FWO22 CB PP C DIS VLV 1CB002C (0-100%) i 100% l FWO23 CB PP D DIS VLV 1CB002D (0-100%) 100% FWO24 FW PP A SUCT ISO ICB005A (0-100%) 100% t FWO25 FW PP B SUCT ISO ICB005B (0-100%) ! 100% i FWO26 FW PP C SUCT ISO 1CB005C (0-100%) [ 100% t FWO27 FW PP A RCRC ISO 1FWO27A (0-100%) i 100% l FWO28 FW PP B RCRC ISO 1FWO27B (0-100%) ! 100%- l FWO29 FW PP C RCRC ISO 1FWO27C (0-100%) ;
.100%
i FWO30 -S/U FW-PUMP RECIRC-1FWO98 (0-100%) l 100% ! FWO31 TEMPER ISOL VLV 1FWO33A (0-100%) i ts 100% { FWO32 TEMPER ISOL VLV 1FWO33B (0-100%) ? 100% ! FWO33 TEMPER ISOL VLV FWO33C (0-100%) f 100% i FWO34 TEMPER ISOL VLV 1FWO33D (0-100%) i 100% FWO35- FW PREHTR BYP 1FWO41A' - (0-100%) 100% + FWO36 FW PRENTR BYP 1FWO41B (0-100%) +
-100% i FWO37 FW PREHTR BYP 1FWO41C (0-100%) !
100% ' FWO38 FW PREHTR BYP 1FWO41D (0-100%) f 100% ? FWO39 FW ISOL BYP 1FWO44A (0-100%) l 100% _[ FWO40 FW ISOL'BYP 1FWO44B (0-100%) : 100% ! FWO41- FW ISOL.BYP 1FWO44C (0-100%) : l.- 1004 -{ FWO42 FW ISOL BYP 1FWO44D (0-100%) i 100% ; O: i, 37 l L, . - _ . _ _ . . _ . _ _ - . _ . _ . _ _ _ _ _ _ . . _ . . _ _ . . _ _?
{ DYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O APPENDIX 2 l REMOTE FUNCTIO' LISTINGS i f i FWO43 AP PP 1A SUCT ISO 1AF002A (0-100%) ; 100% l FWO44 AF PP 18-SUCT ISO 1AF002B (0-100%) l
-100% 1 FWO45 AF PP 1A DIS ISOL 1AF004A (0-1004) 100%
FWO46 A T P)- 18 DIS ISOL 1AF004B (0-100%) -l 100% ; FWO47 DEMIN M/U TO CST OWM423A (0-1004) _! 0% ' FWO48 CND NORM OVF.FLW BYP 1CD146 (0-100%) 0% FWO49 CND EMERG OVRFLW 1CD140 (0-100%) 0%- _; FWO50 CND NORM OVRFtW 1CD143 (0-100%) ! 0% '! FWO51 CND NORM M/U BYP 1CD035 (0-100%) { 0%
- FWOS2 CND EMR /U ICD 028 (0-100%)
FWO53 CND_ NORM M/U 1CD031 (0-100%) .j 0% 1 FWO54 SJAE STM ISOL'VLV iMS107A (0-100%) ! 0% l FWO55 SJhE STM ISOL VLV 1MS107B (0-100%)
- 0% [
FWO56 SJAE'OFF GAS ISOL 10G042A (0-100%) [ 0% 'I FWO 57 ' SJAE OFF GAS ISOL 10G042B _(0-100%) [ 0% - FWO58 _17A NORM DRN 1HD008A IA (OUT/IN) IN FWO59 17A NORM DRN_1HD008A PSN 0%
.(0-100%) l -
FWO60 17A EMRG DRN 1HD038A IA (OUT/IN) L l IN ' FWO61 17A EMRG DRN_1HD038A PSN (0-100%) !
-100% [
.FWO62' 17B NORM DRN 1HD008B IA (OUT/IN) :
IN- _! FWO63 17B NORM =DRN'1HD008B PSN (0-100%) ; 0% [ 1 I 38 !,
. _ _ -- _ _ _ _ _ - . _ - _ _ _ _ . _ _ _ . _ _ . ~ _ _ _ . _ . _ . _ _ _ . _ _ _ _ . _ . _ _ . _ . _ . _ _ _ _ ,
[ BYRON SIMULATOR I ANSI /ANS-3.5-1985 CERTIFICATION REPORT { INITIAL REPORT, SEPTEMBER, 1991 i i APPENDIX 2 REMOTE FUNCTION LISTINGS l i l FWO64 17B EMRG DRN 1HD030B IA (OUT/IN) [ IN l FWO65 17B EMRG DRN 1HD038B PSN (0-100%) { , 100% i
- FWO66 16A NORM DRN 1HD011A IA (OUT/Ill) :
IN l I FWO67 16A NORM DRN 1HD011A PSN (0-100%) 0% ; FWO68 16A EMRG DRN 1HD041A IA (OUT/IN) IN { FWO69 16A E'lRG DRN 1HD041A PSN (0-100%) l 100% FWO70 16P, NORM DRN 1HD011B IA (OUT/IN) l IN ! FWO71 16B NORM DRN 1HD011B PSN (0-100%) i 0% FWO7 2 -- 168 EMRG DRN 1HD041B IA (OUT/IN) ! IN : Q FWO73 16B EMRG DRN 1HD041B PSN (0-790%) ! Q FWO74 100% 15A DRN CLR OUTLT 1HD014A l (0-100%) 100% [ FWO75 15B DRN CLR OUTLT 1HD014B (0-100%) i 100% ! FWO76 -15A EMRG DRN 1HD062A IA (OUT/IN) . IN l FWO77 15A EMRG DRN 1HD062A PSN (0-100%) 100% : FWO78 15B EMRG DRN 1HD062D IA (OUT/IN) l
- IN i FWO79 15B ENRG DRN 1HD062B PSN (0-100%) [
100% l- FWO80 14A NORM DRN 1HD020A IA (OUT/IN) t l- IN l E FWOB1 14A NORM DRN 1HD020A PSN t (0-100%) .I 0% FWOS2 14A EMRG DRN 1HD048A IA (OUT/IN) . IN ; FWO83 14A-EMRG DRN 1HD048A-PSN (0-1005) ! 100% ' FWO84 14B NORM DRN 1HD020B IA (OUT/IN) i p IN ! O. , 39 l C
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
- ~
APPENDIX 2 REMOTE FUllCTION LISTINGS FWOB5 14B NORM DRN 1HD020B PSN (0-100%) 0% FWO86 14B EMRG DRN 1HD048B 1A (OUT/IN) IN FWO 8 7_. 14B EMRG DRN 1HD048B PSN (0-1004) 100% FWO88 14C NORM DRN 1HD020C IA (OUT/IN) IN FWO89 14C NORM DRN 1HD020C PSN (0-100%) 04-FWO90_ 14C ZMRG DRN 1HDocJC IA (OUT/IN) IN FWO91 14C ZMRG DRN 1HD048C PSN (0-100%) 100% FWO92 13 A- NOPJ( DRN 1HD023A I A (OUT/IN) IN FWO93 13A NORM DRN 1HD023A PSN' (0-100%)
.0%
FWO94 13A EMRG DRN 1HD051A IA ' (OUT/IN) \ IN FWO95- 13A EMRG DRN 1HD051A PSN (0-100%) 100% < FWO96 .13B NORM DRN 1HD023B IA (OUT/IN) IN FWO97 13B NORM DRN 1HD023B PSN (0-100%) 0% FWO98 13B EMRG DRN 1HD051B IA (OUT/IN) IN FWO99 13B EMRG DRN 1HD051B PSN (0-100%) 100% FW100 13C NORM DRN 1HD023C IA (OUT/IN) IN FW101 13C NORM DRN 1HD023C PSN (0-100%) 0% FW102 13C EMRG DRN 1HD051C IA (OUT/IN) IN FW103 13C-EMRG DRN 1HD051C PSN (0-100%) 100%- W104 12A-NORM DRN 1HD026A IA (OUT/IN) IN FW105 12A NORM DRN 1HD026A PSN (0-100%S 0% 40 r
r BYRON SIHULATOR , ANSI /ANS-3.5-1985 CERTIFICATION REPORT l INITIAL REPORT, SEPTEMBER, 1991 i b d APPENDIX 2 i REMOTE FUNCTION LISTINGS FW106 12A EMRG DRN lilD054A IA (OUT/IN) IN I FW107 12A EMRG DRN 1HD054A PSN (0-100%) i 100% i FW108 12B NORM DRN 1HD026B IA (OUT/IN) - IN FW109 12B NORM DRN 1HD026B PSN (0-100%) 0% FW110 12B EMRG DRN 1HD054B IA (OUT/IN) IN FW111 ?.2B EMRG DRN 1HD054B PSN (0-100%) 100% FW112- 12C NORM DRN 1HD026C IA (OUT/IN) , IN ' FW113 12C NORM DRN 1HD026C PSN (0-100%) i 0% FW114 12C EMRG DRN 1HD054C IA (OUT/IN) IN
^
FW115 12C EMRG DRN lilD054C PSN ' (0-100%) s 100% FW116 11A DRN CLR DRN 1HD029A IA (OUT/IN) 3 IN - FW117 11A DRN CLR DRN lilD029A PSN (0-100%) 0% [' FW118 FLSH TK 1A DRN 111D094A IA (OUT/IN) IN FW119 FLSH TK 1A'DRN 1HD094A PSN (0-100%) 100% FW120 11B DRN CLR DRN 1HD029B IA (OUT/IN) IN FW121 11B DRN CLR DRN 111D029B PSN (0-100%) 0% FW122 FLSH TK 1B DRN 1HD094B IA (OUT/IN) IN FW123 FLSH TK 1B DRN 1HD094B PSN (0-100%) 100% FW124 11C DRN CLR DRN 1HD029C IA (OUT/IN) l IN FW125 11C DRN CLR DRN 1HD029C PSN (0-100,-) 0% FW126 FLSH TK 1C DRN 1HD094C IA (OUT/IN) IN 41
i p BYRON SIMULATOR ! ANSI /ANS-3.5-1985 CERTIFICATION REPORT ! INITIAL REPORT, SEPTEMBER, 1991 l APPENDIX 2 REMOTE FUNCTION LISTINGS [ i l l FW127 FLSH TK 1C DRN 1HD094C PSN (0-100%) [ 100% ! FW128 HTR 17 BYP ISO 1FWOO5 (0-i t) L 0% { FW129 HDT VENT TO ISA 150 1HD070A (0-10w
^
100%
)
FW130 HDT VENT TO 15B ISO 1HD070B (0-100%) ; 100% t FW131 HD PP CONT VLV ISO 1HD046A (0-100%) 5 100% ' i FW132 HD PP CONT VLV ISO 1HD046B (0-100%) I 100% ; FW133 HD PANEL HI2 RESET BUTTON (NORM / RESET) i NORM i FW134 U1/U2 CST XTIE ISO OCD116 (0-1004) i 0% ( FW135 FW HDR CLEAN UP LOOP FWO95 (0-100%) l 0% v FW136 CP RETURN ISO VLV 1CD211 * (0-100%) ! 0% ; FW137 CP CONTROLLER 1CD210A/B (0-100%) ! 0% FW138 S/U FW PP.SUCT ISO 1CD113 (0-100%) 1004 FW139 l CD M/U PP 0/1 XTIE OCD113 (0-100%) , 100% _. . FW140 CD PP 1A SUCT ISO 1CD027A (0-100%) =i 100%. l ,. FW141- CD PP 1B SUCT ISO 1CD037B (0-100%) : t-100% ! FW142 CD PP 1C SUCT ISO 1CD037C (0-100%) I 100% ! FW143 CD PP-1D SUCT ISO 1CD037D (0-100%) ; 100% t FW144 FWP B SPEED SETTER MOTOR (0-5800 RPM) [ 0 RPM l L FW145 .FWP C SPEED SETTER MOTOR (0-5800 RPM) . 0 RPM.
- FW146 AF PP'A AUX L.O. 'P (STOP/ START)-
STOP i FW147 AF PP B AUX L.O. PP (STOP/ START) l STOP ,t D . j : 42 i
.i
BYRON SIMULATOR , ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS FW148 AF PP B GEAR BOX OIL PP (STOP/ START) STOP FW149 S/U FW PP AUX L.O. PP (STOP/ START) STOP FW150 FW AUX RELAY FUSE TRAIN A (NORMAL / REMOVED) NORMAL FW151 FW AUX RELAY FUSE TRAIN D (NORMAL / REMOVED) NORMAL FW152 FW PP B 0/S TRIP TEST (RESET / NORMAL / TRIP) NORMAL FW153 FW PP C O/S TRIP TEST (RESET / NORMAL / TRIP) NORMAL FW154 111D046A/B VALVE CONTACT 09-11 ON (NORMAL /0 PEN) ILY-HD009A - LOW NPSH NORMAL FW155 1CD157A VALVE CONTACT 15-16 ON PS-CB14X(NORMAL /0 PEN) ON LOW NPSH NORMAL Q FW156 1CD152A VALVE CONTACT 17-18 ON PS-CB14X(NORMAL /0 PEN) Q ON LOW NPSH NORMAL FW157 3CD05PD VALVE C0tjTAca' 03-04 ON PS-CB14X(NORMAL /0 PEN) ON LOW NPSH NORMAL FW158 1PS-CB04X FOR ALL CONTACTS ON CB SUCT (NORMAL /0 PEN) NORMAL FW159 1CD210A/B FOR CONTACTS ON LOW NPSli (NORMAL /0 PEN) NORMAL FW160 1AF01J LOCAL OPERATION (S5/S4/111S/ (NORM / START /STOP) 1F120/S8) NORM FW161 AF 1AF005E HANDWHEEL RF (0-100%) 100% FW162 AF 1AF005F HANDWHEEL RF (0-100%) 100% FW163 AF 1AF005G HANDWilEEL RF (0-100%) 100% FW164 AF=1AF00511 HANDWHEEL RF (0-100%) 100% FW165 AF 1A SUCT PRESS LO-2 (51) NORM / TRIP (NORMAL / TRIP) NORMAL
,n 43 i
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 C APPENDIX 2 REMOTE FUNCTION LISTINGS FW166 AF 1B SUCT PRESS LO-2 (55) NORM / TRIP (NORMAL / TRIP) NORMAL FW167 FW PP 1A RECIRC VLV 1FWC52A PP START (NORMAL /DYPASS) BYPASS O , e a 44
e;
, BYRON SIMULATOR C(C. ANSI /ANS-3.5-1985 CER7IFICATION REPORT
') INITIAL REPORT, SEPTEMBER, 1991
) (T:s> APPENDIX 2 REltOTE FUhCTION LISTINGS 7%
SA TO IA ISOL 1SA113 (0-100%) (#,ML - IA' 100% i IA02 SA TO IA ISOL OSA113 (0-200%)
'N.
. 100%
?f , IA03 SS TO IA ISOL (0-;) 2SA113 (0-100%)
, 100%
IA04 SA TO IA X-TIE (1-0) OIA147 (0-100%) 100% IA05 SA TO IA X-TIE ( 0-2 )' OIA148 (0-100%) 100% IA06 AIR DRYER 1 ISOL IIA 001 (0-100%) 100% IA07 AIR CRYER 0 ISOL OIA001 (0-100%; 0% IA08 AIR DRYER 2 ISOL 2IA001 (0-100%' 100% t09 AIK 1-0 INLET X-TIE OIA053 (0-1004) 100% IA10 AIR 0-2 INLET X-TIE OIA054' (0-100%) 9 - IAll 100% AIR OUTLET ISCL 11A013 (0-100%)
. ,100%
IA12 A1A OUTLET ISCL OIA013 (0-100%? 100% IA13 AIR OUTLET ISOL 2IA013 U:-100% )
),00%
7Al' IA 1-0 OUTLET X TIE OIA114 '0-100%) 100% IA15- IA 0-2 OUTLET X-TIE OIA113 l0-100%) 100% IA16 UNIT X-TIE OIA055 (0-100%)
'00%
IA17 UNIT 1 TB TO AB 01;097A IO-100%) 100% IA18 UNIT 2 TC TO AB OIA097B (0-100%) 100% IA19 AUX BLD HDR X-TIE OIA107 (0-100%) 100% j IA20 AUX BLD HDR Y.-TIE OI!*101 (0-100%) l 100% , g { .'A21 . 74 DUMP SUP ISOL IIA 060 (0-100%) 100% IA22 U-C SAC TRIP BLOCK (UDRM/ BLOCK) g.- 1A23 liORM U-1 SAC TRIP BLOCK (NORM / BLOCK) NORM 45
( BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS IA24 SAC DISCH XTIE OSA277 (0-100%) 100% IA25 PORTABLE COMPRESSOR (OFF/3N) CTF IA26 CONTAIi, MENT LOADS IIA 065 (0-100%) 100% IA27 CONTAINMENT LOADS IIA 066 (0-100%) 100% I 1? 1 AF VALVES / CONT OIA186 (0-100%) 100% IA29 WEST MSIV'S (B & C) IIA 107 (0-100%) 100% IA30 EAST MSIV'S (A & D) IIA 124 (0-100%) 100% IA31 TB SW IIA 055 (0-100%) 100% IA32 TB MID WEST 11A056 (0-100%) 100% IA33 TB NORTH WEST lIA073 (0-100%) g% 100%
\ IA34 TB SE IIA 058 (0-100%)
100% IA35 TB MID EAST 11A059 (0-100%) 100% TA36 TB NORTH EAST lIA061 (0-100%) 100% IA37 STM DUMPS A- f: IIA 132 (0-100%) 100% IA38 STM DUMPS E-H IIA 133 -100%) 100% IA39 STM DUMPS J-M IIA 134 (0-100%) 100% IA40 FW PP RECIRCS lIA136 (0-100%) 100% IA41 N2 SUPPLY TO SAC'S (OFF/ON) OFF IA42 ftISC SYSTEMS ISOL VLV OIA100 (0-100%) 100% IA43 IA ISO TO 11A065 (ON/OFF) ON IA44 IA ISO TO IIA 066 (ON/OFF) ON IA45 1SA01 CMPRSR CONTACT 1PSL-SA004 ON (NCRHAL,' 0 PEN) 3TR RELAY NORMAL IA46 U-1 3CR,4CR, & 8CR LOCAL RESET (NORM / RESET) 46
. - . ._ ._ _ ___ . . . . . . . _ _ _ - ~ _ _ _ . _ . - . _ _ . _ _ . _ _ _ . ...__m_...
i BYRON SIMULATOR-- '[ ANSI /ANS-3.5-1985 CERTIFICATION REPORT ; INITIAL P.EPORT, SEITEMBER,-1991 ' r Oa APPENDIX 2 i REMOTE FUNCTION LISTINGS t
't i
NORM IA47 -U-0-3CR,4CR,-& 8CR LOCAL RESET (NORM / RESET) {
= NORM- +
IA48 U-2 3CR,4CR, & 8CR LOCAL RESET (NORM / RESET) } ,' NORM i IA49 SAC.2-UNLOADER VALVE (0-100%)_ i 64.4%. _ t t I w -t
-f
-i t
t V- t o i t l L
.- t
.. E l
t L 4 L a, 3 47 i ! -i l r
--- ,m.-. _ . - , . , _ . . . _ _
BYRON SIMULATOR ! ANSI /ANS-3.5-1985^ CERTIFICATION REPORT-- ! INITIAL REPORT, SEPTEMBER, 1991 ; LP) ' ; b APPENDIX 2- _ REMOTE FUNCTION LISTINGS j i i MS01 1ST MSR'A 15A VENT ES100A (CLOSE/OPEN) f CLOSE i MSO2 ~1ST MSR B 15B VENT ES100B (CLOSE/OPEN) ! CLOSE
.MS03 IST MSR A 15A VENT ES100C (CLOSE/OPEN) l CLOSE
- MSO4 IST'MSR B 15B VENT ES1000 (CLOSE/OPEN) i CLOSE -t MS05- IST MSR A 17A-VENT ES101A (CLOSE/OPEN) i CLOSE !
MS06- IST MSR B 17B VENT ES101B (CLOSE/OPEN) , CLOSE
~
MS07' 1ST MSR A 17A' VENT ES101C (ClOSE/OPEN) r CLOSE i MS08 11ST MSR B 17B VENT ES101D (CLOSE/OPEN) { CLOSE- : MSO9- STM DUMP ISO'VLV MS003A (0-100%) [ 100% i
<~q MS10 STM DUMP ISO-VLV MS003B (0-100%) ,
! 100%
'~' ,
MS11I STM DUMP ISO VLV MS003C (0-100%) l 100%-
,MS12 STM DUXP ISO VLV MS003D- (0-100%)
-100%-
- MS13 STM DUMP ISO VLV MS003E (0-100%) ,
1004
- MS14 STM DUMP-ISO VLV MS003F (0-100%)' ;
100%- ' MS15 STM. DUMP ISO VLV MS003G. (0-100%) .! 100%' i MS16 STM nUMPzISO'VLV MS003H (0-100%) l'
-100%
MS17 S'IM ~ DUMP ISO VLV MS003J (0-100%) f 100% MS18 STM DUMP ISO VLV MS003K (0-100%)' ; 100% MS19 - STM DUMP ISO VLV MS003L (0-100%) i 100%-
.MS20: STM DUMP ISO VLV-MS003M (0-100%) i
- 1004 -
MS21 1ST ST MSR A CND VENT ES97A (CLOSE/OPEN) l OPEN , ANY 48 -
i BYRON SIMULATOR l ANSI /ANS-3.5-1985 CERTIFICATION REPORT l INITIAL REPORT, SEPTEMBER, 1991 (-
\- APPEND 1X 2 REMOTE FUNCTION LISTINGS MS22 IST S't MSR B CND VENT ES97D (CLOSE/OPEN)
OPEN MS23 IST ST MSR A C'4D VENT ES97C . (CLOSE/OPEN) OPEN
..S24 IST ST MSR 3 CND VENT ES97D (CLOSE/OPEN)
OPEN MS25 2ND ST MSR A CND VENT ES99A (CLOSE/OPEN) OPEN MS26 2ND ST MsR B CND VENT ES99B (CLOSE/OPEN) OPEN MS27 2ND ST MSR A CND VENT ES99C (CLOSE/OPEN) OPEN MS28 2ND S? MSR B CND VENT ES99D (CLOSE/OPEN) OPEN MS29A A MSR SHL NORM POS HD099A (0-100%) 100% MS29B B MSR SHL NORM POS HD099B (0-100%) 100% fs MS29C A MSR SHL NORM POS HD099C (0-100%) 100% MS29D B MSR SHL NORM POS HD099D (0-100%) 100% MS30A A MSR SHL NORM IA* RID 099A (CLOSE/OPEN) OPEN MS30B B MSR SIIL NORM IA HD099B (CLOSE/OPEN) OPEN MS30C A HSR SHL NORM IA HD099C (CLOSE/OPEN) OPEN MS30D B MSR SHL NORM IA HD099D (CLOSE/OPEFi 1 OPEN MS31A A MSR SHL EMER POS HD087A (0-100%) 100% MS31B B MSR E'IL EMER POS HD087B (0-100%) 100% MS31c A MSR SHL EMER POS HD037C (0-100%) 100% MS31D B MSR SHL EMEP POS HD087D (0-100%) 100% MS32A A MSR 6HL EMER IA HD087A (CLOSE/OPEN) OPEN MS32B B MSR SHL EMER IA HD087B (CLOSE/OPEN) OPEN O 49 I i _ _ _ _ _ b
BYRON SIMULATOR ANSI /ANS-3,5-1985.CERTIFIC4 TION REPORT
. INITIAL' REPORT, SEPTEMBER, 1991
--w-" APPENDIX 2 REMOTE FUNCTION LISTINGS
-l MS32C - A MSR SHL EMER IA HD087C (CLOSE/OPFN)
OPEN MS32D B MSR SHL EMER IA HD087D (CLOSE/OPEN) OPEN MS33A A Mc3 IST. NORM POS HD002A (0-1004) 100% MS33B B MSR IST NORM POS HD002B (0-100%) . 100% I MS33C A MSR IST NORM POS HD002C (0-1004) 230% MS33D B MSR'1ST NORM POS HD002D (0-100%) 100%- MS34A A MSR IST NORM IA HD002A (CLOSE/CPEN) l OPEN HS34B B MSR IST NORM IA HD002B (CLOSE/OPEN) OPEN MS34C A MSR IST NORM IA HD002C (CLOSE/OPEN) OPEN f-wg MS34D B MSR IST NORM IA HD002D (CLOSE/OPEN) ; V MS35A OPEN A MSR IST EMER POS HD032A J L (0-100%) . 100% MS35B B MSR 1ST EMER POS HD032B (0-100%) 100% MS35C A MSR.1ST EMER POS HD032C (0-100%) , 1004 g MS35D- B-MSR IST EMER POS HD032D (0-100%) l 100%
~
- . :MS36A JL MSR IST EMER IA HD032A (CLOSE/OPEN) >
0 ~OPEN-L MS36B B.MSR IST EMER 3A=HD032B (CLOSE/OPEN) OPEN
-MS36C- A MSR 1ST EMER IA HD032C (CLOSE/OPEN) l . .
OPEN l MS36D B MSR IST EMER IA HD032D (CLOSE/OPEN) L OPEN j l MS37A A MSR 2ND NORM-POS HD005A (0-100%) i p 100% MS37B 'B-MSR 2ND NORM POS HD005B (0-100%) 100% MS37C A MSR 2ND NORM POS HD005C (0-100%) 100% w :
%) .
50 a
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 r ,
'ws APPENDAX 2 REMOTE FUNCTION LISTINGS i
MS37D B MSR 2ND NORM POS HD005D (0-100%) , 100% MS38A A MSR 2ND NORM IA IID005A (CLOSE/OPEN) OPEN MS38B B MSR 2ND NORM IA HD005B (CLOSE/OPEN) OPEN MS38C A MSR 2ND NORM IA HD005C (CLOSE/OPEN) OPEN MS38D B MSR 2ND NORM IA HD005D (CLOSE/OPEN) OPEN i MS39A A MSR 2ND EMER POS HD035A (0-100%) > 100% MS35B B MSR 2ND EMER POS !!D030B (0-100%) 100% MS39C A MSR 2ND EMER POS HD035C (0-100%) 100% MS39D B MSR 2ND EMER POS HD035D (0-100%) 100%
- 1
("] sq MS40A A MSE 2ND EMER IA HD035A OPEN (CLOSE/OPEN) MS40B B HSR 2ND EMER IA HD035B (CLOSE/OFEN)
. .OPEN MS40C A MSR 2ND EMER IA HD035C (CLOSE/OPEN)
OPEN MS40D B MSR 2ND EMER IA HD035D (CLOSE/OPEN) OPEN MS41 ES TO 17A HTR ES006A (0-100%) 100% MS42 ES TO 17B HTR ES006B (0-100%) 100% MS43 ES TO 16A HTR ES003A (0-100%) 100% MS44 ES TO 16B HTR ES003B (0-100%) l; 100% MS45 ES TO 15A HTR ES009A (0-100%) 100% MS46 ES TO 15B HTR ES009B (0-100%) 100% MS47 MN STM SUPPLY TC GS MS167 (CLOSE/OPEN) CLOSE MS48 AUX STM FD ^.'O GS MS163 (CLOSE/OPEN) CLOSE 51
t i BYRON SIMULATOR '
- ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPOkT, SEPTEMBER, 1991 -s/ APPENDIX 2 REMOTE Fi'NCTION LISTINGS i i
MS49- PRESSURE REGULATED LOAD (0-100 PSIG) 4 50 PSIG -i MS50 BOILER DISCH.VLV AS168- (0-100%) 100% + MSS 1 -SG 1A PORV ISOL VLV MS019A- (0-100%) 100% . MSS 2 SG 1B PORV ISOL VLV MS019B (0-100%) l 100% ' MSS 3 SG 1C PORV ISOL VLV MS019C (0-100%) i 1004
- MS54 SG 1D PORV ISOL VLV MS019D (0-100%) ;
100% > MS55 SG PORV A HAND CONTROL (0-100%) [ 0% i MS56 SG PORV B RAND CONTROL (0-100%) [' 0%' MS57: SG-PORV C HAND-CONTROL (0-100%)- 0% i MS58 SG PORV D KAND CONTROL ' (0-100%) j O- MS$9 0% AUXILIARY BOILER PRESSURE (0-200 PSIG) 180 PSIG- l MS60 - MSIV HYD PP IA ISOL' (NORM /ISOL) : NORM -i MS61 MS FLASH TK DRN MS161 (CLOSE/OPEN) - CLOSE t I r I I i ! l L 52 r i
- - - - - . - - - - , - m,,- , , , . --,,---s , , - , < ~ ~ - . . , - - - , . . - rw,~,, ,- , .vy.
,. - , s, ,- .,e--,-
i BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 (- \~- APPENDIX 2 REMOTE FUNCTION LISTINGS f i NIO1 SR HI S/D FLUX STPNT N31 (10EO-10E6 CPS) 100 NIO2 SR HI S/D FLUX STPNT N32 (10EO-10E6 CPS) 100 NIO3 INCORE DET A EMERG/STOR BOTTOM LIMIT (0-2000 INCH) 134 NIO4 INCORE DET A EMERG/STOR TOP LIMIT (0-2C00 INCH) - 299 + NIO- INCORE DET A CALIBRATE BOTTOM LIMIT (0-2000 INCH)
-1440 NIO6 INCORE DET A CALIBRATE TOP LIMIT (0-2000 INCH)
- 1610 NIO7 INCORE DET B EMERG/STOR BOTTOM LIMIT (0-2000 INCH) ,
217 NIO8 INCORE DET B EMERG/STOR TOP LIMIT (0-2000 INCH) 367 NIO9 INCORE DET B CALIBRATE BOTTOM LIMIT (0-2000 INCH) 1460 NII0 INCORE DET E CALIBRATE TOP' LIMIT (0-2000 INCH) , t
\~'j 1630 Nill INCORE DET C EMERG/STOR-BOTTOM LIMIT (0-2000 INCH) 215 -
NI12 INCORE DET C EMERG/STOR TOP LIMIT (0-2000 INCH) i 365 < NI13 INCORE DET C CALIBRATE BOTTOM LIMIT (0-2000 INCH) 1470 NI14 INCORE DET C CALIBRATE TOP LIMIT (0-2000 INCH) 1640 , NI15 INCORE DET D EMERG/STOR BOTTOM LIMIT (0-2000 INCH) 215 NI16 INCORE DET D EMERG/STOR TOP LIMIT (0-2000 INCH) 365 NI17 INCORE DET D CALIBRATE BOTTOM LIMIT (0-2000 INCH)- 1520 NI18 INCORE DET D CALIBRATE TOP LIMIT (0-2000 INCH) 1690 ' NI19 INCORE DET E EMERG/STOR BOTTOM LIMIT (0-2000 INCH) 215 NI20 INCORE DET E EMERG/STOR TOP LIMIT (0-2000 INCH) 365' NI21 'INCORE DET E CALIBRATE BOTTOM LIMIT (0-2000 INCH) ! 1520 ' v 53
.._ _ . - . . . -. _ . - - . _ . _ _ . _ . - . _ , ~ _ .
_ _ .s.. . i oYRON SIMULATOR i ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORTj SEPTEMBER, 1991 6 APPENDIX 2 REMOTE FUNCTION LISTINGS ! l f NI22 INCORE DET E CALIERATE TOP LIMIT (0-2000 INCH) 1680 NI23 INCORE DET F EMERG/STOR BOTTOM LIMIT (0-2000 INCH) 215 NI24 'INCOT1E DET F--EMERG/STOR TOP LIMIT (0-2000 INCH) ! 365 t NI25- INCORE DET F CALIBRATE BOTTOM LIMIT (0-2000 INCH) I 1520 ' NI26 INCORE DET F CALIBRATE TOP LIMIT (0-2000 INCII) 't 1690 NI27 COURSE GAIN ADJ. ON NI POWER RANGE (0-5 VOLTS) , 1'. VOLT ' I t
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' INITIAL REPORT, SEPTEMBER, 1991 !
I APPENDIX 2 REMOTE FUNCTION-LISTING 3 -
-f
)
RD01 DRPI PWR TRANSFER SWITCH (SWITCH /OFF)- ! SWITCH- ' RD02 PA CONVERTER CB A (0-235 STEPS) I o + RD03 -PA CONVERTER CB T, (0-235 STEPS) i 0 RD04 PA CONVERTER CB D (0-235 STEPS) l 0 ! RDOS PA CONVERTER CB D (0-235 STEPS) ! 0-RD06 'M3 SET BRK A (NORMAL / TRIP) , TRIP -i RD07 MG SET BRK B ' (NORMAL / TRIP) TRIP RDO8 -RESET STOP COUNTER (NOT_ STEP, STEP _0, STEP _ CURRENT) - DURING TRAINER RESET IC & FROZEN NOT STEP I
- RD09A. BANK OVERIIP SETPOINTS (0-500 STEPS) ;
116 STEPS *
- l ..
_ RD09B BANK OVERLAP.SETPOINTS (0-500 STEPS) 231. STEPS ;
- RD09C -BANK OVERLAP SETPp1NTS (0-500 STEPS)' [
232 STEPS i RD09D - -BANK OVERLAP SETPOINTS (0-500 STEPS) ! 347-STEPh ,
. RD09E : BANK OVERLAP-SETPOINTS (0-500 STEPS) i 348 STEPS :
- RD09F= BANK OVERLAP SETPOINTS (0-500 STEPS) -
463 STEPS
- RD* * = ROD'# DRPI SYSTEM OVR-(53_. RODS) _
(0-231 STEPS) 't 0 (FEEDBACK VALUE) ; i i O ! 55
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 [)h
\. APPENDIX 2 REHOTE FUNCTION LISTINGS RH01 RH TO CV LETDOWN RH8734A (0-100%)
100% RH02 RH TO CV LETDOWN RH8734B (0-100%) 0% RH03 RH RECIEC TO RWST RH8735 (0-100%) 0% ' RH04 TPN A RH/RCS SUCT RH8701A (0-100%) 100% RHOS TRN A RH/RCS SUCT RH8701B (0-100%) 100% RH06 TRN B RH/RCS SUCT RH8702A (0-100%) 100% RH07 TRN B RH/RCS SUCT RH8702B (0-100%) 100% RH08 TRN A RH DISCH XTIE RH8716A (0-100%) 0% RH09 TRN B RH DISCH XTIE RH8716B (0-100%) 0% gg RH10 TRN A RH MINIFLOW RH610 (0-100%) (j RH11 100% TRN B RH MINIFLOW RH611 (0-100%) - l 100% i RH12 TRN A RECIRC SUMP SI8811A (0-100%) l 0% , RH13 TRN B RECIRC SUMP SI88118 (0-100%) 0% RH14 THN A RWST TO RH SIB 812A (0-100%) 0% RH15 TRN B RWST TO RH SI8812P (0-100%) ! 0% ! RH16 RH HX A FLOW CONTROL RH606 (0-100%) 0% RH17 RH HX B FLOW CONI.ROL RH607 (0-100%) 0% RH18 RWST LO-2 930C NORM / TRIP (NORMAL / TRIP) NORMAL RH19 RWST LO-2 931C NORM / TRIP (NORMAL / TRIP) NOPMAL RH2O RWST LO-2 932C NORM / TRIP (NORMAL / TRIP) NORMAL RH21 RWST LO-2 933C NORM / TRIP (NORMAL / TRIP) NORMAL
,-m L) 56
DYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O APPENDIX 2 REMOTE FUNCTION LISTINGS FM01 1PR011J HI VAC LOCKOUT (NORM / RESET) NORM O O 57
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
/^T APPENDIX 2 REMOTE FUNCTION LISTINGS RP01 RX TRIP BRK A (52/RTA) (NORMAL / TRIP)
NORM (OUTPUT TRIP) RP02 RX TRIP BRK B (52/RTB) (NORMAL / TRIP) NORM (OUTPUT TRIP) RP03 SSPS GEN WARN BOTH TRAIN (NORMAL / TRIP) NORM PPO4 BYPASS BRK A (52/RTA) (NORMAL / TRIP) NORM RPOS BYPASS BKk B (52/RTB) (NORMAL / TRIP) , NORM RP06 BYA STATUS-BKR A (NORMAL /RACKIN) NORM RP07 BYB STATUS-BKR B (NORMAL /RACKIN) NORM - RP08 LIFTED LEADS CLEARS P-4: TRN A (NORMAL / LIFTED) HORM RP09 LIFTED LEADS CLEARS P-4: TRN B (NORMAL / LIFTED) NORM (~N RP10 CNMT PRESSURE HI-3 PB934A (NORMAL / BYPASS) V, NORM RP11 CNnT PRESSURE HI-1 PB934B (NORMAL / TRIP) NORM RP12 CNMT PRESSURF HI-2 PB934C (NORMAL / TRIP) l NORM ! RP13 CNMT PRESS HI-3 PB935A (NORMAL /DYPASS) NORM RP14 CNMT PRESS HI-1 PB935B (NORMAL / TRIP) l NORM RP15 CNMT PRESS HI-2 PB935C (NORM *.L/ TRIP) NORM RP16 CNMT' PRESS HI-3 PB936A (NORMAL / BYPASS) NORM RP17 CNMT PRESS HI-1 PB936B (NORMAL / TRIP) NORM RP18 CNMT PRESS HI-3 PB937A (NORMAL / BYPASS) NORM RP19 CNMT PRESS HI-2 PB936C (NORMAL / TRIP) NORM RP20 PROTECTION CABINET DOOR #1 (CLOSE/OPEN). CLCSE RP21 PROTECTION CABINET DOOR /2 (CLOSE/OPEN) CLOSE 1
] \_/ <
58 '
1 i BYRON SIMULATOR , ANSI /ANS-3.5-1NffS CERTIFICATION REPORT ! INITILL IMPORT,. SEPTEMBER, 1991-O APPENDIX 2 REMOTE FUNCTION LISTINGS i RP22 PROTECTIOti CABINET DOOR #3 (CLOSE/OPEN) ; CLOSE r RP23 PROTECTION CABINET DOOR #4 (CLOSE/OPEN) f CLOSE RP24 BDPS TEST SW RP-31A- (NORM / BYPASS) i NORM ! RP25 BDPS TEST SW RP-32A (NORM / BYPASS) ; NORM t RP26 SLAVE K606. PHASE A TRN A (NORMALIN/OUT) { NORM > RP27 SLAVE K612 PHASE A TRN A (NORMAL /IN/OUT) NOPM RP28 SLAVE K614 PHASE A TRN A [ (NORMAL /IN/OUT) ;
-NORM-
- RP29 SLAVE K605 PHASE A TRN A (NORMAL /IN/OUT)
NORM i RP30 SLAVE K607 PHASE A TRN A (NORMAL /IN/OUT) ! NORM i RP31' SLAVE K613 PHASE A TRN A (NORMAL /IN/OUT) > y NORM RP32 SLAVE K622 CNMT VENT TRN A (NORMAL /IN/OUT) ; NORM - ; RP33 SLAVE K615 CNET VENT TRN A- -(NORMAL /IN/OUT) NORM ' RP34- SLAVE K623 MS ISOL TRN A (NORMAL /IN/OUT) NORM ; RP35- SLAVE K616 MS ISOL TRN A (NORMAL /IN/OUT) ; l NORM I' RP36- SLAVE K644-CS ACT TRN A (NORMAL /IN/OUT)-- [ NORM ;
- RP37 SLAVE K643 CS ACT TRN A (FORMAL /IN/OUT)
NORM . ! RP38 SLAVE K633'AF PUMPS 1/4 S/G LO-2 TRN A (NORMAL /IN/OUT)- ! - NORM ; RP39 SLAVE K647 SI TRN A- (NORMAL /IN/OUT) i NOPE ' RP40 SLAVE K626 PHASE B TRN A
~
NORMAL /IN/OUT) -f NORM- i RP41 SLAVE K618' PHASE B TRN A (NORMAL /IN/OUT) NORM t l RP42- SIAVE K648 RWST LO-2 TRN A (NORMAL /IN/OUT) NORM i
+ - .:
/] l 59 ,
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 (" V) APPENDIX 2 REMOTE PUNCTION LISTINCS i RP43 SLAVE K621 FW TRIP TRN A (NORMAL /IN/OUT) ! NORM ' RP44 SLAVE K602 SI TRN A (NORMAL /IN/OUT) NORM RP45 SLAVE K604 SI TRN A (NORMAL /IN/OUT) NORM RP46 SLAVE K609 SI TRN A (NORMAL /IN/OUT) , NORM RP47 SLAVE K611 SI TRN A (NORMAL /IN/OUT) NORM RP48 SLAVE K631 LO LO TAVG TRN A (NORMAL /IN/OUT) : NORM RP49 SLAVE K603 SI TRN A (NORMAL /IN/OUT) NORM RP50 SLAVE K608 SI TRN A (NORMAL /IN/OUT) NORM ' RPS1 SLAVE K610 SI TRN A (NORMAL /IN/OUT) NORM ,q RPS2 SLAVE K606 PHASE A TRN B (NORMAL /IN/OUT) \J RP53 NORM SLAVE K612 PHASE A TRN B (NORMAL /IN/OUT) NORM RP54 SLAVE K614 PHASE A TRN B (NORMAL /IN/OUT) i NORM RP55 SLAVE K605 PHASE A TRN B (NORMAL /IN/OUT) NORM RP56 SLAVE K607 PHASE A TRN B (NORMAL /IN/OUT) NORM RP57 SLAVE K613 PHASE A TRN B (NORMAL /IN/OUT) NORM RP58 SLAVE K622 CNMT VENT TRN B (NORMAL /IN/OUT)
- NORM RP59 SLAVE K615 CNMT VENT TRN B (NORE %/IN/OUT)
NORM RP60 SLAVE K623 MS ISOL TRN B (NORMAL /IN/OUT) . NORM RP61 SLAVE K616 MS ISOL TPM B (NORMAL /IN/OUT) l NORM RP62 SLAVE K644 CS ACT TRN B (NORMAL /IN/OUT) NORM RP63 SLAVE K643 CS ACT TRN B (NORMAL /IN/OUT)
- NORM 60 e
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL R.TPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS RP64 SLAVE K633 AF PUMPS 1/4 S/G LO-2 TRN B (NORMAL /IN/OUT) NORM RP65 SLAVE K' - 7 SI B TRN B (NORMAL /IN/OUT) NORM RP66 SLAVE K626 FHASE B TRN B '(NORMAL /IN/OUT) NORM RP67 SLAVE K618 PHASE B TRN B (NORMAL /IN/OUT) NORM RP68 SLliVE K648 RWST LO-2 TRN B (NORMAL /IN/OUT) NORM RP69 SLAVE K621 FW TRIP TRN B (NORMAL /IN/OUT) NORM RP70 SLAVE K602 SI TRN B (NORMAL /IN/OUT) NORM RP71 SLAVE K604 S. TRN B (NORMAL /IN/OUT) NORM RP72 SLAVE K609 SI TRN B (NORMAL /IN/OUT)
- NORM
/~T RP73 SLAVE K611 SI TRN B (NORMAL /IN/OUT) () RP74 NORM SLAVE K631 LO LO TAVG TRN B (NORMAL /IN/OUT) NORM RP75 SLAVE K603 SI TRN,B (NORMAL /IN(OUT) NORM NP76 SLAVE K608 SI TRN B (NORMAL /IN/G'JT) NORM RP77 SLAVE K610 SI TRN B (NORMAL /IN/OUT) NORM RP78 FW PP/VLV TRIP FUSES TRN A (NORMAL / REMOVED) NORM RP79 FW PP/VLV TRIP FUSES TRN B (NORMAL / REMOVED) NORM-RPf'O MULTIPLEXER TEST SW A,B (NORM /INHA/INHB/AB_A/AB_B) NORM RP81 INPUT ERROR INHIBIT A,B (NORM /INHIBITA/INHIBITB) NORM RP82 MSTR OUTPUT SELECTOR SW-A,B (NORM / TESTA /TESTB) NORM RP83 SAFEGUARD ACTUATION SARA 1-2 CONTACT (NORMAL /OPEN) FOR 1ACV NORMAL rO k 61
. . -n....- , -..- -- -
_ ~ . . - . - - . - - - . - . . . - . . - . - - . _ . . . . - . . - - - . . . .
-i !
e 1 BYRON SIMULATOR ~l ANSI /ANS-3.5-1985 CERTIFICATION REPORT ! INITIAL REPORT, SEPTEMBER, 1991 i APPENDIX 2- :! REMOTE FUNCTION LISTINGS ! 4 i i I RP84 SAFEGUARD ACTUATION SARB 3-4 CONTACT (NORMAL /OPEN) I
;-FOR 1BSI- !
RP85 SAFEGUA ATION SARB 7-8 CONTACT (NORMAL /OPEN) FOR 1BRH ; NORMAL RP86 SAFEGUARD ACTUATION SARA 9-10 CONTACT (NORMAL /OPEN) ! FOR OA VC CHILLER j
-NORMAL f RP87 SAFEGUARD ACTITATION SARB 11-12 CONTACT (NORMAL /OPEN)
FOR 1BCS-- 1 NORMAI. l RP88' SAFEGUARD ACTUATION SARA 13-14 CONTACT l(NORMAL /OPEN) l FOR 1A + 0 CC ' i NORMAL- !
-RP89 SAFEGUARD ACTUATION ~SARB 15-16 CONTACT (NORMAL /OPEN) !
N R 1BSX--- -i NORMAL- ! ,.. RP90 SAFEGUARD ACTUATION SARA 17-18 CONTACT (NORMAL /OPEN)' 3 l; - FOR 1AAF l L NORMAL- 1 ! RP91 TRIP ALL ATWS,SG LEVEL B/S AND IMP B/S (NORMAL / TEST) ,1
-(TEST /DYPASS)-
NORMAL- ' f I e t Ll h' i L i L- ! L, : l l n i h i
- u. . !
!. l l y j is [- f G2 '!
.i i
.; ..u. -. _. . _ . . - _ . . . _ - . . _ - -
.x--.--.,,-,-- . .._..'_._
BYRON SIMULATOR , ANSI /ANS-3.5-1985 CERTIFICATION REPORT ! INITIAL REPORT, SEPTEMBER, 1991 13 i s/- APPENDIX 2 REMOTE FUNCTION LISTINGS ; RX001 RCS LO FLOW LOOP 1 FB414A (NORMAL / TRIP) f NCRM i RX002 RCS LO FLOW LOOP 1 FB415A (NORMAL / TRIP) NORM RX003 RCS LO FLOW LOOP 1 FB416A (NORMAL / TRIP) NORM 1 RX004' RCS LO FLOW LOOP 2 FB424A (NORMAL / TRIP) . NORM RX005 RCS LO FLOW LOOP 2 FB425A (NorNL/ TRIP) ; NORM > RXOO6 RCS LO FLOW LOOP 2 FB426A (NORMAL / TRIP) ! NORM } RCS LO FLOW LOOP 3 FB434A
~
RXOO7 (NORMAL / TRIP) NORM .- RX0L3 RCS LO FLOW LOOP 3 FB435A (NORMAL / TRIP) '
, NORM RX009 RCS LO FLOW LOOP 3 FB436A- (NORMAL / TRIP)
NORM CY RX01" RCS LO FLOW LOOP 4 FB444A (NORMAL / TRIP) (/ NORM RX011 RCS LO FLOW LOOP 4 FB445A (NORMAL / TRIP) :,
. . NORM )
RX012-- RCS LO FLOW LOOP 4 FB44CA (NORMAL / TRIP) NORM RXOD _ RCS OT DELTA T TB411C (NORMAL / TRIP) NORM - RX014, RCS OP DELTA T TB411G (NORMAL / TRIP) . NORM ! RX015 LO-LO TAVG TB412D. -(NORMAL / TRIP). NORM. . RXOl6- LOW TAVG TB412G (NORMAL / TRIP) [ NORM + P.X017 RCS OT DELTA T TB421C (NORMAL / TRIP) NORM. ~ RX018 RCS OP DELTA T TB421G (NORMAL / TRIP) ' NORM RX019 14-LO TAVG TB422D (NORMAL / TRIP) , NORM RX020 LOW TAVG TB422G (NORMAL / TRIP) NORM ! RXO21 RCS OT DELTA T TB431C (NORMAL / TRIP) i NORM-63 ;
.. . . - . - - - ~ . .- . _ . _, . . ~ ._-.- - . . - ~ _ - _. . . _ , _
h BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT,_ SEPTEMBER,.1991 ; i
'O. APPENDIX 2 {
REMOTE FUNCTION LISTINGS - s l
)
RXO22 RCS OP DELTA T TB431G (NORMAL / TRIP) ! Junut l- RX023 LO-LO TAVG TB432D (NORMAL / TRIP) ! NORM RXO24 LOW TAVG.TB432G (NORMAL /TuIP) l NORM : RXO25 RCS OT DELTA T TB441C (NORMAL / TRIP). : {0RM RXO26 RCS OP bELTA T TB441G
- NORM (NORMAL / TRIP) i
{ ! RX027: LO-LO T AVG TB442D (NORMAL / TRIP) e NORM RX028 LOW TAVG TB442G (NORMAL / TRIP)- . NORM i RXO29 PZR HI WATER LEVEL'PB459A (NORMAL / TRIP)' ! ! NORM- l c RXO30 PZR HI-WATER LEVEL PB460A (NORMAL / TRIP) j
- NORM- t
-RXO31 P3R-HI WATER LEVEL PB461A (NORMAL / TRIP) ;
NORM i RXO32 PZR-HI PRESSURE PB455A (NORMAL / TRIP) i
. . NORM l
RXO33> PZR ENABLE BLOCK-SI PB455B (NORMAL / TRIP) ! p HORM ' RXO34- PZR LOW PRESS TRIP PB455C (NORMAL / TRIP)- NORM:
- RXO35 PZR LOW PRESS SI-PB455D (NORMAL / TRIP)
NORM RXO36' -PZR HI PRESSURE PB456A (NORMAL / TRIP) - NORM '
'RX037 PZR= ENABLE-BLOCK SI PB456B (NORMAL / TRIP)- ,
-NORM i RXO36- PZR1 LOW PRESS TRIP PB456C (NORMAL / TRIP) _ ,
NORM- ! RXO39- PZRl LOW PRESS SI PB456D (NORMAL / TRIP) : NORM ' PXO 4 0. PZR HI PRESSURE PB457A (NORMAL / TRIP) NORM- : RXO41 'PZR-ENABLE' BLOCK SI PB457B (NORMAL / TRIP)
~
. NORM- !
RXO42- :PZR LOW-PRESS TRIP PB457C (NORMAL / TRIP)
- NORM ,
^
64 e ', e i i
BYRON SIMULATOR ANSI /ANS-3,5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 , I REMOTE FUNOTION LISTINGS RXO43 PZR LOW PRESS SI PB457D (NORMAL / TRIP) NORM - RXO44 PZR HI PRESSURE PB458A (NORMAL / TRIP) NORM ' RXO45 PZR LOW PRESS TRIP PB458C (NORMAL / TRIP) NORM , RXO46 PZR LOW PRESS SI PB458D (NORMAL / TRIP) NORM RXO47 SG1 HI-HI LEVEL LB517A (NORMAL / TRIP) NORM
- RXO48 SG1 LO-2 WATER LB517B (NORMAL / TRIP)
NORM , RXO49 SG1 HI-HI LEVEL LB518A (NORMAL / TRIP) , NORM RXO50. SG1 LO-2 WATER LVL L3518B (NORMAL / TRIP) ' NORM RXO51 SG1 HI-HI LEVEL LB519A (NORMAL / TRIP) NORM ( RX052 SG1 LO-2 WATER LVL LB519B (NORMAL / TRIP) Q] RX053 NORM SG2 HI-HI LEVEL LBS27A (NORMAL / TRIP) , NORM - RX054 SG2 LO-2 WATER LVL LB527B (NORMAL / TRIP) . NORM RXO55 SG2 HI-HI LEVEL LBS28A (NORMAL / TRIP) NORM RX056 SG2 LO-2 WATER LVL LB528B (NORMAL / TRIP) NORM ; RXO57 SG2 HI-HI LEVEL LBS29A (NORMAL / TRIP) NORM RX058 SG2 LO-2 WATER LVL LB529B (NORMAL / TRIP) NORM RX059 SG3 HI-HI LEVEL LB537A (NORMAL / TRIP) NORM RXO60 SG3 LO-2 WATER LVL LB537B (NORMAL / TRIP) NORM RXO61 SG3 HI-HI LEVEL LB538A (NORMAL / TRIP) r NORM RXO62 SG3 LO-2 WATER LVL LB538B (NORMAL / TRIP) NORM RXO63 SG3 HI-HI LEVEL LB539A (NORMAL / TRIP) NORM M4 v/ 65
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT i INITIAL REPORT, SEPTEMBER, 1993 , ()/
\- APPENDIX 2 REMOTE FUNCTION LISTINGS i
RXO64 SG3 LO-2 WATER LVL LB539B (NORMAL / TRIP) NORM RXO65 SG4 HI-HI LEVEL LB547A (NORMAL / TRIP) NORM RXO66 SG4 LO-2 WATER LVL LB547B (NORMAL / TRIP) NORM RXO67 SG4 HI-HI LEVEL LB548A (NORMAL / TRIP) NORM RXO68 SG4 LO-2 WATER LVL LB548P (NORMAL / TRIP) NORM RXO69 SG4 HI-HI LEVEL LB549A (NORMAL / TRIP) NORM RXO70 SG4 LO-2 WATER LVL LB549B (NORMAL / TRIP) NORM . RX071 SG1 LO-2 WATER LVL LB556C (NORMAL / TRIP) NORM RXO72 SG1 LO-2-WATER LVL LB557C (NORMAL / TRIP) NORM - fs RXO73 SG1 LO-2 WATER LVL LB558C (NORMAL / TRIP) l () RXO74 NORM SG1 TO-2 WATER LVL LBS59C ' (NORMAL / TRIP) ! NORM RXO75 SG1 HI STM RATE PB514A (NORMAL / TRIP) NORM RXO76 SG1 LO STM PRESS PB514B (NORMAL / TRIP) NORM RXO77 SG1 HI STM RATE P PB515A (NORMAL / TRIP) , NORM RXO78 SG1 LO STM. PRESS PB515B (NORMAL / TRIP) NORM RXO79 SG1 HI STM RATE PB516C (NORMAL / TRIP) NORM RX080 SG1 LO STM PRESS PB516A (NORMAL / TRIP) NORM i RXO81 SG2 HI STM RATE P PB524A (NORMAL / TRIP) NORM RX082 -SG2 LO STM PRESS PB524B (NORMAL / TRIP) NORM RX083 SG2 HI STM RATE P PB525A (NORMAL / TRIP) NOP.M . RX084 SG2 LO STM PRESS PB525B (NORMAL / TRIP) NOax
. [~h x>
66 9
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPCRT INITIAL REPORT, SEPTEMBER, 1991 V APPENDIX 2 , REMOTE FUNCTION LISTINGS RXO8t M2 HI STM RATE P PB526C (NORMAL / TRIP) NOPE RXO86 SG2 LO STM PRESS PB526A (NORMAL / TRIP) NORM RXO87 SG3 HI STM RATE P PB534A (NORMAL / TRIP) NORM " RXO88 SG3 LO STM PRESS PB534B (NORMAL / TRIP) NORM RXO89 SG3 HI STM RATE P PB535A (NORMAL / TRIP) NORM RXO90 SG3 LO STII PRESS PB535B (NORMAL / TRIP) NORM RXO91 SG3 HI STM RATE P PB536D (NORMAL / TRIP)
- HORM ,
RXO92 SG3 LO STM PRESS PB536A (NORMAL / TRIP) - NORM RXO93 SG4 HI STM RATE P PB544A (NORMAL / TRIP) NORM l A RXO94 SG4 LO STM PRESS PB544B (NORMAL / TRIP) l (j NORM RXO95 SG4 HI STM RLfE P PB545A (NORMAL / TRIP) - NORM RXO96 SG4 LO STM PRESS "PB545B (NORMAL / TRIP) NORM RXO97 SG4 HI S'.'M RATE P PB546D (NORMAL / TRIP) . l NORM r RXO98 SG4 LO S'fM PRESS PB546A (NORMAL / TRIP) NORM RXO99 -NOT ASSIGNED-I RX10C SG1 WTR HUiMER PROT. PB514C (NORMAL / TRIP) NORM RX101 SG2 WTR HAMMER PROT. PB524C (NORMAL / TRIP) NORM RX2 3.2 SG3 WTR HAMMER PROT. PB534C (NORMAL / TRIP) NORM RX103 SG4 WTR HAMMER PROT. PB544C (NORMAL / TRIP) NORM RX104 SG1 WTR HAMMEh PROT. PB515C (NORMAL / TRIP) NORM RX105 9G2 WTR HAMMER PROT. PB525C (NORMAL / TRIP) NORn
't o :
67 r
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INI*IAL REPORT, SEPTEMBER, 1991 ( ) APPENDIX 2 REMOTE FUNCTION LISTINGS RX106 SG3 WTR !!AMMER PROT. PB535C (NORMAL / TRIP) NORM RX107 SG4 WTR HAMMER PROT. PB545C (NORMAL / TRIP) NORM RX108 SG1 WTR HAMMER PROT. LB517D (NORR\L/ TRIP) NORM RX109 SG1 WTR HAMMER PROT. LB519F (NORMAL / TRIP) NORM RX110 SG1 WTR HAMMER PROT. LB556A (NORMAL / TRIP) NORM RX111 SG2 WTR HAMMER PROT. LB528D (NORMAL / TRIP) NORM RX112 SG2 WTR HAMMER PROT. LBS29F (NORMAL / TRIP) NORM RX113 SG2 WTR HAMMER PROT. LBS57A (NORMAL / TRIP) NORM RX114 SG3 WTR HAMMER PROT. LB538D (NORMAL / TRIP) NORM r~% g RX115 SG3 WTR HAMMER PROT. LB539F (NORMAL / TRIP)
! I NORM
f RX116 SG3 WTR HAMMER PROT. LB55BA (NORMAL / TRIP)
NORM RX117 SG4 WTR HAMMER PROT. LB547D (NORMAL /TRIF) NORM RX118 SG4 WTR HAMMER PROT. LB549F (NORMAL / TRIP) NORM RX119 SG4 WTR HAMMER PROT. LB559A (NORMAL / TRIP) NORM RX120 SG1 WTR HAMMER PROT. PB51GD (NORMAL / TRIP) NORM RX121 SG2 WTR HAMMER PROT. PB526D (NORMAL / TRIP) NORM RX122 SG3 WTR HAMMER PROT. PB536C (NORMAL / TRIP) NORM RX123 SG4 WTR HAMMER PROT. PB546C (NORMAL / TRIP) NORM RX124 SG1 HI-HI LEVEL LB556B (NORMAL / TRIP) NORM RX125 SG2 HI-HI LEVEL LB557B (NORMAL / TRIP) NORM RX126 SG3 HI-HI LEVEL LB558B (NORMAL / TRIP) NORM 1 l
./^'
v 68 1
BYRON SIMULATOR l ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O APPENDIX 2 REMOTE FUNCTION LISTINGS RX127 SG4 HI-HI LEVEL LB559B (NORMAL / TRIP) NORM RX128 -NOT ASSIGNED-RX129 -NOT ASSIGNED-RX130 -NOT ASSIGNED-RX131 -NOT ASSIGNED-RX132 -NOT ASSIGNED-RX133 -NOT ASSIGNED-RX134 -NOT ASSIGNED-RX135 RC LP1 OT DELTA T C3 TB411D (NORMAL / TRIP) NORM RX136 RC LP1 OP DELTA T C4 TB411H (NORMAL / TRIP) _f s NORM RX137 RC LP2 OT DELTA T C3 TB421D (NORMAL / TRIP)
. NORM RX138 RC LP2 OP DELTA T C4 TB421H (NORMAL / TRIP)
NORM RX139 RC LP3 OT DELTA T C3 TB431D (NORMAL / TRIP) NORM RX140 RC LP3 OP DELTA T C4 TB431H (NORMAL / TRIP) NORM RX141 RC LP4 OT DELTA T C3 TB441D (NORMAL / TRIP) NORM RX142 RC LP4 OP DELTA T C4 TB441H (NORMAL / TRIP) NORM RX143 TURBINE POWER P-13 PB505A (NORMAL / TRIP) NORM RX144 TURBINE POWER P-13 PB506A (NORMAL / TRIP) NORM RX145 SG1 LO-3 LEVEL LIS 431 (NORMAL / TRIP) NORMAL RX146 SC2 LO-3 LEVEL LIS 432 (NORMAL, TRIP) NORMAL RX147 SG3 LO-3 LEVEL IIS 433 (NORMAL / TRIP) NORMAL O 1 69 ,
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BYRON 3IMULATOR ANSI /ANS-3.5-1985 CERTIFICAT!CN REPORT INITIAL REPORT, SEPTEMBER, 1991 O APPENDIX 2 REMOTE FUNCTION LISTINGS RX148 SG4 LO-3 LEVEL LIS 434 (NORMAL / TRIP) NORMAL RX149 3PS-0505 AMS C-20 (NORMAL / TRIP) NORMAL RX150 1PS-0506 AMS C-20 (NORMAL / TRIP) NORMAL e O O O 70
i BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 b) APPENDIX 2 REMOTE FUNCTION LISTINGS SIO1 SI PP 1A DISCH VLV SI8921A (0-100%) 100% SIO2 SI PP 1D DISCH VLV SIB 921B (0-100%) 100% SIO3 SI TEST TO RWST VLV SI8963 (CLOSE/OPEN) CLOSE SIO4 1A CS RECIRC TO RWST SI001A (CLOSE/OPEN) CLOSE SIOS 1B CS RECIRC TO RWST SIOO1B (CLOSE/OPEN) CLOSE SIO6 SI PP RWST SUCT POS SI8806 ~ (0-100%) 100% SIO7 SI TO CL VLV POS SI8802A (0-100%) 100% SIO8 SI TO ,, D FOS SI8835 (0-100%) SIO9 SI TO Ht ,a C POS SI8802B (0-100%) 100% ( c' SIl0 PWR FOR SI CL TEST SI8823 (OFF/ON) OFF Sill PWR FOR SI HL TEST SI8824 . (OFF/ON) OFF SI12 PWR FOR RH HL TEST SI8825 (OFF/ON) OFF SI13 RH DISCH TO CL POS SI8809A (0-100%) 100% SI14 RH DISCH TO CL POS SI6809B (0-100%) 100% SI15 RH DISCH TO HL POS SI8840 (0-100%) 0% SI16 SI SUCT FROM RH POS SI8804B (0-100%) 0% SI17 PWR FOR ACCUM M/U SIB 871 (OFF/ON) OFF SI18 CV INJ LINE POS SI8801A (0-100%) 0% SI19 CV INJ LINE POS SI8801B (0-100%) 0% SI20 PWR TO RH HL TEST SI8890A (OFF/ON) OFF r (m 71
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS a SI21 PWR TO RH HL TEST SI8890B (OFF/ON) , OFF l SI22 PWR TO SI HL TEST SI8881 (OFF/ON) OFF SI23 PWR TO CV HL TEST SI8843 (OFF/ON) ; OFF i i i O : h r r h t t 6 i O ! 72 ,
?
-r s ..-r _ . . _ - , - --- . . , , , , . . . , . . ..,--.,y-c_,..--,m.,--.. .. - -... % w. ,. .._. ..-.,
BYRON-SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS SWO1 CC HX 0 OUTLET OSX007 (0-100%) 25% = 6000 GPM SWO2 CC HX 1 OUTLET 1SXOO7 (0-100%) 25% = 8000 GPM SWO3 SX PP A L.O. PP (OFF/ON) OFF SWO4 SX PP B L.O.-PP (OFF/ON) OFF i SWOS. SX PP 1A STNR DRN ISX150A (0-100%) 0%
-SWO6 SX PP 1B STNR DRN 1SX150B (0-100%) .
a% i SWO7 U-2 SX SUPPLY 2SX005 (0-100%) l 0% SWO8- SX TO FP ,CTIE OSX174 (0-100%) 0%. SWO9 SA COMP 1-WS312 (0-100%) 0% SW10 CB PP A OIL-CLR WS021A l
-(*}
Q, .0% (0-100%) SW11- CB PP B OIL CLR WS021B (0-100%) 0%. SW12 CB PP C CIL CLR TISO21C (0-100%) 0%
-SW13 CB PP D OIL CLR WS021D (0-100%)
0% SW14 CD PP A OIL CLR WS023A (0-100%) 0%. SW1b CD PP B OIL CLR WS023B (0-100%) 0% SW16 CD PP C OIL CLR WS023C (0-100%) 0% SW17 CD PP D OIL CLR WS023D (0-100%) 0%
- SW18 - FW PP A OIL CLR WS087 (0-100%)
04 SW19 GEN HYD COOLER WSO44A (0-100%) 0% SW20 GEN HYD COOLER WSO44B (0-100%) 0% SW21 GEN HYD COOLER WSO44C (0-100%)- 0%- 73 L
, BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS SW22 GEN HYD COOLER WSO44D (0-100%)
0% SW23 BLOWDOWN CONDENSER WS069 (0-100%) 100% SW24 WS PP 1A DISCH VLV OWS001A (0-100%) 100% SW25 WS PP 1B DISCH VLV OWS001B (0-100%) 100%
-SW26 WS PP 1C DISCH VLV OWS001C (0-100%)
100% SW27 WW TO SX BASIN POS WWO19A (0-100%) 0% SW28 WW TO SX BASIN POS WWO19B (0-100%) 0% SU29 FW PP B CLR CNTL SETPT ( 0-2 00'F) 12 0'F SW30 FW PP C CLR CNTL SETPT ( 0-2 00'F) 12 0'F SW31 EH CLR TEMP CNTL SETPT ( 0-2 00'F) i 110'F l SW32 EXCITER TEMP CNTL SETPT ( 0-100*C) , 4 0'C
~SW33 GC TEMP CNTL SETPT ( 0-2 00'F) 105'F SW34 TO CLR TEMP CNTL SETPT ( 0-2 00'F) 110'F SW35 ASSO OLR CNTL SETPT ( 0-2 00'F) 105'F SW36 H2SSO CLR CNTL SETPT ( 0-2 00'F) 105*F SW37 OSWO2PA PUMP CONTACT OLS-SXO96 ON (NORMAL /OPEN)
LOW BASIN LEVEL NORMAL SW38 OWS01PA PUMP CONTACT 5-7 ON OPLS-WS008A(NORMAL /OPEN) ON LOW NPSH NORMAL SW39 SW COOLING TOWER BLOWDOWN VLV OSX161A (0-100%) 100% SW40 SW COOLING TOWER BLOWDOWN VLV OSX161B (0-100%) 100% O 74
, .?
t BYRON ' SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 i 1 APPENDIX 2
- REMOTE FUNCTION LISTINGS e
TC01 DEH COMPUTER (RUN/ HALT) RUN , TCO2 EGC PERMISSIVE (NORM /IITHIBIT) ! NORM v TCO3 REMOTE MANUAL TURBINE TRIP (NORM / TRIP) NORM TC04 OPC CYCLING OF IV'S (NORM / INHIBIT) ! NORM TC05 EGC RAISE SIGNAL (NORM / RAISE) NORM ! TC06 EGC LOWER SIGNAL (NORM / LOWER) : NORM ' TC07 TURB TRIP BLOCK LEVER (NORM / TEST) NORM TC08 VACUUM TRIP TEST VALVE (CLOSE/OPEN) t CLOSE ! TC09 OVERSPEED TRIP TEST VALVE (CLOSE/OPEN)
/^ CLOSE
! \ TC10 THRUST BEAR TRIP TEST VLV (CLOSE/OPEN) ; CLOSE : l TC11. BEARING OIL TRIP TEST VLV (CLOSE/OPEN) l CLOSE i l l i
/
i (_/ 25 ;
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX-2 REMOTE FUNCTION LISTINGS THol RCP A OC TRIP DEFEAT (NORMAL / DEFEAT) NORM TH02 RCP B OC TRIP DEFEAT (NORMAL / DEFEAT) NORM TH03 RCP C OC TRIP DEFEAT (NORMAL / DEFEAT) NORM TH04 RCP D OC TRIP DEFEAT (NORMAL / DEFEAT) NORM THOS RCP A OVERCORRENT RESET (NORMAL / RESET) NORM TH06 RCP B OVERCURRENT RESET (NORMAL / RESET) NORM TH07 RCP C OVERCURRENT RESET (NORMAL /RESCT; NORM THOB RCP D OVERCURRENT RESET (NORMAL / RESET) NORM TH09. PRESSURIZER SPRAY ISO VLV RYO23 (0-100%)
- 100%
TH10 PRESSURIZER SPRAY ISO VLV RYO24 (0-100%) 100% 1 THil PRT VENT TO CNTMT 8043 (0-100%) 0% > TH12 PRT N2 SUPPLY REG STPT (0-50 PSIG) , 3 PSIG j TH13 LOCAL TRIP OF RCP 1A (HORMAL/ TRIP) ! NORM ! TH14 LOCAL TRIP OF RCP 1B (NORMAL / TRIP) NORM THIS LOCAL TRIP OF RCP 1C (NORMAL / TRIP) NORM TH16 LOCAL TRIP OF RCP 1D (NORMAL / TRIP) ! NORM TH17 REACT. VSL LVL ISOLATION (ISO /OPEN) OPEN TH18 LOOSE PARTS MONITORING SYS ALARM RESET (NORMAL / RESET) NORMAL i 76
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 e APPENDIX 2 REMOTE FUNCTION LISTINGS TP01 H2SSOP BYPASS VLV iTOS242 (0-100%) 50% TP02 GEN HYD VENT VIN 1HY5024 (0-100%) 0% TP03 GC FILT INLT GC5403/GC5404 (GC5403/GC5404) GC5403 TPO4 GC HX #2 OUTLT GC5405 (0-100%) 100% TP05 GC HX OUTLT GC5406/GC5407 (GC5406/GC5407) GC5407 TP06 GC HX INLT GC5408/GC5409 (GC5408/GC5409) GC5409 TP07 GC DEMIN INL GC5420/GC5422 (GC5420/GC5422) GC5420 TP08 GC DEMIN BYPASS GC5424 (0-100%) 0% TP09 GEN H2 SUPPLi REG 1HY5054 (0-100 PSIG) O PTIG () TP10 GEN CO2 SUPPLY 1HY5005 (0-100 PSIG) 3 PSIG TP11 ASSO B/U REG 1TOS264 (0-50 PSID) 8 PSID TP12 ASSO PRESS REG 1TOS256 (0-50 PSID) 12 PSID TP13 H2 PRESS REG TOS210/TOS217 (-50-+50 INH 2O) 0 INH 2O TP14 1GC01PA PUMP CONTACT 13B-13C ON (NORMAL /OPEN) 1PDS-GCO23 ON LOW D/P NORMAL TP15 TP LOCAL ALARM ACKNOWLEDGE (NORMAL /ACK) NORMAL O i 77 1
.. . . . . . . . ~ . .. - . . - . . _ - - -.
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS TUO1 TURNING GEAR LOCAL CONTROL SWITCH (AUTO / MANUAL) AUTO TUO2 TURNING GEAR LOCAL PUSHBUTTON (NORMAL /STOP/ START) NORMAL TUO3 TURNING OIL MAKEUP (CLOSE/OPEN) CICSE TUO4 TURNING OIL DRAIN (CLOSE/OPEN) CLOSE O O 78
_ . . . _ . . . _ _ . _ . - _ . - _ _ _. _- - - - - . -._.-_.-.-----m_. J BYRON SIMULATOR
.- ANSI /ANS-3.5-1985 CERTIFICATION REPORT-INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2- !
REMOTE FUNCTION LISTINGS
- WD01 SG A-BD CV SD0054A' (0-100%)
0%
. WD02 SG A BD-CV-SD0054B (0-100%)
- 0% '
WD03 SG D BD CV SD0054C (0-100%) l 0% ; WD04 SG D BD CV S O O54D (0-100%) ! 0% i WDOS SG B-BD CV SD0054E (0-1004) _ 0% ?
-WD06 SG B BD CV SD0054F (0-100%) f 0%
.WD07 SG C BD CV SD0054G (0-100%)
0% WD08 SG C BD CV SD0054H (0-100%) ; 0% l WD09 -CST /COND SEL WX293/WX883A (CST / CONDENSER) l
~
CST ;
; WD10 -- RCDT DRAIN TO SUMP RE9163 -(CLOSE/OPEN) .l .- CLOSE- '
WD11 RCDT DISCH RE9171/AB8551 (RWST/ HUT) M e
-WD12 RELEASE TK PUMP (OFF/ON)-
OFF- . WD13 RELEASE.TK DISCH VALVE (CLOSE/OPEN) -l CLOSE ; f i i f h I i e 10 ! l 79 -!
.a ,--. - - - . . . . - . . . - . . . . _ _ . . . . . _ . . - _ - - - - - , . . _ - . . - _ . . . . . _ . _ - _ _ _ _ . - _----..-____cu - - - -
l BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, ?.991 APPENDIX 2 REMOTE FUNCTION LISTINGS YRol THE RM11 POWER SUPPLY SW (NORMAL / BACKUP) NORMAL YR02 RM23 REMOTE / LOCAL SW (REMOTE / LOCAL) LOCAL O V 80
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT SEPTEMBER, 1991 O APPENDIX 3 : l LIST OF ACRONYMS / ABBREVIATIONS a O l 1 ) (BYRONSIM 113/38 08/22/91)
/
BYRON SIMULATOR ANSI /ANS-3,5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
/N U APPENDIX 3 LIST OF ACRONYMS / ABBREVIATIONS ACRONYM /ABBREVIMlCLN DESCRIPTIQS AF Aux 111ary Feedwater AN Annunciators BDPS Boron Dilution Prevention System BOL, BOC Beginning of Life (Cycle)
BOS Byron Operating Surve111 ante BVS Byron Tech Staff Surveillance CB Control Bank CC/CCH Component Cooling Water C/D Cooldown C&E Cause and Effects CH Containment CND Condenser CS Containment Spray CV/CVC Chemical & Volume Control CH Circulating Hater DC Direct Current r DCRDR Detailed Control Room Design Review ( D/G Diesel Generator DVR Deviation Report ED Electrical Power System EG Electrical Generators EOL, EOC End of Life (Cycle) ESD Equipment Status Display ESF Engineered Safety Features FP Fire Protection FH Feedwater, Heater Drain, Condensate GSEP Generating Station Emergency Plan HD Heater Drains HV Ventilation HX Heat Exchanger IA Instrument Air / Service Air IC Initial Condition i l O (BYRONSIM 113/39 08/22/91)
BYRON SIHULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 3 LIST OF ACRONYMS / ABBREVIATIONS (continued) ACROMtilABBEIYlAIl0N DISCE1EllDE KV Kilovolts LED Light Emitting Diode LER Licensee Event Report HF Halfunction MIDS Hovable Incore Detector System HOL, MOC Middle of Life (Cycle) HH/HWE Hegawatt Electrical NI/NIS Nuclear Instrumentation System PA Public Address PPC Plant Process Computer , PPH Parts per Hillion PRS /PZR Pressurizer i PS Primary Sampling PTA0 Production Training Administrative Procedure - Ope'ations r PHR Pressurized Water Reactor l RCFC Reactor Containment Fan Cooler .- Reactor Coolant Pump RCP RCS Reactor Coolant System l RD Rod Drive ; RF Remote function RH/RHR Residual Heat Removal i RIL Rod Insertion Limit r RH Radiation Monitoring '; RP Reactor Protection RPM Revolutions per Minute RX Reactor, Reactor Control , S/D Shutdown e SER Sequence of Events Recorder l S/G Steam Generator i SI Safety Injection ! SPDS Safety Parameter Display System , SS Steady State S/U Startup SH, SX Essential Service Hater l TC Turbine Control TH Thermohydraulics Model, Retact (RCS System) . TP Turbine Plant Aux 111arles : O TR TV Transient Test Turbine Oil [ (BYRONSIM 113/40 08/22/91) i
i BYRON SIMULATOR i
~
ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 0- APPENDIX 3 I LIST OF ACRONYMS / ABBREVIATIONS (continued) ! ACRONYM / ABBREVIATION DISCRIEIL0fJ UF Under Frequency ! UV Under Voltage ! VC Control Roc,m Ventilation $ HD Haste Drains, Gas Decay [ HR Hide Range /Hork Request ! XE Xenon l YR Radiation Monitor Display i l i I O ' h I i I O l (BYRONSIM 113/41 08/22/91) , -r. ...m-. , - , . . . , - . -
- - _~ -._ . _ . - - . . . _. - _
BYRON S!HULATOR l ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 ] -O- l i APPENDIX 4
-{
BYRON SIFJLATOR TRANSIENT TEST REVIEH BOARD QUALIFICATIONS O V
.(BYRONSIM 113/42 08/22/91) ,
)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT 1 INITIAL REPORT, SEPTEMBER, 1991- l APPENDIX 4 BYRON SIMULATOR TRANSIENT REVIEH BOARD QUALIFICATIONS The following is a list of the members and qualifications of the Byron Simulator Transient Review Board. MEMBEB QUAllflIAIl0MS
- 1. Dan J. Popkins Position - Byron Simulator Training 3 yrs.
Supervisor Background - SR0 Certified, Byron Station 1.5 yrs
. SR0 License, Byron Station 6.0 yrs.
- Shift Engineer, Byron Station 2.0 yrs.
- Shift foreman, Byron Station 2.0 yrs.
- Rad-Chem Foreman, Byron Station 2.0 yrs.
- Nuclear Station Operator, Byron 4.0 yrs.
Station
- Rad Chem Technician, Quad 4,0 yrs.
Cities Station
- 2. David H. Farr Position - Station Reactor Engineer, Byron 1.5 yrs.
Station Background - SRO License, Byron Station 3.0 yrs. SCRE, Byron Station 1.0 frs.
- Technica1 Staff Group Leader, 2.0 yrs.
Byron Station
- Shift Technical Advisor, Byron 1.0 yr.
Station Technical Staff Engineer, Byron 2.5 yrs, Station
- 3. William F. Hochstetter Position - Simulator Instructor, Byron 1.0 yr.
Station Background - Systems Qualified, Byron Station
- NRC SRO CertifIclation, SONGS
- General Services Instructor, 1.0 yr.
Dyron Station Electrical Maintenance 2.0 yrs. Instructor, Byron Station
- License /Non-License Operator 2.0 yrs.
Instructor, Byron Station
- - License /Non-License Operator 4.0 yrs.
Instruction, San Onofre i - U.S. Navy - Hech. Operator, 8.0 yrs. ! ELT, LELT, Prototype Instructor O 1 (BYRONSIM 113/43 08/22/91)
l BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 i APPENDIX 4 BYRON SIMULATOR TRANSIENT REVIEH BOARD QUALIFICATIONS (continued) HEMBER QUALIFICAT101(S
- 4. Martin R. Holfe Position - Simulator Instructor, Byron 2.0 yrs.
Station Background - SR0 Ceritification, 4.0 yrs. Byron /Braidwood Stations
- R0 License, Byron Station 4.0 yri.
- Simulator Instructor, 4.0 yrs.
Byron /Braidwood
- Nuclear Station Operator, Byron 4.0 yrs.
Station Equipment Operator, Byron 3.0 yrs. Station
- Foss11 Stationman, Kincaid
- 5. Steven H. Pettinger Position - Simulator Instructor, Byron 2.5 yrs.
Station Background - SRO License Byron Station O - R0 License Byron Station Shift Foreman, Byron Station 3.0 yrs. 4.0 yrs. 1.0 yr.
- Nuclear Station Operator, Byron 3.0 yrs.
Station
- Egalpment Operator, Byron 1.0 yr.
Station
- Euqipment Attendant, Byron 3.0 yrs.
Station O (BYRONSIM 113/44 08/22/91)
i BYRON SIMULATOR . AN$1/ANS-3.5-1985 CERTIFICATION REPORT l INITIAL REPORT, SEPTEMBER, 1991 l 78 - (v) - ! t APPENDIX 5 [ ANSI /ANS-3.5-1985 - CERTIFICATION REPORT -r CROSS REFERENCE MATRIX f f
?
I t i t [ l L i 7 8 1 (BYRONSIH 113/45 08/22/91) l 1
BYRON SIMULATOR t ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 ! APPENDIX 5 ANSI /ANS-3.5-1985-CERTIFICATION REPORT ' CROSS REFERENCE HATRIX ; 1 LOCATION IN CERTIFICATION ANSI /ANS-3.5-1985 REQUIREMENT REPORT- !
-i 1 CI l 0ff DESCRIPTION SECTION l 3.1.1 Normal Plant Evolutions A 3.2. Attachment 2 l 3,1,2 Plant Halfunctions A.1.3.2, A.3.4, Attachment 6 I r
3.2.1 Degree of Panel Simulation A.I.2.2 Attachment 5 1 3.2.2 Controls on Panels A.1.2.2
.i 3.2.3 Control Room Environment A.I.2.1, A.I.2.4 3.3.1 Control Room Systems A.1.2.3 t r
3.3.2 System Operation Outsids Control A.1.3.3, Appendix 2 l Room 3.4.1 Initial Conditions A.I.3.1, Appendix I i 3.4.2 Halfunctions~ A.I.3.2 3.4.3 Other Control Features A.I.3.4 3.4.4 Instructor Interface A.1.3.3, Appendix 2 { 4.1- Steady State Operation A 3.2, Attachment 2 4.2 Transient Operation A.1.3.2, A.3.2, A.3.3, ; Attachments 2 & 6 4,3 Simulator Operating Limits A'.3.4 4.4 Honitoring Capability Attachment 2 O i (BYRONSIH 113/46 08/22/91) ;
m , . . BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT
- INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 5 ANSI /ANS-3.5-1985-CERTIFICATION REPORT CROSS REFERENCE HATRIX LOCATION IN CERTIFICATION ANSI /ANS-3.5-1985 REQUIREMENT REPORT SECTION DESCRIPTION SECTION 5.1 Simulator Design Data A.2, Attachment 4 5.2 Simulator Update Design Data A.I.5, A.4.2, Attachment 4 5.3 Simulator Hodifications A.1.5, A.4.2, Attachment 4 5.4.1 Simulator Performance Testing A.2, Attachment 2 S.4.2 Simulator Operability Testing Attachments 2 L 6 g .
APPENDIX A. GUIDE FOR DOCUMENTING SIMULATOR PERFORMANCE, HAS UTILIZED AS THE FORMAT FOR THIS REPORT. THEREFORE, O
- APPENDIX A
.........c....CRO.S.S-REFERE.NCE MATRIX DATA HILL NOT........
.. ....... ........................... BE.L.ISTED.
- B.2.1 Steady State Performance A.3.2, Attachment 2 B,2.2 Transient Performance A.3.2, Attachment 2 O <
(BYRONSIH 113/47 08122/91)
- +%4 4 --.h.,,-
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 . n .q) , APPENDIX 6 ! SIMULATOR TESTING PROCEDURE AND HALFUNCTION f TESTING SCHEDULE , 5 b t I i c I b l (BYRONSIM 113/48 08/22/91) [
_ . _ _ . . . _ _ . _._._.-__..m _ . - - _ . _ - _ _ _ _ _ _. _ _ _ ... _ . _ _ . _ _ _ ._.. _ - PTA0-105 - l tsvisica 0 ! November, 1989 SIMULATot CERTIFICATION REPORTING AND TESTING PROGRAM. A. Purpose -1 i The purpose of this procedure is to:
~
-{
- 1. standardize initial and annual simulator certification report formate. l 1
- 2. Provide an approval mechanism for simulator certification reports.
- 3. define time requirements for installation of a reference plant modification.
4 standardize simulator certification testing procedures, j
- 5. establish an administrative procedure for performing simulator l certification testing.
{ B . -- References ! i
-1. ANSI /ANS-3.5-1985: Nuclear Power Plant simulators for Use'in !
Operator Training- ! I
- 2. 10CFR 55.45: Operating Tests
- 3. NRC Reg Guide 1.149 - Nuclear ?ower Plant Simulation Facilities for :;
- +
Use in Operator' License Examinations: i l' -(
- 4. NRC-NUREG 1258: Evaluation Procedure for Simulation Pacilities i Certified-under 10CFR 55 t
- 5. INP0 TQ-504: Simulator Configuration Management System - Good !
Practices -}
- 6. PTAG-115: Review and Processing of Operating Experience Event Reporta [
t
- 7. . PTAG-202: Production Training Department Revision Process }
l 1
- 8. Operations Policy #1: Configuration Management 't t
j' 9. Operations Policy #2: Simulator Pidelity and Appearance I i L 10. PTLO-101: Docunant Tracking and Review Process Procedure 5 I
- 11. PTAO-102: Tracking Training Course Changes Procedure -j
- 12. PTAO-103:- Simulator Work tequest Procedure -
- 13. PTAO-104: Simulator Review Soard Procedure i
I 1 305P 01/90 j l l I E.__ - . _ ._- _ _ _ . .- _ _ _ _ _ . . _.
PTAO-105 Revisicn 0 N:vember, 1989 C. Definitions
- 1. confiauration Manasament Control - A system that ensures that all training programs and the simulator appearance, performance, and environment are kept current and reflect the reference plant as closely as possible.
- 2. Damian Database - A collection of material which documents the current performance and appearance status of the simulator hardware and software. It is further defined as the contents of the General Tiles Pattern Simulator (SIM) file. Any document that is E2I in the General Files Pattern Simulator (SIM) file is considered RQI part of the Simulator Design Database.
- 3. Environ =antal Fidelity - The degree of similarity between the simulator and the reference plant in the environmental aspects such as lighting circuits, lighting inttusity, annunciator sound levels, and carpeting / flooring of the control room.
- 4. Fidality - The combination of Environmental, Functional, and Physical Fidelity.
- 5. Funetianm1 Fidality - The degree of similarity between the simulator l and the reference plant in the static and dynamic response of 1 equipment and controls. ,
- 6. Parformance Tanta - The tests used to verify that the dynamic behavior of the simulator adequately represent that of the reference plant as required by ANGI /ANS-5.5-1945 section 5.4 and NRC Reg Guide 1.149 section C.5.
7.. Phvaleal Fidelity - The degree of similarity between the simulator 1 L and the reference plant in the physical design and location of the 1 panels, equipment, instruments, and controla. I
- 3. Referanea Plant - The specific nuclear power plant reactor from which the simulator control room configuration, system control arrangement, and simulator design data is derived.
- 9. Simulator - A simulator incorporating detailed modeling of systema of the reference plant with which the operator interfaces in the control room. The control room operating consoles are included. Such a simulator demonstrates expected plant response to normal and off-normal conditions.
l l
- 10. Work Raousat - A document that identifies and tracks deviations in simulator performance or appecrance from the current Design Database; or a document that is used to justify simulator design changes that might be incorporated into the Design Database.
LO 2 305P 01/90
_ . _ _ _ . _ _ ..._ _ . _-. _ _ _ _ . - . _ _ _ . _ _ _ _ _ _ _ . , . _ _ _.m. .-._._ PTAO-105 { Rovicica 0 : , November, 1989 ! l n ~D. Procedure
- 1. ' Certification Reporting l
\
- a. Each <roduction Training Department Site Operations Staff !
preparea an initial-simulator certification report to be j submitted to the Simulator Review Board for approval. ,
- b. -!
After the initial reporte:each Production Training Department i Site Operation Staff. prepares a annual simulator certification I report which updates.the initial report. The annual simulator certification report is prepared on the anniversary date of the '{ i initial report. The annual. report-is used for~ internal ! documentation-only and approved by the Simulator Review Board. j
- c. Every four years after the initial simulator certification report, each Production Training Department Site Operations Staff prepares a Simulator Certification Update Report to be- i suhaitted to the-Simulator Review Board for approval. The i
Simulator Certification Update-Report'summarises the activities i of the previous 4 years on the simulator.- ' i t - d.- .The Initial, Annual, and Four Year Update certification reporte ! are written in the format identified in appendix A.of ~
-ANSI /ANS-3.5-1985: Nuclear Power Plant Simulators for Use:in:
Operator Training. An example,-the Braidwood Initial Certification Report is included as Attachnent T-1.-
- e. Por purposes of simulator certification reporting, the i Production Training Department has interpreted-l ANSI /ANS-3.5-1985: Nuclear power. Plant Simulators for Use in ;
operator Training, section=5.3 Simulator Modifications, to mean { the fellowing: 1 I
" Bach Production Training Department Site Operations Staff must '
identify reference plant modifications which have been declared operational on the next annual simulator certification report. -! The Production Training Department-Site Operations Staff then
- has one year (until the subsequent annual simulator '
(. certification report) to install the modification on the aimulator." In order to 4seure the highest fidelity of the simulator and the i ' best possible training environment, it is Production Training ; Department philosophy that plant modifications be installed and ' operational on the simulator within 12 months of the omarational l p Agla of the reference plant modification.- 1 f 3 305P 01/90 ! {
PTAO-105 Revielen 0 November, 1989
) 2. Certification Testing - Overview
- a. Each Production Training Department Site Operations Staff shall !
prepare certification test procedures to verify the fidelity of ' the simulator. The depth of these procedures shall be specific enough to ensure repeatability. Example of a test proceduree can be found in Attachment 2.
- b. Each year, the Production Training Department Site Operations Staff conducts performance tests as-required by NRC Reg Guide 1.149 section C.5. Each Production Training Department Site Operations Staff prepares a guideline specifying the testing schedule for each test.
- 3. Car'ification Testing Administrative Procedure
- a. A copy of the Simulator Test Cover Sheet, PTAO-105T1, shall be attached to each simulator cet tification test being performed with the test title, number, date performed, and a brief description of the test written on the Simulator Test Cover theet, FTAO-10$T1.
- b. The ou, one of the test shall be indicated on the Simulator Test Cover Sheet, FTAO-105T1 as follows:-
ps .........................'......................................- S
- NOTE
- e No test can be signed as successful and complete if e a any stau'ea tor work request (s) were written as a result
- of performing the test. All simulator work request (s) *
- associated with a particular test must be cleared
- Prior to accepting that test as completed. *
*eeeeeee**eeeeeeeeeeeeeeeeeeeeee................................
- 1) If the test PASSES and E0 mi-nlator work raouants were written as a result of performing this test, the test is considered acceptables a) check the appropriate space on the Simulator Test-Cover Sheet, PTA0-105T1.
I b) sign and date the Simulator Test Cover Sheet,
?TA0-105T1.
c) file in the SIM file. O 4 305P 01/90 1
PTAO-105 Revisica 0 Navtaber, 1989
- 2) If the test PASSES, but gema simulator work recuenta y ng written as a result of performing this test, the test is considered acceptable but not complete until all associated work request have been completed:
a) check the appropriate space on the Simulator Test Cover Sheet, PTAO-05T1. b) sign and date the Simulator Test Cover Sheet, PTAO-105T1. c) write any simulator work requests referencing the test by number on the work request. d) write the simulator work requests number (s) on the Simulator Test Cover Sheet, PTAO-10$T1, when work request numbers have been assigned. e) after the associated simulator work request era completed, so indicate on the Simulator Test Cover Sheat, PTAO-105T1. f) after all simulator work requests are completed, file in the SIM file.
- 3) If the test FAII.5 a) check the appropriate space on the Simulator Test -
Cover Sheet, FTA0-105T1. b) sign and date the Simulator Test Cove'r Sheet, PTAO-105T1. c) attach Simulator Test Cover Sheet, PTAO-105T1, to the test docusant. d) write any simulator work requests referencing the test by number on the work request. e) write the slaulator work requests number (s) on the Simulator Test Cover Sheet, PTAO-105T1, when work request numbers have been assigned. f) after the simulator work requests are completed, so j_ indicate on the Simulator Test Cover Sheet, PTAO-105T1. l g) use additional Simulator Test Cover Sheets,
- PTAO-105T1, for performing subsequent-tests. Use the i
original test number on any additional sheets. The original test sheet must remain with the test document. O 5 305P 01/90
-1 i
PTAO-105 I tevision 0 I
.Movember, 1989 E.- Attachments-Appendix 1. Braidwood Simulator Initial Certification Report !
i Appendix 2. Examples of Testing Procedures i PTA0-105T1 Simulator Test Cover Sheet l t l i i i i t o
- i i ;
1 Arthur M. Roberts , Production T;2ining Manager f h b I L i L ! [ t O . 6 305P 01/90
DYRON SIMULATOR ! ANSl/ANS 3.51985 CERIFICATION REPORT l INITIAL REPORT, SEPTEMBER,1991 l APPENDIX 6 , O SIMULATOR M ALFUNCTION TESTING SCHEDULE l Int 2 11In Ini_CICLLIDMARILEdLAlu !
! AN01 LOSS OF ANNUNCIAlOR HORN 1s11992 l AN02 LOSS OF FUSE TO THE AN CABINET RACK 1s11993 !
CC01 COW PUMP FAILS TO STAfVTRIP 1s11992 f CCO2 CCW PUMP DISCH PRESS INDICATOR FAILURE ist 1992 [ CC03 CC# SURGE TANK LEVEL INDICATOR FAILURE 1:11993 i CC04 ESSENTIAL CCW TO RUR HX LF,*A 1si1992 l CC05 CCW TJ THE CCW HX PIFING BREAK 1:11993 j CC06 NON ESSENTIAL CCW S" STEM LEAh, 1st 1994 ! CC07 RCP THERMAL B8 RRIER LEAK 1611995 f CC08 CW HX TUBE LEAK 1st 1995 f CC09 THERMAL BARRIER CCW FLOW X MITTER FAILURE 1st 1994 i CH01 RCFC FAN FAILS TO START / TRIP, LOW SPEED 1st 1993 ! CHD2 RCFC FAN FAILS TO START / TRIP, HIGH SPEED ist-1994 CH03 CRDM FAN FAtLS TO START / TRIP ist 1995 CH04 RE ACTOR CAVITY BOOT FAILURE 1st 1994 i CS01 CONTAINMENT SPRAY PUMP FAILS TO START / TRIP 1411995 l CS02 CONT AINMENT SPRAY PUMP SUCTION LINE BREAK 1s11994 l CV01 CHARGING PUMP FAILS TO START / TRIP 1:11993 l 0' CV02 CV03 PRI WATER MAKE-UP PUMP FAILS TO START / TRIP DORIC ACID XFER PUMP 1 AB03P FAILS TO START / TRIP ist 1992 It.t 1995 . CV04 VCT DIVERT VALVE FAILURE (112A) 1st 1992
- CV03 PCV 131 AUTO CONTROL FAILURE 1st 1993
~
CV06 CLOGGED RCS FILTER (1CV3CF) 1st 1992 CV07 CLOGGED SEAL INJ FILTER 1st 1993 l CV08 I FAILURE OF PT 131 (LTDN PRESS) 1st 1992 CV09 FAILURE OF TE 130 (LTDN HX TEMP) 1st 1993 ! CV10 FLOW CONTROL VALVE 1CV121 FAILURE tst 1994 f CV11 CVCS UNDORATED MIXED BED DEMINERAllZER 1st 1992 I CV12 LTON RELIEF VALVE FAILS OPEN ist 1992 CV13 CHARGING LINE LEAK OUTSIDE CONTAINMENT 1st 1993 CV14 REGENERATIVE HX TUBE LEAK ist 1992 i CV15 SEALWATER HX TUBE LEAK 1st 1993 ! CV16 VCT LEVEL MALFUNCTION (112) 1st 1994 l CV17 VCT LEVEL MALFUNCTION (185) 1st 1995 [ CV18 VCT PRESS MALFUNCTION 1st 1995 ) CV19 MAKE UP CONTROL l- ALLURE 1st-1993 -
~
CV20 DORIC ACID rLOW TRANSMirTER (FT 110) FAILURE 1st 1994 C"21 CHARGING HEADER HCV 182 CONTROL FAILURE 1st 1995 CV22 LTDN LINE LEAK INSIDE CONTAINMENT 1511994 CV23 LTDN HX TUBE LEAK 1s11994 CV24 LTDN LINE LEAK OUTSIDE CONTAINMENT 1st 1995 CV25 CHARGING LINE LEAK INSIDE CONTAINMENT 1st 1995 i [
BYRON SIMULATOP ANSt/ANS 3.51985 CERIFICATION REPORT INITIAL REPORT, SEPTEMBER,1991 APPENDIX 6 O SIMJLATOR MALFUNCTION V TESTING SCHEDULE mun uta nu_cictumanuunu CV26 SEAL INJ LINE LEAKS 1st 1992 CV27 RCP SEAL st FAILURE ist 1994 CV28 RCP SEAL #2 FAILURE 1st 1995 CWOI CIRC WATER PUMP FAILS TO START / TRIP 1st 1993 CWO2 CIRC WATER PUMP DISCHARGE VALVE FAILURE 1s11994 , CWO3 NDCT LOSS OF EFFICIENCY 1st 1995 ED01 345 KV SWITCHYARD BREAKER FAILS TO TRIP 1st 1992 ED02 34$ KV SWITCHYARD BREAKER TRIP ist 1993 ED03 FAILURE OF UNIT AUX TRANSFr*"(ER (UAT) ist 1994 ED04 FAILURE OF SYSTEM AUX TB' '"4MER (SAT) 1st 1995 ED05 LOSS OF 6.9KV bus 1st 1992 ED06 FAILURE OF 6.9KV ABT 1st 1993 ED07 LOSS OF 4160V BUS 1sta 992 ED00 LOSS OF FEED TO GOV NON ESF BUS OR MCC ist1993 ED09 LOSS OF FEED TO 480V ESF BUS OR MCC 1st 1994 ED10 LOSS OF 120 VAC ESF CONSTANT VOLTAGE XFMR ist 1992 ED11 120 VAC INSTRUMENT BUS INVERTER FAILURE 1st 1993 ED12 LOSS OF DC DISTRIBUTK)N BUS 1s11995 ED13 1st 1994 O' ED14 OC CONTROL POWER FA' LURE (4160V) DC CONTROL POWER FAILURE (480V) 1st 1995 ED15 345 KV BUS FAULT . 1st 1992 ED16 LOSS 0" FEED TO 120V NON ESF PANEL 1st 1994 Era 7 LOSS 4 FEED TO 120V E3F FANEL 1st 1995 EG01 MAIN GENERATOR AUTO Vol.TAGE REGULATOR FAILUPC 1st 19CJ EG02 MAIN GENERATOR EXCTTER FAILURE 1st 1994 EG03 MAIN GENERATOR FIELD FORCING 1st 1995 EG04 iMSE FOLLOWER UNIT FAILS TO TRACK ist 1992 EGOS MAIN POWER TRANSFORMER TRIP 1st 1993 EGoo D/G FAILURE TO FLASH GENERATOR FIELD 1st 1994 EG07 D/G ELECTRIC SPEED CONTROL FAILURE 1st 1995 EGOS D/G SElZURE 1st 1992 EG09 D/G DIFFERENTIAL OVERC' .RRENT TRIP 1s11993 FP01 MANUAL FIRE SUPRESSON WATER SYSTEM 2nd 1994 FP02 AUTO FIRE SUPRESSION WATER SYSTEM ACTIVATON 1st 1995 FW01 MAIN FW PUMP FAILS TO START / TRIP (MOTOR) 2nd 1992 l FWO2 MAIN CW PUMP FAILS TO START / TRIP (TURBINE) 2nd 1993 l FWO3 START UP FEED PUMP FAILS TO START / TRIP 2nd 1994 i FWO4 MAIN FW OIL PUMP FAILS TO START / TRIP 2nd 1995 FWOS TURBINE DRIVEN MFP CONTROL VALVE FAILURE 2nd 1992 FWO6 TURBINE DRIVEN FW PUMP SPEED CONTROL FAILURE 2nd 1993 l FWO7 FW PUMP SPEED CONTROL OSCILLATES 2nd 1994 FWOS LOSS OF FW PUMP SPEED CONTROL 2nd 1995 l
BYRON SIMULATOR ANSl/ANS 3.51985 CERIFICATION REPORT INITIAL REPORT, SEPTEMBER,1991 APPENDIX 6 A SIMULATOR MALFUNCTION ly TESTING SCHEDULE ggg1B IRL1 Inv crett rouantig.nAgi FWO9 S/G FW CONTROL VALVE FAILURE 2nd 1992 FW10 FW REGULATION BYPASS VALVE FAILURE 2nd 1991 FW11 FW TEMPERING LINE ISOLATION VALVE FAILURE 2nd 1994 FW12 FW PREHEATER BYPASS VALVE FAILURE 2nd 1995 FW13 FW ISOLATION VA'.V i FAILURE 2nd 1992 FW14 FEED LINE BREAK b.! TWEEN FWOO9 & CONTAINMENT 2nd 1993 FW15 MAIN FW PUMP SHAFT BREAK 2nd 1994 FW16 FW HEADER PRESS FAILURE 2nd 1995 FW17 HEATER DRAIN TANK LEVEL CONTROLLER FAILURE 2nd 1992 FW18 FW HEATER TUBE LEAK (17) 2nd 1993 FW19 FW LINE BREAK INSIDE CONTAINMENT 2nd 1994 FW20 FW LINE BREAK OUTSIDE CONTAINMENT 2nd 1995 FW21 S/G TEMPERING LINE RUPTURE 2nd 1992 FW22 CONDENSATE PUMP FAILS TO START / TRIP 2nd 1993 FW23 FW HEATER BYPASS VALVE FAILURE (ICB025) 2nd 1994 FW24 CONDENSER EXHAUST HOOD PRESS XMITTER FAILURE 2nd 1995 FW25 GLAND STEAM CONDENSER MALFUNCTION 2nd 1992 FW26 MAIN FEED REGULATING VALVE SEAT LEAKAGE 2nd 1993 FW27 FW HEATER TUBE LEAK (11 DC) 2nd 1992 FW78 FW HEATER TUBE LEAK (11) 2nd 1993 FW29 FW HEATER TUBE LEAK (12) 2nd 1994 FW30 FW HEATER TUBE LEAK (13) 2nd 1995 FW31 FW HEATER TUBE LEAK (14) 2nd 1992 FW32 FW HEATER TUBE LEAK (15 DC) 2nd 1993 FW33 FW HEATER TUBE LEAK (15) 2nd 1994 FW34 FW HEATER TUBE LEAK (16) 2nd 1995 FW35 HEATER DRAIN PUMP FA!LS TO START / TRIP 2nd 1994 FW36 LOSS OF CONDENSER VACUUM 2nd 1995 FW37 HOTWELL LEVEL CONTROLLER FAILURE 2nd 1992 FW38 HOTWELL LEVEL CONTROLLER FAILURE 2nd-1993 FW39 HOTWELL LEVEL CONTROLLER FAILURE 2nd 1994 FW40 HOTWELL LEVEL CONTROLLER FAILURE 2nd 1995 FW41 FW ISOL AUX RELAY FAILURE (TRAIN A) 2nd 1992 FW42 FW ISOL AUX RELAY FAILURE (TRAIN B) 2nd 1993 FW43 AUX FW PUMP FAILS TO START / TRIP (MOTOR) 2nd 1994 FW44 AUX FW PUMP FAILS TO START / TRIP (TURBINE) 2nd-1995 FW45 AUX FW VALVE FAILURE 2nd 1992 FW46 AU FW LINE RUPTURE 2nd 1993 HV01 CONTROL ROOM MAKE UP FAN FAILS TO START / TRIP 2nd 1994 HV02 AUX BLDG CHARCOAL BOOSTER FAN FAILS TO 2nd 1995 IA01 LOSS OF INSTRUMENT AIR 2nd 1992 lA02 LOSS OF SERVICE AIR 2nd 1993
I BYRON SIMULATOR ANSl/ANS 3.51985 CERIFICATION REPORT INITIAL REPORT, SEPTEMBER,1991 APPENDIX 6 i C) S'*"#M8 1 M M'" - W H1LB 11111 1L1LucLE f 0WARILIL!iAR) f IA03 IA LEAK INSIDE OF CONTAINMENT 2nd 1994 f IA04 lA LEAK ON THE TURBINE BLDG HEADER 2nd 1995 { IA05 SERVICE AIR COMPRESSOR FAILS TO START / TRIP 2nd 1992 ( IA06 MSIV ROOM HEADER LEAK 2nd 1993 l' IA07 STEAM DUMP HEADER LEAK 2nd 1994 IA08 Al>X FEED VALVES HEADER LEAK l 2M 1995 IA09 PENETRATION AREA HEADER LEAK 2nd 1992 - MS01 FAILURE OF MAIN STEAM ISOLATION VALVE (S) 2nd 1993 [ MS02 MSIV BYPASS VALVE FAILUP.E 2nd 1994 ;
- MS03 SG SAFETY VALVE FAILURE 2nd 1995 i MSO4 S/G PORV CONTROLLER FAILURE 2nd 1992 i MS05 STUCK STEAM DUMP 2nd 1993 l MS06 MSR FAILS TO ISOLATE 2nd 1994 f MS07 STEAMLINE BREAK INSIDE CONTAINMENT 2nd 1995 i MS08 STEAMLINE BREAK OUTSIDE CONTAINMENT 2nd 1992 f
MSO9 FAAIN STEAM HEADER CROSS TIE RUPTURE 2nd 1993 l MS10 HEATER 13 EXTRACTION STEAM LINE BREAK 2nd 19s e N101 SR CHANNEL FAILURE 2nd 1995 N102 NCISY SR CHANNEL 2nd 1992 N103 SR CHANNEL HIGH VOLTAGE 2nd 1993 N104 FAILURE OF SR HIGH VOLTAGE TO DISCONNECT 2nd 1994 N105 SR DISCRIMINATOR FAILURE 2nd 1995 Nios IR CHANNEL FAILURE 2nd 1992 N107 INTER. RANGE CHANNEL GAMMA COMPENSATION 2nd 1993 N108 PR DETECTOR FAILURE 3rd 1994 N109 PR CHANNEL FAILURE 2nd 1995 N110 INCORE MONITORING SYSTEM FAILURE 3rd 1992 Nili STUCK INCORE DETECTOR 3rd 1993 N112 LEAK INTO GUIDE TUBE FOR INCORE DETECTOR 3rd 1994 i RD01 ROD DRIVE MG SET TRIP 3rd 1995 l RD02 DROPPED ROD 3rd 1992 i RD03 DROPPING ROD 3rd 1993 ( RD04 ROD EJECTION 3rd 1994 RDOS STUCK ROD 3rd 1995 RD06 RODS FAIL TO MOVE 3rd 1992 RD07 UNCONTROLLED ROD MOVEMENT 3rd 1993 RD08 DRPI DATA CABINET FAILURE 3rd 1994 RD09 AUTO ROD SPEED CONTROLLER FAILURE 3rd 1995 RD10 FAILURE ON LOGIC CABINET 3rd 1992 RD11 POWER CABINET FAILURE 3rd 1993 RD12 ROD STOPS Fall 3rd 1994 RD13 DRPI OPEN OR SHORTED COIL 3rd 1995 1
1 BYRON SIMULATOR ' ANS1/ANS 3.51985 CERIFICATION REPORT INITIAL REPORT, SEPTEMBER,1991 - APPENDlX 6 O tmutu nIn "WNN " its t..cicit. mMARTLE.IMju RH01 RHR PUMP FAILS TO ST ART /IRIP 3rd 1992 RH02 RHR HX FLOW CONTROL VALVE F ALLURE 3rd 1993 RH03 RHR HX BYPASS VALVE CONTROL FAILURE 3rd 1994 RH04 RHR AUTO SWITCH OVER MALFUNCTON 3rd 1995 RHOS RWST LEVEL TRANSMITTER MALFUNCTON 3rd 1992 RHoc RHR HX TUBE LEAK 3rd 1993 RH07 RHR HX BYPASd LINE LEAK 3rd 1994 RHOS RWST LEAK 3rd 1995 RH09 RHR '"MP SUCTON HEADER BREAK 3rd 1992 RH10 RHR ' MP DISCHARGE HEADER BREAK 3rc.1993 RH11 RELILF VALVE FAILURE 3rd 1994 RM01 AREA RADIATON PONITOR ACTUATON 3rd 1995 RM02 INOPERABLE RADIATON PONITOR 3rd 1992 RM03 INADVERTANT AUTO RADIATON IONITOR ACTUATON 3rd 1993 RM04 PROCESS RADIATON MONITOR ACTUATON 3rd 1994 RM05 RADIATON MONITOR INTERLOCK ACTUATON FAILURE 3rd 1995 RM06 GASEOUS AIR MONITOR FAILURE 3rd 1992 RP01 REACTOR TRIP FAILURE 3rd 1993 RP02 REACTOR TRIP BREAKER FAILURE 3rd 1994 v RP03 REACTOR TRIP BYPASS BREAKER FA: LURE 3rd 1995 RPO4 FAILURE OF PHASE A CNTMNT ISOL TO ACTUATE 3rd 1992 RP05 FAILURE OF PHASE B CNTMNT ISOL TO ACTUATE 3rd 1993 RF06 TURBINE TRIP INTERLOCK C-8 FAILS 3rd 1994 RP07 UNDER-FREQUENCY ON RCP DUSES 3rd 1995 RP08 UND5R VOLTAGE ON RCP BUS 3rd 1992 RP09 INADVERTANT FW ISOLATON 3rd 1993 RP10 INADVERTENT PHASE A CONTAINMENT ISOLATON 3rd 1994 RP11 INADVERTENT PHASE B CONTAINMENT ISOLATON 3rd 1995 RP12 IN AOVERTENT CONTROL ROOM VENT ISOLATON 3rd 1992 l RP13 REACTOR TRIP PERMISSIVE P-4 FAIL $ (O ACTUATE 3rd 1993 , RP14 FAILURE OF SAFETY INJ TO ACTUATE 3rd 1994 RP15 SAFEGUARD SEQUENCING FAILURE 3rd 1995 RP16 POWER PERMISSIVE P 6 FAILS TO ACTUATE 3rd 1992 RP17 POWER PERMISSIVE P 7 FAILS TO ACTUATE 3rd 1993 RPIB POWER PERMISSIVE P-8 FAILS TO ACTUATE 3rd 1994 RP19 POWER PERMISSIVE P 10 F AILS TO ACTUATE 3rd 1995 RP20 PZR PRESS LOW PERMISSIVE P 11 FAILG TO ACTUATE 3rd 1992 RP21 LO-LO TAVG PERMISSIVE P 12 FAILS TO ACTUATE 3rd 1993 RP22 POWER PERMISSIVE P 13 FAILS TO ACTUATE 3rd 1994 > RP23 Hi Hi S/G LEVEL PERMISSIVE P 14 FAILS TO ACTLIATE 3rd 1995 RX01 STEAM PRESS DETECTOR FAILURE 3rd 1992 j RX02 UNSTABLE S/G LEVEL CONTROLLER 3rd 1993 i
BYRON SIMULATOR ANSI /ANS 3.51985 CERIFICATION REPORT INITIAL REPORT, SEPTEMBER,1991 APPENDIX 6 SIMULATOR MALFUNCTION O, TESTING SCHEDULE twntia 111u lut evetr nouu1DuuB) RXO3 STEAM FLOW DETECTOR F AILURE 3rd 1994 RXO4 FW FLOW TRANSMITTER FAILURE 3rd 1995 RX05 STEAM LINE PRESS DETECTOR (PT 507, FAILURE 3rd 1992 RXOG NARROW RANGE S/G LEVEL FAILURE 3rd 1993 RX07 WIDE RANGE S/G LEVEL FAILURE 3rd 1994 RXO8 STEAM DUMP COOLDOWN VALVES CON 1 ROL FAILURE 3rd 1995 RX09 STEAM FLOW OSCILLATION TIME 3rd 1992 RX10 FIRST STAGE PRESS TRANSMITTER FA' LURE 3rd 1993 RX11 STEAM FLOW OSCILLATION . MAGNITUDE 3rd-1994 RX12 TREF FAILURE 3rd 1995 RX13 PZR LEVEL CHANNEL FAILURE 3rd 1992 RX14 FW PUMP MASTER SPEED CONTROLLER FAILURE 3rd 1993 RX15 PZR PRESS MASTER CONTROLLER FAILURE 3rd 1994 RX16 PZR LEVEL MASTER CONTROLLER FAILURE 3rd 1995 RX17 ROD CONTROL SYSTEM FAILURE 3rd 1992 RX18 FAULTY PRIMARY RTD (NARROW RANGE) (TC&TH) 4th 1992 RX19 LOSS OF LOAD INTERLOCK C 7 FAILS 4th 1993 RX20 CONDENSER AVAILABLE INTERLOCK C 9 FAILS 3rd 1995 O RX21 RX22 PZR PRESS CHANNEL FAILURE (455 & 456) PZR PRESS CHANNEL FAILURE (457 & 458) 4th 1991 4th 1992 RX23 , OVERPOWER DELTA T SETPOINT FAILURE 4th 1993 j
- RX24 OVERTEMPERATURE DELTA T SETPOINT FAILURE 4th 1994 RX25 RCS PRESS TRANSMITTER FAILURE (403 & 405) 4th 1991 RX26 RCS PRESS TRANSMITTER FAILURE (406 & 407) 4th 1992 RX27 RCS PRESS TRANSMITTER FAILURE (408 & 409) 4th 1993 RX28 RCS LOOP FLOW TRANSMITTER FAILURE 4th 1994 Stol SAFETY INJ PUMP FAILS TO START / TRIP 4th 1991 S10 2 SI ACCUMULATOR LEVEL XMITTER FAILURE 4th 1992 Sl03 COLD LEG INJ CHECK VALVE LEAKAGE (Sl8818) 4th 1993 l S104 COLD LEO INJ CHECK VALVE LEAKAGE (Sl8819) ,
4th 1994 S10 5 COLD LEO INJ CHECK VALVE LEAKAGE (S18948) 4th 1991 S106 COLD LEG INJ CHECK VALVE LEAKAGE (Sl8956) 4th 1992 Sl07 HOT LEG INJ CHECK VALVE LEAKAGE (Sl8905) 4th 1993 S108 HOT LEG INJ CHECK VALVE LEAKAGE (Sl8841) 4th 1994 S109 HOT LEG INJ CHECK VALVE LEAKAGE (Sl8949) 4th 1991 Sl10 HIGH HEAD SI LEAK INSIDE CONTAINMENT 4th 1992 Sit t SI ACCUMULATOR TANK RUPTURE 4th 1993 SWO1 SX PUMP FA!LS TO START / TRIP 4th 1994 SWO2 SX BREAK INSIDE CONTAINMENT 4th1991 SWO3 LOSS OF SX COOLING TO D/G 4th 1992 i SWO4 SX DISCHARGE HEADER BREAK 4th 1993 l SWOS WS HEADER BREAK 4 4 1994 l
- l. - - - - - .
BYRON SIMULATOR ANSl/ANS 3.51985 CERIFICATION REPORT INITIAL REPORT, SEPTEMBER,1991 APPENDIX 6 - O ttutt LB EILE SIMULATOR M ALFUNCTION TESTING SCHEDULE IL3LCICLL.lQUARIERlLAPJ T C01 INADVERTENT 1URBINE HUNDACK 4th 1991 TCO2 TURBINE TRIP ON LOW LOAD INDICAT ON (PDS T0071) 4th 1992 1C03 TURBINE AUTO TRIP FAILURE 4th 1993 TC04 TURBINE AUTO RUNDACK FAILURE 4th 1994 TC05 OPC . LP TURB INLET PRESS SENSOR (PT MS003) 4th 1991 TC06 DEHC IMPULSE PRESS TFMNSMITTER FAILURE 4th 1992 TC07 DEHC MW TRANSDUCER FAILURE 4th 1993 TCOB DEHC GV5V OSCILLATON TIME 4th 1994 TC09 DEHC . GWTV OSCILLATION . h%GNITUDE 4th 1991 TC10 LOSS OF DEHC SPEED CONTROL CHANNEL (S) 4th 1992 TC11 LOSS OF DEHC SUPERVISORY SPEED CHANNEL 4tN1993 TC12 EHC PILOT OPERATED IA VALVE STICKS (1EH5042) 4th 1994 TC13 TV SERVO FAILURE VALVE FAILS 4th 1991 TC14 GV SERVO FAILURE VALVE FAILS 4th 1992 TC15 EH SYSTEM LEAK 4th 1993 TC16 GOVERNOR VALVES NOT TRACKING AUTO 4th 1994 TC17 EH PUMP FAILS TO START / TRIP 4th 1991 i TH01 PZR STEAM SPACE LE AK 4th 1992 O TH02 TH03 PZR RELIEF TANK LEAK S/G TUBE LEAK 4th 1993 4th-1994 , TH04 RCS LEAK, HOT LEG (HIGH) 4th 1991 1H05 RCS LEAK, HOT LEG (MEDIUM) 4th 1992 THOG RCS LEAK, COLD LEG 4tha 993 ; TH07 REACTOR VESSEL FLANGE LEAK 4th 1994 ; TH08 RCS FUEL ELEMENT FAILURE 4th 1991 ! TH09 RTD MANIFOLD FAULTY FLOW CONDIT ONS 4th 1992 TH10 PZA SPRAY VALVE FAILURE 4th 1993 TH11 PZR POWER OPERATED RELIEF VALVE FAILURE 4th 1994 TH12 PZR SAFETY VALVE FAILURE 4th 1991 TH13 PZR LEVEL DETECTOR REFNARLABLE LEG LEAK 4th 1992 TH14 PZR RELIEF LINE RTD FAILURE 4th 1903 , THIS RCS WIDE RANGE HTD FAILURE a 4th 1994 TH16 RCP FAILS TO START / TRIP 1 4th 1991 ! TH17 RCP DEGRADED PI-RFORMANCEA.OCKED FK?l'OR 4th 1992 ' TH18 RCP SHAFT BREAK 4th 1993 TP01 STATOR COOLING WATER PUMP FAILS TO START / TRIP 4th 1994 [ TP02 ST ATOR COOLING WATER HIGH CONDUCTIVITY 4th 1991 TP03 SEAL OIL SYSTEM PUMP FAILS TO START / TRIP 4th.1992 i TUO1 TURBINE VIBRATON 4th 1993 l TUD2 TURBINE BEARING OIL PUMP FAILS TO START /IPiP 4th 1994 f TUO3 TURBINE HP SEAL OIL BU PUMP FAILS TO START /T Al? 4th 1991 [ TUO4 TURBINE DC EMER OIL PUMP FAILS TO START / TRIP 4th 1993
DYRON SIMULATOR I ANSI /ANS-3.51985 CERIFICATION REPORT INITIAL REPORT, SEPTEMBER,1991 APPENDIX 6 O EWERIB 11111
%^ Mere 8tE' "
ILif CYctf fQUARnaIIAR) ; TUO5 1URBINE OlL JYSTEM LEAK 4th 1992 i 1UOO DEARING LIFT PUMP SUCTON STRAINER CLOG 4th 1991 l WD01 GAS DECAY TANK RUPTURE 4th 1992 ! YR01 LOSS OF RM 11 COMMUNICATON LOOP 4th 1994 1 i I L i P l l i
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BYRON S!HULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INiilAL REPORT, SEPTEMBER, 1991 ATTACHMENT 1
- REG. GUIDE 1.149 REQUIREMENTS FOR DUAL PLANT SlHULATION FACILITY Comparison of the Byron Simulator to Byron Unit 2.
bJ O (BYRONSIM 113/49 08/22/91)
BYRON S!HULATOR ANS!/ANS-3.5-1985 CERTIFICA110N REPORT INITIAL REPORT, SEPTEMBER, 1991
'") LER DESCRIPIlON CQttLMIS l 1
90-001 MS Line Isolation /S! on S/G Pressure Tested Satisfactorily l Channel SptLing w/1 in Test Added to HF-RX01 C & E 90-002 fHI from 1Rfi B Rx Trip Breaker Not Tested j Unknown Cause, Inadvertent fHI Tested During Hf-fW9 Testing 90-006 Inadvertent SI Tested Satisfactorily No Specific HF 90-009 ESF Actuation from Lo-2 S/G Level Tested Satisfactorily During Draindown No Specific HF 90-010 MS Line Leal Manual RX & MS Line Tested Satisfactorily. r~T Isolatten Added to HF-MS08 C & E V O (BYRONSIH 113/51 08/22/91)
BYROH SlHULATOR ANSI /ANS-3.5-1985 CERTIFICA110N REPORT INITIAL REPORT, SEPTEMBER, 1991 O Production Training Department will re-evaluate the differences between the Unit I and Unit 2 S/G operations via surveys of the Byron Station Control Room operators and the DVR/LER review process. This re-evaulatuion will be conducted throughout the Unit 2 cycle 3 operation. He currently train the operators on the Unit 2 D-5 S/G classroom Initial and Requalification Training programs. This training incorporates the D-5 S/G alarm setpoints, ESF actuntion setpoints and the normal operating S/G 1evel. The operational characteristics of Byron Untt 2 compared to the simulator are considered equivalent. Above 307., Byron station feedback has reported that Unit I and Unit 2 respond in a similar manner. Since Unit I and Unit 2 are alnost identical, except for the steam generator model, adequate Unit 2 training is conducted by covering low-power operations (i.e., startups, shutdowns) and setpoints in the classroom. O Since Unit I and Unit 2 operate in a similar manner, only Unit 1 Procedures are maintained and used for simulator training. Unit 2 abnormal and emergency precedures are not maintained in the simulator since the Unit I abnormal and emergency procedures are utilized for Unit 2 abnormal operations and casualty training. The Unit 2 abnormal and emergency procedures are developed from Unit 1 abnormal and emergency procedures and are almost identical. In addition, Byron Units 1 and 2 emergency procedures are validated on the simulator. O (DYRONS!H 113/53 08/22/91)
BYRON SlHULATOR ANSI /ANS-3,5-1985 CERilf! CATION REPORT INITIAL REPORT SEPTEMBER, 1991 O l ATTACHMENT 2 STEADY STATE / NORMAL OPERATIONS / REAL TIME /1RANSIENT TEST RESULTS l l l l O t t l o l l (BYRONS!H 113/54 08/22/91) n ,. . - - , . . . . - - . - n-m..u, , - .r,-- - > - -,-e.-m-r -~ w - - . - - ,,.,,m-e,rv-,- w
BYRON SlHULATOR ANS!/ANS-3.5-1985 CERilflCATION REPORT INITIAL REPOPT, SEPTEMBER, 1991 BYRON SlHULATOR STEADY STATE TESTING The objective of the Steady State Testing is to verify the Byron Simulator performance meets the criteria of ANSI /ANS-3.5-1985 Section 4.1. Steady State heat balance tests were performed at 30%, 90% and 100% power. These power i levels were chosen due to availability of Byron Unit I plant data. I Additionally, a 100% power. 60 minute stability test was performed. Abstracts for these tests and associated results are included in this attachment. These tests were performed using a computer data collection program called POWER. Plant values obtained from the plant process computer were input and appear in the data sheets under the column heading " DATA". The program then collected the values from the simuletor computed variables, listed these undv the column heading " Actual", and j Os computed a percent error. Two data sheets are attached to each test; one for critical parameters and.one for non-critical parameters. The data was collected in accordance with ANSI /ANS-3.5-1985, Appendix B.2.1 with the exception of Boron Concentration and Control Rod Positions. Since Boron Concentration and Control Rod Positions vary depending on core conditions (previous operations, core burnup, and the current core cycle) these parameters were not included in the POWER program. Boron Concentrations for all tests were collected and compared to plant values resulting in deviations of ~ 7% to 201. Control Rod Positions for all tests were collected and compared to plant values resulting in deviations of .5% to 10%. These deviations are not considered discrepancies because the parameters vary based on core conditions and the simulator values do not detract from training. r k (BYRONSlH 113/55 08/22/91)
i DYRON S! HULA 10R t ANSI /Ahi-3.5-1985 CERTIFICAT!0N REPORT ! INITIAL REPORT, SEPTEMBER, 1991 l ( 1' BYRON S! HULA 10R STEADY STATE TEST p 30% POWER TEST r l The 30% Power Steady Statt Heat Balance fest was performed from a beginning of life, 30% power Initial Condittor (IC23). Data was collected and compared using the POWER program on the simulator. All critical i parameters were within 2% plus instrument error and all non-critical parameters were within 10% plus instrument error. Additionally, the critical and non-critical parameters values on the Simulator do not detract from training. ! P , () 7 i i 1 l l l (BYRONS!H 113/56 08/22/91) I
07/31/91 05:10:51 TASE 8 1C000107 LOAD G00LO C.$.0. aPr 32 i
. i CECO OTRON TR AINER S AL ANCE PERFORM ANCE 3 O $c CCIT CM U K t *!i re" 2 5
$YM60L sh04T DESC11PT!04 UNIT ACTUAL DATA y Egn0R CaeN NORM 4LilE0 CORE POWER OPLS .31 . 31 5 .03 0049 21090 PWR #NG CN 41 (3UA0 PC 30.80 31.193 -1.26 0050 21090 PWR.RNG CN 42 (9040 PC 31.00 31.394 1.21 l 0051 21090 PWR RNG CN 43 (QUAD PC 30.79 31.094 .95 ~I 0052 210VO PWR RNG CN 44 (QUA0 PC 10.92 31.084 .52 !
0406 06825 #C Lo0P 1 A de COLD DEdF 554.18 554.333 . 05 , 042s 06810 AC LOOP It WR COLD DEGF 554.15 555.03a .15 I 0446 06950 RC Loor 1C Wa COLD DEGF $54.18 553.643 .10 i 046e 07040 RC LOOP 19 WR COLD DEGF 554.19 5 5 4.13a .01 ! 0=14 - 06830 RC LOOP 14 WR NOT L DEGF $72.53 575.464 .51 ! 0439 06910 RC LOOP 13 W4 NOT L DEGF 572.53 575.44a . 50 ! 0459 069Y0 RC LOOP 1C We NOT L DEGF 572.53 579.664 1.23- -! 0470 4 07080 RC LOOP it WR NOT L 0EGF 572.59 577.84a . 91 i 0499 07120 AUCTIONEERED HIGN T DEGF 563.34 563.554 .04 l 0480 067k0 PRE 55UR12ER PRESS Pl!G 2231.74 2235.484 . 17 i 0480- 06550 PRESSURIZER LEVEL L PC , 36.66 36.143 1.65 I 0480 71245 PRES $URIZER WTA T DEGF 652.14 649.704 .ls ! 0600 06350 $/G 1A NAR R46 LEVE PC 62.78 61.804 1.5s ! 0420 06400 5/614 NAR RN6 LEVE PC 62.79 62.79a .01 ! 0443 06430 $/G 1C NAR ANG LEVE PC 62.81 64.883 -3.19 ! 0460 06500 5/6 10 NAR RNG LEVE PC 62. 81 62.603 .33 ! 0400 06590 $/G 1 A STMLINE-PRES PSIG' 1004.62 1024.165 -1.91 I 0 0422 06640 5/G iS STMLINE PRES PSIS- 1004.63 1002.514 .21 .I 0442 06670 5/G 1C STMLINE PRES PSIG 1004.63 978.004 2.72 i 0460 ~ 06680' S/G 19 STMLINE PRES Ps!G 1004.65 1000.23a 44-0418 34540 STM GEN 1 A FEEDWATE -DEGF 327.40 332.92a -1.66 0436 34550 STM GEN 19 FEE 8WATE DEGF 327.40- 333.123 -1.72 ' 0455 348a0 STM SEN 15 FEEDWATE DEGF 327.40 332.92a -1.66 : 045e 34860 $79 GEN 1C FEEDWATE DEGF 327.40 333.214 -1.74 i , 2239 34240 $/S 1A FW TEMPERIN8' GPM 97.13 101.003 - 3. $ 4 ! 2240 34250 $/G 12 FW TEMPERING GPM 97.19 99.998 - 2. 51 - l 2241 34260 $/3 1C FW TEMPERING GPM 99.53 99.00d .53 ! 2242 34270 $/G 10 FW TEMPta!NG GPM 101.43 -102.008 .56 ; 0403 06040 5/6 FW-F FT-510 K9N 1017.92 1055.47A -3.56 ! 0*24 06130 S/3 la FW F FT-521 K 9 N -- 1017.96- 1033.805 -1.53 i 0443 06200 S/G 1C FW F FT-530 K5N 1016.91 1049.43d -3.10 [ 046* -Oo340 s/6 10 FW F FT-541 KPN 1017.62 1021. 07a .34 j 2$00 17070 3EN MW MW 309.92 318.708' -2.75 ! 0407 07040 $/G 1 A LOWER SD LIN GPM 71.06 70.06a 1.42 [ 0427 .07050 $/G 15 LOWER ap LIN GPM 71 .06 70.06a 1.42 ; 0447 07060 $/3 1C LOWER 90 LIN GPM 71.06 70.06a ,_ .1.43 0467 07070 5/3 10 LOWER 40 LIN~ G'M 71 . 0 6 70.06d 1.42 D ATA VALUE 3 ASED ON 31.02 1 CORE POWER i
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l i
07/31/91 05: 42:4o Task 8 20000124 LOAD 000LD C.s.o. cox-32
, CECO SYRON TRA!NER S AL ANC E PER FORM AN C'
_? c h dw. cir7:c at t 4 C." f N E b
$fM80L 3dORT ?'.tCR!*T!ON UNIT ACTUAL DATA t EdRoa CR1N NORMALIZE 0 CORE POWEt DML5 31 .31 8 .01 0600 06010 RC LOOP 1AF FT-414 PC 39.73 99.204 .$. ,
0420 06090 RC LOOP 19 F FT-624 PC 99.75 97.23a 2.59 "440 l Oo170 RC LOOP 1C F FT-434 PC 99.78 99.69d .09 ; 0640 36250-4C Loor 10 F FT-444 PC 99.76 100.734 -1.00 !
. 1000 09050 CONTAIN4ENT PRE $$ PS!3 .59 .563 6.0F * ;
0403 06823RC Lo0P 1 A DELTA PC 32.90 34.254 -3.94 ; 0423 06800 RC LOOP 18 DELTA T PC 32.89 32.23a 2.06 ! 0443 Oo940 *C Loor 1C DELTA T PC 32.49 33.84d ~2. $1 i 0463 07030-4C Loor 10 DELTA T PC 32.95 30.544 7.90 * -i 0131 27010 RCP 14.s E AL I NJ WAT 3*H 3.06 7.934 1.61 E 0129 27010 RCP 18 S E AL I NJ W AT 3*M t.06 S.198 -3.95 ! 0127 27010 RCP 1C SEAL INJ WAT GPM , 6.06 8.48d -4.9e 0125 ! 27010 RC' 10 SE AL INJ W AT GPM 1.06 7.774 3.90 ! l 0415 91140 RCP 1A MT4 LOWER RA DEGF 120.57 127.024 -1.0$
- 0435 l 91170 RCP 18-4TR LOWER RA DEGF 120.57 131.031 ~7.95
- i 0655 91200 RC* 1C MTR L0sta RA DEGF 120.57 127.223 -5.23 * !
0475 71230 tC* 10 MTR LodER RA DEGF 120.57 131.024 -7.45
- i 0035 21040 INTERMEDIATE RNG CH .9 C A M P 102.67 99.968 2.72 !
0036 21040 !NTER1E0! ATE RNG CH 1 CAMP 102.91 95.39a 7. 85
- i 2205 34432 EX4 HOOD 1 A * !NHGA 1.29 1.164 11.5?
- i 36545 TUR$ FIRST STAGE PR PC 24.40 26.564 - 9.13 * !
0 039 A 0399 Oo5d6 TJRs FIAST STAGE PR PC 24.40 26.574 - 4.17 * ! 0404 06370 5/G 1A W10E thS LEV PC 59.87 58.53a 2.29 l 0424 So640 $/3 la W!OE RNG S EV PC 59.87 57.933 3.35 0444 ! 0o490 $/G IC WIDE RNG LEV *C 59.87 59.938 .09 j 04o4 0o540 s/3 10 W10E RNG LEY *C 59.87 59.734 .24 ; 2418 07130 CND$4 INLEl-LINE A 0 F. G F 79.62 75.393 5.61
- i DeOS 0$000 S/3 1A STEAM F FT-5 K9M 1033.44 952.30a 5.21
- I 0425 06140 3/G-1d STEAN F FT-3 KSH 1033.*8 1003.443 2.39
, 0445 06220 $/3 1C STEAM F FT-5 KBH 1033.57 1104.654 -6.41 . ! 0465 06290 S/3 10 STEAM'F FT-5 CSM 1035.96 973.013 6.60
- 3 I
04T4 VALUE MASED ON 31.13 % CORE 80WER I L ! i l l . I N l i i ! l [ i ! I
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, Sr.PTEMBER, 1991 (3 V BYRON SIHULATOR STEADY STATE TEST 90% POWER TEST The 90% Power Steady State Heat Balance Test was performed from a beginning of life, 90% power Initial Condition (IC31). Data was collected and compared using the POWER program on the simulator. All critical parameters wers within 2% plus instrument error and all non-critical parameters were within 10% plus instrument error with the exception of Intermediate Range Current. Work Request 08-91-0005 was written to correct this discrepancy. Estimated completion date for this Work Request is December, 1991. . Additionally, the critical and non-critical parameters values on the Simulator do not detract from training. (IR current is displayed on a logarithmic scale, so even with the error, the indicated value on the Control Board meters is within 1 division of the reference plant data.) l l O (BYRONS!H 113/57 08/22/91)
1 07/31/91 04: 56:22 TASK # 210000F4 LOAD G0ULD C.S.D. Mox.32
....................................................................... i CECO STRON TRAINER 3AL4NCE PERFORMANCE 9 0 f,, CCZTICAL >W Did ri c h ;
gTndOL SHORT oi$CRIPTION UNIT ACTUAL DATA I ERROP , CRON NORMALIIED CORE POWER DMLt .89 .693 .,og , 0049 21090 PWR RNG th 41 (ouAD PC 58.14 89.153 -1.14 0050 21090 PWR RNG CH 42 (40AD PC 88.07 88.F24 .54 , 0051 21090 PWt RNG CH 43 (GU40 PC 38.06 48.878 . 91 0052 21090 PWR RNG CH 44-(QUAD PC 55 06 88.363 . 13 0406 06825 RC LOOP 1A WR COLD DEGF 550.63 544.553 .38 0426 06870 RC LOOP 18 WR COLD DE3F $50.63 549.25a . '21 0446 00950 RC LOOP 1C WR COLD DEGF $50.63 548.243 .44 0 66 07040 RC LOOP 10 WR COLD DEGF $50.64 548.253 .44 0419 06830 RC LOOP 1 A WR HOT L DEGF 601.77 604.93a . 52 0439 0o910 RC LOOP 18 WR NOT L DEGF 601.77 603.373 . 27 ; 0459 06990 RC LOOP 1C WR' HOT L DEGF 601.77 609.523 +1.27 0*19 07080 RC LOOP 10 WR HOT L. DEGF 601. 80 606 164 . 72 l 0499 07120 AUCTIONEERED HIGH T DEGF- 576 18 575.97a .04 ; 0480 06720 PREssuRIIER press PSIG 2231.60 2233.84a . 10 . 0480 06550 PRE 55URIIER LEVEL L *C . 55.49 55.953 .37 0480 91245 PRESSURIIER WTR T DEGF 652.26 6 49. 51 a .42 0400 06350 $/G 1A NAR ANG LEVE PC 63.11 62.094 1.64 0440 06400 5/6 18 NAR RNG LEVE PC 63.12 62.313 1.29 0'43 064d0 $/6 1C NAR ANG LEVE PC 63.1,4 63.053 .14 > Oute 06500 s/G 10 NAR RNG LEVE PC 63.14 62.50a 1.02
- 06590 $/G 1 A STMLINE PRES P S I G' 585.77 912.913 2.64 O04000422 00640 $/G 18 STMLINE PRES P$1G 888.77 912.333 2,$9 ,
0442 06670 S/G 1C SYRLINE PRES PSIG 85R.77 911.753 -2.52 l 0460 00660 $/G 1D STMLINE PRF1- PSIG 888.78 912.323 -2.58 0416 34840 STM 3EN 1A FEEDWATF. DE6F 426.61 424.974 .39 , 0438 34850 STM GEN 15 FEEDWATE DEGF 426.41 424.874 .41 ! 0455 34860 ST9 GEN 1C FEEDWATE DEGF 426.61 424.879 41 0*$3 34500 STM GEN 1C FEEDWATE DEGF 426.61 424.633 46 ! 2t39 34240 $/G 1 A FW TEMPERING GPM 97.17 101.003 +3.79 2440 34250 S/G 18 FW TEMPiRING GPM 97.21 99.034 -1.53 2241 34269 s/G 1C FW TEMPERING GPM 99.57 99.003 .57 ! 2242 34270's/G 10 FW TEMPERING GPM 101.45 102.00a .54 0403 06040 S/3 F W F FT-510 (3H 3334.72 3308.848 .76 0424 06130 S/3 Id FW F FT-521 (4H 3334.86 3297.923 1.12 0643 06200 S/S IC FW F FT*>30 (SH 3334.37 3332.413 .05 3 0464 06340 $/G 10 FW F FT-541 K9H 3334.49 3282.368 1.59 - 2d00 17070 GEN MW MW 1030.10 1018.178 1.17 ' l 0407 07040 3/41 A LOWER SD LIN GPM 75.56 74.873 .91 ! 0427 07050 S/G 13 LOWER 39 LIN GPM 75.56 T4.878 91 l 0447 07060-S/3 1C L0bER 50 LIN GPM 75.56 74.878 .92 0467 37070 0/1 1D LOWER 90 LIN GPM 75.56 74.874 . 91 DATA VALUE dASED ON 89.47 X CORE POWER O
07/31/91 05:04:25 TAst d IF0000FE LOAD G0ULO C.S.D. RPE-32
------------.---------------------------------------------------------. l CECO BYRON TRAINER 8ALANCE PERFORMANCE ;
qcg pa y . : CIT c4L P A C KH E ' A f L sfugot SHORT JESCA!PTION UNIT ACTUAL DATA 5 ERe04 ! CR04 NORMALIZED CORE POWER 04LS .90 .90s .01 l 0400 06010 RC LOOP 1A F F T -414 PC 99.18 99.109 .08 ; 0420 06090 RC LOOP 18 F FT-424 PC 99.19 99.643 .45 ! 0440 06170 tC LOOP 1C F FT-434 PC 99.22 98.723 .50 ; 0460 06250 RC LOOP 10 F FT-444 ,PC 99.21 99.048 .17 i 1000 09060 C04TAINMENT 'RESS P$IG 47 .473 .
.53 0403 06823RC LOOP 1A DELTA PC 91. 45 93.70a -2.40 !
0423 06860 RC LOOP 18 DELTA T 90.343 PC 91 .45 1.23 0443 06940 RC LOOP 1C DELTA Y PC 91.44 92.723 -1.33 0463 07030 RC LOOP 10 DELTA T PC 91. 46 89.149 2.63 0131 27010 RCP 14 SEAL INJ WAT GPM 9.24 8. 81 8 4.92 0129 27010 #CP t a SE AL INJ W A f GPM V. 24 9.398 -1.52 0127 27010 R:P i C SE AL INJ WAT G'M 9.24 9. 31 4 .70 0125 27010 RCP 10 S E A L I NJ W A T GPM 9.24 S.843 4.52 0415 91140 KCP 1A MT4 LOWER RA DEGF 136.09 128.663 5.77 = 0435 91170 RCP 13 MTR LOWER RA DEdF 136.09 132.953 2.36 0455 91200 RCP IC MTR LOWER RA DEGF 136.09 128.963 S.53 0475 71230 RCP 10 MTR LOWER RA DEGF 136.09 132.768 2. 51 0035 21040 INTERMEDIATE RNd CH MCAPP 327.72 . 294.45d 11.30
- 0036 21043 INTERMEDIATE RNG CH MCAMP 32d.21 266.754 23.03
- 2205 34432 EXH N000 1A P thMGA 2.24 2.423 -7.18 06585 TURS FIRST STAGE PR PC 87.94 M7.173 .te O039803v9 06540 TUR3 FIRST $TAGE PR PC 97.94 $8.053 .13 0404 06390 S/G 1 A WIDE RNG LEY PC 61 . 2 0 60.743 .75
'0424 06440'S/S IS' WIDE RNG LEV PC 61 . 21 60.14a 1.76 0444 06490 $/G 1C WIDE RNE LEV PC 61 . 21 61.753 .69 0464 06540 $/G 10 WIDE RNG LEV PC 61 . 21 61.755 .87 2415 07130 CNDSR INLET-LINE 4 DEGF 34.13 88.674. -5.12
- 0405 06060 S/G 1A STEAM F TT-5 (dH 3354.14 3583.434 -6.40 e 0625 06140 3/G 15 STEAM F FT-5 KSH 3354.96 3644.683 -7.95
- 0445 06220 S/G 1C STEAM F FT-5 KWH 3354.47 3664.164 -8.44
- 0465 06290 $/G 1b STEAM F FT-5 K8H 3355.67 3584(443 -6.35
- DATA VALUE 34SEO ON $9.33 Y CORE POWER 4
0 e
BYRON SIHULATOR I ANSI /ANS-3.5-1985 CERTIFICATION REPORT ! INITIAL REPORT SEPTEMBER, 1991 j O BYRON SlHULATOR STEADY STATE TEST , l 100% POWER TEST l The 100% Power Steady State Heat Balance Test was performed from a beginning of itfe, 100% power initial Condition (IC21). Data was collected and compared using the POWER program on the simulator. All critical parameters were within 2% plus instrument error and all non-critical parameters were within 10% plus instrument error with the exception of Intermediate Range Current. Work Request 08-91-0005 was written to correct this discrepancy. Estimated completion date for this Hork Request is December, 1991. Additionally, the critical and non-critical parameters values on the Simulator do not detract from training. (IR current is displayed on a logarithmic scale, so even with the error, the Indicated value on the Control Board meters is within 1 division of the reference plant data.) O (BYRONSIM 113/58 08/22/91) -
. . _ . . ._ ,_ - -- . , , ~ . .
I 07/31/91 04: 39: 32 TASc e 320000EE LOAD G0ULO C.S.o. Aox-16 CECO SYRON TRAINER BALANCE PERFORMANCE
^
l (w 'n f;r c h Tz C at M A i M b v STp40L SH04T )ESCR!pf!ON UNIT ACTUAL DATA t ER409 CegN NORMALIZED CORE DOWER ONLS 99 995 0.00 0400 36010 RC LOOP 1A F FT-414 PC 92.70 99.243 .47 0420 06090 RC LOOP 19 F FT-424 PC 98. 71 97.783 75 0440 36170 RC LOOP 1C F FT-434 PC 08.73 98.513 .22 0660 06250 RC LOOP 10 F FT-444 PC 48.72 99.369 .07 1000 09080 CONTAINMENT PRESS PSIG . 31 .32a .34 0403 06823RC LOOP 1A DELTA PC 100.39 100.293 .09 0423 06860 RC LOOP 10 DELTA T PC 100.37 97.66a 2.75 0443 06940 RC LOOP 1C DELTA T PC 100.36 100.744 .18 0463 07030 tC LOOP 10 DiLTA T PC 100.40 96,47a 4.05 0131 27010 RCP 1A SF AL I NJ WAT JPM 9.24 9.213 6.93
- 0129 27010 RCP 13 SE AL INJ WAT GSM 9.84 10.083 -2.35 0127 27010 RC" 1 C S E AL INJ WAT GPM 9.85 10.164 -3.06 0125 27010 RCP 10 SEAL INJ WAT GPM 9 84 V.304 5.32
- 0415 V1140 ACP 14 MTR LOWER RA DEGF 137.26 128.033 7.21
- 0435 91170 RCP id MTR LOWER RA DEGF 137.26 133.963 2.40 0455 91200 RCP 1C MTR LOWER RA DEGF 137.26 129.00d 6.40
- 0475 91230 RCP 10 MTR LOWER AA DEGF 137.26 133.184 3.06 0035 21040 INTERMEDIATE RNG CH MCAMP 369.94 326.328 13.37
- 0036 21040 INTERMEDIATE RNG CH MCAMP 370.98 288.008 28.51 e 2205 34432 ExN H000 1A P !NHGA 2.56 2.35a M.92 *
('S 039$ 06585 TURB FIRST STAGI PR PC 100.16 97.54a 2.69 ( ,) 03V9 065d6 TURS FIRST STAGE PR PC 100.16 98.903 1.28 0404 06390 $/31 A WIDE RNG LEV PC 61. 64 61.474 .27 0424 064 0~S/G 16 WIDE RNG LEV PC 61.64 61.733 .15 0446 06490 S/G 1C WIDE RNG LEV PC 61. 75 63.043 -2.04 0464 06540 S/G 10 WIDE RNG LEV PC 61.64 62.183 .57 2418 37130 CND SR INLET-LINE 4 DEGF 96.51 82.48a 4.Ss 0405 06060 S/3 1A STEAM F FT-5 KBH 3782.23 4058.30a -6.30
- 1 0 25 06140 S/G 19 STEAM F FT-5 (dH 3751.76 1998.08a -5.41
- 0445 06220 S/G 1C STEAM F FT-5 K6H 3732.16 4127.183 -3.36
- 0465 00290 S/G 10 STEAM F FT-5 K8H 3783.41 4018.55a -5.45
- S4TA VALUE 9ASED ON 79.16 % CORE POWER Ci V
1 07/31/91 04:29:02 TASK W 090000E6 LOA 0 GouLD C.S.D. ppx-32 CECO SVRON TRAINER SALANCE PERFORMANCE j ([ f, c h r:c4L i% h"ti ?i d s 1
$YN80L SHORT DESCRIPTION UNIT ACTUAL DATA 1 ERROR I
< l CR$N NORMALIZE 0 CORE POWER OMLS 94 .995 .02 0049 21090 PWR RNG CH 41 (GUA0 PC 99.56 99.54d .02 0050 21090 PWR RNG CH 42 (QUAD PC 99.74 99.068 .68 0051 21090 PWR RNG CH 43 (GU40 PC 99.24 98.908 .34 !
0052 21090 Pdt tNG CH 44 (eUA0 PC 99.65 48.484 1.19 0406 06(25 RC LOOP 1A WA COLD DEGF $52.16 550.70s .2s 0426 0',870 RC LOOP 18 WR COLD DEGF $ 5 2.16 550.928 .22 0646 06950 RC LOOP 1C WR COLD DEGF $ 5 2.17 550.218 .36 0466 07040 RC LOOP 10 WR COLO DEGF $ 5 2.17 550.21e .36 0419 06830 RC LOOP 1A WR HOT L DEGF 608.36 610.218 .30 4 0439 06910 R C LOOP' 19 WR HOT L DEGF 608.36 608.614 .04
-0459 06990 RC LOOP 1C WR HOT L DEGF 608.36 615.878 -1.22 0479 07080 RC LOOP it WR HOT L DEGF 608.39 612.57a . 68 i 0699 07120 AUCTIONEERED MIGH T DEGF 580.24 579.578 .12 0480 06720-PRES $URIZER PRESS PSIG 2231.85 2236.594 . 21 04$0 06550 PRESSURIZER LEVEL L PC - 59.95 _59.864 .15 0680 91245 PRE 550RIZER WTR T. DEGF e52.31 649.999 .3e 0400 06350 5/G 1A NAR RNE LEVE PC 63.07 62.20e 1.61 0420 06400 $/G 19 NAR RNG LEVE PC 63.07 63.268 .31 0443 064s0 $/3.1C NAR RNG LEVE PC 63.57 63.003 91 0460 06500 s/G 10 NAR RNG LEVE PC 63.08 63.084 .01 0400 06590 $/5 1A STMLINE PRES PSIG 885.14 895.301 -1.14 0422 06660 5/G 18 STMLINE PRES PSIG 835 14 882.528 l
l 0'0642 0460 06670 $/G 1C ST4LINE PRES 06640 $/G 10 $TMLINE p*ES PSIG Ps!G 845.14 885.14 864.35a 884.358
.30
.09
.09 0416 34840 STM GEN 1A FEE 0eATE DEGF 439.26 434.51a 1.09 0633 34850 STM GEN 18' FEEDW4TE DEGF 439.26 434.691 1.05 0458 CEDWATE DEGF 439.26 434.498 1.10 045d 34Se0 34860 Sf9 STM GENSEN 1C A 1C (%EDWATE DEGF 439.26 434.378 1.13 2239 34240 $/G 1 A FW Ti U1PERING GPM '97.19 101.008 -3.77 2240 34250 $/G 18 FW Tl'IPERING GPM 96.30 100.924 -4.57 2241 34260 $/G 1C FW TEMPERING GPM 99.59 100.928 -1.32
-2262 34270 $/G 10 FW TEMPERIkG GPM 101.47 101.044 .43 0403 06040 5/G FW F FT-510 K8H 3770.76 3762.733 .21 0426 06130 S/G 13 FW F FT-521 K8N 3771.53 3725.858 1.23 0643 06200 S/G 1C FW F FT-530 (BH 3766.52 3505.048 .' 9 e 0666 06340 5/G 10 FW F-FT-541 K8H 3770.50 3781.159 .28 2!00 17070 GEN MW- MW 1153.95 1149.278 41 0407 07040 $/G 1A LOWER SD LIN GPM 79.58 79.80s .27 0627 07050 5/G 13 LOWER 80 LIN GPM 79.58 79.793 .26 .
0447 07060 5/G 1C LOWER SD LIN GPM 79.59 79.79a ,
.20 ;
- 0467 07070 $/3 10 LOWER ap LIN GPM 79.58 79.79a .26 l
DATA VALUE 9ASED ON 99.15 2 CORE POWER O
.~ _ . _ . _ _. _ _ __._ _ _ _ _ _ _ _ _ _ _ . _ _ __ _ _ _ _
BYRON S!HULATOR ANSI /ANS-3.5-1985 CERTIf! CATION REPORT INITIAL REPORT. SEPTEMBER, 1991 O BYRON SlHULATOR STEADY STATE TEST 100% STABILITY TEST The 100% Power Stability Test was performed from a beginning of life, 100% power Initial Condition (IC21). Data was collected wtth the POWER program. The simulator was run for 60 minutes. Following 60 minutes of operation, data was recorded again. The final values-did not ury more than s 2% of the initial values. The results of the 100% Power Stability test were acceptable. O . e O (BYRONSIM 113/59 08/22/91)
v3/01/v1 vt:3V: 6% TALv 8 !!00024* LOAD c:UL: C.E.:. vos< CiC2 LY40h T'A;Ni' J' LANCE 8!8F PwANCF O O SG. D nm bb nd 12m E) (00% pW -- T SYa3GL Sn3*T Si$C4: 8T:CN U%:t Atital OtTA 1 fosos C A 1 t. NORhAL: lid C081 20dit O6l* 1.0C # 1.CC: .'] 0;4G 21Cv0 8.3 865 CW 61 (4Ua0 PC 1C1.$9* GC.4Ci 1,tv 0]5s 21090 *W *NG CH 42 (iUAt *C 101.14" GS. ?? 1.77 UG51 21090 *WW 'NG Ch 43 (;UA0 at 101.19" 49.2tt 1.0 0052 L 10 9 C 8.' 8 'NG C8 64 (;U'S SC 100.92# 9t.t$2 2.70 + 0*06 3cf25 RC LOCP 14 hi COLD Di38 552.1C' 5?C.?C: .27 0%2e Oct?C AC LOO
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- Sto O S/G 1? ETMLIst ois 03:s f t !.00 - e f1. 4 0 ; 41 C642 3e670 0/ 3 10 ST*L2Ne **!! #3;J !
- 5. L C ' t!3.3Cs .17 0.a) ):tsC 1/ 3 1; JT* LINS ooit P3:1 h ? 5. 01 - f?1.301 .19 01- ?-143 ST'* 314 1A FliOWAT: DT38 440.51 ' 4?*.50t 1 . 31 0 3e 34t>3 Sir 3 f %- 1: F ! C D . L T t. 055' 4 4 C . 51 ' 435.00t 1.27 C.5: J tcC-CT* 4!N 1C FE 04 Air -Dt3r 640.51" 434.10C 1.11 0 5a 3etc0 ST' lih 1C 718.0, ATE Dint 440.51
- 434.707 1.1.
2i39 3 24C 5/1 1A F. T!VocSING GS6 1C1.3t' 101.CCC .H li r 4 0 3 2$0 3/3 1-3 TI*pid!NG 5tr 100.17' 101.00P .92 i;41 3 23; 5/5 1C 84 Tieptu!b6 3:M 00.7&' 101.000 -1.25 2d&1 3 2/C 5/i 1D F* Tcwo*&th5 CD' 101. !C ' 101.00' 79 0603 JoC.C S/3 Fa F F T - 510 <-n !?13.32' 377G.CC4 01 342* ]t130 S/0 1* Fw r :v.371 (:r 1ri,.14e 1741.00 1.9s C 42 0:250 S/1 1C F 'd 5 *T-530 O'b 3 F 14. 0 3' 2d72.CJi '.?1 C*o4 ):3.C S/3 10 FW r rT-541 589 351 87" 3799.20; 41 2c0J 17C70 GCN *s % *164.77* 1153.907 1.37 0*07 370*C 3/3 1A LO.!i :D L!N Jc6 ? 0.0 e ' 50.CCi .07 C*27 L7020 3/1 la L3*!* :: L;N co* $ 0 . fe " fC.CCE .09 i C647 370s0 5/1 1C L0did it L: N GSC 'O.0e* fG.00s .09 i C=of J707C 3/3 1; L3 18 i; LI\ 03* 'O . 0 t* 80.004 .07 CATA VAL (f 4ASEO DN 100.;) A C0#E SCaii l (~ t t
s3/01/41 J: 44vt.k T4b<
- 30"'.0094 LOAC 00VLC : t.o. wou Ci:0 f Y .10 h T31!NF? 'ataAC; etareeMANC8 k
SYseCL In0PT D13 ' lot:CN UN!' ACTUAL DATA
- F'*38 CPJN N0P*nttIiD C04E 80 !v c'LS 1.00 1.003 71 9*00 06012 *C LOOP 18 F F?-414 *C 95.63,' C8.2Cr 4.
0 2C 01090 # C LOO' 13 F FT-426 *C 0:.ti' 07.70i 97 044C J6170 WC L7: 3 1 F F'-636 *C 94.eM' 4E.50: .13 0 6C 0: 250 RC LS P 10 F FT-e*4 *C 93.et' CC..Ca .74 0123 2 7010 C *a 3 31NG HOR FLOW G'F 131.30- 50.40t 45.3*
- 0136 27C1C L(T30nN LINE S L O 'a' 38P 113.0d' 54.00I 36. 5 2 =
1000 07040 CONTn:NM!NT ***!5 at:0 . 31 ' . 31 t - 1.1 '1 0.J3 N3 MC LOS* 1a 05LT4 FC 1C1.?!' 100.5CA 7. 0 20 GedoC RC LOOD 1 DELTA 1 8C 101.26* 97.CC? 3.42
- C ",41 0694C PC L30F 1C CELis T *C 101.23 ' 101.001 .23 0.o3 07C00 8C LU30 10 CCLT. T PC 101.27
- Ge.70t 4.73
- L131 27C10 5,CP 1A 31AL INJ w4T Gav o.50' 9.122 3.00
- 0127 27C1 #C* 19 !!al : AJ .' a i Gow 9.50/ 1C.11s -t.05
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- PVFSL1DLKF PCP 13 3Iat u1 LgCFF Flow La/s .47 / .00d********** *
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- 0675 1123C *C8'13 MTA L0ait 5& O!GF 1?5. 1' 133.20s 1.6$ '
OC3d 2104'J IhT!*Vr0! ATE Dh5 Ch 4C4WD 373.35' 327.4$v 14.17
- OC3e 21C40 INT!4ME): ATI ANG C6 VC8vp 373.95r ???.712 2C.52
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- INHCa 3.53' 3.462 1.73
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- 2379 0:5:o TUP 4 FIRST 3TA"I at DC 1C1.37' CC.20A 2.01
- Gs04 De390 S/i 1,a!)C 8%G LEV PC ( 1. 7 4 " f1.!Of .39 0424 0:4 0 S/3 16 m:0! 'N' LEV DC 61.74 - 61.50( .90 06*. J 4#0 $/G 1C WI)~ SN1 LIV PC (1. 51 ' e 3.1 C 2 -2.05
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- 2002 1c03C LS TURF it INL:T "5 .
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- 8 6.50* 32.20? 2. 00
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- C.25 Ob1 C */3 12 3TIAM F FT-! Ksk 3'?$.d7' 4010.2C; -4.60 =
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;*c5 0:2i] t/3 1D ST!'" 8 TT-5 K'r 36.27.35- LC34.CCi -5.12
- 14TA v4Lui I AGIC ON 100.21 1 CJ81 00 wen
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- i OuS1 210&O *a* 'Ni CH 3 (;UAD #C 101.45 Gs.2ti 2.24 * '
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DYRON SIMULATOR ! ANSI /ANS-3.5-1985 CERTIFICATION REPORT ! INITIAL REPORT. SEPTEMBER, 1991 j l {}~ BYRON SIMULATOR ! NORMAL OPERATIONS TEST I The objective of the Normal Operations Tests is to verify that the Byron Simulator performance meets the criteria of ANSI /ANS-3.5-1985 Section 3.1.1. The Normal ! Operations Tests were performed per the attached using Byron Station General : Procedures. The tests performed and results are as follows: 1
- a. Plant Startup - Cold Shutdown to Hot Standby Accepted !
- b. Reactor Startup to ~100% Power Accepted ,
(includes turbine startup and generator synchronization) i
- c. Reactor 1rto Followed by Recovery to 100% Power Accepted (
(includes operations at hot standby and load changes)
,-~, . 's / d. Plant Shutdown from 100% Power to Hot Standby Accepted and Cooldown to Cold Shutdewn I e
h h i f i l A (BYRONSIM 113/60 08/22/91) , 1
. . _ _ . _ _ _ . . . _ _ _ _ _ _ . ~ . _ _ _ . _ . _ . . _ _ . . _ . _
BYRON SIMULATOR' ! ANSI /ANS-3.5-1985 CERTIFICATION REPORT . INITIAL REPORT, SEPTEMBER, 1991 i g BYRON SIMULATOR NORMAL OPERATIONS TESTING l
- n. PURPOSE '
The purpose of this procedure is to verify that normal plant evolutions can be -l conducted on the simulator as required by ANSI /ANS-3.5-1985. i B. REFERENCES
- 1. ANSI /ANS-3.5-1985: Nuclear Power Plant Simulators for Use in Operator Training. !
- 2. BGP 100-1 + 5: Byron General Procedures.
- 3. PTAO-105: Simulator Certification Reporting and Testing Pregram C. INITIAL CONDITIONS i
- 1. The Initial Conditions (IC's) will be specified under Section E Test _
Instructions. l D. DATA COLLECTION- '
- 1. BGP Flowcharts shall be used to verify and document simulator compliance with
- the normal operations testing. ;
E. TEST INSTRUCTIONS !
- 1. Using the latest revision-of the Byron _ Unit One General Procedures (BGP's),. j>
L perform the e,11owing evolutions: j
- a. Plant startup from cold shutdown to hot standby. Use the cold S/D'IC I which enters BGP 100-1 at n ip 1. i b, Reactor startup to'1007. power. Use the BOL, hot standby IC which enters BGP 100-2 at Step 1. !
L 1) This evolution includes turbine startup, generator synchronization. ! and load changes. ' L 2) Startup surveillances may be documented-in accordance with !
- Surveillance Test.
- c. Reactor trip from full power followed by recovery to full power. Usethek BOL, 1001, power, equilibrium xenc,n IC to start the evolution (Unit'2 BGP f
! _ /% may be used), f
- 1) This evolution includes operations at hot standby, turbine startup, f
generator synchronization, and load changes. j ( _ (BYRONSIM 113/61 08/2?/91) l L : L. . . .- _.,_..,._----,.--~.L.-.~_.~.----------. ----------~-d
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 .( BYRON SIMULATOR NORMAL OPERAT!ONS TEST-(continued)
- d. Plant shutdown from full power to hot standby and cooldown to cold shutdown.- Use the BOL,1007. power, equilibrium xenon IC and enter BGP 100-4 e. Step 1
- 1) This evolution includes operations at hot standby, load changes, and >
shutdown operations witt less than full reactor coo 1W flow. fiQIIS
- 1. Startup and power operations with less than full
- reactor coolant flow are not puformed since only
- full reactor flow critical operation is allowed
- at Byron Stations. *
- 2. Operator conducted surveillance testing on safety related equipment or syster.5, plant heat balance
- and shutdown margin determination are addressed in the Simulator Surveillance Testing Procedure.
- 3. Measuremtnts of reactivity coefficients and
- O
- control red worth'will not be performed since *
-V
- these tests require the use of a reactivity computer (which is not a permanently installed instrument) and the operator is not involved in *
. . . . . . . . .t .h e... r.e..a ....e**.
- c. t .i v i ty c a .l c. u..... .l a t. .i...
- o. n ...( Te. .c h S..t a f......
- f. . f u. n. c. t .i o. n ) .
F. ACCEPTANCE CRITERIA
- 1. Each evolution can be performed satisfactorily using Byron Unit One General Procedures.
- 2. The observable change in the parameters correspond'in direction to those expected from a best estimate for each evolution and do not violate the physical laws ai nature.
- 3. The simulate: slid 11 not fall to cause an alarm or automatic action if Byron-Unit Jne would have caused an alarm or automatic action, and c)nversely, the simulator shall'not cause an alarm or automatic action if-Byron Unit One would not cause an alarm or automatic action.
G. DOCUMENTATION
- 1. Retain th: Flowcharts to document simulator compliance.
s (BYR0t!SIM 113/62 08/22/91)-
O O O IIIGP 100-1T1 ENTER I!EVISION 2 DATE Q glc)l l
; P <, _ ES 11 8 SE eee 1BGP 100-1 Flowchart D PRECAUTIONS Exceptions c 4 e -
- t> i T ~ , m W>< N re-M.-- Qg-6 qt nE LIMITATIONS E AND ACTONS Initial each ROO sao -
MODE STO4 1 g GDT/ WT HEATUP HVAC 19
, 21 MC8 ,.
RCS PZR RCS MODE
PZR VCT VENT PZR PRT PRESS BUBBLE CHEM CS 5-4 RH BUBBLE O 2
q' _
,c, _ _
TUNNEL 22 rwWC RT u HVAC 23 24} 25 26 27 STARTS L 28 29 - f> 32 33 3 r~1 5 y d4 i 'e ,1 l_ l. N Y -
$f Msty AUGN A C N cw g SEC CHEM Ol4 L 4TO3 30 l 31 ;
0 J'i , y$ _ 0907 b6 . SEC SEC 7 S/G S/G S!G STEAMUNE O' as o - 1 17 - 34 5 36 TO 8 9 10 usty ,f N s, g pf w' ] $( APPROVED FW Pp PREP yy _y_ M23$ s . .; B.O.S.R.
O O O-IBG .00-1T1 REVISION 2 RECORDCB IN LOOP EVERY 4 HOURS WHILE RC TEMP IS > 100*F AND < 5501.
" ^ - " ~ " - " -
T.AE DATE LOOP PZR TIME DATE LOOP PZR 1BGP 100-1 Flowchart Exceptions Initial each RO O suo e' L ICV 129 AF MODE RCS 6 PORE" MSIV PRESS PZR SEAL RCS M/U 557'F RCS LEAK l RH SI/CV 43 PRESS PW P-11 ACCUM CONT PRESS INJ LETDOWN ALGN 46 49 54 55 56 60 61 d 41 42 ' - i g# 1P T%T g ACCUM T+ fpF F
' 'fES' 'fE5' b '
STM OM l Co m ETE Y C T GEN
^ ITG
- G 7 57 N "7 APPROVED Tui 1500
" DATE 3[,3/9 JAN 2 31990 B.O.S.R. _
O O O AFFROVED
- REV N3 B.O.S.R.
O ID 1BGP 100-2 Flowchart SE c PneReOi,SirtS Exceptions D PntCAtmONS s t iAnONS AND ACTIONS
; MODE
~
1 t Initial each ROOSRO - RD - p r-~~-] 4 TRP N3 I6 CPS N 31 30 CPS *
/ l MSfV e BRKRS
$+ N 32 (3 CPS N 32 3I CPS 2 -
3 m# 10 FLOWCHART N R. 45 2 CPS AUDK) BOPS , p 1BGP t00-2A1 g Q C 1 4 y-g v vSID iv: e Cg * ! ECC ECC VERIF BANKS e ,,,,j b s D tE H 7 i
'AY CW 21 g qg b BYPASS p FW TURB PREPS TO b c"Ec"S '
g Cy ru wcarou o2 oia2
O O O ' JP 100 ITI REVISION 3 1BGP 100-2 Flowchart : Exceptions ! [ ~ ~,~ ~ ~S~ ~! Initial each RO O suo ]
- VQ! ,
i I t 2-3% PONER STM ' l g 1BOS NR-1
) DUMP CHEMISN ' .
l DsLUTE , TIME COZ5 EXIT y 26 DATE Nfth SE b l WIN W AFPROVED FEB 15 r190 B.O.S.R. FR.E LOCATION 107 01r
, . . . - +,,.-..-....~~--.-.-c. . .. . .-y. ,., . . . . , , - - . , + e.,-.. .,,...,,...-v.,....,, _ . . , . . - . . . . . , _ _ - _
o o' o, IBGPitm#2T3 REVISION 0 .
-ra u ,'
mm - SE om 1BGP 100-2A1 Flowchart Exceptions C PREREOutSITES
" ~~ -
Initial each RO SRO E tanTATMS AND ACTMS BLOCK , SHFT PEfBESS W HB if S/U ' SdCOONTS g- ADOMENTATM FOR SC LD ALM NR-45 SUmnERANCES MODE 3-2 n - O n n n n - t FLOWCHART Q7W '
#F
- v
-M Qy Q1# Q l Q _
~
SOURCE RANGE N 31 70 CPS N 32 1 CPS
; APPROVED <
FEB 15tWO B.O.S.R. FILE LOCATION: 1.02.0132 i I
GX O, 0) IBGP ltGII3 REVISIGN 0 1BGP 100-2A1 Flowchart Exceptions
.i Initial each RO O suo __
1 Jj$ 1> (f'g->) . x 3 I)A ""**?< 11ME ' 3lff'?/ EXIT a- RX ;BGP 100-2A1 13 DATE Tfo~'y ;- V V ' COMPLETE un W 'T NM ff~Y TAVE ,
, A T5T C fft
' B ff7 D (3T BANK 1 AT/ 56 c, / ZW PPM AFPROVED FE8151990 (FINAIJ
-2_ B.O.S.R.
FILE LOCATION: 1.02.0132
O O O ' 1BGP ILwT1 REVISION 2 mm 1BGP 100-3 Flowchart
=" --
SE Exceptions j t
- i. C PREREQUISITES D PRECAUTKXiS -
) ! m pg
~
E t m AT m S AND ACTIONS l r) U CORE i '; , MODE 1 i g , 2TO1 MODE 8% PIO P7 s.15 TOTg. 2 1 3 o 7 i. . TuRB G U G U
~
b TURB $20 1700 pyg 1000 pyu IBOS TRP RNO SYNC ORD NOTFY LD SD
/m- LATCH RTC pyu TS-M1 TEST BUS PREP DET SYNC OOV
~
12 14 16 17 18 19 20 21 22
}} 4 6 13 26 h I\ S LEVELS h f g pf '
pf ( SJAE y\
)
W IPI-TC136 (p
- g 27 A
t3 , sTu ouneS Ab % , pp 11 8 t
\ / APPHOVED
~ ~
OfC 161969 B. O. S. R. i
O O CF IBGP10 twt 1 REVISION 2 1BGP 100-3 Flowchart Exceptions r' 1750-: RODS '
! 33j t Initial each Ro O suo 4
P -13 53 [ 34 STA P.s RTC 20 % o 43 46 FW FW FW SEQ
- Se %
AUTO LINEUP - MASTER VALVE 30 % 50 % CALOR
- 36 37 38 -
ELEC , 7: FW F W Pp g ; LINEUP MS CDICB HD ALIGN
- h v
42 47 48 49 52 ! b H2 TEMP O CTEMP 44 SEAL OIL APPROVED DEC 1 a 19e9 j B.o.s. a.
- _ . _ _ - - _ - - - . _ - . ~ . - ~ . . - _ - - - _ . _ . . - _ _ - . - . . _ . . - . . _ . _ - _ _ . . . _ . _ _ _ - - - . - . _ _ - . - . . _ . - _ - . . . _ _ _
O O O' 1BGP 100JT1 REVISION 2 1BGP 100-3 Flowchart Exceptions Initial each RO O sao _J DDiC v . 90% 100 %
"I5* ihr B' 5" 5' ~; ';L),' ~:
U U U U U y l b mNA1J APPROVED
~ ~
DEC 161969 B.O.S.R.
O O~ O~L . 100-ZTI REVISION 3 w., u ; O SE 2BGP 100-2 Flowchart n EA l'of c enEnEatnSirtS Exceptions D PRECAUTIONS E LWADONS MCACDONS - Initial each ROOSRO - I IAODE g SOURCE RANGE SOURCE RANGE 4 N 31 h CPS N 31 . CPS N 32 27o CPS CPS _y gg N 32 3 10 2 U
' ALDO BDPS p 2BGP 100-2A1 g FLOWCHART N R- 45 . 2 CPS D D D' Y (M D O D (D iD: DFr '
C De SID e CB ' 8 ECCVERIF - BANKS e ECC , ' l C EH CW 20 F W REG BYPASS ; h AFFROVED TO
'" O' f CHECKS ,,
~
, TURS PREPS FEB 0 91990 g, g, ,g, FILE LOCATION: 102 0132
AP 10rJITI REVISION 3 2BGP 100-2 Flowchart Exceptions I Initial each RO O sao l I l 2-3% 8 POYr1ER STM l i a 290S NR-t DUMPS l EMifTE , DEMSTM TIME r,9ys EXIT h U h U U 24 $$ 25 l DATE Y/ <,' /W L W of W a in gg st 9 f-b APPROVED FEB 0 91990 B. O. S. p, FILE LOCATot 1 02 0132
* ~ ~
\
O' O~ O 2BGP 100-Z13 REVISION O mm SE 2BGP 100-2A1 Flowchart Exceptions C PREREQUISITES D PRECAUTIONS - Initial each RO SRO ~ E L** TAT m S AND ACDONS 4 il BLOCK l SHFT PERMISSION HO S/U g' j _'] AUOMENTAT FOR SU m[ LD Q m Q ALM NR45 g[ SRCOUNTS m Q m Q SURVIELLANCES n Q MODE 3-2
~
- rtowCuwT
%F 9F' l SOURCE RANGE l N3s SE]. CPS N 32 660 CPS APPROVED FEB 0 91990 l
_i_ B.O.S.R. FILE LOCATlON: 1.02.0132 l
o O' O 2BGP 100-2T3 REVISION O 2BGP 100-2A1 Flev chart
~ Exceptions Initial each RO O suo hlb 10 4
AMPS NR-45 a "* 7tI l Q[ V Q Y Q U hf' 2BGP 100-2A TIME DATE ss 085l f // g [q / EXIT z 9 ,e , was " IE"a N 36 8C'I TAVE A 5 57 C 5 54 B 557 0 557 BANK 0 AT33 i CB 7 W PPM APPitOVED muru FEB 09 MO B.O.S.R. FILE LOCATION: 1.02.0132
o- o, 2flGP 10uJTl o REVISION 2 DA1E
"=" -
SE 2BGP 100-3 Flowchart Exceptions C PREREQUISITES
~
{ D PRECAUTIONS UMITATIONS !O AND ACTO 4S CORE W ES e4 [ 10 % 0 P10f f P7
~
MAND TOTMS f3 10 46 TUR8 0
$20 9
1700 1900 2BOS TuRs TRP V RNG SYNC OFO NOTFY b ' 2 - SUS PREP DET LD SD SYNC OOV VLV FW LATCH RTC RPM RPM RPM TS-M1 TEST 3 4 5 7 13 14, 15 18 }9_ 20 YL 22 g [ I *' LE LS SJAE (t' 2Pl-TO136 S
@sTM
? 0g b APPROVED k[
DEC 181989 I_ B.O.S.R.
O~' O' O 2BGP 10bv s'1 REVISION 2 1 2BGP 100-3 Flowchart Exceptions i
~
I ~ ~AblO ~! ROOS '
- Initial each RO O suo J AS I j i-[
34 {g-STATUS LNMTTS P-8 RTC 15 % , 3 J f6 l MZZLE LOAD NCR FW SEO- # 50 % 0 AFER 1g . 29% , a U m UASTER VALVE n40 q 30 % 80 % CALOR a
-W 36 37 38 HH n50 H@ 54 4
smouws , \qg/ g% < <
, w :,
- r w n, y .tsc -----. uS on,e co,ce no rw Ation ,
Q' %L i 47 ** _gs
-O,7
~g@
O b 'Dv S_ v APPROVED ! -2_ DEC18I?a9 B. O. s. R. q _ . _ _ . . . . , _ , . . . . - - - . - - - - , . , - _ . . - - - - - . - - - - - - - - - ~ . - - , . . - . - -- - - - - - -- - - - - - - -
i O O. O 2BGP 100-3Tl REV!SION 2 2BGP 100-3 Flowchart Exceptions t Initial each RO O suo 4 Dec i {Ol-00
,o% 100%
90% FW C40R too% M Y 11ME
- 55 h ht r h g r' DATE EXIT 3g 14' fv Sf ,
l b t (FINAM APPROVED E I O 1969
- 8. o. s. R. ,
O O O IBGP 1004TI REVISION 1 ENTER g3ggy g g,, g ,
-E SE oe e 1BGP 100-4 Flowchart
, Exceptions C PREREQU: SITES o gREc uT s Initial each ROO suo :
E ji^Qs . DEC TO <a0% F W Pp DEC TO DfpH DEC TO FLOWCHART RRD 50 % POWER S/D 20% r 7 5 VES J5% d
- 4 17 7 F 3 fr status UGHTS
? FW c no ep SID O'"r -G- tssc UP b
15 v' 'ca
,o sioltvEts K' (?
100 % PERCENT POWER 50 % OCT 26 088
O O O CA 20 DEC TO la=J! a DUWPS 1BGP 100-4 Flowchart 1 Exceptions P - 13 h P.7 Initial each ROO suo P-to 4 ; R SD g_ -C bh C-
~ ~
H D Pp *
- MSR
^
22 3 32 N (4 % _ EXIT Siu rw Pp LEVELS
~~~
L L
~ ^ If SI l
M4 #F SE i o , 15 % 10 % 5% PERCENT POWER inut, APPROVED OCT 261988
,, n -
1BGP 100 771 Revision 1 F 1BGP 100-771 [ REFERENCE REACTIVITY DATA WORKSHEET >
. EgIt . !
- This worksheet will be retained as plant documentation. .
- DO NOT DISCARD. Torward completed form to the Operating .
- Staff when no longer required on shift for reference.
- 1.a. Shutdown Date $ 8t #7 1 Shutdown Times NI2 1.b. Control Bank at IS steps. {
r
- 1.c. Inserted Control Bank Worth l l (Trom BCB-1, rigure 82): (-) O pcm
- 1.d Critical Boron Concentration from (CIRC!,E mode of analysis used):- [
Just prior to a planned shutdown, t 2). Just af ter a reactor trip, or ' 3). Calculated by the Qualified Nuclear Engineer (Attach calcuhtions, logs, point history used) j
,( C3._ ppe ;
t Sample or Calculated Time / Dates / i 1.e. Power ?.evel prior-to shutdown from (CIRCLE information source used): 1 1). NR-45 t 2). IBOS NR-1 Computers Type / Program C M tf E M d Firl'^4 cum / M ; Power prior to shutdown: / Oo. 3 g l 1.f. Total Power Defect from (CIRCLE information source used): [ 1). BCB-1, rigure 917A 2). BCB-1, Table.2-1 Total Power Defects (-) l I OD pcm
. s l
APPROVED i FEB 151990 t i Io V o
- 1- ,
l (14o3vio111v/o11590) B. O. S. R. , l , I
+
Mw*111- m * 'T "7"'-- P' T'-'p p r r -sy y f "~r?"**-- T me9 y W .r gs,w-me- vi-NT- n ip-w*
lbM 100-7C; APPROVED Revision 1 FEB 151990 l 1BGP 100-771 B.O.S.R. RErERENCE REACTIVITY DATA WORKSHEET (continued) 1.g. RECORD accumulated core average burnup at shutdown f rom (CIRCLE inforestion source used):
. IBOS NR-1 2). Computer Type / Program Core Average Burnups h EPPH 1.h. Equivalent Power for Samarium Calculation f rom (CIRCLE ir*ormation source used):
1 DOS NR-1 2). Computer Type / Program: Sm Eq. PWR = Unweighted average powwr over 5 days (120 hrs) prior to shutdown Sm Eq. PWR = [GO % c.4. Determine the Equivalent Power for Kenon Calculation f rom (CIRCLE information source used): 1M 1BOS NR-1 (m') 2). Computers Type / Program: Hour s Average Hou'rs Average Prior to Power Multiplier Product Prior to Power Multiplier Product Shutdown (%) . Shutdown (%) 0 to 1 N x6 = 18 to 19 [M x2 = 1 to 2 T x5 = 19 to 20 i x2 = 2 to 3 I x5 = 20 to 21 1 x2 = 3 to 4 i x5 = 21 to 22 I x2 = 4 to 5 x4 = 22 to 23 I x2 = 5 to 6 x4 = 23 to 24 ' x2 = 6 to 7 x4 = 24 to 25 l x2 = 7 to 8 x4 = 25 to 26 x1 = 8 to 9 x4 = 26 to 27 x1 = 9 to 10 m3 = 27 to 28 x1 = 10 to 11 x3 = 28 to 29 x1 = 11 to 12 x3 = 29 to 30 x1 = 12 to 13 x3 = 30 to 31 x1 = 13 to 14 x3 = 31 to 32 x1 = 14 to 15 x3 = 32 to 33 x1 = 15 to 16 x3 = 33 to 34 x1 = 16 to 17 x2 = 34 to 35 x1 = 17 to 16 T x2 = 35 to 36 4 x1 = v mA1. 9: 00 (1403V/0111V/011590)
1BGP 100-771 R3 vision 1 1BGP 100-7T1 REFERENCE REACTIVITY DATA WORKSHEET (continued) 1.1 (continued) Equivalent Power for Xenon . Total = 9fGO 91 91 Xe Eq. PWR lCO % Remarks: W VW2 ftS- LA44 NG LWUICt rWo uH
- NOTE .
- II this procedure is performed by an NSO, Ilil21 this *
- procedure shall be reviewed by a Qualified Nuclear *
- Engineers or, IE this-procedure is performed by a Qualified *
- Huclear Engineer, 23G2[ this procedure shall be reviewed *
- by the NSO. Typleally, this procedure should be prepared *
- by the Technical Staf f Nuclear Group. .
Performed by: G& / 18 Qualified Nuclear Engineer), Name Date Reviewed by: / (NSO, Qualifled Nuclear Engiaeer) Name Date SRO: / Name Date 4 1 4
- APPROVED I
FEB 151990 (ri==1) B.O.S.R. 4 pa .,. (1403V/0111V/011590)
O O O lik,t' 100-5T1 REVISION 3 DNIE 3l(tlcjl SE zes 1BGP 100-5 Flowchart c eRERE=S""* Exceptions D PRECAUTKWS E o= tan =s AnoAcnONS Initial each RO SRO - I N ~~~~
' 8 0 ' ' "
Rn j f~~~~7 CfD STM {
- RX SID S SOM g TAVE, HSB e DEGAS CV PZR s RCP RCP 1BOS Duw b RRD 11 - 12 13 14 16 f18 19 20 21 22 23 24 25 !
L V l l 2 + 3 r DE 8F - 8
. roav '
</, ------
f 15 l 2s* go , s 5 m py,,a v c+e, m ,o w - l~l ta n, b> , cg a 2 o -Q(P" 4 N RPRMS i ps .c, ,alyz ' * 17 ve
'"'"k 27 FW "aoncno" 1%
~
t9 C; 33 (V 10 l StG SAMPLE AE r OG 8 bV 9 29 w dL - V jf oS 7 api-HOVED FEB 2 31989 o^-a .
O O O IBGP 100-6T1 REVISION 3 1BGP 100-5 Flowchart Exceptions 6 e we ecs , caw u, e es , te nor %st. Vacuun, Initial each RO SRO - LETDOWN PZR RCS SI MODE RH RH SX SUCT MODE RCS RLEVEL PRESe P - 11 < ACCUM CV 3-4 PZR CC RH 1BOS LETDOWN VLVS SI/CV 212 *F AF 45 , 4 d 28 30 31 34 3s H g 37 3a 39 40 41 42 43 44 - g 52
~ ~
y s w y o 4F b "oav 94 v " b c -
- d APPROVED FEB 2 31989
-2_ B.O.S.R.
I - 1 IBGP 100-6TI REVISION 3 1BGP 100-5 Flowchart j Exceptions b -t rus c5 =cz , aux- m7 a vase 4 1 Initial each RO SRO P mw )\, ,._______, y, ____________ y &A . RcDuctD .-_____,______, l C8
' l CEM l
, h' RCP RCS SOLID - CID RCP PRESS
' INVENTORY e* DRAff ' StD TRANpfG 's ,'
a CS .e e ADD
.e
.e se
.. RCS ,. HVAC ,'
s u ms 53 54 55 56 57 58 59 60 - - - 61 62 63 COMr1ETE
,4 k
3 l OG VACUUM GS ! MS SIG l F W Pp CD,CB
- l l l TIME CGto '
4 45 46 47 48 49 50 51 j l DATE 7/gq l l i s _____. i i APPROVED EXIT FEB 2 31989 B.O.S.R. ,
., . . _ - . . _ _ _ . - __ _ -- . . _ . . - , - . . _ . _ _ . _ _ . _ ~ . . . - . _ _ . _ _ _ . . _ _ . - - _ . _ _ _ _ . .
1BCS 4.9.1.1 1 Revision $1 RIA~ TOR 0;C:Ri! SYSTEM PRI.SSURE/TDiPERATURE LIMIT SURVEILLANCE A. STATEMO.T OF AFFL:0A3 '. m*: This procedure applies to the verification that RCS pressure and temperature are within limits in all modos during:
- 1. Heatup (RCS)
- 2. Cooldown (RCS)
- 3. Inser" ice Leak Testing (applies to RCS pressure / temperature limits only)
- 4. Hydrostatic Testing (applies to RCS pressure / temperature limits only)
B.
REFERENCES:
- 1. Technical Specification 3.4.9.1.1
- 2. BGP 100-1 Plant Heatup
- 3. BGP 100-5 Plant Shutdown Cooldown s
C. PREREOUISITESt_
- 1. Receive paraission from the Shift Engineer or the designated SRO licensed assistant prior to performing this surveillance by having the Data Package Cover Sheet signed and dated.
D. PRIEAITTIONS t
- 1. t;one E. LIMITATIONS AND ACTIONS:
- 1. As stated in Technical Specifications Limiting Condition for Cperation (140) 3.4.9.1.
- 2. In the e' ent the Acceptance Criteria is not met during the performa sce of this surveillance, IMMEDIATELY notify the Shif t Engineer to initiate LCOAR procedure 1BOS 4.9.1-Aa.
- 3. The limit s of Byron General Operating Procedures (BGP) for RCS heatup and cool town areyg?& a ma timum rate
^eeaov5o O AUG 14 885 I
B. O. S. R. (2534P)
1805 4.1.1.;-1 Revision $1 i
'- " =
O 1. DnER the starting date on the Data Sheet (D-2). l! ! 1
- 2. Place an X in sectirn 2 of the Data Sheet for the condition (s) that :
-initiated this procedure.
............................................n ..........
. NCYTE a . ,
- Steps 3 through 8 must be performed at least once *
- per 30 minutes during conditions requiring this * ;
- procedure. For ease in determining that the i
- Acceptanes Criteria han been ret, the data should be **
- taken at the same time interval for every reading !
- 3. DfTER in the First Line of Columns 3. 4. and 5 the intial time. RCS {l pressure using step 4 criteria and RCS Temp using Step 5 criteria, j
- 4. DlTER the highest indicated RCS pressure f rom any of the following. ll An operable Pressuriser channel. RCS Loop A Wide Range. RCS Loop C Wide Range _or an RCS Low Range pressure channel in colu w 4. Use that following list to verify that the chart recorder for the selected +
?
pressure is recording. . ; Chart Recorder Pressure Channel ; [T
%) -
- 4. 1PI-455A 1PR-455 ;
- b. -1PI-456 IPR-455
- c. IPI-457 1PR-455
- d. IPI-458 1PR-455
- e. IPI-403/403A 1PR-403 :
- f. IPI-405/405A IPR-403 ,
- g. IPI-RCO21 none DCER the reading on the lowest operable RCS Cold Leg Wide Range- [
-5._
temperature channel (*F) in column 5 of _ the Data Sheet and verify _the channel is being recorded on its applicable chart recorder. Temperature Channel Chart Recorder j T
- a. ITI-4135 1TR-4'.3B ,
- b. ITI-423B 1TR-413B~
- c. ITI-433B 1TR-433B pp yg
- d. ITI-443B 1TR-4333 g E-4 ,
(2534P) B. O. S. R. . r
1505 4. 9. ; . ; ; Revaston 5; I RECORD :ne :me. R;S pressare. ar.: .i :rt;.rt . :.; ste; 4 a.3 !
- 6. -
criteraa at intervals no greater : L- ... .ar..:es. Tc1;cvin; l
- 7. CALCULATE the Temperature change :j *:.
" e p Change F.,*
- s e n t te r r" -
- -e".;jr to ; ('ri Enter Temp Change in colurt. * :. . *a a Sheet.
Negative change indicates coo *.$-vn:.. positive change indicates hes:.:;. l B. CALCt'I. ATE the heatup or cooldown : tr.: foll: win; eethod. Temp Change _(Col.7) x 60_ min r;apsed Time (mins) hr. Enter Rate in Colume 8. l
- 9. VERITY RCS temperature and pressuit tr-e within the limits of Technical Specifications Tigures 1 $ . t or 2.4-3a as appropriate,
- a. In the case of a cooldown. se :r. t rate calculated in step 6 to select the appropriate lini: :.:- e on T agure 3. 4-3a.
A Limit lines for cooldown rates :eu:: ween those presented in rigure (') b. 3.4-3a may be obtained by ic:e.7c.:'atier..
- c. If temperature and pressure ari .v: thin limits then place intials an column 9 of the Data Sheet,
- d. If pericaing a RCS Inservi:a
- da s.,: Ces: or RCS dydrostatic Test abut the limit curves f or hattu, . or :ooldown then verify that the limit of 10'T temperature -= ce in any 1-hour period is not exceeded and place init4.als :: ::.:;u .n 9.
- 10. USE comments column to provide adt:: ~ nal information if necessary. 1 Such information may include exp*.a.:.t:L:.:ns for large or small changes / variations for system te:74nt. ure or pressure
- .utes w .i;e ene Of
;1. FERTCTd the cal:alations at less; . -: . per2*
the following conditions exists:
- a. RCS Heatup
- b. RCS Cooldown
- c. RCS Inservice Leak Testing
- d. RCS Hydrostatic Testing
- 12. COMPLETE the Data Fackage Cover S.:.se: (D-;).
[ ) V APPROVED l 3 AUG 14 $85 , (2534p) 8. O. S. R. ) l l l i
1805 4.9.;.;-; i Rovasaon 51 [ G. ACCEF*AN~E ORITERIA;
- 1. RCS pressure and temperature are within the limit s shown on Technical Specification rigures 3.4-2a and 3.4-3a withs
- a. A maximum heatup of ,00'T in any 1-hour period. .
- b. A maximum cooldown of 100'r in any ;-hour period, and f
- c. A maximum temperature change of less than or equal to 10*r in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves. ;
F O ' e O FINAL APPROVED AUG 14 085 (2534p) B. O. S. R.
b IBOS 4.9.1.1-1 Revision 51 REACTOR COOLANT SYSTD4 ITESSURE/TDtFERATUR.E LIMIT SURVEILIA4CE
, / _
- 1. DATE: 3/I'/W __.
- 2. GIECK APPLICABILITY _ _
// I _ l RCS itE^ tup QCS COOLDOWN l[lRCSINSERVICELEAKTEST l~_l RCS IIYDROSTATIC TEST
~ ^
~
J. TIME 4. PRESSURE 5. RCS COLC 7. TD4P 8. RATE 9. IN LIMITS l (*FIHR, Fig 3.4-2/3.4-3 _. CONo j (PSIG) LIXI TDdP(*F) OtANGE _ Ib 2 2 ~5 V TS ] NA NA f NA __ Initial Data ; 7 EE3 y 6 g O f, ,
, , _ t .
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l 8 hk3I esef 2 60 $z5 R32 64 , nc 75 .__ 1 f _ _ _ _ l i f
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te);5 3 g, ;;;;c 34 69 , tad r Act RcP , m(%,,,,g, ATTACII additional sheets (D-3) as necced _ __ APPROVED o-2 (2
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_ ___53_4P) - __ _. _ _ ... _ . - _- __ _ _ , _ - _ _ _ . _ .. , _ - ___ _ ._._ ._ , __. - - -
ll lll llIl nu
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1 IBCS 4.9.2-1 , Kevisaon 51 FRES$*.*R::ER TD'.PERATURE LIMIT SURVEILLANCE A. STATD'.ctT Cr AFFL:0 ABILITY: This procedure applies to the verification that Pressuriser temperature and spray water temperature differential are within limits in all modes during system heatup or cooldown. B. RETERDJOE3
- 1. Technical Specification 4.4.9.2
- 2. B3P 100-1 Plant HeatJp
- 3. BGP 100-5 Plant Shutdown Cooldown C. PREREQUISITESt
- 1. Receive permission from the Shif t Engineer or designated SRO licensed assistant prior to perfoming this surveillance by having the Data .
Package Cover Sheet (D-1), signed and dated. D. PRDCAUTICNSt b 1. None E. LIMITATIONS MID ACTIONS:
- 1. As stated in Technical Specifications Limiting Condition for Operation (LCO) 3.4.9.2.
- 2. In the event the Acceptance Criteria is not met during the performance of this surveillance. IMMEDIATELY notify the Shift Engineer to initiate LCOAR procedure 1BOS 4.9.2-la. l
- 3. The limits of Byron General Operating Procedures (BGP) for Pressurizer temperature are:
- a. A maximum heatup of SC*P/hr (Admin. Limit) and
- b. A maximum cooldown of 100'r/hr (Admin. Limit) 16 N
] APPROVED AU314 $85 (4990P) g g, g, o
.. . . - . . _ . - - - - . _- - - . ~ - - - . - - - , . - , -
m _._._.___. __ _ _.- _ _ _ _ ___..._.- _ _.._._-.~._-._ _ __m I i 1805 4.9.2-1 ! kovision $1 ! f i T. ttAIN BSDYa ;
- 1. Df7ER the starting time and date in section 1 of the Data Sheet (D.2). !
\
- 2. PLACE an X in section 2 of the Data Sheet for the condition (s) that {
initiated this procedure. ! e...e. nee.eeeeeeeeeeeeeen eeeeeeeeeeeeeee.neeeeeeeeeeeen j e e um - t e
* {
Steps 3 through 0 must be perforwed at least once * ! Per 30 minutes during conditions requiring this * !
- procedure. For ease in determining that tAe *
{ Acceptance Critoria has been met, the data should * ;
- be taken on the same minute of each succeeding hour.* !
eeeeeeeeeeeeeeee ...... eeee .....ee....eneeeeeeeeeeeeen !
- 3. Of7ER the date and time in column 3 of the Data Sheet.
t
- 4. OTTER the reading of the Pressuriser water space temperature channel I (171-453) in column 4 of the Data Sheet. I s
- 5. RECORD the rate of Pressuriser temperature change from the previous i entry as follows: '
i
- a. CALCULATE: I L
O Rate ('F/hr) . Frement taan (*F) - Previous Elapsed time (min) ta=_a f'Fi 60 min hr ( Negative rate indicates cooldown. Positive rate ladicates heatup. 5 i
- b. RECORD.the rate of temperature change ('F/hr) in colman 5 of the ;
Data Sheet.
/!
eseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen ! um If only availlary spray is being used then skip steps
- a j 6 through 8 and enter N/A in columns 6 through 8 of the * ,
- Data Sheet. *
- l eeeeeeeeeeeeen neeeeeeeeeeeeeeeeneeeeeeeeeeeeeeemeneneseeeen i
t S. RECORD the lowest RCS cold leg wide range temp (*r) of the operating ' loops providing pressuriser spray (171-4338 or 171-4435) in column 6 l of the Data Sheet. b
- 7. ' RECORD the temp. (*F) from pressuriser vapor space. 171-454. In column 7 of the Data Sheet. -
i
. i APPROVED l
* ' II E !
t (4990P) B. O. S. R. . t.
'I b
. , . , , - _ . - _ , , ~ , , , . ,.--g..y,,, -
- __._.______._...__._.____..._.__._._.m . _ . _ _ _ . _ _ _ . . _ .
I 1Bos 4.9.3-1 Revision 51 t i O 8. CrIERMIhT the spray water temperature differential using the formula in thas step and record it in column 8 of the Data Shett.
)
i Pressuriser Temp. (171-454) - Cold Leg Temp. (171-4333 or 171-4433) ! a spray Water Temp. Diff. I
- 9. REFEAT steps 3 through 8 at least once per 30 minutes while one of the following conditions exists:
- a. Pressuriser Heatup .
- b. Pressuriser Cooldown !
- 10. COMPLETE the Data Package Cover Sheet (D-1).
G. AOCEPTANCE CRITERIA:
- 1. Pressuriser temperature is limited to: I a.- A maximum heat.up of 100'F in any 1-hour period. and i
- b. A maximum cooldown of 200*r in any 1-hour period. !
c. f A maximum spray water temperature differential of 320*F. j [ I i l f i i a APPR0VED HNAL AUliIti$8$ 3 s. o s. = - (4990P) 4
,. - . - - . _ , _ . . , . r e., e ~w.,.-_.=
O O O APPROVED 180S 4.9.2-1
/,0314 WS Revision si
// 13.O.S.P ACTUAL REQUIRED ACTUAL FEQtJIRED ge/'f/
3.jDr.TE 4. PRESSURIZER
- 5. RATE RATE 6. COLD LT73 7. PRESSURIZER 8. SFRAY WATErr SPRAY WATDP TIME WATER TD4P (*r) (*r/HR) ( *r/IIR) TEMP (*r) VAPOR TD9P (*r) TDEP DIrr (*r} TD9P DIrr I47 66 3 g !E!"I*BC"'I"S;;; 6~S7 43 6 e < 320 r
% 15 s d's J
~
o, lEl"I'$C'**i"dw, " FJ7 E6 3- /cs ( <30r
< Limit A Heatu t Nb bb [b d i Limit B Cooldown Sb NO [ M_ t. < 320*r_
< Limit A W atup
( < Limit B Cooldown c < 320*r
< Limit A Heatup_
ceA7 vzo ' ( < 1 Xt B Coola ~n 4G T (stz I57 e < 320 r
< Limit A Heat f
_lMO 3GT 't < Limit B Cooldown 16 5 MO 7s3 i < 320 r
< Limit A Heatop_
I%T )b 70 t < Limit B Cooldown lO 5 diC [6 e < 320*r
< Limit A h atup IdlO >h 'v0 g < Limit B Cooldown [NS hk MO t < 320*r
< Limit A Hea*up bd rD 3h O e # Limit B Cooldown @T _
2h t < 320*r
< Limit A Heatup
< 320*r hEti JLo c ettC[ t < Limit B Cooldown (
< Limit A Heatuo ll/lO h -
t < Limit B Cooldown lh$ 70 5 ( < 320*r
< Limit A Ileatup
[b31 3[O J 7e < Limit B Cooldown [O 3
!Df b t < 320*r 7W 18 i gl mtg /77 ??S YL' g < 320 y f ( Limit A fleatup .
'E ,o
~f3 E)O 9f( < Limit B Cooldown
< Limit A Hertup_
e < 320*r t < Limit B Cooldown __ t < 320*r,,
< Limit A W atup
( < Limit B Cooldown t ( 320*r
< '.imit 4 lleatup t < Limit B Cooldown* t < 320*r_
~
< Limit A Heatup_
c -( L mit E Cooldown t < 320*r i C-3 (4990P) HIW
O O O AppHOVED loos 4.9.2-1 Revision 51 isJ 141985 B. O. S. P PRESSURIZER TDFERATUstE LIMIT SUliVEIID NCE
- 1. TIME c7 2. L DATE 3/ / 'f /
- 2. APPLICABILITY: / LIMITS:
- a. r PZR Heatup ,( a. T/S < 100*F/Mr AEBLIN < 50*r/kst i
- b. P PZR Cooldown b. T/S < 200*F/Hr AEBEIN < 100*F/lgt ACTtshL anguraED ACTUAL REQUIRED
- 3. DATE 4. PRESSURIZER 5. RATE RATE 6. COLD LEG 7. PRESSURIZER 8. SPRAY WATDr SPRAY WATER TIME WATER TEMP (*F) ( *F/fW) (*F/fWt) TDEP (*F) VAPOR TDeP (*T) TEMP DIFr (*F) TD9P DIrr
-J /y4/ . < Limit A Heatup G)
't z t, -
d ( Limit B Cooldows I8 , EJO T f ( 320*r [?? f C Limit A Heatup , , i9 Z b,- d < Limit B Cooldous '># - hfO g ( 320*r
< Limit A Heatup C 3b 5[O O ( ( Limit B Cooldown 3 g ( 320*r 8 262' F , U$ 5 D'n d /f f 2 b~ fo e < 320 r p5 277 '# , l[l"!!^0,i*dow. E/o t TT 4'r G, < 320 r 720 17B W ,
) (("m!t a cooI L 2 I T E70 ?'T 6 e < 32c*r q < Limit A Heatup ; {
7q ,.7 i d'{ s _.] O d < Limit B Cooldo J 4r
/ t ( 320*r
, f C Limit A l'Attg> 'y bs!M , I/6 /2Y!!M d C Lierit F Coo 1N d ( 320*r gefE '2
< Limit A Heatup -
c / p 2 ,< j, i J9' " { 2J) ( < L.mit B Coolfesa < < 320*r iN- 00 g < ait down f ( 320*r C. Limit A Heptup_ j
~
t < Limit a Ccoldown f ( 320*r
< Limit A Heat h d < Limit a C M I .
t < 320*F
< Limit A Heatup
- d < Limit 9 CoolEuw f ( 320*r j <LimitAHeatugd
( ( Limit B Cool _dmy. f ( 320*r
< Limit A Heatu L i g < Limit B Cooldown) t1 ( < 320*r .
ATTACl! APDITIONAL SHEETS (D-3) aa needed. l Q alt E.J- p :+ v ,,t d ie k .bs e F2 ~ M22__PJ 0 . _ , , _ _ _ , _ , , _ _ , , , _ , , _ , , _ _ _ , , . _ _ _ , _
i t BYRON SlHULATOR I ANSI /ANS-3.5-1985 CERTIFICATION REPMT [ IN111AL REPORT, SEPTEMBER, 1991 I ( E BYRON $1HULATOR r SURVEILLANCE TESTS i i i Surveillance tests were conducted in accordance with ANSI /ANS-3.5-1985 Section 3.1.1 using the attached procedure. The actual Byron Operating Surveillances (805) were : performed on the Simulator. The results are as follows: I
- a. Shutdown Margin Surveillance Accepted
- b. RCS Minimum Temperature for Criticality Surveillance Accepted ;
- c. Hovable Control Assemblies Month'y Surveillance Accepted :
- d. Shutdown Rod insertion Limit Durlig Approach to Accepted f Criticality Surve111ance
- e. Quadrant Power Tilt Ratto Surveillance Accepted
- f. -Caloriretric Calculation Daily Surveillance 9 Turbine Throttle, Governor, Reheat and Intercept Accepted i Valve Monthly Surveillance ,
l
- h. P.CS Controlled Leakage Monthly Surveillance Accepted i Os 1. RCS Hater Inventory Balance 72 Hour Survelliance Accepted
- j. Repctor Containment Fan Cooler Monthly Surveillance Accepted y
- k. CC System Valve Lineup to Safety Related Equipment Accepted Monthly Surveillance ,
- 1. CC Pump Op3rability Monthly Surveillance Accepted
- m. IA D/G Operability Monthly Surveillance Accepted ,
- n. 18 D/G Operability Monthly Surveillance Accepted
- o. DC Bus Train Operablitty Neekly Surveillance Accepted l
i O (BYRONSIM 113/63 08/22/91)
. . . . . - . - - . - - - . _ . ~ . - . . - . . . - ~ ~ . - - . . - . . - . - . - _ - . . . .
i BYRON SIMULATOR [ ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT. SEPTEMBER, 1991 { j O BYRON SIMULATOR
!t SURVEILLANCE TESTING l i
A. PURPOSE The purpose of this procedure is to: ' Verify that operator conducted surveillance testing on safety-related equipment or systems can be conducted as required by ANSI /ANS-3.5-1985. ! B. REFERENCES
- 1. ANSI /ANS-3,5-1985: Nuclear Power Plant Simulators for Use in Operator Training.
l i
- 2. Byron Unit One Survei11ance Procedures.
t
- 3. PTAO-105: Simulator Certification Reporting and Testing Program i i
C. . SURVEILLANCE SELECTION CRITERIA The selection eriteria used to meet ANSI /ANS-3.5-1985, sect 1on 3.1.1(10) -I ' requirements (simulator surveillance testing) are:
- 1. - Surveillance is safety-related. !
, 2. Surveillance frequency is monthly.or less. .
.I
- 3. Surveillance-contains control room Indications or requires control board !
-manipulations.
l D. INITIAL CONDITIONS
- 1. Use the BOL, 100% power, equilibrium xenon _ initial condition (IC) unless a l Iower power level is noted in the survelliance procedure. -
i E. DATA COLLECTION k 1, The Control Room data required by each surveillance procedure shall be f collected. t
- 2. Data that is obtained from outside the Control Room shall be obtained,.lf _,
'" l la l M'" '"'i te" !' %.' ' ' ""' " '"' ' ' ' " '
v i l' - i i (BYRONSIM 113/64 08/22/91) I i
- ?
BYRON S1HULATOR AN51/ANS-3.5-1985 CERTIFICATION REPORT l INITIAL REPORT, SEPTEMBER, 1991 O BYRON SlHULATOR SURVEILLANCE TESTING (continued) ' F. TEST INSTRUCTIONS
- 1. Ensure that the simulator meets the initial condition as specified in Section D. .
[ NOTE - The simulator has the capability to conduct the
- shiftly/ daily surveillances, various channel check * ,
- surveillances and the system lineup surveillances. * '
. . . . . e. .s e. .r.s u. . v. e. .i l .l a. n. c. e s . w. .i l l no. .t . b. e. . p e. r f. o. rme. d.
Th r l
- 2. Using the latest revision of the Byron Unit One Surveillances (C0S's),
perform the following procedures: '
- a. IBOS 1.1.1.1.e-1: Shutdown Margin Surveillance i
/~] b. 1805 1.1.4.a-1: RCS Minimum Temperature for Criticality Surveillance i
- c. 1RX 1.3.1.2 1: Hovable Control Assemblies Monthly Surveillance
- d. 1005 1.3.5-1: Shutdown Rod Insertion Limit During Approach to !
Criticality Surveillance
- e. IBOS 2.4.1.a-1: Quadrant Power Tilt Ratio Surveillance i
- f. IBOS 3.1.1-2: Calorimetric Calculation Daily Surveillance
- g. IBOS 3.4.2.a-1: Turbine Throttle, Governor, Reheat and Intercept !
Valve Monthly Surveillance i
- h. IBOS 4.6.2.1.c-1: RCS Controlled Leakage Monthly Surveillance
- 1. IBOS 4.6.2.1.d-1: RCS Hater Inventory . Balance 72 Hour Surveillance
- j. 1805 6.2.3.a-1: Reactor Containment Fan Cooler Monthly Surveillance ,
- k. IBOS 7.3.1-1: CC System Vaive Lineup to Safety Related Equipment Monthly Surveillance
- 1. 1B05 7.3.2.a-1: CC Pump _ Operability Monthly Surveillance *
- m. 1B05 8.1.1.2,a-1: 1A D/G Operability Monthly Surveillance I
- n. 1805 8.1.1.2.a-2: IB D/G Operability Monthly Surveillance ,
I
- o. IBOS 8.2.1.1-1: DC Bus Train.0perability Heekly Surveillance O i (BYRONSIH 113/65 0'/22/91)
L - _ -- -. . . . ._. - - . . . _ -
BVRON $1Mui,ATOR ANGI /Aks-3,5-198$ CERilflCATION REPORT INTfi % REPORT, SEPIEHDER 1991 CTROM S1FULATOR SURVEILLANCE TESTING (contlitue#) G. ACCEPTANCE CR11ERIA
- 1. Each surveillance can be performed satisfactorily using installed control board instrumentation or variables available on the simulator data pool and meets the acceptance criteria given in the surveillance.
- 2. The observable change in the parameters correspond in direction to those expected from a best estimate for each surveillance test and do not violate the physical laws of nature.
- 3. ~he simulator shall not fat) to cause an alarm or automatic action if Byron Unit One would have caused an alarm or automatic action, and conversely, the simulator shall not cause an alarm or automatic action if Dyron Unit One would not cause an alarm or automatic action, H. DOCUMENTA110N
- 1. Retain the surveillance procedures, O ,
(BYRONS!H 113/65 08/22/91)
1805 1.1.1.1.e.1 Revision
- k UNIT CHE SHU'JVOMN MARDIN SURVE!LLANCE A. SIA!QiD(T OF APPLICAEIL M
- 1. this procedure applies to tL verification of Shutdown Margin in Mode 2 when the reactor is not critical and MODES 3, 4 and $.
- a. After detection of an inoperable control rod.
- b. Daily in Hodes 3, 4, and 5.
B. RErIRENCES1
- 1. Technical Specifications (Surveillance Requirements):
- a. 4.1.1.1.1.a
- b. 4.1.2.31.1.e
- c. 4.1.1.2.a ,
- d. 4.1.1.2.b e 2. Station Procedures
('
- a. SCB.1, Byron Curve Book . Unit One.
- b. 1BCP 100 791. Reference Reactivity Data Worksheet,
- c. 1905 NR.1, Power 51 story Rourly Sur'.elliance.
- d. 190S 1.1.1.la, LCOAR - Soration Control . SECf . Tave : 200*r.
- e. 1805 1.1.2 1a. LCOAR - Reactivity Cor. trol - SDH - Tave t 200'r.
C. PREFEQ[JISITES r Receive permission from the Shift Engineer or designated SRO licensed assistant prior to perferning the surveillance by having the Data Package Cover Sheet signed and dated. APFHOVED WAR 2 31989 l B.O.S.R. 1 (021DV/0023V/022489) i
.. __ _ - - - - _ _ - _ - _ _ ~ . . . . . . _ _ - _ . - _ _
1805 1.1.1.1. e - 1 Revision 1 O V D. ERffitrnmnf, None. E. LIMITATI(t[E AND ACTI{2($1
- 1. As stated in Technical Specification Limiting Condition f or Operation
- a. 3.1.1.1
- b. 3.1.1.2
- 2. In the event the Acceptance Criteria is not met during the performance of this surve113 ace, IMHEDIATELY notify the Shif t Engineer or designated 590 licensed assistaat to initiate LCOAA procedure 1Bos 1.1.1-la or 1805 1.1.2-la as applicable.
F. MAIN BODYi
- 1. Present onditions neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen ,
- E021
- e Use Reference Reactivity Data worksheet for power history *
- prior to shutdown - R.R.D. Incr 100-771. Initial as *
- applicable. -
e / eneeeee............. eenneeeeeeemene***eewoneeeeeeeeeeeeeeeeeeee eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeceeeeeeeeeeeeeeeeeeene e gggg e
- Dual verification of this surveillance will be performed
- by an SRO upon NEO completion.
- eeeeeeeeeeeeeee...eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen
- a. RECORD date and time of calculation.
- b. RECDED core average burnup f rom 190C WR-1 (multiply the number .
of ErPE by the ETPR to mwd /MTU conversion f actor f or this cycle as f ound in the note on DCB-1 Table 1-6). i
- c. PCCORD core average temperature.
- d. RECORD time since plant shutdown for menon/ samarium calculationr 4 (f.1.a Date/ Time - R.R.D Step T.1.a).
- e. RECORD power level prior to shutdown (R.R.D. Step r.l.e). a
- f. RECORD Lhe present boron concentration.
- 2. Minimum Boron Concentration
'~> a. RECORD Minimum Boron Concentration f rom BCB-1 Table 1-1 at ) temperatare f rom step F.1.c and burnup f rom step T.1.b.
APPROVED
.,. MAR 2 31989 (0210V/0023V/022489) EB. C). S. R.
_ .__ . - - -_ _-_ . -_.. .~.. _ . - _ _ _ _ _ T inos 1.1.1.1.e.) Revision 7 - () b. EUBTRACT the present boton ec scentration ao recor6ud in 14ep F.1.f from the minimum boron concontration recoried in Stop I Y.2.a. '
- c. If the issult of the subtrhetion in Step f.2.b is negative, the ,
Technical Specification 6DH requiren.snt is satisfied, provided l not more than 1 rod is stuck out of the core, and no further ' calculation is required. If the result is sero or positiva, j continue with step r.3. ; I
............................c, n................e...+............. ,
- UCl$
- l
- 1).The minimum boron concentrocious in Table 1-1 are * !
- calculated assuming that no tenon or sansrium are prosent* ,
- la the co*e, and that all rods are insertad minus the *
- highest worth RCCA. *
- 2).A f actor of safety (100 ppm) has been added to tbs a ;
minimum boron concentrations calculated in Table 1 1
- l
- tc account for calculation 61 uncertainty. *
- 3). Included in the table are the changes in the totst * !
- temperature defect and roevorth aerociated with * ;
- changes in temperature and buruup. * [
- 4).No further calculations are required .
- a. !! no cc. *ections to account for menon and samarium
- L
- are required and, .
- b. If the SDN for the conditsens in T.1 above is 1300
_f-~v l e pas, or 1000 pom for Mode 5, and,
- I l
*~')
- c. if no more than on RCCA le stuck out of the core end.*
l
- 6. the present boron concenttstion in F.1.f is greater
- l
*' than the minimum boron concentration in F.2.a. *
................................................................ i l
- 3. Kenon Worth Correction (b or c)
- a. RECORD power level prior to trip (IBGP 100-771 KRD step r.l.s) l b. RECORD worth of senon present f rom BCB-1 Table 1-2 or BCB-1 l Figure SC (based on the time f rom stop r.l.d and power f rom step ',
T.1.e). 1). Table 1-2 and Figure 8C are total a enon worth as a function } l of equilibrium power level and time following a plant tr!p. ! i 1 l 2). Road the renon directly f rom the table or the figure and [ enter.the value onto the data sheet. I t
- c. RECORD senon worth correction f rom BCl-1 Table 1-2 or BCB-1 l l- Figure SC (based on the time f rom step r.1.d and equivalent ;
i power). : r
/APF> Fic)N/ EC) 1). The Equivalent power for xenon Calculations portion of the j Reference Reactivity Data worksheet from 1RGP 100 771 is
()
+
MAR { } jggg used in conjunction with BCS-1 figure SC or Table 1-2 Af f the reactor was not at an *quillbtf un condition with ; I EB. C). 55. Ft. P'** ** *** n Prior to the trip. ; ( 0210V / 0023'4022489 ) !
= _ . ~ - , . . - _ . - . . - - 4 . - _ - - . - . ,_%-.- . .- -_ , . -m 4 ..- . , ,- . - -. _ , . - . , -
4 1B05 1.1.1.1.e.1 Nevision 7 Q 4. Samarites Worth Correction eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene e part *
- When the reactor conditions before the shutdown are at
- d equilibrium with respect to samarium, the worth of senarium *
- present can be read directly from the table. *
- If the reactor is not at equilibrium at the time of *
- nhutdown, the average power over the previous $ days should
- 1 # be used to read the table. Samarium corrections need not
- be accounted for until core average burnup is at least *
- 1000 M@/Mn!. e neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen. .ee........
- a. RECORD average power level prior to shutdown (average over previous $ days).
- b. Sweatium worth present f rom BCB-1 Table 1-4 based on the power recorded in step r.4.a and the time recorded in step r.l.d.
- 5. SDM Requireeent Correction
, s. RECORD SDM requirement correction. i 1). If the core average temperature fioen step r.l.e is 1 200'r enter -lQ,Q pcm. + 2). If the core average temperature f rom stop r.l.c is > 200*r enter 0. . r eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene5ce. ... ......................
. ggg e
- The minimum boron concentrbtion in Step r.2.a is calculated *
- assuming all rods are inserted minus the highest, worth RCCA.*
eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee 1
- 6. Isenovable/Untrippable Rod Correctica.
- a. RECORD the number of known leueovable and/or untrippable control rods and subtract 1.
e ggg a j
- If step r.6.a is i sero then enter sero in step r 6.b.
- e e e e e e e e e e e e e e e e e e e n e *
- e n e e e e e e m e n ee e ee e e e e e e e e e e n,e e e e e e e e e e e e e *
, b. Multiply the number of inenovable and/or untrippable control rods I from T.6.a by the cycle specific value of the predicted highest , worth stuck rod, as found in the note on BCB-1, Table 1-6. g' APPROVED O win 23iS89 L B. O. S. R. l l -4 1 (0210V/0023V/022489)
lbOS 1.1.1.1.e.1 Revision 7 - (" , C. 7. Corrected Minimum Poron Concentration Calculation i f
- a. Total Xenos Worth Correction (1 or 2). ;
1). RECORD the value from T.3.b for stable conditions prior to , shutdown. l 2). RECORD the value f rom T.3.c for unstable conditions prior i to shutdown. '
- b. Total Samarisse Worth Correction !
1). RECORD the value used in step r.4.b ,
- c. For total Renon and Samarium Correction add the total Xenon :
worth f rom step r.7.a and the total Samarium worth f rom step T.7.b and record on data sheet.
- d. Integral Boron Worth !
1). Deter 1mine the integral boron worth f tom BCB-1 Table 1-5 at ; the temperature recorded in step T.1.c and the boron , concentration from step r.2.a.
- e. RECORD the Correction f actor f or Boron ef fects on Xenon and Samarium worth from BCB-1, rigure 83, et the boron worth f rom O T.7.d.
l
- f. Total reactivity correction times the reactivity multiplier.
1). Multiply the value obtained from step r.7.c by the value obtained from stop r.7.e and record on data sheet.
- g. Total teactivity Correction 1). Add step r.5.a, F.6.b and step r.7.f and record on data sheet.
l
- h. Corrected minimum Soron concentration integral boron worth.
1). Obtain the value f rom step r.7.d and subtract the value from step r 7 9 and record on data sheet, eeeeeeeeeeeeeeeeeeeeementeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene '
- H2ZT. * !
If the result of the subtraction in Step r.7.h is positive.
- use 0 ppm boron concentration in Step T.7.1.
- neeeeeeeeeeeeeeeeeeeeeemeneeeeeeeeeeeeeeeeeeeeeene... eeeeeeeen. ;
- 1. Corrected Minimwn Boron Concentration. l
' t 1). Using the boron worth from step r.7.h and the temperature ! s
' N 2 3 \909 from step r.l.c, obtain the corrected miplasse boron l
- concentration f rom BCB-1 Table 1-5 and record on data sheet.
, B. O. S. R. [ [ l (0210V/0023V/022489) i
?
1905 1.1.1.1.e-1 Revisico 7
- 4. Shutdoarn Margia Boron Requirement.
- a. Corrected minimum boron concentration f rom step F.7.1 minus present boron concentration from step F.1.f.
- b. If the result of the subtraction in step T.8.r. As negative. the Technical Specification SDN requirement is satisfied.
- E221
- j
* !! the result of the subtraction in step F.8.a is Po81tive. * !
- IMMEDIATELY notify the Shift Engineer or desiganted SRO *
- licensed assistaat to initiate LCOAR 190s 1.1.1.-In * ;
e..................................................weneseeeeeeen i G. ACCEPTANCE.CRITERIAt [ i The actual boron concentration must be i the c6rrected minimum boron concentratf or, as recorded in Step T.2.a or Step r.7.1. I i O l ; I I i l ; i I t t l. APPROVED , r p) w MAR 2 31989 f (rAnal) B.O.S.R.
- I 6
(0210V/0023V/022489) 4 I
f f 1805 1.1.1.1.e.1 Revision 7 l UNIT WC SEJTD0tet MARGIN CALCUt.AT!W SMRET ! uMIT M Dm ')ln / 9' 7:we /o I E I SHUTDOWN DATE 3 I TIME N (R.R.D Step r.1.a)
- 1. PRES 23tT CWDITICMS r i
1 eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee IK2II
- i
- Use reference Reactivity Data Worksheet R.R.D 1BGP 100-771 * !
for power history prior to shutdown. Sign off each step as
- lt is completed.
l eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen .............................. I eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee--eeeeeeeeenen i e um . -l Dual verification of this surveillance will be perfonned * !
- by as SRO upoa NSO completion, e seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen ;
- a. Calculation fe,r Date 9 Time /b / d t
......eeeeeeeeeeeeeeeeeeeeeeeeee........ . ....................
- gg23 e !
- Multiply the number of trPR by the EFFE to NND/M
- l
- conversion factor for this cycle as found in the note *
~
- on SCB-1, Table 1-6.
- eeeeeeeeeeeeeeeeeena. eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee ;
\
- b. Core Average Duraup D mwd / m ,
- c. Core Average Temperature M7 'r i
- d. Time since plaat shutdown for i senon/samarine calculations b hra (r.1.s Date/ Time - R.R.D. Step F.1.a) ,
- e. Power level just prior to shutdown (R.R.D Step F.1.e) 100. 3 nercent
- f. Present Boron Concentration F ops !
i
- 2. MINIMUM BORCM CWCENTRATION j i
i
- s. Mlaimum Sorom Concentratloa '
(ECS-1 Table 1-1) at temperature ! (T.1.c) and Burnup (F.1.b) 9N ops i l meeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemeneseeeeeeeeeeeeeeee e gggg a ;
- The value in (r.2.a) was conservatively calculated with no *
- menon or samarium and the maximum SDM of 1300 pan is a r l
- provided.
- seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee i l 's APPROVED I (o21ov/oc23v/oso9ss) 8.O.S.R. !
4'
, , , , , , , _ . , , . , . . , , - . . , , , , . , , . , , , , ,.,,._mn,- x --,
-,e---,...m , , , , -
1608 1.1.1.1.e-1 Revision 7 (A] UNIT CNE SBUT14. net MARGIN CALCULATION SdEET (Continued)
- d. 9D& ., . _B47 op . 57 pp Miniews boron Present toron concentration Concentration from T.2.a trem r.l.f
- c. If the result of the subtraction in Step T.2.b is negative, and no more than 1 RCCA is stuck out of the core, then the Technical Specification 5m requirement is satisfied and no further calculations are required.
/. / _
IISO DATE SRO DATE
- d. If the result is sero or pouttive continue to Step T.3.
- 3. KENCBI WORTH CORRECT!CM (b or c)
............ ............................e**e..................e e gggg a If the plaat is at or usar squilibrium with respect to menon* *
- before trip use F.3.a and T.3.b to calculate the menon worthe
- correction, otherwise use T.3.c. If t.be reactor was at *
- non-equilibrime conditions before trip then use BC31 Table
- O d
- 1-2 or aca-1 figure SC at an equivalent power determined
- from the IBGP 100 771 RED Performed after the trip to a
a determine the menon correction and record in F.3.c. *
- eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee .....
- a. Power level leefore trip
- oorcent (RRD step r.l.e)
- b. North of senos present (from BCE 1 Table 1-2 or Figure SC) using Power (f.3.a) and time (F.1.d) _ ~30l7 pcm
- c. Kenon worth correction A o_ cm
- 4. SAMARIUM WORTE CORRECTION e.................. ........... eeeeeeeeeeeeeeeeeeen............
ETIE
- e Samarium corrections need not be accounted for until Core *
- Average Burnup le at least 1000 W D/MTU.
- eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene
- a. Average power level before trip (average over previoue 5 days). /00 percent
- b. Semarium worth present (from APPROVED O BC3-1 Table 1-4) basei on power (r.4.a) and time (r.1.d) __ , - M pen MAR 2 3 GH
_D3 B.O.S.R. (0210v/0023v/0309ss)
1905 1.1.1.1.e.1 Revision 7 O ->T-- SHUTDOWN MARGIN CALCULATICW SEEET (Continued)
- 5. SDN REQUIRENENT CORRECT! Cat
- a. SDN Requirement Correction
((If core average temperature (r.1.c) is 1 200'r enter 300 pen, ot.berwise enter 0.)] O ncza
- 6. IMARLE/UN71tIPPARLE ROD CORRECTICat
- a. Record the atenber of known inanovable and/or untrippable control rode then subtract 1 O rods -1 = '!
eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen e gggg .
- If Step r.6.a is a sero then*
- enter sero in step r.6.b. e
- b. Correction for inunovable and/or
- untrippable control rods
((f.6.a) a cycle specific value of the predicted highest worth stuck rod from the note on DC3-1, Table 1 6] O rode , ncm,,od , o pcm.
, (r.6.a) .
l-
- 7. CORRECTED MINIMUN 90RCBI CCEICENTRATICBI CALCULATICM
- a. Total Xenon Worth Correction (r.3.b) or (r.3.c) - 3 Ol 7 pcm
- b. Total Samarium Worth Correction ~
(r.4.b) oca
- c. Total Kenoa and Samarium Correction ((r.7.a) * (r.7.b)] 77 pcza e pcm e pcm
- d. Integral Boron Worth (from BCS-1 Table 1-5) at ~
temperature (r.l.c) and boron yr 3/4/Q concentration (r.2.a) ~WW pcm
- e. Correction factor for Boron s3 ef fects on Xenon and Samarium worth (sCs-1 rigure as) at APPROVED Boron Worth from F.7.d.
O f. Total Reactivity Correction times the Reactivity Multiplier B.O.S.R. [(r.7.c) (r.7.e))
- M M pcm 9 (correction ,33q factor) pcm
-D4-(C210V/0023V/030988)
i
'l I
190S 1.1.1.1.e-1 , Revision 7 l t O SHUTCOWN MARGIN CALCULATION SHECT (Continued) UNIT ONE h 9 Total teactivity Correction f ((r.$.a) . (r.6.b) . O pem . M en e(T.7.f))37tipem a
- 33fl nem
- h. Cortseted Minimum Boron '
i Concentration integral boron worth ((r.7.d) . (r.7.g)] , p ppl
., j 9
- w,e saa . -Aill nem '
e
~
'( '
oca ! 93f5 h e..eeKee.(v ( e ne.....eenee.ne.een.ee..ee .......eeeeeeeeene... .een. g . e 1 k If the results of the subtraction in Step r.7.h is positive.e 3 use O ppm boros concentration in step r A neeeeeeeeeeeeeeeeen eneeeeeeeeeeeeeeeee.eee.7.1. eeeeeeeeeeeeeeeeeeee.
- 1. Corrected Minimum Boron , i Concentration (From BC3-1 Table 1-5) corresponding to boron worth (r.7.h) and temperature gy, ,,. W" 7q 9g j (r.l.c) >*-'- :
ppm '
. 8. Shutdown Margin boron REQUIRENDfT t,
Corrected minimum boron tr.7.1) minue actual boron concentration !' O (r.l.f) e Shutdown borom : G '4 4- (r.7.1) ppm I ! R4 7 ___ (r.1. f) ppe . -3 ( 3 p,a 6 N /. . N / r NGO Date $RO Date l eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen e _j ggg e - If shutdown boron is positive inusediately actify the Shift * ' Engineer or designated SRO licensed assistant and initiate
- j LCoha 1808 1.1.1 1a.
- eeeeeeeeeeeeeeeeeeeeeeee...eeeeeeneneeseeeeeeeeen. .eeeeeeeeeee.
l I l 847. .
.%cra<vdC !
(Final)
.. )'
.ps.
, (0210V/0023V/030958) IGR 2 31707 O.O.S.P.. i l :
I ! 1 1
. . , , . . , , , ._.~...m., ..,..._,,....__.,,..-----,.m,., , _ . . _ _ . . _ _ _ . _ _ _ _ . . _ , , , , _ . - . - . . , - . - - . . _ , _ . _ _ . , - -
1905 1.1. 4. a-1 i Revision 51 [ I REACTOR COOLANT SYSTDI MINIMUM TEMPERATURE TCR CRITICALITY SURVEILLANCE ( A. STATDENT OF APPLICABILITY: This procedure applies to the verification of RCS temperature (Tave) in , Mode 2,15 minutos prior to achieving criticality. !
- 3. RDTRDCES t
- 1. Technical Specifications 4.1.1.4.a
- 3. BAR's 1-14-A3, 1-14-33, 1-14-C3, 1-14-D3 and 1-14-E1.
C. PRERECUISITESt
- 1. This DOS must be performed within a 15 minute period prior to achieving criticality in the reactor.. -
L D. PREAUTIONS l
- 1. The RCS temperature must be greater than or equal to 550*r prior to , ,.
achieving criticality.
- 2. If greater than 15 mins. has passed from stop lb and the reactor is not critical. this DOS oust be performed again.
E. LIMITATIONS AND ACTIONS: ,
- 1. As stated its Technical Specifications Limiting Condition for <
Ope ration (L. '*.O. ) 3.1.1. 4.
- 2. In the event the Acceptance Criteria is not met during the performance of this surveillance. DMEDIATELY notify the Shif t Engineer to initiate 140AR procedure DOS 1.1.4-14.
F. MAIN BODY ( ,
. m .
- Inital each step in the space provided adjacent to the *
- Main Body step number after the step has been sucessfully *
- completed.
- M. Enter
- a. Date { / /C f $l
- b. Time O8 O ,
l i O ^eeaov"o AUS 14 885 l B. O. S. R. (2536P)
1906 1.1.4.a-1 R: vision 51 Within 15 minutes prior to anticipated criticality, log RCS Imps g, - Tave using 1TI-412(Loop A),171-422(tmp 3),1TI-432(Loop C), and 1TI-442(Loop D) Temperature i Imp 1A Tave (171-412): a 657 'r l i Loop 15 Tave (171-422): e ss7 *t Imp 1C Tave (1T1-432): edh *r i Imp 1C Tave (171-442) e .-97
. 'T
[. _3 VERIFY that the lowest loop Tave is 2550'r. [ Record time of criticality. Ob 7 ;
'ift Engineer
). 5 l /$ Vl r signature Da t e j I
ACCEPTANCE CRITERIAt
- 1. The Reactor Coolant System temperature (Tave) shall be determined to, i be 1550' withis: 15 minutes prior to achieving reactor critir.ality. .
n v k I i
?
i i i APPROVED FINAL AUG 141985 l' l ! g, o, g, g, 1536P)- ( ;
.u- ....... .
Revision 2 MOVEARLE CONTROL At3EMBLIES HONTHLY SURVE!LLANCE A. EIAIt.NENT. Of APPLIC)J11LII11 r] (~/ This prot;edure applies to t.he verification of control assembly operability in Modes 1 and 2.
- a. EllL11lict&1
- 1. Technical Specifications 4.1.3.1.1.
C. t1EREQL1111%T&1 ;
- 1. Receive permission f rom the Shif t Engineet or designated 3RO licensed assistant prior to performing this surveillance by having the Data Package Cover Sheet signed and dated.
- 2. A visual inspection inside of all 5 RD power cabinets smilcates that no blown fuse indicators are tripped.
D. PRECAlfTitME: l i i
- 1. Before transferring to automatic control, ensure permissive C-5 is estinguished.
- 1. Avoid variations in plant lone, reactor coolant temperature. and
- boron concentration. >
- 3. During the surveillance. . reactor coolant average temperature changes
[ greater than -4*r or +1'r shall be ccepensated for by moving rods ( intermittently to antch TAVE and TREr. l
- 4. Maintain W1 within prescribed limits. ,
i
- 5. Before transferring to automatic reactor centrol. manually adjust l Tavg to within s l'T of the reference temperature to avoid a transient following the transfer.
l E. LIMITATIf.ME AND ACTICME t ?
- 1. As stated in Technical specifications Limiting Condition for l Operation 3.1.3.1.
- 2. In the event the Acceptance Criteria is not met during the perf ormance of this surveillance. 1Hr(EDIA*tELY notify the Shift Engineer to initiate LCOAR 1906 1.3.1-la. ,
1 ggEVEREMCE : peptovgD JAN 0 6 W l O , 8.O. S. R. (0665V/0061V/010590) I 4 F
ABOb 1.3 1 ;.1 Rcvision 2
- r. ti&ig RODY t seeeeeeeeeeeeeeeeeeeeeeeeen. ...eeeeeeeee....eeeeeeeeeeeeeeeeeen e
NOTE e Initial each step in the space providJd adjacent to the a e main body step number ATTD the stop has been EUCCEEEFULLY a e completed. Persons performing independent veriflestion
- e should initial la the space provided after the step. e nessee,eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen JQ 1. ExTER: Time 9[I Det. 3 b 0/
- 2. TRANSTER/ VERITY tod control to manual ,
- s. PLACE /VER!rY bank selector switch to MANUA1. position,
- b. Utilising the Rod Motion Control switch MAINTAIN TAVE matched with TREr.
- 3. Shutdown banks
- a. DrTER in column 3a. the initial group 1 and group 2 stop counter readings for Shutdown Banks A, B, C, D, and E. (Note . There art, no group 2 Step Counter Readings for 5/D Banks C, D & E)
- b. SELECT Shutdown Bank E by placing bank select switch in SBC position. .
- c. Utilising the rod motion control switch, INSERT Shutdown Bank E 10 15 steps.
- d. RECORD in column 3d group 1 and group 2 step counter readings.
- e. VER!rY, utilising DRPI, that each rod in Shutdown Bank E mov'ed
, 10 15 steps and signify this by laitiallag in space provided in column 3e,
- f. Utilising the rod motion control switch, WITHDRAW Shutdown Bank E to 231 steps.
- g. RECORD in column 3g final group 1 and group 2 step counter readings.
- h. VERIFT that the DRP! indication for all rode in Shutdown Bank E is 231 steps and signify this by initialing in space provided in column 3h.
- 1. REPEAT steps b. through h. for Shutdown Banks D, C, B, A.
APPROVED JAN 0 61990 B. O. S. R. (0665V/0061V/010590) l l
Ab;$ 1.4 1.1 1 3 R3 vision 2
$hutdown Red Sant 'la, initial Step '3d. Step Counter '3e. fach tes in '3g. Final ;tep '3h, att se en in l Counter Reedingt After henn teeved CovLler ten 6 at [
O 3. Readine Genue 1 Grgua 2 Grous 1 lttartien Graua 7 10-16 Steps tandtnen Graue I Graue 2 231 tiept [ s6 aide.,n ioni i r?/ 23/ _ ?f/ MJ , sfd "O ?O _ Mi ssui .wn s. i e 7 5./ 23/ 1 71 ?fl,F "l Z/T T'/I_ l
,p utde.n sank C M/ W/A 27J m a N %, m W ssutdown aank D 73/ N/A N/A e N/A 7 l uitown tank r 2S! N/A N/A r 1 ! N/A '
\T4. 7 Control Banks [
- a. ENTER f n column to the initAal group 1 and group 2 step courter l readings for ';ontrol Banks A, B, C, and D.
i esseesse....eLeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeebeeeeeeeeeeeeeeeees e e e
- If the bank is fully inserted, record the group 1 and *
- group
- step counter read.ings, mark all other columns on *
- Data t' et N/A and do act proceed with surveillance for *
- that bank. * '
e..............oe.............. eeeeeeeeeeeeeeeeeeeeeeeeeeeeee,e.
- b. SELECT Control Sauk A by placing bank select evitch in CBA position. .
..................................e.......ee....................
e ggg e
- Control Banks may be moved 10-15 steps in or out et the *
- discretion of the S/E or his designee to meet the
- a requirements of this surh illance. Monitor Reactor Power * '
- and Tave closely and correct as necessary to minimise plant *
- transients.
- t eeeeee...eeeeee.....eeeeeeeeeeeen ...eeeeeeeeeeeeeeces....eeeeee
- c. Utilising the rod motion control switch, NOVE Control Bank A ,
10-15 steps.
- d. RECORD la coluonn (d. group 1 and group 2 step counter readings.
- e. VERITY, utilising DRPI, that each rod la Control Bank A moved 10-15 steps and signify this by initialing in space provided in column 4e.
- f. Utilising the rod motion control switch, pos!TIObi Control Bank A to original controlling position.
APPROVED l . q ~ JAN 0 61990 B.O.S.R. (0665V/0061V/010590) P
IBOS 1.3.1.2 1 R3 vision 2 9 RECORD in colume 49 final grceup 1 and grcup 2 stOp cou2 tor readings.
- h. VER!rY, ut!!ising DRFI and group *tep counters, that all rods in 3
-N Control Bank A are RESTORED to their original position and sigalfy this by initialing in space **" 'ided in column (b.
- 1. REPEAT steps b. through h. for Control Banks B, C, and D.
Control med Sank *4a. Itit'al Step 'ed. Step Counter '4e. Each Rod in '4g. Fine) Step 'eh. A11 rods at Cevater Reedings After Senk Hoved (9unter original 4, _ ,i< V33e havament 10 1$ Steps sandinan position Grnua i Graus 2 draum 1 Graum 2 Grous 1 Grous 2 contr.i s.nm A ? fI /i/ 22/ 22/ , s7# 75/ 23/ 7# contr.t n a e 23/ 2 T/ 27/ 22/ , 7# n' /?/ (TA e.oirai n m e 2?/ 73/ 27/ 2Z / , J4' 73/ 23/ J N- J Coetrot aank D M7 # f. 47 /f[ , t7M MI 33/ 8/~l RESTCk'. rod control to automatic.
- a. VERITY Low Pswer Interlock C-5 NOT LIT.
INDEPENDENT VERITICATICII
- b. VERITY TAVE-TRET deviation i l'T.
O- INDS, PENDENT VERIFICATICBf i
'd
\ 9/ te. PLACE bank selwetor switch in atr!O.'
INDEPENDENT VERITICATICR4
. 6. Notify Chemistry Department of rod movement to deterinine if RCCA cladding defect sampling should be obtained per BCP 210-19 and/or DCP 210 G. AcerPTANcr cafTraf Ai
- 1. Each rod not fully inserted in the core shall be determined OPERABLE at least once each 31 days by movemont of at least 10 steps in any one direction.
APPROVED trinal) JAN 0 61990 A B.O.S.R. U 4 (0665V/0061V/010590)
130s 1.3.5-1 R3visicn $1 i SHUTDOWN ROD l
~
INSERTICBI LIMIT DURING APPROACH ! TO CRITICALITY SURVEILLANCE , i A. STATmDIT OF AP 8LICABILITY: \, I This procedure applies to the verification that each shutdown rod is fully withdrawn within 15 minutes prior to the withdrawal of any rods in Control ; bank A, B, C or D in N3DE 2. l B. grro w : j l'. Technical Specificatica 4.1.3.5 - *
)
- 2. BGP 100-2 C. PREREQUISITES:
- 1. Receive permission from the Shift Engineer or designated SRO licensed ;
assistant prior to perforwing this sutveillance by having the Data i Package Cover Sheet signed and dated. , D. PRECAUTIONS:
- 1. None ;
O Q
~
E. LIMITATIONS AND ACTICBS: F
- 1. As stated in Technical 9pecafications Limiting Condition for :
Operation (LCO) 3.'. 3.5.
- 2. In the event the Acceptance Criteria is not met during the performance of this surveillance, IletEDIATELY notify the Shift ;
. Engineer to initiate ECOAR 1808 1.3.5-la.
F. -HAIN BODY:- l
- 1. DITER i
- a. Starting Time Ob26 .
[
- b. Starting Dato i / i y /41
. VERIFT on the Chart Below by initials that for ecch Shuudown Bank all ;
nods in that Bank are fully withdrawn 1229 steps as displayed on the ! digital rod position indicatica parel. 2g Shutdown Bank A d Z 3i ' Shutdown Bank B g 23/ Shutdown Bank C d e 5, / Shutdown Bank D d 2w# Shutdown Bank E d TA I APPROVED ; AUG 121985 l
~~
B . O . S . P.. j (2511P)
_ ._ . _ _ _ _ - _ . - _ . -_ ._.m _ . . _ __ IBOS 1.3.5-1 R:visicn 51
'q W, 3 Drnst the time and date control bank rod withdrawal began.
t n P ~t T / 1/ o v/9 9 h- VEl RIFT that each shutdown rod was determined to be fully withdrawn "b 4. l and that this verification was completed starting within a 15 minute _ period prior to control bank withdrawal on an approach to reactor criticality by initialing this Step. t _G. ACCEPTANCE CRITUtIAt
.1. . _Each shutdown rod shall be determined fully withdrawn within 15 minutes y rior to withdrawal of any rods in Control Banks A, B, C, or D during en approach to reactor criticality. j
. . . . c.. . . .: .
i 1 , F t t ( i I l, i i l-
^**aoveo O ,
j RNAL AUS 121985 i B. O. S. R. ; (2511P) i
- I e- , . . - - -- - + - . , . . . . . . - - , . ~ . . _ - _ _ - . . m - - - - - .
1BOS 2.4.1.0-1 R3 vision 2 QUADRANT PCNER TILT RATIO CALCULATItat
~
O A. STATEMENT OF APPLIt'leILITYL This procedure applies to the verification of Quadrant Power Tilt Ratio in Mode 1 above 50% Rated Themal Power, weekly when either the computer alarm or the flux deviation alarms f or NIS Power Range Tilts are operable and Shiftly when all alarms are inoperable. This procedure also verifles Quadrant Power Tilt Ratio hourly when any alarm indicates a tilt is present. If one Power Range escore channel is inoperable and the unit is in mode 1 above 75% of Rated 7hermal Power, this procedure may be utilised to calculate the Quadrant Power Tilt Ratio utilising the three remaining power range channels for comparison to incore flux map results per 1BVS 2.4.2 1. B. REFERENCES 1
- 1. Technical Specification 4.2.4.1.a
- 2. Technical Specification 4.2.4.1.b
- 3. LCOAR 1BOS 2.4.1-la.
C. PEEREC7'I KITEE i
- 1. Receive permission from the Shift Engineer or designated SRO licensed assistant prior to performing this surveillance by having the Data Package Cover Sheet signed and dated.
- 2. Reactor power should be constant while recording data from NIS.
J. Obtain the last determined loo % Power NIS Detector Currents from the Station Nuclear Engineer or the Operator Aid on 1PMo7J. D. PRECLUTIattE n None E. LIMITATICMS E C l3 E1
- 1. As stated in Technical Epocification Limiting Condition for Operation 3.2.4
- 2. In the event the Acceptance Criteria is not met during the performance of this procedure I MEDIATELY notify the Shift Engineer to Initiate LCOAR 1505 2.4.1-la.
APPROVED SEP 121990
' *~
u4eevio112viosotoo) .
-- - - - - --.m__._._ . __ _ . _ ___ _ _____ _ _ _ _ _ _ _ _ , _ _ _
1908 2.4.1.0-1 R2vicisa 2 [r
- r. MAIN 30DYi ;
t nv meeeeeeeeeeeeeen...eeeeeeeene eeeeeeeeeeeeeeeeeeeeeeeeeen.eeeeee e - e e Initial each step in the space provided adjacent to the * . e
- Main Body stop number AFTER the step has been EUCCESSFULLY e completed. L eeeeeeeeeeeeeeeeeeeneseeeeeeeeeeeeeeeeeeeenneenneeeeeeeeeeeeeeen i.
[ ..eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee***enee****eeeeeeeeeeeee
- M
- I
- If one Power Range Channel is inoperable, the OPTR may be
- 7
- calculated using the three operable channels. Record N/A * ;
- for the inoperable channel *
....ee......... eeeeeeeeeeene...eeeeeeeeeeeeeeeeeeeeee...ee..... ;
4d/1 1 Record the reactor powet from the NIS Power Range Drawers. l f NR41 NR42 NR43 NR44 by '?$, l % N ??% 'l4.$ % l
- 2. DETEEKINE the Quadrant Power Tilt Ratio, for the Upper (A) & Lower -l (3) Detectors, la the Data Tables belows t
- a. Present Detector Current
- h. Last determined 100% Power NIS Dstector Current, (Obtain from i Station Nuclear Ragineer or the operator aid on IPN07J). .
? c. Normalised Detector Currents = Detector Current 100% current .
. . I
- d. Average Normalised Currest e Etam af Mormailmed Detectar currmata ,
6 of NIS f*ha==als operable [ i
- e. Power Tilt Ratio = unmaliand Detectar currane )
Average Normalised Current i i
?
e t
~
i APPROVED i SEP 121990 ! B.O.S.R. j
-2 .
O (1466V/01137/090490) b ( t
, .--yy.----..rg--yy--pgr. e-- yw- y *r---y nwg e v--W#
. . . -. . . . - _ ._- -. . . . ~ . - . . - . .. . . . _ . = . _ _ . ~ _ . . -.
[ 190S 2.4.1.a.1 R3 vision 2 J i UPPER DETECTORS (A) N41 M42 N43 N44
.. Detector Current j g. ) c 4/ 2 /6 7c7 j
,2 ) T, } 2C$.4 22 C. Y 21.) , ~-
I be r Current '/77 3 .777I' . 77T ri727 [
- d. Average Normul- //////////////
- p7 y
, /////////////// l inne Current ////////////// ///////////////
**h.*tNNI1.02) /. W / e / C('I e /. c 2 e . 'I'/ I e i
LOWER DETECERS (B) M41 M42 N43 N44 j
- n. Detector Current Q3( jf( ) )y 2l[ i j
- b. 100% Detector .
Current 2.1(, '/ / $f,l/ ~) l j', ( } }g', '/ l
- c. Nors=11 sed ,9'777 , H S/ '
D.t.etor Curr..t , 'Mg2 /. v c. 3 1 I J
- d. Average Normal- ////////////// /////////////// .
laed Current ////////////// . $$$b /////////////// o 1.02) . /k e /. 0 0 e
- e .T e !
G. ACCEPTANCE CRITERIAt O " " - ' ' " ' ' - i I 1 r t i t l ! I t l i I APPROVED l (ri==1) SEP 121990 i B.O.S.R. j l O,- (1466V/0113V/090490) T i 1 t f
, . . - - - - - - . . , . - - , - - . . , . . . ~ , - . , - - - . - - - .
I 1BOS 3.1.1 2 R:visica 3 5 CALOR! METRIC CALCULATICBI DAILY SURVEILLANCE j.
'/ Dt A. SIgrrunrr 'or APPLIciart tTr n l This procedure provides the necessary instructions and worksheets to ['
perform a 6econdary side calorimetric at least once each 24 hours when in Mode 1 above 15% rated thermal power. The calorimetric will be used to . verify and/or adjust the Nuclear Instrumentation System's Power Range f channels. y B. RIZZRENCES2
- 1. Technical Specification 4.3.1.1 [
i
- 2. SNUPP's GEN-N-05 ;
- 3. 1BGP 100-3 ,
- 4. ASME Steam Tables C. PREREQUISITES 1 ,
- 1. Receive permission from the Shif t Engineer or designated SRO licensed ,
assistant prior to performing this surveillance by having the Data > Package Cover Sheet signed and dated.
- 2. The reactor has been at a constant power level above 15% of rated ;
thermal power sad ths unit has been at a steady state load for greater than 5 minutes. .
- 3. The steen generator's levels and steen pressures have been constant I for greater than 5 minutes. i
- 4. There has been no rod motion for greater than 5 minutes. !
l
- 5. Feedwater flow and temperature have been constant for greater than 7 5 minutes. ,
- 6. Steam Generator Blowdown flows have been constant for greater than 5 minutes. ;
D.- PRECAUTICBIS 1 i
- 1. When using the process computer to perform the calorimetric calculation, care must be taken to ensure that the steem generator blowdown flowrates are correctly input into the computer AI ALL l TIMES. .This must be done in order to ensure the eight hour average ;
. power values are correct. t
- 2. If any process computer calorimetric program input value is added, removed, or modified, a minimum of 11 minutes must elapse prior to :
initiation of the calorimetric to ensure that the 10 minute historical calculation performed 1)y the computer contains the new value(s) for the entire 10 minute calculated period. APPROVED JUN 1 1 mo ' l (0437V/0043V/053190) B.O.S R.
%J -
t t
ISOS 3.1.1-2 23visin 3
- 3. Unit operating parameters shall not be changed while performing the calor.imetric or adjusting the NIS Power Range channels.
\
\
- 4. Any power range channel (NI41, NI42, N143, N!44) shall be adjusted if, based on the calorimetric, the absolute difference is greater than two percent, or if indicated power is less than that obtained in this calculation.
- 5. Data shall be obtained concurrently so that it is compatible.
- 6. If the calorimetric indicates the need to adjust the NIS Power Range channels, this adjustment shall be accomplished promptly after the calorimetric calculation and prior to a power change.
- 7. Care should be taken when adjusting NIS Power Range channels to prevent an inadvertent reactor trip due to an excessive rate of-adjustment and/or failure to reset rate trips prior to adjusting subsequent channels.
- 8. Changes in Steen Generator Blowdown will affect Reactor Power.
Verify P.eactor Power < 100% prior to increasing Blowdown flow. E. LIMITATIG($ AND ACTIGIEt
- 1. In the event the Acceptacce criteria is not met during the performance of this surveillance, IIMEDIATELY notify the Shift Engineer to initiate LCOAR procedure 190S 3.1.1-la.
- 2. If the process computer calorimetric program is used to calculats
, power,-the Data sheet and Worksheet are not required to be used.
( The computer printout should be attached to the NIS Worksheet and rett.ined. ,
- 3. The following applies t> the QUALITY assigned to the values used in l-Plant Process Computer applications. See'Appendia A for a list of i computer inputs to the Calorimetric programs-
- a. SUSPECT (an "S" follows tha value) means the data was not collected under optimal conditions or is t.be result of a l manually entered input. N walum in mer==* =M a if verified.
- . b. POOR (a "P" follows the value) means the value is marginal.
Every effort must first be made to determine and correct the cause of a POOR final calorimetric output and the SE or designee != must approve its use.
- c. BAD ("KKKK" is displayed in place of the value) means the value is unacceptable for use.
- d. The qualif ty for each value is carried through any calculation l using that value. The quality that appears is the worst quality -
that went into the calculation. The only exception is that a-POOR combined with a SUSPECT or another POOR will result in c nAD quality. APPROVED
- - _,_ JUN 111990 (0437V/0043V/053190) g,g,c g
1BOS 3.1.1-2 ' R visica 3 ! i i
- 4. Any value that will require manual input for greater thto one shif t l shoulp be tracked on unit turnover sheet. (BAP 335-176 Unit NSO turnover.)
( F. MAIN BODY 1 I
- 1. ENTfR the date and time the calorimetric was started and the name of the operator Performing it in Block 1 of Calorimet.*1c Data sheet. j r
eneeeeeeeeeeeeeeeeeeemeneseen eeeeeeeeeeeeeee ...eene e**enesee
- I
. NOTE
- The computer Foints listed on the Data sheet may be used *
- if the computer _is in service. This will increase data a
- accuracy and lower calculation time.
- een neene eeene**eeene****e***e ..........ne** ......... .....
- 2. ENTER the gross megawatts electric and the control rod bank positions in the spaces available and ensure that all Ef1RECI&5121.5 (Section C) are fulfilled in Block 2 of the Data sheet. g
- 3. ENTER percent power readings from NR-41 NR-42, NR-43, and NR-44 in
[ Block 3. eeeeeeeeeee........eeeeeeeeeeee............... ** ......e** ...
- 52IE .
- It is possible to perform the calorimetric calculation *
- using the program on the process computer. If this is *
- done, a 10 minute average calorimetric with a long output *
- must be used. This is to average out feedwater flow values *
* .to obtain more accurate results. If the computer is used, *
- t a proceed to stop 21.
- e.......................... ***e ..............................
...e*** ........................................................
- It2ZE *
- If the computer is unavailable,. request Instrument
- Maintenance to obtain readings with Fluke multimeter from
- emplifiers inside IPA 50J for feedwater temperature. *
**e eeeeeeeeeeeeeeeeeeeeeeeeeeeeene**eeenannenneeen ......e** .
- 4. ~13fTER computer points 70418, 70438, 70458, and 10478 in Block 4 of the Data sheet. ,
- 5. ENTER steam pressures for each loop from indicators or the average i from computer points listed on the Data sheet in Block 5. If the ;
indicators were used. CALCULATE the average pressure for each loop j and record in Block 5. !
- 6. EKTER feedwater flow for each loop from flow indicators or ENTER '
feedwater DP from computer points listed on the Data sheet in Block 6. l l APPROVED JUN 1 11990 . B.(3.S.Ft. (0437V/0043V/053190) 1 i
,-m
I-l 1805 3.1.1-2 l R:;visica 3
- 7. ENITR blowdown flow for each loop in gpm on the Data sheet in Block 1.
O
~
l
- If tempering line flow la isoleted v6ter 0 for tempering l
*- flow in Block 8.
.................n
- 6..w...............s....e.................
j 8. DfTER tecepering line flew f#r each 1907 in 9pm in Block 8 on the Data sheet.
- 9. CCHVERT the average staatn gehe'tstor pressure for each loop to psia by adding 14.7 psi to convert to pala. RECORD in Block 9 of the Worksheet.
- 10. CALCULATE the average feedwater flow if the indleators were used and record in Block 10 of the Workshee*., Tt the computer points were used, CALCULATE the average feedwater flow in KBH using the equations in Block 10 of the Worksheet.
- 11. CALCULATE blev$own flew ir,f2W csirg the equation listed in Block 11 l .of the Worksheet.
l ( 12. CALCULATE tempering line flow for each loop in KBH using the equation listed in Block 12 of the Worksheet. I
- 13. CALCULATE not feedwater flow by adding feedwater flow from Block 10 and tempering line flow in Block 12. RECORD in Block 13 of the Work sheet. -
.f%
14. t) DEnvE the steem enthal,y, h,, usin, saturated steem at the a ora,e steem generator pressure for each loop. RECORD in Blocs 14 of the
, Worksheet.
- 15. DERIVE the steen generator blowdown enthalpy, h3, using saturated liquid at the average steem generator pressure for each loop.
RECORD in Block 15 of the Worksheet.
- 16. DERIVE the feedwatei enthalpy, h , using compressed 11guld at the
! average steen generator pressure and feedwater temperature for each loop. RECORD in Buck 16 of the Worksheet.
- 17. DLRIVE the steem mathalpy, hs . by using the following equation and
! RECORD in Block 17 of the Worksheet. I hs=xhg + (1-z)h3 where x = steem quality = .9979
- 18. CALCULATE each loop's the?<.a1 power by using the following equation in Block 18 of the Worksheett (W-w)hs
- wh3 - Wh, = Thermal Power (Btu /lb) l l W = pet reedwater riow (ib/hr) w = Blowdown riow (1b/hr) APPROVED hs = Steen Enthalpy (Stu/lbi h3 a Blowdown Enthalpy (Btu /lb) JUN 111990 hw = reedwater Enthalpy (Btu /lb)
B.O.S.R. O (0437V/0043V/053190) [G
1805 3.1.1-2 R:visian 3
- 19. ADD all four loops thermal power together in Block 19 of the Worksheet.
- 20. . Utillaing.the following formula, DETERMINE the percent power and ENTER in Block 20 of the Worksheet.
Eum of Leon never fBlock 19) B*fif /hr K 100% 0.49% e Percent power 11.6417 K 109 Btu /lb
- EM *
[
* ,The 0.49%'la the equation accounts for RCP heat input and a !
- ambient losses.
- I
................................................................ j
- BM *
- Perform steps 21 through 23 only if using the process *
*- computer. If the manual method is used go to step 24. * !
- 21. DEPRESS MINU.
- 22. SELECT option 23 (Calorimetric). i i
- CAUTICEt * '
- STEAM GENERATOR BLONDONN TLONS.MUST BE MANUALLY ENTERED * .
p
- UNTIL MODIFICATIONS CONNECTING TREM 1D TWE COMPUTER . [
'g
\
- ARE DGtE. ALL MANUALLY ENTORED VALUES MUST BE VERIFIED
- CORRECT AND KEPT UP TO DATE SO TEE EIGWY NOUR AVERAGE
=
l
- CALORIMETRIC IS ACCURATE.. ALSO, 4E1 MANUALLY ENTERED
- j
- VALUE TRAT IS ADDED, REMOVED,.OR MODIFIED, REQUIRES THAT f
- A MINIMUM OF 11 MINUTES ELAPSE PRIOR TO INITIATICEE OF A *
* :10 MINUTE AVERAGE CALORIMETRIC 70 DISURE TEAT CALCULATICIE *
- PCRFORMED BY TEE COMPUTER CONTAINS TEE NEW VALUE(S) FOR THE
- h
- ENTIRE 10 MINUTE CALCULATED PERIOO. SEE APPEatDIX A FOR
- i
* -.A LIST OF TEESE INPUTS.
- i t
L ; APPROVED JLM 1 11990 ! B.O.S.R. (0437Vv0043V/053190) b
190$ 3.1.1-2 R:visies 3
. ******e e* ........................ ee ***en...... e***eeseen p
- NDIE e (q) .
- Data for the process computer calorimetric program may be
- taken from control board indication and manually entered
- to allow the computer to perforce the calculations. Also, .
- Af a channel is out of service, a value consistant with *-
- remaining instrumentation as serified by a channel check
- a may be manually entered into the computer. * !
............... ..e****e................mecom nene ne.** .......
- 23. a. ENTER 1 for current data.
- b. ENTER 6 for a 10 minute average long output. ;
- c. SELECT desired output device.
- d. ENTER steam generator blowdown flows for each loop. ;
e. DEPRESS EKECUTE.
- 24. On the NIS Worksheet in Block 24, ENTER the NIS indicated power from I Block 3 of the Calorimetric Data sheet for each channel. l
- 25. ENTER percent power calculated in step 20 of the Worksheet for all i four channels in Block 25 of the NIS Worksheet. ;
- 26. Using the formula below, DETERMINE power difference and ENTER results '
in Block 26 of the NIS Worksheet for all channels. Block 24 (NIS indicated power) - Block 25 (Calorkmetric Power) e I Block 26 (Power difference). ;
- 27. It' Block 26 is a posit ive number and less than 2%, INITIAL in Block
- 27. REPEAT for all four channels. If any answer is negative or
,/T greater than _ or equal to a positive '2%, PROCEED to step 28. If all
( ,) anewers are positive and less than 2% adjustments to MIS power range channels are not required but may be performed at the discretion of
- the Shift Engineer or his designee. ,
- 28. RECORD the CURRENT percent power readings from NR-41 NR-42. NR-43 and NR-44 in Block 28. '
- 29. SUBTRACT the Po er difference (Block 26) from the current NIS -
readings (Block 28) to determine the indicated power level to adjust to. RECORD in Block 29.
- 30. PLACE the Rod control system in MANUAL.
f
- 31. Perform this step only if one NIS Power Range Channel is Inoperable. I l
one....ne..... e*****e **ene****e ....e***eneenen....eeeene.e*** ;
- NOTE *
- Ensure the Technical Specification Action Statement for
- l-
- one inoperable Power Range chonnel is compiled with. =
nenne...**ene.............***eene***eene..**ee.............. i l
- a. INSTALL the control power fuse for the inoperable channel. ,
APPROVED . JUN 111990 (0437V/0043V/053190) ( F3.C).Si.Ft. f 4
1 Bot. 3.1.1 _ _ _ R3visica 3 I
-t eneeeeeeeeeeeeeeemene***eeeeeeeeemeneseeeeeeeeeeeeeeeeeeeeeeeen. ;
e gggg e i
- The Lo RK Trip cannot be reset above 10% RTP. * *
\ -
ennemen **ene ne...e**eneen.eame .***eneeneene eeeeeeeeeeeeeen.. { b.- ADJUST the gain potentiometer (R303) on the inopers.ble_NIS channel power range drawer B until the 41 Ra trip bistable can l be reset, i i eeeeeeeeeeeee*********ene. eenneeeeeeee*****eeeeeeeeeeeeeeeeene* ,
- NOIE - *
- The pegative and positive rate trips must be reset on the *
* . inoperable channel prior to adjusting the gelus on the * ,
- operable channels. This will ensure that a 2/4 coincidence
- j
* (Rt trip) will not occur. !
.. eene.. e** e.eeeeeeeeeeen.e eeeeeeeee.**.eenemen.. eeee...een i
- c. Then RESET the followingt i
- 1) Positive rate trip l
- 2) Negative rate trip
- d. If any of the spy 11 cable trip blatables cannot be reset, j thea DO NCTI continue and NOTIFE the Shif t Engineer.
.J
- e. If.all of the applicable trip bistables are reset on the [
laoperable NIS chtanel,-theh PROCEED to step 32 of this [ procedure. -; i 3 2. - ADJUST 'the out of tolerance channels one at a time'utilising the ; following format , 1 c ................... e... ....................... ............... j
- cauTune a -:
*. TWE FCLLONING ACT7 Cat COULD CAUSE A FI/JK RATE TRIP OF TME
- j
- DETECTOR (S) EEING ADJUSTED. 'IWO OF FOUR CEANNELS WILL *
- CAUSS'A REACTOR TRIP. ADJUST ONE CEANNEL AT & TINE. * .
....,....e............. e...............................ee.....e !
.................................................we.....ne....- t
. gggg .
- If gain potentiometer R303 cannot ne adjusted enough-to * !
- obtain agreement with the calculated value of-percoat * ,
* -power, contact the IM Department. Have the Technician.
- j
- adjust the course grain pot R312 and R303 as necessary
- j
- to _ obtain- agreement with the calculated value'. *
**e ..................e**en.... neen...........................e i
- m. ADJUST the gain potentiometer (R303) on one of the operable NIS !
power range drawer B until'the percent power reading agrees with ; the calculated value from Block 29 of the NIS Worksheet. [ r
- b. VERITY / RESET the rate trip. f APPROVED j Y\\Y r (0417V/0043V/053190) B.O.S. R. ;
?
I
1905 3.1.1 2 ; R3visisa 3 c.- REFEAT a and b for the remaining operable channels if necessary.
- 6. INITIAL in Block 32 for each chnanel adjustment comp 1sted.
- 33. PERFORM this step only if an inoperable NIS power range channel was I restored in step 31 of this procedure. !
- a. VERIFT/ RESET the following bistables on the operable channels.
- 1) Hi Rn trip I
- 2) positive rate trip 3)- Negative rate trip }
- b. If the applicable trip bistables cannot be reset-on the operable : !,
chant,els, then DO NOT continue and NOTIFY the Shif t Engineer. , I If the trip bistables are reset, then CONTINUE to the nest stop. l
- c. r
- d. REMOVE the control power fuse for the inoperable power range ;
channel. .
- e. VERITY the following bistable tripped ,
- 1) Lo Rs trip
- 2) Hi Rs trip
- 3) positive rate trip
- 4) Negative rate trip
- 34. RE'! URN the Rod control syster, to AUTO when Tavy is within 1.0 F of ,
Tref. t G. ACCEPTANCE CRITEkIA All NIS power range instr oents t.o be within a positive 2% reading of j calculated theresal power og 6he calorimetric as indicated by initial in Block 27 or adjusted to_within a positive 2% tw indicated by initial in Block 32.- _ i
?
i 4 f APPROVED } JUN 111990 : f B.O.F R. ; ' (0437V/OD43V/0!.upo) , t b' I I l
. - - - . . - . . . ~ . . - . . - - - . . - .-. - - .
1905 3.1.1 2 l R3vitica 3 APPENDIK A !
. Calorimetric Process Computer Inputs POINT ID DESCRIPT12 UNITS S N0049 PWR RNG CH 41 (QUAD 4) DET Q PERCENT !
N0050 ! PWR RNG CH 42 (QUAD 2) DET Q PERCENT N0051 PWK RNG CH 43 (QUAD 1) DET Q PERCENT r N0052 PWR RNG CH 44 (QUAD 3) DET Q PERCENT { U1150 PWR RNG NUCL CHANNEL AVG T1H Q PERCENT t 70418 S/G 1A TEEDWATER IN 7 DEGF f 70438 S/G 18 TEEDWATER-IN T DEGT 70458 S/G IC TEEDWATER IN 7 DEGr ' 70478 S/G 1D TEEDWATER IN T DEGr
.UO490 AVERAGE TEEDWATER TEMP DEGr f PO400 S/G 1A-STMLINE PRESS PT-514 PSIG h P0401 S/G 1A STMLINE PRESS PT-515 PSIG PO402 S/G 1A STMLINE PRESS PT-516 PSIG f UO414 S/G 1A AVG STM PRESS PSIG ,
t PO420 S/G 15 STMLINE PRESS PT-524 PSIG P0421 S/G 13 51MLINE PRESS PT-525 PSIG l PO422 S/G 18 57MLINE PRESS FT-526 PSIG i UO434 S/G 18 AVG STM PRESS PSIC l PO440 S/G IC STMLINE PRESS PT-534 PSIG
- j f
PO441 S/G IC STMLINE PRESS PT-535 PSIG PO442 S/G 1C STMLINE PRESS FT-536 PSIG ( U0454 S/G IC AVG S1H PRESS PSIG PO4 60' S/G 1D STMLINE PRES 3 PT-544 PSIG ! l PO461 S/G ID STMLINE PRESS PT-545 PSIG ! l PO462 S/G 1D STMLINE PRESS PT-546 PSIG , UO474 S/G 1D AVG STM PRESS PSIC U8020 S/G 1A RAW FW DP FT-510 INWC I U8021 S/G 1A RAW TW DP (7 511 INWC I
.UB022 S/G 13 RAW TW DP FT-520 INWC [
U8023 O/G 1B RAW TW DP FT-521 INWC + U8024 S/G IC RAW TW DP TT-530 INWC ; U8025 S/G 1C RAW FW DP FT-531 IWWC ! U8026 S/G 1D RAW TW DP rT-540 INWC j j U8027 S/G 1D RAW FW DP FT-541 INWC i
- r0407 S/G 1A BLOWDOWN GPM -
! F0427 S/G 18 BLOWDOWN GPM $ (. T0447 S/G IC BLOWDONH GPM T0467 S/G 1D BLOWDOWN GPM ' i r2239 S/G 1A FW TEMPERING LINE r GPM r2240 S/G 15 rW TEMPER!rts LINE r GPM APPROVED F2241 S/G 1C FW TEMPERING LINE F GPM l- F2242 S/G ID FW TEMPERING LINE F GPM JUN 1 1 1990 (rinal) . 5.0.F R. l (0437V/0043V/053190) e
.~ . , - - - . , - . . , - - . - -
,. . , - - - .. . - . . - . , - _ - - ~ ,
. - , ~ ~ . _ . _ . - - - . - . . . . - - . . . . - . . _
1905 3.1.1-2 ~ I R vision 3 t CALORIMETRIC DATASREET I f i
- 1. Dates w. /7.*U Times // I4 -
Performed by b> [
- 2. MWe (gross): / / f Control Bank Positions: C1 3 'l steps [
C2 2 steps [ D1 /W steps } D2 /+& steps l All prerequisites have boon met (RO) N i
- 3. Initial NIS Power !
i NR41(N0049) #i / % NR42 (N0050) #If./% NR43(N0051199 b% NR44(N0052) 97 9% l
- 4. Feedwater temperature (computer points l: f A. To41s- M 1*r ~B'. sosse '/ M 'r C. To45s 'M 2 'r D. To47 s 'M'/. ? 'r
- 5. Steam Pressure (psig) -
l Average A. PI-514A _Yi1 PI-515A 8 $ PI-516A T O or UO414 M [i[ ! L B. PI-524A,DO PI-525A W PI-526A N ' Average or UD434 TiO [ r Average C. PI-53fA W PI-535A 4'I0 FI-536A f/N2 or UO454 E i l
~h !
D. PI-544A b# P1-545A 4U PI-546A SNE O 4 fit 5 i
- 6. reedwater rlow (K'BR or inches water) 'f A. TI-510 3770 r!-511 5 W or Us020 Ue021 B. TI-520 3 M FI-521 3 7#ld or U8022 U8023 C. FI-530 M FI-531 3741 or UIO24 U8025 !
?
D. rI-540 3 M ' FI-541 373C or UB026 Ut027 f i
- 7. Blowdown Flow (gym) [
A. 7' [ b~ B. 70 WC. 7%ID. 77 /S~ j s
-8. Tempering riow (gym): j A. FK-251'(r2239) f/3 B. FK-252 (r2240) U f C. TK-253 (F2241) iY D. FK-254.(F2242)
/7 APPROVED .
1
-D2- JUN 111990 ;
__ 3 (0437v/0043v/053190) g g c. q
~
. - ~. .. . , -
100$ 3.1.1-2 Rovision 3 CALORIMETRIC WORKSHEET
- 9. Avarage stssm. generator pressure Y- A. Ave k O'U l
- 14.7 = N #* - Psia APPROVED B. Ave +me . 14.7 . S ev. 7 psi.
gj;g C. Ave Fif I' + 14.7 = ' psia D. Ave DiI + 14.7 a if 3 psia 8' O'
- S*
- 10. Ave.rege feedwater riov If from indicators:
A. r!-530 3 770 + TI-511 3VM ,9/ 2 B. TI-520 3790 + FI-521 3718 , s
-.if&.
2 C. r!-530 3 M + r!-531 3 7W 3 7 eg 2 D. ft-540 3WO + ri-541 3 37g 2 f~ If from computer points 6
\
' W.
. ,a y where W = teedwater flow (LBH) for a particular tap a = feedwater flow constant for appropriate tap (see below) ra e thermal espansion f actor = ((1.524 h 10-5) (rW temp)) + .9989 DP = feedwater DP from computer points v = apecific vol.sne of feedwater at rW temp and steen pressure reedwater flow constant (a) tne 510 511 520 _ 521 530 531 540 541 a 2.493E4 12.505E4 2.481C4 2.434E4 2.47BE4 2.477E4 2.484E4 2.485E4 Feedwater loop A B C D a 2.493E4 2.505Es 2.481Et L(ligi 2.47EE4 2.477E4 2.484E4 2.485E4 ra DP v _
W _ Average feedwater flow in KBH (W) = P3 + M2 for each loop 2(1000) Loop A Loop B Loop C Loop D Ave TW flow KBH KBE FBB .KBH O (0437V/0043V/053190)
-D3-
1BOS 3.1.1 2 R3 vision 3 CALORIMETRIC WORKSHEET
- 11. Blowdown flow (KBH)
A. N N gym LdQ10n . 38. C .- KBH (.01660) B. 7#/* W gpm f.00802) , 3Lf KBH N (.01660) C. 7f 85 gpm f.00202) , 3 6' f KBH (.01660) D. 7/- ( [ gpm f . 00 80U , 3 9, f KBH (.01660)
- 12. Tempering Line Flow (KBH)
TT = ( 00802) U v . Loop A Lo0P B Loop C Loop D T1
'r y 'i 2 'I s/ cf 7 v , r /7 /$ e / 9 /9 .c/9/F e /9 /v TT 34E fl _ 3 4 Y7 3Y,3/ yr , gg
- 13. Het Teodwater flow ,
x /0 # A. Ave Teod Flow 37E KB9 + TT .%' #/ KBH = 3 M iKSH (1000) = 3.V2D LB r (q'j B. Ave Teod T1on I7 NO KBH 4 TF 3 r f KBH = 3 *I' f KBH (1000) . L,12if L'B' g C. Ave Teod Flov 3 7 '/ /; KBH + TF 3L4 KBH = IV213 KBH (1000) = 15'.33 lA1} D. Ave Teod flow D t0 KBH + TT Vt.6 KBl! e M KpH (1000) = 3 f W 'LNH 14 Steam Enthalpy' 15. Blowdown Enthalpy 16. Teodwater Enthalpy 17. Corrected Steam th 9) (h3) (h,) enthalpy (h ) Loop A, 11 'll . */ 54? u <0 i <c , , r, ( g. Loop B 11 % . 4 [21, f 1 o f. .i t t o <1./ , et Loop C 1141.1 ?? ?,6 n/s , n f, s .< v Loop D 11if.3 TR1 //5, 35- ,, e u 7 Wheres hs = shg + (1.x) h 33 a steem quality . 9979 APPROVED JUN 111990 (0437V/0043V/053190) B.O.F R.
.- _ . _ _ _ . . .--- _.- . - . . . . . - ~ . - . - _ - - - _ _ _ - - . _ . - _ - _ - -
6 190S 3.1.1-1 R$visien 3 , I CALORIMETRIC WORKSEEET - 18.. Loop Thermal Power ! r (W-w)h + wh - Whw . Power
.A. ,
( 3mv 4 f.2 - SM.) t > ir //cir
- e . 2.3r i) n:>~( Ref .3. i#.f) -- 3 Y214
/, f e 3 7 or 2, '/ %'d ( u/t.4)I yd 9
. I t
- 3. (3 TWI - NI)' '/U 4 + 3%2,'rI 3(Ulf ) 3TM I( '//f IV)' . 1 V C29' Y Ar s 6 s oc ',, /, & c St se . .7. f '/ Y r Jr Y {
f C. .( Y l'/ d 3 9 I ) 'I6 ## + M ((27f) . ! Yc'2 G snS s 9. c t est rn?. 3 5l> /.te k%*//t w IY)$9,, f */ 3 C y tr 9 I t D. ( 3 T 5 . NI) //k'*/ T + 3T 5 ( 'IJ7 2 ) IMi Y/I' N)4 , . , [
- t/, f311 yse 5 e 2.c 211 tr - t. ( rf cak 2.9 VTc 1tr' '
t
- 19. Swn of loop powers - //, 7 73 4 er 'e .
1 l
- 20. Calculation of % Power t i
fsum of inan newera) atu/hr / ('E / x 100% - 0.49% . % Power 11.6417.1 10 9:Stu/hr 8 l .- ; i I t i i i i i APPROVED : i i JUN 1 11990 i
-D5- t (0431V/0043V/053190) B. O. S. R. ;
lL " ! L i [ f l -1 I i ?. l-
- i. !
. . - , . , - . . - . . - - . , . . ...c.,._,_____..
I
. _ . . . . . . ._. . _ _ . ~ _ - - _ _ - _.___._.____.__ _ _ __ _ - - -
. ..- .- - . . . . - . . _ ~ . . . , . . - -., _
1908 3.1.1-2 , R3visica 3 ! NIS WORKSHEET f;
- 24. HIS Power 25. Calorimetric 26. Power Difference 27. Initial for No ;
Power NIE Mina tment - l N41 'i 'l /tf i * /. I t N42 44 I !!' i ~ !. f N43 WT /*(<l ~ 2.1 l N44 9 G' 4 ' f rC* I ~ /* ? l
}
28.-Cutrent NIS Power 29. (Step 25 26) Power to 32. Adjustment Complete l adinat NIS to , N41 'r '! it e i Sss ; N42 %# U f- ( -W'- ; N43 'I t i et/
- 64/' !
N4s v s . st ir t .t ssf t I t i
?
r I e i 1-t I (q v-l , i L i t i L i
'l I
APPROVED : i (Final) JUN 111990 i l
-D6- B.O.S R. I (04377/0043V/053190) ^
l.. t
1 DOS 3.4.2.0-1 Rovision 2
, ~
'IURBINE THRCTTLE, GOVERNOR, REHEAT, AND INTERCEPT VALVE
' HONTELY SURVEILLANCE A. 32A'IyxrNT OF APPLICABILI"'Y t This procedere applies to the monthly verification, by direct obssrvation, of the Turbine Overspeed Protection System operability in moues 1,2 and 3.
B. R E FERENCE'il
- 1. Technical Specification 4.3.4.2.a.
- 2. Westinghouse Instruction Book No. 13A4930, Vol. 1.
- 3. Station Procedure 1BOS 3.4-la, LCOAR-Turbine Overspeed Protection.
- 4. Westinghouse 10CTR50.59 Notification on Turbine Valve binding, January 21 & 22, 1988.
- 5. Station Connitments,
- m. 88-6-0499.
- b. 37-6-0020.
- 6. Westinghouse Operation and Maintenance Memo 090.
o b C. EEIRECXff 91 TEST
- 1. Receive permission f rr the Shif t Engineer or designated SRO licensed assistant prior to tstfonsing this surveillance by having the Data Package Cover Sheet signed and dated.
. DEH system must be in "OPER AUTO".
- 3. Impulse Pressure Teodback (" IMP IN") is selected.
v/. 4 Megawatt reedback ("HW OUI") is selected. ,
/
V5. Unit load shall be greater than 15% and less than or equal to 85%. 7 fP, l
- 6. An operator must be available to directly observe each valve's movement, for smooth operation, as it is tested.
D. PRECAUTI{RIS1 The observing operator shall stand clear of all turbine valves 1. throughout the test. j[ Number 1 and 3 Throttle Valves interlock with NDCT Riser Valves. !! : When the Throttle Valves close, the NDCT will transfer from the riser to bypass mode of operation if the NDCT Turbine Trip Interlock switch is NOT in the OVERRIDE position.
- -o FOR REFERENCE AUG 2 81989 (0529V/0049V/082889)
B.O.S.R.
. \
IBOS 3.4.2.0-1 i R;visica 2 i
- /] -3.- To' ensure the probability of an overspeed condition or destructive
.(/ overspeed condition due to a stuck open Throttle Valve ir adequately reduced, prior to testing any Throttle Valve, the associated Governor ,
Valves must both have been a geessfully tested. ;
- 4. Monitor MW meter during the transfer from single valve to sequential valve mode of control and vice versa to verify generator load remains ;
stable.
- 5. Various valves will stroke as a result cf closure of Throttle Valve 1 and Thr.ottle_ Valve 3. ,
- s. Components affected by the TV-1 Limit Switch closed. :
i 1). 1ES005 ADV HP Heaters 17A & 17B Eat chk. l 2). 1ES008 ACTI LP Heaters 15A & 15R Est chk. 3). 1ES011A ACN LP Senter 12A Est chk. ; 4). 1ES015A ADV LP Henter 13A Est chk. 5). 1ES017A ADV LP Heater 14A Ext chk. 6). 1ES022 A0V HP Heaters 17A & 178 Ext. Stm. Spill Viv. 7). 1ES028A ADV LP Etr '12A Est Sta Spill V1v. { ( 8). 1ES030A ADV tt 3 't 13A Ert Ste Spill V1v.
- 9). 1ES032A A0V LP atr li[ Eat Stan Spill Viv.
10). 1ES024 ADV LP Etrs 15A & 15B Ext Stm Spill V1vs. 11). 1ES062A ADV NSR 1A first Stage Ratt Est cbk.- 12). 1CWOO4C NDCT Riser V1v. 13). 1CWOO4D NDCT Riser V1v. 14).1CWOO4E NDCT Riser Viv. 15). ICWOO4F NDCT Riser Viv.
- b. Components af fected by the TV-3 Limit Switch closed. ,
[ 1). 1ES002 ADV LP Rtr 16A & 17B Est chk. l l 2). 1ES011B ADV LP Btr 128 Est chk. , t 1 -. 3). IES011C ADV LP Etr 12C Est chk.
+
l . 4). 1ES015B ADV LP Btr 13B Ext chk. APPROVED 5). 1ES015C ADV LP Btr 13C Eat chk. AUG 2 81989 6). 1ES017B AOV LP Ett 14B Est chk. B.O.S.R. (0529V/0049V/082889)
1BOS 3.4.2.c-1
'R2Visica 2 (N 7). 1ES017C ADV LP Htr 14C Est chk. .Q' !
8). 1ES019 ADV LP Ntra 16A & 16B Est Stm Spill Viv.
- i 9). 1ES028B ADV LP Htr 12B Est Stm Spill V1v.
10). 1ES028C A0V LP Htr 12C Est Sta Spill V1v. + 11). 1ES0305 ADV LP Btr 13B Est Stm Spill Viv. ; 12). 1ES030C ADV LP Rtr 13C Est Stm Spill V1v. f L 13). 1ES0328 ADV LP htr 148 Est Stm Spill V1v. ; i 14). 1ES032C ADV LP Htr 14C Est Sta Spill V1v. , 15). 1ES062B ADV MSR 15 First stuge Rhtr Fat chk. ; 16). 1CWOO4A NDCT Riser Viv. ! t 17). 1CWOO4B NDCT Riser Viv. [
- f. . LIMITATICRfS AND ACTICBISt i
- 1. As-stated la Technical Specification Limiting Confition for Operation 3.3.4.
[X , yl 2. In the event any of the Acesptance Criteria-is not met during the i performance of this procedure. IM0fDIATELY notify the Shift Engineer f i .to initiate LCOAR procedure 1BOS 3.4-la.
- 3. During the performance of the Governor Valve Slagle/ Sequential !
Transfer if an uncontrolled rapid oscillations occurs, then depress ,
" TURBINE MANUAL" on the DEU Turbine Control Panel and "GV Raise" or "GV LOWER" to adjust governor valve position to maintain desired turbine load. ,
- 4. The perferred method for performing this test la with the Impulse .
Pressure feedback loop gserve and the Megawatt Feedback loop out of service. The test may be performed with the loops in a different I configuration at the discretion of the Shift Engineer. _If the test I is performed with both feedback loops out of service unit load swings can be expected.
- 5. If during the stroke test of a governor or throttle valve any l evidence of binding occurs the System Engineer should be notified as ,
the probability of a destructive overspeed could be increased to l unacceptable levels. *, 5.a ; j_
- 6. The throttle valve under test should not be lef t in the fully closed ;
l position for more than 1 minute. If the valve is left closed for more than 1 minute it should be retested to verify no evidence of ( fT thermally induced binding is present. *, 5.a { U APPROVED ! 3 AUG 2 81989 (0529V/0049V/087 88's) B.O.S.R. l
i 180S'3.4.2.c.1 ! Rovislos 2 i T. MAIN BODY t i ee e e ee e ee ee e ee e e nne e e e e e e e e e e e nn e ee e e e e e e e e ee ee e e e e e e e n....e e m a n i e- g e l
- When performing' this surveillance at power, WLY Section e l
*- One (1), Testing At Power, should be performed. e l
e e ; I
- When performing this surveillance as part of the Unit * !
- Startup per the BGP's, NLY Section Two (2), Testing During
- i
- Plant Startup, should be per formed.
- i neeeeeeeeeeeeeeen.eene.neeeeeeeen.eeeeeeeeeeeeeeeeeeeeeeeee mene .
1.0 Testina At Powgg 1.1 Enter DATE i i
TIME ON 6 eene.neamenemen.neeeeeeeeeeeeeeen.eeeeeeet eeeeeeeeeeeeenmeenee. l
- ErrE o ;
- If, during the performance of Throttle Valve testing, * !
a the operator wishes to temporarily interrupt the test to '*-
- utilise the display for other purposes, all lights *
- associated with the test will turn off. To resume the
- -
- test, the operator will have to dept ess the " VALVE TEST" e l
- and "TV" pushbuttons. [
neeeeeeeee**eeeeeeeeeeeeeeeee.ne.eeeeeeeeeeeeeeeeeeeeeeeeeeeeeen ; ,4
.nenen.een.eeeeeeenanneen.ne.ne.eeeeeeee**eeeeeeee..eeeeeeeeeeen l 3
* -Perform steps F.1.2 and F.1.3 if it is required to transfer * ,
- the Governor Valves f rom "SEQUENTI AL VALVE" to " SINGLE ,
- VALVE" mode of operation otherwise proceed to step T.1.4 *
- eeeeeeeen.nense. nee.eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenne.*
l een...... eeeeee.. ....een.eeeeeeeeeeeeen..eeeeeenen.. .enene.e. \
-* CAUTIM *- I
*- IF RAPID VALVE OSCILLATINS OCCURS, THEN DEPRESS " TURBINE - * !
- MANUAL" W THE DER TURBINE PANEL, AND "GV RAISE" OR "GV * ;
- LOMER" TO ADJUST GOVERNOR VALVE POSITIW TO MAINTAIN DESIRED *
- TURBINE LOAD.
n e e e e e e e * ** ee.n e e e e e ee e e ** ee e e ee en e m o n e ne se e na a n.n eee e e e e e e e e men ee**eeeeeeeen eeeeeeenneeeeeeeeeeeeeeeen nenenemanneeeeeeeneseen a NOTE * !
- The transfer from sequential to single valve mode may * !
a
- require several minutes. Upon depressing the pushbutton, j l'
- the SEQ VALVE _ lamp will go out and the SINGLE VALVE lamp -
j e will begin flashing.- Completion of the transfer is * [ t ,
- Indicated by the SINGLE VALVE lamp being steady-on. .
! enamenenamenemmeneameen.e***enenene***enanneeeeeeeeeeeeeeeeeeee* ;
?
DEPRESS " SINGLE VALVE / SEQ VALVE" pushbutton on the DER Turbine - [\ 1.2 Control Panel. located on IPM02J. APPROVED !
-t AUG 2 61969 i (0529V/0049V/082889) B.O.S.R. l
IBOS 3.4.2.0-1 R3 vision 2 4
- 43 q p 9 M i
3 VERIIT the SINGLE VALVE lamp stays steady on.
- % / 2/
- J ' v bi s
m.___ . 4 VERIfT/ PLACE the U-1 NDCT Turbine Trip Interlock switch to DVERRIDE. *, 5.b h 1. 5 ENSURE an operator is stationed to directly observe the movement of each valve to be tested through one complete cycle f rote the running position. e ne esee n e. nom enene ne..... ann e e e e ee e ee e e e e e ee e ne n e see n e e nne n e n e n.
- HOTE
- Due to the operating characteristics of the governor, *
- reheat stop, and intercept valves, the local method of a
- testing is not an acceptable alternative a,- *hese valves. .
e me eene ne***enen eneenenne nen...... ..e - seemenneneenennen enennenemonenemanneenenneen neneseenemeneeeeeeeeeeeeeeeeeeeeeene
- NOPIT
- e The preferred method of testing the Throttle Valves is f rom *
- the HCB (Remotely). If the remote test fails the Throttle a
- Valve (s) may be tested locally. If local steps are not
= performed the sign off blanks for these steps can have
- a
- N/A (Not Applicable) written for them.
e e ee ee e ee e e e e e eem e** *s eme n e e se e e e e e e e e ee n e s amene es eee ee e e eeee ene enee. menene ne ee conee....seeneeneneenanneenesenemoneeseenenen e, a ggry,
- Steps F1.6 through F1.'25 mhy be done independently, or *
(
- individually, for Pntti?1 Surveillances provided steps *
- T1.1 through F1.5 acd F1.24 through F1.27 are performed.
- eneenneennameneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee**eeeeeeeeee ne e ee m a n n e.n o nso n e
- o n e en he * *
- e m e * *e e n e * * *
- e n e e * *
- e e e e e e e e e * * * *
- e RGIT.
- If, during the perf ormance of the gr ve toor valve test, the
- e
- test is interrup. by selseting anotM r display function.
- JE" buttons will renaain illuminated, *
- the "0PD!" and
- tive. To resume the test, dopress the
- a but wila ta ine
* " VALVE TEST
- pt.rtbutton causing it and " VALVE STATUS" and *
* "GV" pushbuttons to illurnicate. The governor valve no. *
- being tested will appear in the " DISPLAY DCKAND" window *
- and its percent of full opsn position will appear in the *
* " DISPLAY" window.
noenemanne eneeeemeneennemmennenseenene...ee **eemanneneanneesee seen**eneseeeeeeeeemenenenemanneeeeeeeeeeeeeeeeeeeeeeeeeeeeeemee e
- CAUTIctt O ,
e Ir, c; RING Tut PERroRMANCE or THE covERuoR VALVE TEST,
- ao
- THE T '.BINE CONTROL SYSTEM IS TRANSTERRED TO TURBINE MANUAL,*
) .
- TuE VERN a. VALVE BEING TESTED CAN BE REOPENED BY O * @
- DEPRESSING THE "oPDI" PUSHBUTTON, HO'rfEVER, THE "GV LOWER" *
- g.
- g, Q
- PUSHBUTInt HUST BE ALTERNATELY DEPRESSED 'IO MAINTAIN THE R. ::s *
- LOAD APPROKIMATELY COISTANT. THE VALVE UNDER TE67 WILL T "
- MOVE AT A TASTER RATE THAN DURING " VALVE TEST" SO UNIT *
(]
- LOAD CHANGES MAY OCCUR.
- y.f eeeeeeeeeeenenenee***eneeeeeeeeeeeeeeeeeeeemenenesemeeeeeeeeeeee (0529V/0049V/082889)
u
}BOS 3.4.2.0-1 R:; vision 2 fS ennenneeeeeeeeeeeeeeeeeeeen....eeeeeeeeeeeeeeeenneeeeeeeeeeeeeen s_j
- liUII *
- As soon as a Governor Valve begins to close, the ' CLOS E "
- O e and "OPEN" pushbutt ns illuminate, signifying that the a y ,ck- , sat is in progress. When the Governor Valve is fully
- l> 52 % *
~
closed, the "OPEN" light will go out. The "OPEN" and
- O a eo g "CLOSE" lights will doth go out when the valve is returned a CC cv '
- to its original position. As the Governor Valve modulates,
- E c9
- the other 3 Governor Valves will automatically modulate to
- kQ
- maintain the set load.
e.. .. ... ............................... .. .................. eeeeeeeeeeeeeeeeeeeeeeeeeeeenneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene a ligII *
- In perfoaming step r.1.6.e, r.1.7.c, T.1.8.c, r.1.P.c *
- valve closure time will be dependent on the set rate.
- eeeeee-ne eeeeeeeeeeeeeeeeeeeeee. ..............................
1.6 Governor Valve No. 1 test. j Me Va/i/L Oh
- V a. , DEPRESS th9m" VALVE TEST" pushbutton. VERIrv " VALVE TESI" and
( " VALVE STATUS" pushbuttons illuminate. , m Qw a r*f _ M Nb. DEPRESS the "GV" pushbutton and VERITY it 811uminates.
- k. DEPRESS No. "1" on the keyboard and VERITY 0001 appears in the rm " DISPLAY DEMAND" window.
,I d.
14 A.&& 8*3 " # DEPRESS "ENT'R". sVf~ actual Governor Valve posittotr'Tilapfear w
- s.
', ' ', p in the "DISPLjY" window as percent of full open./g g yH 'A e (u l L e. DEPRESS and HOLD the "CLOSE" pushbutton until Governtrr'751v/ e1 is fully closed. 9 ,', b M W '9 7(l-Q w n MC -
f,% E (1 f . LoceMy VERITY / OBSERVE Governor Valve No. I travels fully CLOSED. c ~ -
. g. VERITY "GV 1 CLOSED" indicator is illuminated and "CN TL CPEN1'I indicator is off. ' 04 I h. RELEASE the "CLOSE" pushbutton and DEPRESS and HOLD the "OPLN" l
pushbutton until the "OPEN" and "CLOSE" pushbuttons' lamps go off, indicating that the Governor Valve 1 has returned to its l pretest position. 3 ,* g*
) g [-f l c MfC d " 1. Lovtr217 VERIFY /OESERVE Governor Valve No. I travels OPEN to I approximately its original position. y ,W l 1.7 Governor Valve No. 2 test.
- a. DEPRESS No. "2" on the keyboard and VERIPT 0002 appars in the N
" DISPLAY DEMAND" window. _. _
1 rm *b. DEPRESS " ENTER"". The actual Governor Valve position will j appear in the " DISPLAY" window as percent of full open.
. ] 4 g/x (0529V/0049V/082889)
]d s
APPROVED IBOS 3.4.2.a-1 R visi n 2 l AUG 2 6 g B.O.S.R. " c. DEPRESS and llOLD the "CLOSE" pushbutton until Governor Velve 2 (T is fully closed. t d. Locally VERITY / OBSERVE Governor Valve No. 2 travels fully CLOSED.
- e. VERITY "GV 2 CLOSED" indicator is illuminated and "GV 2 OPDi" indicator is off, l'
RELEASE the "CLOSE" pushbutton and DEPRESS and HOLD the "OPDt" [ f. pushbutton until the "OPEN" and "CLOSE" pu'.hbuttons ' lamps go off indicating that the Governor Valve 2 hus returned to its Protest position. t g. Loca14y VERITY / OBSERVE Governor Valve No. 2 travels OPEN to
- approximately its, original position.
1.8 Governor valve No. 3 test. M h a. DEPRES:; No. "3" on the keyboard and VERITY 0003 appears in the N'
" DISPLAY DD4AND" wir6dow. .
- b. DEPRESS " ENTER". The actual Governor Valve position will appear in the " DISPLAY" window as percent of full open.
- c. DEPRESS and HOLD the "CLOSE" pushbutton until Governor Valve 3 is fully closed.
~
f t d. Locally Vi2ITY/ OBSERVE Governor Valve No. 3 t.*avels fully CLOSED. I e. VERITY "GV 3 CICSED" indicator is illuminated and "GV 3 OPD4" indicator is off.
\)* .
- f. RELEASE the "CLOSE" pushbutton and DEPRESS and HOLD the "OPEN" pushbutton until the "OPEN" and "CLOSE" pushbuttons' lamps go of f indicating that the Governor Valve 3 has returned to its pretest position.
d g. Locally VERITY / OBSERVE Governor Valve No. 3 travels OPEN to
"- approximately its original position. h:,
1.9 Governor Valve No. 4 test. x 4 70 s D_li U '\ ^0 7 3 1
- a. DEPRESS No. "4" on the keyboard and VERITY 0004 appears in the
" DISPLAY DEKAND" window.
O
- b. DEPRESS " ENTER". The actual Governor Valvo position will appear in the " DISPLAY" window as percent of full open.
- c. DEPRESS and HOLD the "CLOSE" pushbutton until Governor Valve 4 is fully closed.
') W d. Locally VERITY / OBSERVE Governor Valve No. 4 travels fully CLOSED.
A VERITY "C7 4 CLOSED" indicator is illuminated and "GV 4 OPEN"
'Q e.
indicator is off.
-7a (0529V/0049V/082889)
n - .. .. APPROVED 1BOS 3.4.2.0-1 A$ 2 6 669 R3 vision 2 B.O.S.R. O f. RELLASE the "CLOSE" pushbutton and DEPRESS and HOLD the "OPEN" O' pusbhutton until the "OPEN" and "CLOSL" pushbuttons' lamps yo off indicating that the Governor
- Valve 4 has returned to its
- p. pretast positjon. '
\ k(! g 9 Locally VERITY / OBSERVE Governor Valve No. 4 travels OPEN to appror.imately its original position.
1.10 Throttle Valve No. I test. (Remoto)
- a. DEPJESSA he~" VALVE TEST" pushbutton. VERITY " VALVE TEFT" and
"$LVE STAWS" pushbutton illuminate.
w;m. _
# b. DEPRESS the "TV" pushbutton. VERITY "TV" pushbutton illuminates.
- c. DEPRESS No. "1" on the keyboard. VERITY 0001 appears in the
" DISPLAY DDtAND" window.
- d. DEPRESS " ENTER". The actual Throttle Valve position will appear in the " DISPLAY" window as percent of f ull open. /d o ') .
/
- e. DEPRESS and BOLD the *CLOSE" pushbutton until the Throttle Valve 1 is fully closed.
7 c/' W / f. ioca44y VEPIFY/OESERVE Throttle Valve No. I tr avels f ully CLOSED.-
/ . . ~
A g. VERITY "'IV 1 CIDSED" indicator is illuminated and "TV 1 OPEN"/ k
/ Indicator is off. Mc) g j h. , RELEASE the "CLOSE" pyshbutton and VERITY the Throttle Valve i reopens to its original position by observing the " DISPLAY" window and the position indicating lights.
nPC.- t l1.
- c i,17 VERII"Y/OBSETAVE Throttle Valve No. I travels OPEN to approximately its original position. , ,,
1.11 Throttle Valve No. 2 ter ". f*emoto) d(
\ a. DEPRESS No. "2" on the keyboard. VERITY 0002 appears in the
" DISPLAY DEMAND" window.
) The actual Throttle Valve position will appear
- b. DEPRESS " ENTER".
in the " DISPLAY" window as percent of full open.
- c. DEPRESS and h0LD the "CLOSE" pushbutton until the Throttle Valve 2 is fully closed.
,7 3 t d. Locally VERITY / OBSERVE Throttle Valve No. 2 travels fully CLOSED.
d VERITY "TV 2 CLOSED" indicator is illuminated and "TV 2 OPEN"
\ e.
indicator is off. k f. RELEASE the "CLOSE" pushbutton and VERITY the Throttle Valve 2 Q ' reopens to 1ts original position by observing the "DISPPY" window and the position indicating lights. 8 (0529V/0049V/082889) h \
' I i
APP 23VED 1 DOS 3.4.2.o.1 ggg R::vnsics 2 B. O. S. Pt. (> f t 9 Locally VERIFT/0* ERVE Throttle Valve No. 2 travels OPEN to approntmately 15. original position. ,[' [ i 1.12 Throttle Valve No. 3 test. (Remoto) ; g a. DEPRESS No. "3" on the keyboard. VERITY 0003 sppears in the
" DISPLAY DD4AND" window. l
- b. DEPRESS " ENTER". The actual Throttle Valve position will appear {
in the " DISPLAY" window as percent of full open. t 0 ; , ^c. DEPRESS and MOLD the "CLOSE" pushbutton until the Throttle Valve 3 is fully closed. . hl (6 d.
/d "
L3tuTRy VERITY / OBSERVE Throttle Valve No. 3 travels fully CLOSED.
-e. VERITY "TV 3 CLOSED" indicator is illuminated and "TV 3 OPDf" indicator is off.
7'3 Jk
- f. RELEASE the "CLOSE" pushbutton and VER!rY the Throttle Valve reopens to its originkl position by observing the " DISPLAY" window and the position indicating lights.
\ h \d
( 9 eseeM y VERITY / OBSERVE 2nrottle Valve No. 3 travels OPDI to apprositately its original position. fg* 1 1.13 Throttle Valve.No. 4 test. (Remoto) D
- a. DEPRESS No. "4" on the keyboned. VERITY 0004 appears in the
- " DISPLAY DDGWD" window. .
- b. DEPRESS "F$f7ER". The actual Thrott's Valve position will appear in the " DISPLAY" window as percent of full open.
,,,,,,,,,c. DEPRESS and WOLD the "CLOSE" pushbutton until the Throttle Valve 4 is folly closed.
d d. Locally "ERITY/ OBSERVE Throttle Valve No. 4 tr. was fully CLOSEL. 1
. e. VER!!T "1V 4 CLOSED" indicator is illuminated and IV 4 OPDf" d indicator is off.
k
! f. RELEASE the "CLOSE" pushbutton and VERITY the Throtele Valve 4 reopens to its original position by observing the " DISPLAY" window and the position indicating lights.
- g. Locally VERITY / OBSERVE Throttle Valve No. 4 travels OPDI to Lt approximately its original position.
1.14 Throttle Valve Eo. 1 test. (Local)
- a. DEPRESS the " VALVE STAWS" pushbutton. VERITY " VALVE STAWS"
\ 111umir. ate.
O b. DEPRESS the "TV" pushbutton. VERITY "TV" pushbutton illuminates.
-9 ,
(0529V/0049V/082889)
l 1306 3.4.2.0 1 t R visica 2 l l
- c. DEPRESS the No. "1" on the keyboard. VERITY 0001 appears in the
DISPLAY DEMAND" vindow.
i
- d. DEPREES " ENTER" pushbutton. The actual Throttle Valve position j will appear in the " DISPLAY" window as percent of f ull opsn. j i
- e. CLOSE 1EH5009A. High Pressure EH T1uld Supply 1 solation Valve. I e f. When 1EH5009A is CLOSED, locally VERITY / OBSERVE Throttle valve (
Mo. 1 traveis fully CLOSED. l
\ .
9 VER1rY "TV 1 CLOSE" indicator is illuminated and "TV 1 OPEN" { indicator is off after valve has stroked closed. !
- h. OPEN 1EN5009A, High Pressure EH Fluid Supply 1 solation Valve. !
t 1. When 1EH5009A is OPENED, locally VERITY /OBBERVE Throttle Valve No. 1 Travels OPEN to apptosimately its original positic3. }
- j. VERITY Throttle Valve il reopens to its original position by observing the " DISPLAY" window and the position ladicating lights. l l
1.1$ Throttle Valve No. 2 test. (Local) {
~~
- a. DEPEESS the " VALVE STAWS" pushbutton. VER1rY " VALVE STAWS" l p pushbutton 111uminates.' l Q
- b. DEPRESS the "W" pushbutton. VER1rY "TV" pushbutton illuminates. l
- c. DEPRESS No. "2" on the leyboard. VER17Y 0002 appears in the ,
" DISPLAY DEMAND" w1ndow.
- d. 6EPRESS " ENTER" pushbutton. The Actual D rottle Valve position i
'\ w!!! appear in the " DISPLAY" window as a percent of full open. }
- w. CLOSE 1EH5009R. High pressure EH Fluid Supply Isolation Valve.
t f. When 1E550095 is CLOSED, locally VERITY / OBSERVE Throttle Velve No. 2 travels fully CLOSED. r) . VERITY "TV 2 CLO W" indicator is 111unineted and "TV 2 OPEN" l Indicator is off after valve has stroked closed. [
,,, b . OPEN 1EH50095, High Pressure EH T1uld Supply Isolation Valve. .
t
# 1. When 1EH50095 is OPENED. LOCALLY VERITY / OBSERVE Throttle Valve No. 2 Travt1s OPEN to approalmately its original position.
i
). VER1rY Throttle Valve 42 reopens to its original- position by observing the " DISPLAY" window and the position indicating ,
l lights. . ; O arraovso ; AUG 2 81969 : f (0529V/0049V/082889) B.O.S.R. i F l- - , _ _ ._._. _ - ._. .. ._ _. _ _ _ _ . _ _ _ , _ . . _ _ _ . _
1BOS 3.4.2.o.1 l Revisies 2 !
)
i 1.16 Throttle Valve No. 3 test. (Local)
)
f k a. DEPRESS the " VALVE STAWS" pushbutton. VER!rY " VALVE STAWS" pushbutton illuminates. f O = W I Q' - ev "W" pushbutton 111uminates.
- b. DEPRESS the "W" pushbutton. VER!rY !
3m c. DEPRESS the No. "3" on the keyboard. VER!rY 0003 appears in the
" DISPLAY DEKAND" window. ;
i
- d. DEPRESS " ENTER" pushbutton. The Actual Throttle Valve position vill appear in the " DISPLAY" window as a percent of full open. '
)
- e. CLOSE 1EH5009C, High Pressure EH Fluid Supply Isolation Valve. j g f. When 1EH5009C is CLOSED. locally VERITY / OBSERVE Throttle VLive No. 3 travels fully CLOSED.
- g. VERITY "TV 3 CLOSE" indicator is illum'inated and "TV 3 OPEN" indicator is off after valve has stroked closed. .
- h. OPEN 1EH5009C, High Pressure EH Fluid Supply Isolation Valve. I t 1. When 1EH5009C is CPENED, locally VER!rY/ OBSERVE Throttle Valve !
No. 3 travels OPEN to approximately its original position. '
- j. VERITY Throttle Valve 43 roopens to its original position by [
Q observing the " DISPLAY" window and the position indicating i lights. . 1.17 Throttle Valve No. 4 test. (Local)
- a. DEPRESS the " VALVE STATUS" pushbutton. VERITY " VALVE STAWS" pushbutton illuminates. >
- b. DEPRESS the "TV" pushbutton. VERIFY "TV" pushbutton illuminates,
- c. DEPRESS the No. "4" on the keyboard. VERIFT 0004 appears in the j
" DISPLAY DD4AND" wlndow. ,
- d. DEPRESS " ENTER" pushbutton. The Actus! Throttle Valve position will appear in the " DISPLAY" windov as a percent of full open.
- e. CLOSE 1EH5009D, High Pressure EH T1uid Supply Isolation Valve.
When 1EH5009D is CLOSED, locally VERITY / OBSERVE Throttle Valve l t f. No. 4 travels fully CLOSED.
- g. VERITY "TV.4 CLOSE" ludicator is illuminated and "TV 4 OPEN" indicator is off after valve has stroked closed. i
- h. OPEN 1EH5009D, High Pressure EH Fluid Supply Isolation valve.
g 1. When 1EH5009C is OPENED, locally VER!rY/ OBSERVE Throttle Valve No. 4 travels OPEN to approsimately its original position. (0529V/0049V/082889) . c
1905 3.4.2.o.1 Rovlsios 2
- j. VERITY Throttle Valve 44 reopens to its original position by O observing the " DISPLAY" window and the position indicating lights.
O gge
- UI eene ......... eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen g
O
- The test circuits are interlocked so it is not possible to
- O e test the reboat stop and intercept valves on one side f a e vg/ ,
h3
- a low pressure turbine when the corresponding valves on the other side are less than f ull open.
eeeeeeeeeeeeeeeeeeeeeeeeeee...ne................................
- u '(ff l 5.
1.18 Lef t Side 1dv and 11V test. DEPRESS and HOLD the " TEST" pushbutton associated with the 1RV and 11V until.the associated "1RV CLOSED" and "11V CLOSED" indicators are illuminated and "1RV OPEN" and "11V OPEN" indicators are off.
# 1). Locally VERITY / OBSERVE the Left Side 1RV travels tully CLOSED.
# 2). Locally VERIFT/ OBSERVE the Lef t Side 11V travels f ully
, CLOSED.
y 6 k '% i b. RELEASE the " TEST" pushbutton and VERIFY 1RV and 11V are open as indicated by the associated "1RV OPEN" and "11V OPEN" Andicators illumine.ted and "1R CLOSED" and "11V CLOSED" indicators of f, i t 1). Locally VERITY / OBSERVE the Left Side 1RV travels fully OPEN. i t 2). Locally VERITY / OBSERVE the Left Side !!V travels fully OPEN. 1.19 Right Side 1RV and 11V test.
. DEPRESS and HOLD tl.e " TEST" pushbutton associated with the 1RV and IIV until the associated "1RV CLOSED" and "11V CLOSED" indicators are illuminated and "1RV OPIM" and "11V OPEN" indicatora are off.
t 1). Locally VERITY / OBSERVE the Right Side 1RV travels fully CLOSED. h
\j t 2). Locally VERIFT/ OBSERVE the Right Sida 11V travels fully CICSED.
l b. RELEASE the " TEST" pushbutton and VERITY 1RV and IIV reopen as indicated by the associated "1RV OPEN" and "1IV OPEN" indicators are illuminated and "1RV CLOSED" and "12V CLOSED" indicators off.
# 1). Locally VER!tT/ OBSERVE the Right Side 1RV travels fully OPEN.
# 2). Locally VERITY / OBSERVE the Right Side 11V travels fully OPEN.
(0529V/0049V/082889) l-t
..,.. -,-... . ,,_, , ., . . - , , ~ , . . -
D 1905 3.4.2.a.1
\b R0Visies 2 g 1.20 Left Side 2RV and 21V test.
- a. LEPRESS and HOLD the "TESY" pushbutton associated with the 2RV
\
and 21V until the associated "2RV CLOSED" and "21V CLOSED" g indicators are illuminated and "2RV OPEN" and "2IV OPEN" Andicators are off. en d-W 1). Locally VER1rY/ OBSERVE the Left Side 2RV travels fully CL SED. N 0 N t 2). Locally VERIFY / OBSERVE the Lef t Side 21V travels f ully CLOSED.
- b. RELEASE the " TEST" pushbutton and VERIFT 2RV and 21V reopen as indicated by the associated "2RV OPEN" and "21V OPEN" indicators are illuminated and "2RV CLOSED" and "22V CLOSED" indicators off.
# 1). Locally VER1rY/ OBSERVE the Left $1de 2RV travels fully OPEN.
# 2). Locally VERITY / OBSERVE the Lef t Side 21V travels f ully OPEN.
'N 1.21 Right side 2RV and 21V test.
( DEPRESS and HOLD the "TESY" pushbutton associated with the 2RV and 21V until the associated "2RV CLOSED" and "23V CLOSED" indicators are illuminated and "2RV OPEN" and "21V OPEN" [ \ indicators are off. g , v. 1). Locally VER!rY/ OBSERVE the Right Side 2RV travels fully CLOSED.
# 1). Locally VER!rY/ OBSERVE the Right Side 21V. travels fully CLOSED.
- b. RELEASE the " TEST" pushbutton and VERITY 2RV and IIV reopen as indicated by the associated "2RV OPEN" and "21V OPEN" indicators are illuminated and "2RV CLOSED" and "21V CLOSED" indicators off.
t 1). Locally VERIFT/ OBSERVE the Right Side 2RV travcas fully OPEN.
# 2). Locally VER1rf/ OBSERVE the Right Side 21V travels fully
/,4 OPEN.
1 22 Left Side 3RV and 31V test. a / DEPRESS and HOLD the " TEST" pushbutton associated with the 3RV
'd a .
f and 31V until the associated "3RV CLOSED" and "31V CLOSED" indicators.are illuminated and "3RV OPEN" and "31V OPEN" indicators are off. t 1). Locally VERIFT/ OBSERVE the Lef t Side 3RV travels fully l CLOSED.
# 2). Locally VER1rY/ OBSERVE the Left Side 31V travels fully C14 SED.
(OS29V/0049V/082889)
l 1505 3.4.2.a-1 R:visica 2 i i
- b. RELEASE the "7ES7" pushbutton and VER1rf 3RV and 31V reopen as
['~' x indicated by the associated "3RV OPEH" and "31V OPEN" lodicators are illuminated and "3RV CLOSED" and "31V CLOSED" indicators of f. t_ 1). Locally VERITY /0BSERVE the Lef t Side 3RV travels fully OPEN. ; ( _ 2). Locally VERITY /0BSERVE the Lef t Sids 32V travels fully OPEN. 1.23 Right side 3RV and 31V test,
- s. DEPRESS and HOLD the "TES7" pushbutton associated with the 3RV and 31V until the associated "3RV CLOSED" and "31V CLOSED" l Indicators are illuminated and "3RV OPEN" and "31V OPEH" '
indicators are off. p!.s t 1). Locally VERITY /0BSERVE the Right Side 3RV travels fully [
}h~ . CLOSED.
\I ^
(_ 2). Locally VER!rY/0BSERVE the Right Side 31V travels fully CLOSED.
- b. RELEA3E the " TEST" pushbutton and VERITY 3RV and 32V reopen as indicated by the associated "3RV OPEN" and "31V OPEN" indicators are illuminated and "3RY CLOSED" and "31V CLOSED" indicators off. [
t- 1). Locelly VERIFT/0BSERVE the Right Side 3RV travels fully p OPEN. !
\
# 2). Locally VER1rY/0BSERVE the Right Side 31V travels fully
. , OPEH.
VER!rY valve position limit re st to its protest value, t eneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen.eeeeeeeeeeeeeeeeeee.e ' e gggg e i e Perform steps P.1.25 and F.1.26 if it la desired to *
- transfer the Governor Valves f rom " SINGLE VALVE" the
- e "gEQUENTIAL VALVE" mode of operation at the discretion *
- of the Shif t Engineer. otherwise proceed to step r.1.27.
- eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee**eneeseene ,
neeeeeeeeeeeee**eeeeeeeeeeeeeeee**enenemonemenenneeeeeeeeeeeeeee
- CAUTItat * (
- Ir RAPID VALVE OSCILLATIONS OCCURS, TKEN DEPRESS "7URBINE *
- MANUAL" CBI TWE DEH TURBINE PMEL, AND "GV RAISE" OR "GV *
- LOWER" TO ADJUST GCNERNOR VALVE POSITICat TO MAINTAIN
- DESIRED TURBINE LOAD.
- eenenenemoneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee ,
t APPROVED AUG 2 81989 tos29V/co49V/os2ss9) 8.O.S.R. i
. - _ - . - - . - _ _ . - - . - - . - . . ~ . _ . _ - - - _ . - _ - .
I 1905 3.4.2.a-1 l R3violes 2
............e,e....e...eoeaeseeeeaeenee.ee...eeenese...ee... e.e l O e
- The transfer from single to sequential valve mode may
- e l
- require several minutes. Upon depressing the pushbutton,
- j
- the SINGLE VALVE lamp will go out and the SEQ VALVE lamp
- l e will begin flashing. Completion of the transfer is
- l
- Andicated by the SEQ VALVE lamp being steady on. * !
ene.eeeeeeeen.eeeeeeeenenene.eee. ... ..e......... ... ......... {
' 1.25 DEPRESS " SINGLE VALVE / SEQ VALVE" pushbutton on the DEM Turbine l Control Panel located on 1PM02J. '
l 1 1.26 VER1rY the SEQ VALVE lamp is steady on. l 1.27 VERITY / PLACE the U-1 NDCT Turbine Trip Interlock Control Switch to MORMAL. If desired. l: INDEPENDENT VERIPICATION ! I etee.teeeeeeeeeeeeeeeeeeeeeeee*6eeenemoneneneneneeenennemanneeen
.. % M
- l
. .The-fo11ovinh . e are to be performed la conjunction with
- j m a, Plant,Startup lag performance of the applicable
- j
- 9ertions.cf 1BGP 100 2 an&/or 1BGP 100 3.
- eeeeeeeeeeeeeeeeeeeeeeeeeeeeen.eeeeeeeeeeeeeenneeeeeeeeeeeenes.e j t
2.0 Testina Durina Plant startum O l-g M 2.1 ENSURE an operator is stationed to directly observe th" movement of I [ - each valve to be tested through one complete cycle ! rom the running position.
+
l 2.2 During the step for PREPARAT!CW POR ROLLING THE MAIN WRBINE (IBGP 100-2). locally ENSURE the following D a. All ISV's are OPEN. b b. All R5V's are OPEN. All Governor Valves are OPEN. 2.3 When the WRBINE TRIP pushbutton is depressed (1RGP 100-2), locally [ VERIFT/ OBSERVE the follodag N [
#F a. Lef t Side 3RV traveled fully CLOSED.
W V b. Right Side 1RV traveled fully CLOSED. 1
- e c. Lef t Side $RV traveled fully CLOSED. !
! WM . . - Right Side 2RV traveled fully CLOSED. l W e. Left side 3Rv traveled fully CLOSED. APPROVED ! t M. Right Side 3Rv traveled fully CLOSED. gggg B.O.s,R* I; (0529V/0049V/082889) ; I i
. . - . ~ -.,,...~-...,-..~-...,n... .
v.-...._ . _ . , . - - . _ . . . , . _ _ . - . . - - _ - . _ - . -. . . . . - - - , . - .
i 1BOS 3.4.2.0-1 : R3visica 2 L t" g. Left Gide 11V traveled fully CLOSED. { t h. Right Side 11V traveled fully CLOSED. t b 1. Left Side 21V traveled fully Ct4 SED. t j. Right Side 2IV traveled fully CLOSED. t k. Left Side 31V traveled fully CthSED. t D. 1 Right Side 31V traveled fully CLOSED.
#1 m. Governor Valve No.1 traveled fully CLOSED.
e n. Governor Valve No. 2 travelow fully CLOSED. ! t u o. Governor Valve No. 3 traveled fully CLOSED. l t p. Governor valve No. 4 traveled fuily CLOSED. f 2.4 When the TURBINE !.ATCE Pushbutton is depressed following the Turbine [ Trip (IBGP 100 2), locally ENSURE the followings f t a. Lef t Side IRY traveled fully OPEN. t b. Right, Side 1RV traveled f ully OPEM. t c. Lef t Side 2RV traveled fully OPEN. f
~
W.[/2.d. Right Side 2RV traveled fully OfEN. i WM e. Lef t Side 3RV traveled fully OPEN. I W f. Right Side 3RV traveled f ully OPEN. t 9 Lef t Side 11V traveled fully OPEN. ;
#' h. Right Side LIV traveled f ully OPEN. i t
W. 1. Lef t Side 2IV traveled f ully OPDt. Wk j. Right Side 2IV traveled fully OPEN. ff k. Lef t Side 31V traveled fully OPEN. W 1. Right Side 3IV traveled f ully OPEN. l t m. Governor Valve No.1 traveled fully OPEN. tb n. Governor Valve No. 2 traveled fully OPEN. I eb o. Governor Valve No. 3 traveled fully OPEN. l
', APPROVED .
t p. Governor Valve No. 4 traveled fully OPEN. I i AUG 2 81989
-16 B.O.S.R.
(0529V/0049V/082889) i r
1805 1.4.2.e-1 R3 vision 2 2.5 During the step for TURB1HE SPEED INCREASE 'JO 110.Q RPM (180P 100-3),
- 0. locally ENSURE:
W a. All Throttle Valves are OPEN. 2.6 During the step for ACWAL WRBINE TRIP TEST (1BGP 100-3), locally ENSURE the followings t a. Throttle Valve No. 1 traveled fully CLOSED. b te b. Throttle Valve No. 2 traveled f ully CLOSED. tf c. Throttle Valve No. 3 traveled fully CLOSED. t b de Throttle Valve No. 4 traveled fully CLOSED. 2.7 When the turbine is latched and the TRANSPER TV-GV Pushbutton is depressed (IBGP 100 3), locally ENSURE the followings t a. Throttle Valve No. 1 traveled fully OPEN, t b. Throttle Valve No. 2 traveled fully OPEN. t c. Throttle Valve No. 3 traveled fully OPEN. t d. Throttle Valve No. 4 traveled fully OPEN. G. ACCEPTANCE CRITERIAt
- 1. Each high pressure turbine throttle and governor valve and each low pressure turbine rebeat and intercept valve shall be cycled through one complete cycle f rom the running position with direct observation locally for verification of smooth and proper operation as indicated by initialing in the designated steps in the MAIN BODY of the
-procedure.
l l l l c . APPROVED l C (rinal) AUG 2 81969 B.O.S.R. (0529V/0049V/082889)
1805 4.6.2.1.c-1 Revision 51
- REACTOR COOLANT SYSTD4 CONTROLLED LEAKAGE MONTHLY SURVEILLANCE ;
(% A. STATEKENT Or APPLICABILITY: This procedure applies to the monthly verification of Reactor Coolant . System Controlled Leakage in Modes 1, 2, 3 and 4.
- 5. _R_EFERENCES t ,
- 1. Technical Specification Surveillance 4.4.6.2.1.c.
C. PREREQUISITES:
- 1. Receive pennission from the Shift Engineer or designated SRO Licensed Assistant prior to performing this surveillance by having the Data Package Cover Sheet signed and dated.
- 2. Reactor Coolant Pressure between 2215 and 2255.
- 3. One Centrifugal charging pwsp shall be in operation and flow control valve FCV-121 shall be under automatic pressuriser level control.
D. PRECAUTIONSt_ . As defined by Technical Specification, CONTROLLED LEAFME shall be
~
1. that seal water flow supplied to the Reactor Coolant P.stp seals. P E. LIMITATIONS AND ACTIONSt ! 1. As stated in Technical Specification Liaiting Condition for Operation 3/4.6.2. . .
- 2. If the Acceptance Criteria is not met, Ile(EDIATELY notify the Shif t Engineer to initiate LCOAR procedure 1905 4.6.2-la.
F. MAIN BODYt
- 1. RECORD the Time and Date:
TIME f 4T DArz 3 / ls / 9 1
- NOTE
- Perform Steps F.2 through F.4 quickly to prevent an **
- eacessive change in Pressurisar Level.
FOR REFERENC . APPROVED
\ 3 l (2514P) gg4g l
S. O. S. P
1B05 4.6.2.1.c-1 R2vicion 51 N82. PLACE ITV 121 in MANUAL and slowly OPEN to 100%. ADJUST ICV 182 as necessary to MAIICAIN Total Seal Injection riow to
- 23. all 4 RCP's i 40 gpa.
- 4. RD"l0RD individual RCP Seal Injection flows, position of ICV-121, and RCS pressure.
RCP SEAL INJDCTION TLOWS
- a. lA RCP (IRC01PA) 1r1 145A 9.l gpm
- b. 1B RCP (IRC01PB) 1r1 144A 92 gpm
- c. 1C RCP (1RC01PC) 1r! 143A 9.I gpm
- d. 1D RCP (1RC01PD) 1r! 142A ').1 gpm
- e. ICV-121 position e /CO % Open(100%)
- f. RCS pressure e_ Ts4c psig(2215-2255 psig)
$5. ADJUST HCV-182 to ESTABLISH nomal charging and seal injection flows. Y 6. SUM the seal injection flows from step 4 and enters e 3 (r . (e . (i 40 gpm) . M 7. AICUST ITV 121 to HAINTAIN normal pressuriser level, then PLACE TUV 121 in AUTO. .
- 18. NOTITY the Shif t Engineer that this surveillance is cotrpleted.
G. ACCEPTANCE CRITERIA:
- 1. RCS CONTROLLED LDTAGE at a Reactor Coolant System pressure of 2215 to 2255 psig shala be limited to 40 gpm with itV-121 100% OPEN.
FINAL APPROVED
-:- AU3141985 (2514P) 9. O. S. P
1908 4. 6. 2.1.d.1 R;visica 2 REACTOR COOLANT SYSTEM WAT!t DfVENTORY BALANCE 72 HOUR SURVE!LLANCE O A. $7ATDG2f7 Of. APPLIPAR1LITYt This procedure provides the steps necessary for determining the teactor Coolant System identified and unidentitled leakage in Mode 1, 2, 3. and 4 using a band calculation, or the Process Computer RCS Leaktate Code. B. REf f1ENCZE t
- 1. Technical Specifications 4.4.6.2.1
- 2. IfUR20-09 86
- 3. Station Procedures
- a. BCP 300-9 Steen Generator Tube Leak Bate Determination
- b. 1908 4.6.2.la, LCOAt . Reactor Coolant System - Operational Leakage l C. PREREGJIEITERi ,
- 1. Receive permisalos from the Shif t Engineer or designated SRO licensed l assistaat prior to performing this surveillance by having the , Data l (. Package Cover Sheet signed and dated.
/2. Divert valve 1CV112A must be la the VCT positloa. !? 1CV112A is diverted to the HUT, TIRN terminate the surveillance and restart only
. when 1CV112A is la the VCT position.
- 3. When performing the Computer Code method of this surveillance the following assumptions are made due to instrument limitations.
Therefore, the computer cha only be used la Modes 1, 2 and 3 with the following conditions
- a. The pressuriser must be la a condittom of saturation.
- b. RCS pressure must be between 2150 and 2350 PSIG.
- c. BCS temperature (TAVG) must be between 530 and 650'f.
- d. RCDT pumpdowns are not allowed during the course of this procedure.
l l 4. In the event the Process Camputer is going to be used for the leaktate calculation, the Process Computer will need .to be etable over the entire surveillance period. Y APPROVED
.o o m,,,
(0793V/0068V/070889) B.O.S.R.
1 DOS 4.6.2.1.d.1 R:visies 2 D. PRECAUT1Cassi
- 1. While performing leak rate calculations, plant parameters must remain l 0 f airly constant (e.g. no power slynificaat changes or menon oscillations). Considerations should be givoa to making borations/ dilutions prior to initial data taking such t. hat RCS Tave remains fairly constant.
- 2. Any draining or sampling activities must be terminated during the performance of this surveillance.
- 3. Any drain Anputs or outputs to the PRT or RCDT other than f rem BC or l
- CV, must be terminated during the performance of this surveillance.
- 4. Makeup to the VCT may invalidate the resalte of this calculation. l Minimise the need for makeup by starting with a VCT 1evel on the high
.end of the normal operating band. I E. LIMITATICalE. AND ACTItalE4
- 1. As stated in Technical Specification 3/4.4.6.2.
- 2. In the event the Feceptance Criteria is not met during the performance of this surveillance, DeGDIATELT notify the Shif t - . )
Engineer to initiate LCOAR 1906 4.6.2 1a. i
- 3. Required data taken during the performance of this procedure shall be [
I recorded on the surveillance data shoot. O U r. niin BoDri
...s............................................................
. gggg e.
- If using the Process Computer I,eak Rate Program to *
- determine the RCS Leak Rete TREN perform section A and
- use the process Computer Data sheets. tr manually *
- calculatlag the RCS Leak Rate TEIN perform Section 3 and *
- use the Manual Calculation Data Sheets.
- SECTICat A, PROCESS CCMPUTER LEAR RATE CALCULAT!Calt
- 1. RECORD start Date.
- 2. Manually pump down the RCDT to a low lent, it desired.
- 3. PLACE the RCFr pwnpa to the STOP position.
- 4. RECORD the following laitial data on data sheets
- a. PRIMARY WATER / DORIC ACID TOTAL FtON INTEGRATOR reading,
- b. RCDT Level t. Temperature (obtain readings locally at panel ORE 01J-from Rad Waste Operator).
- c. TIME /INITIALE. APPROVED 2 Aug 141969 (0793V/0060V/070889) r B.O.S.R. ;
i
19054.6.2.141 i R visies 1 e... ... ...................... ......................... een..e l
. ggzg e ,
I
- Ramping the Unit, load following. boration/ dilution for a f
- Tay,/A1 control will mot allow the BCS parameters to e
- be steady long enough for a valid RCS leaktate. The e !
- optimum time f rame for the Isak rate is 2 hours but may a
- be changed at the discretion of the SE/SCRE. * :
e e e e ee ****ee e e eeeeee eee eee e e ee eeeee e eeee e e eee e ee e ee ee e ee ee ee e e e e
- 5. ArTER the desired time has elspeed. RECORD the final data for the .
parameters listed above la step 4. ; 1
- 6. DEPRESS " MENU" on the Process Computer Terminal. t
- 7. SELECT Group 429. RCS Lean Rate menu option and DEPRESS the esecute buttoa.
neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee **eean. .........eee , e gazg a
- The Least Squares fit Method is the preferred method. *
- If the Least Squares rit is unacceptable, e Point to e
- Polat Method Leak Rate Calculation may be used.- If the * ,
- point to point method is unacceptable the computer method n
[
- may not be used. Continue to Section B for Manual Leak e . !
- Rate Calcualtion. . ;
eeneenneseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemene.......... * [ 8. ENTER the follow 1ogi
/h (s,/ a. Select "1" for toast Squares Calestation method, or select "2" for Point to Point Calculation. ,
i
- b. Select desired output device.
- c. ENTER recorded PW/ DORIC ACID INTEGRATOR initial and final values lato the provided entry fields. !
- d. ENTER recorded RCDT initial and final values ists the provided l entry fields. >
e, atTER a "0" for the initial and final RCDT pump run times.
- f. SELRCT the desired tLme interval, corresponding to step 4.c.
- 9. DEPRESS esecute and obtain output. ,
- 10. Evaluate Error / Warning messages against Appendia R and INITIATE any required action.
i , 11. If the output results are acceptable attach pristout and proceed to l step 12. APPROVEO O ' " * *
- 8. O. S. R.
t (0793V/0068V/070889) e r
+
.-. -~ - - . - - . - , .,,.._.+.~,,m,..,.,, ,_,.m.w,, , - --.-,,.,r,- .-
i 1805 4.6.2.1.d-1 l Rovisics 2 e...............................eeeeeeeeeeeeeeeeeeeeeeeeeeeenen.
- H2IE
- O
- If the confidence error is greater than the acceptable
- limit or the correlation coef ficient is lower the.n the
- acceptable limit an error code will be printed. e
- 12. CCHPLETE the Process Computer Data Sheet.
- a. C!tCLE the method used.
- b. CALCULATE the Total Identified Leakage by adding the latest S/G Tube Leakage to the Known Leakage.
- c. Total S/G Tube Leakage.
- d. Individual S/G Tube Leakage.
- e. DETERMINE the Unidentified Leakage Rate by subtracting the Total Identified Leak Rate Crom the Reactor Coolant Gross Leak Rate.
- f. PLACE the RCDT punops to the Auto position. INITI AL Data Sheet and receive Independent Verification by having another N50 initial the Data Sheet.
- g. DETERMINE !! the acceptance criteria is met and signify such by placing a circle on yes or no on the Data Sheet and Initial and Date space provided.
- h. IP the acceptance criteria is not met. IMMEDIATELY notify the Shift Engineer to initiate LCOAR 1805 4.6.2-14 and t.han PROCEED to Appendix A to help locate and isolate any leakage sources.
APPROVED O . iun om
-4 B.O.S.R.
(0793V/0068V/0700(9)
t 1908 4. 6. 2.1. d-1 ! R visito 2 l i SECT 10H B, MANUAL POINT M POINT LEAR RATE CALCULATICM f n ................................................................ U . um . , Use t.be process computer to call up the individual points. *
. (0roup 105) If it is not available, use instrumentation * ,
- on NC3. . t
)
i
- 1. RECORD start Date.
- 2. MANUALLT ptanp deva the RCDT to a low level. if desired. !
t
- 3. PLACE the RCDT pumps to the STOP position.
- 4. RECORD the following initial data ;
- a. PER LEVEL, Point OLO480, LO481, or LO482 and RECORD point used.
- b. PZR TTMPERA'2VRE, Po. at $T0480.
- c. VCT LEVEL, Point OLO112.
- d. 79t/'!OTAL FLOW INTEGRATOR reading. .
.a...*........................,.................................
MM .
- If Tave < 112'T omit step, e. If Tave 1 11Q'r
- 6* . omit steps f f. g.
e.- RC Tave (av rage) Point 400404 e,x titu.D g.
-sr for Tave's 1530*P.yp& rma O/s)
- f. 907 LEG WR TEMPERATURE, Point l's 70419, 70439, 70459, and 70479.
- g. COLD LEO WR TEMPERA 7URE, Point l's 70406, 70426, 70446, and 70466.
- h. PRT LEVEL, Point 6LO485.
- 1. PRT TEHFSRA'IURE, Polat 70485
- j. RCDT LEVEL, (obtain reading locally at panel ORE 01J f rom the Rad Maste Operator). M Na. . Wb( ttcb'T
- k. TIME /IMITIALS APPROVED AUG 141969 l
! -s. B. O. S. R. (0793v/00sev/070sso) l
__. _ _ . . _ . - --__ _ . _ - _ _.____..___-__._._____.m i 1905 4.6.2.1.d 1 ; R;visies 2 ;
. ggg . :
O
- Ramping the Unit, load following, boration/dilutica for
. 'tave/A! control will not allow the RCS parameters to
- be steady long enough for a valid RCS leaktate. The l
- optimum time frame for the leak rate is 2-4 hours but may
- l
- be changed at the discretion of the SE/SCRE. . '
i
- 5. ATTER the desired time has elapsed, RECORD the final data for the '
parameters listed above, in step 4. l
- 6. DETERMINE the dif ference in FIR level (final-initial) and convert it f to gallons. l l
- 7. DETERMINE the dif ference in VCT level (final-initial) and convert it t to gallons. '!
I
- 8. DETERMINE the total makeup volume by subtracting the initial }
integrator reading f rom the final.
. gggg .
. If T ay, t 110*r omit Step 9. If Teve 1 11G*r omit Step 10. * .
(; t
/ 9. With Teve 1110'r, DETERMINE the RCS Average Tave.
n V 10. With Tave < 110'F, DETERMINE average teve by totaling the Not f. Cc,16 leg temperatures and dividlag by 8 for both initial and final data and then DETERMINE the RCS Average Tave. p i
- 11. DETERMINE the change in RCS density by selecting a' vslue for Ap/'r .
from Tabis A using Ave 7,y, and multiplying it by the change in Tave. j
- 12. CALCULATE & RCS volume per the Data Sheet. f
- 13. DETERMINE the average PER temp and obtain the p PER f rom TARLE R.
- 14. DETERMINE the Graan Leakage Rate by performing the calculation on the i Data Sheet. !
- 15. OSTAIN PRT (Final and initial) gallons and density f rom TABLE D and C i respectively, and enter- Anto the APRT mass equation.
- 16. CALCULATE APRT mass and RECORD the results.
- 17. DETERMINE the leakage into the PRT by performing the calculation on the Data Sheet. i f
( f APPROVED i AUG 141989
-s- 8. O. S. R.
(0793V/006BV/070889)
. . . _ . . . . . _ ~ . _ _ _ _ . - _
_ - , _ . . _ , .. _ . _ . - ~ _ . . _ ~ _ . _ - . . _ . . _ -. .
1805 4.6.2.1.d.1 R:visisc 2
- 10. ORTAIN RCDT (Flaal and laitial) gallone fron' TABLE E and determine the leakage lato the BCDT by perfonelag the calculation on the Data 9 19.
,,eet.
DETERMINE the RCS Known Leakage Rate by performing the calculation on the Data Sheet.
- 20. ORTAIN the latest BC Steen Generator Tube Leakage Rate and add it to the RCS Knova Leakage Rate to obtain the Total Identified Leakage Rate.
neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen a gggg a
- The A error calculated for the.0ross Leakage Rate must be e
- carried over to the Unidentified Leakage Rate la step 21 e
- and must be assessed as a penalty when comparlag the *
- calculated Unidentified Leakage Rate to the Acceptance *
- Criteria.
- eeeeeeeeeeeen.. eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen......e
- 21. DETERMINE the tinidentiflad Leakage Rate iry subtracting the Identified Leakage Rate f rom the Gross Leakage Rate.
- 22. PLACE the RCIPT pumps' to the AUTO posit 10a. INITIAL Data Sheet and
- receive INDEFENDf3tT VERITICATICRt by haylag another N50 initial the Data Sheet.
- 23. DETERMINE-if acceptance criteria is met and signify such by placing a circle on yes or ao on the Data Sheet and IMITIAL and Vate space
-o provided.
l . 24. IF. the acceptance criteria is not met, DetEDIATELY notify the Shif t Engineer to laitiate LCOAR 1905 4.6.2-la and then PROCEED to Appendia A to help locate and isolate acy leakage sources. G. ACCEPTAleCE CRITERIAq
- i. SC Leakage Rate shall be less than or equal to 12 gym Total I 3dentified and 1 gym Valdostified. Included la the it gym Identified Leakage, Beactor to Secondary Leakage through all Stesa Generators
- not isolated f rom the RCS shall be less thma or equal to 1 gym with no more than 100 gyd (1347 GPM) through any one Steam Generator. {
! APPROVED O aum = 5.O.S.R. (o793v/co6sv/o7 case)
'[
+ - . . . _ . - ~ . , .
1908 4. 6. 2.1.d-1 R:visico 2 TABLE A AVERAGE RATE Of CHANGE OF DDISITY PER 'T TOR CCHPRESSED LIQUID AT 2250 Pf!L Aya Tava dit = f Ave T*ve ea = f I
/ft ) /ft i AYa.Tava ea = f /ft 3)
('T) 'T ' T ('T) 'T 'r ('T) 'T 'r 200-209 0.023 430-439 0.043 5) $-57 9 0.074 210-219 0.025 440-449 0.045 580-584 0.076 220-229 0.025 450-459 0.045 585-589 0.080 230-239 0.027- 460-469 0.048 590-594 0.082
, 240 349 0.027 470-479 0.048 595-599 0.084 250-259 0.027 480-489 0.050 260-269 0.029 490-494 0.050 270-279 0.029 495-499 0.052 280-289 0.030 500-504 0.054 290-299 0.030 505-509 0.054 300-309 0.032 510-514 0.056 310-319 0.032 515-519 0.056 320-329 0.033 520-524 0.056 330-339 0.034 525 529 0.058
'N 340-349 0.034 530-534' O.060
' ) 350-359 360 369 0.036 0.036 535 539 540-544 0.062 0.062
. 370-379. 0 037 545-549 0.064 -
380-389 0.038 550-554 0.065 390-399 0.040 555 559 0.067 400-409 0.040- 560 564 0.068 410-419 0.041 - 565-569 0.070 420-429 0.042 570-574 0.072 6 i t a d h
- 8 B. O. S. R. .
(0793V/0068V/070089) 9 -'y +
--<v v v v v , - .wy4 , , - - * - - w tr - - - . - , , , ,r- - - e -- --~,-e- -+, - - ' -- - - - . - --i--+-
. _ _ ~ . - - . - . - . _ . - . _ - - . - - . . - - . . , - - . _ . . - ~ . - . . .
eg r r o w * " '- i 1 DOS 4. 6. 2.1.4 1 ! AUS \ 4 0 Revisies 2 i
- 5. U. 3. N.
TABLE 8 , DENSITY Or i O SA'WRATED FLUIDS / CASES p(1bm/ft 3) Temp ('T) j Temp ('F) p(1bm/ft 3) -jf 400 53.65 600 42.3012 "( 410 53.2401 602 42.1408 I 420 52.7983 604 41.9815 l 430 52.3697 606 41.8060 ! 440 $1.9211 608 41.6320 ! 450 51.4536 610 41.4594 l 455 51.3149 612 41.2882 ! 50.9944 460 614 41.1015 ! 465 50.7421 616 40.9165 470 50.5051 618 40.7332
- I 475 50.2513 620 40.5515 400 50.0000 622 40.3633 I 485 49.7265 624 40.1768 l 490 49.4682 626 39.9760 i 495 49.2126 628 39.7772 !
$00 48.9476 630 39.5804 M 505 48.6559 632 39.3856 ,;
$10 48.3793 634 39.1773 ll 515 48.1058 636 38.9712 * -'!
b20 47.8240 61a 1a.7522 !
*t5 47.5172 640 38.5356
, .s. 47.2255 641 38.4246 ,
Ti$ 46.9208 642 32.3142 ! l $go 46.5983 643 38.2044 O- _J 45 46.2981 644 38.0952 [; 550 45.9664 645 37.9795 552 45.8295 646' 37.8644 . 554 45.7038 647 37.7501 ! 556 45.5789 648 37.6364 I 558 45.4442 649 37.5164 ; 560 45.3104 650 37.3972 U 562 45.1671 651 37.2787 j! 564 45.0248 652 37.1609 : 566 44.8833 653 37.0336 568 44.7427 654 36.9072 570 44.6030 655 36.7816 572 44.4642 656 36.6569 574 44.3164 657 36.5230 '
$76 44.1696 658 36.3901 578 44.0238 659 36.2582 540 43.8789 660 36.1272 582 43.7254 661 35.9874 e 584 43.5730 662 35.8487 ,
586 43.4216 663 35.7111 7 588 + 43'.2713 664 35.5745 j 590 53.1127 665 35.4264 592 42.9553 666 35.2796 ,
$94 42.7991 667 35.1339 596 42.6439 '668 34.9895 ;
598 42.4719 669 34.8280
- O- 670 34.6681 .
9 l 0793V/0068V/080389 l
i 1908 4.6.2.1.d-1 l R;visics 2 ,
~
TABLE C O' CCHPRESSED LIQUID AT $0 PSIA
?
I of I I# /ft Il of I I of IDf t $ 21*L),et T('f1 /ft 3) 2L'Il /ft n Inn f 50 62.42 70 62.32 114 61.81 158 61.04 '
$1 62.42 71 62.31 115 61.80 159 61.02 b 52 62.42 72 62.30 116 61.78 160 .
61.00 i
$3 62.41 73 62.29 117 61.77 161 60.98 ; -- 54 A2.41 74 62.28 118 61.75 162 60.96 i0 55 62.40 75 62.28 119 61. 't 4 163 60.94 ;
16 62.40 76 62.27 120 61.72 164 60.92 ' 57 62.40 77 62.26 121 61.71 165 60.89
$8 62.39 78 62.25 122 61.69 564 60.04 i 59 62.39 79 62.24 123 61.67 is7 60.86 ;
60 62.38 80 62.23 124 61.66 148 60.84 ! 61 62.38 81 62.22 125 61.64 165 60.82 e2 62.37 82 62.21 126 61.63 T/C 60.79 63 62.36 83 62.20 127 61.61 181 60.77 64 62.36 84 62.19 128 61.59 172 60.75 , i 65 62.35 85 62.18 129 61.38 173 60.73 i 66 62.34 86 62.17 130 61.56 174 60.71 l+ 67 62.34 47 62.16 131 61.54 175 60.69 68 62.33 88 62.15 132 61.53 176 60.67 O d 69 62.32 89 90 62.14 62.13 133 134 61.51 61.49 177 178 60.64 60.62 t [ 91 62.11 135 61.47 179 60.60 t 92 62.10 136 61.46 180 60.58 93 62.09 137 61.44 181 60.56 ! 94 62.00 138 61.42 182 60.53 , 95 62.07 139 61.40 183 60.51 96 62.06 140 61.38 184 60.49 97 62.04 141 61.37 185 60.47 _ 98 62.03 142 61.35 186 60.44 99 62.02 143 61.33 187 60.42 ! 100 62.01 144 61.31 188 60.40 , 101 61.99 145 61.29 189 60.37 102 61.98 146 61.27 190 60.35 [ 103 61.97 147 61.26 191 60.33 [ 104 61.95 148 61.24 192 60.30 105 61.94 149 61.22 193 60.28 106- 61.93 150 61.20 194 60.26 107 61.91 151 61.18 195 60.23 - 108 61.90 152 61.16 196 60.21 ; 109 61.88 153 61.14 197 60.19 ; 110 61. 87 154 61.12 198 60.16 [ 111 61.86 155 61.10 199 60.14 112 61.84 156 61.08 200 60.12 113 61.83 157 61.06 i AMROVED ,
.O AUG 141989, t
10 ~ (0793V/0068V/070889) 8. O. S. R. t y-, c w,+ ,p.r.,. - _ - , . , , u---pp z--2-m -- --r m--,
O O O 18CS 4.6.2.1.d-1 Revision 2 PRESSURIZER.RELIEP TANK, (PRT) LEVEL /70LUME C0efvERSIOutS TABLE D g 12VgL yrw = t car ) " g Lgynt yrwe - (car 1 g EEVEL ' Trw rw(car 1 g r2ygt yrw - fcar) g Lgygt ynr ma(car )
. O 322.81 21 2530.40 41 5402.34 61 8474.01 81 11300.15 1 394.59 22 2461.97 42 5554.49 62 8624.95 82 11426.24 2 4i0.94 23 2795.20 p 5707.89 63 8775.24 83 11550.34 3 551.57 24 2930.03 44 5861.26 64 8924.81 84 11672.36' 4 636.22 25 3066.39 45 6014.96 65 9073.61 85 11792.22 5 724.65 26 3204.21 46 ,
6168.92 66 9221.60 86 11909.81 6 816.68 27 3343.40 .47 6323.10 67 9368.70 87 12025.05 7 912.11 28 3483.92 48 6477.43 68 9514.85 88 12137.82 8 1010.77 29 3625.69 49 6631.88 69 9660.00 89 12248.02 9 1112.52 30 3768.65 50 6786.37 70 9804.09 90 12355.52 10 1217.22 31 3912.74 51 6940.86 71 9947.05 91 12460.22 11 1324.73 32 4057.89 52 7095.31 72 19088.82 92 12561.97
, 12 1434.92 33 4204.05' 53 7249.64 73 19229.34 93 1266G.64 13 1547.69 34 4351.14 54 7403.82 74 10368.53 94 12756.06 14 1662.93 35 4499.13 55 7557.78 75 10506.35 95 12848.09 15 1780.52 36 4647.93 56 7711.48 76 10642.71 96 12936.53 ;
16 1900.38 37 4797.50 57 7864.85 77 19777.54 97 13021.17 I 17 2022.40 38 4947.79 58 8017.85 78 10910.78 98 13101.80 18 2146.50 39 5098.73 59 8170.40 79 11042.34 99 13178.15 19 2272.59 40 5250.27 60 8322.47 to 11172.16 100 13249.93 20 2t00.58
- 222.82 ,.1 to toF or t..=
l
, APPROVED AUG I 41989
~
B.O.S.R.
O O- 0 180S 4.6.2.1.d-1
. Revision 2 SEAC7DS COOLANT DSAIN TANE, (SCDI) LEVEL / VOLUME CONVERSIONS TABLE E g ta,.m vrw r n g eir i s tavan vrw me f CAL) s trvrL vnr tne t car-1 s Lave vrv enetaar i s 12vzL vnr m-f eir i 61 219.73 81 288.91 17.84 21 74.36 41 144.70 0 62 223.42 82 291.97 22 77.58 42 148.43 1 19.96 227.09 83 295.00 80.85 43 152.17 63 2 22.15 23 84 298.00 84.16 44 155.91 64 230.75 3 24.42 24 85 300.94 45 159.67 65 234.39 4 26.74 25 87.50 86 303.85 46 163.42 66 238.01 5 29.13 26 90.88 87 306.72 47 167.19 67 241.62 6 31.59 27 94.30 88 309.54 170.96 68 245.19 7 34.10 28 97.74 48 312.31 101.22 49 174.73 69 248.75 89 8 36.67 29 90 315.04 104.73 50 178.50 70 252.28 9 39.29 30 91 317.71 108.26 51 182.27 71 255.78 10 41.97 31 92 320.33 111.81 52 185.05 72 259.26 11 44.69 32 93 322.90 115.39 53 189.81 73 262.71 12 47.47 33 94 325.42 119.00 54 193.58 74 266.12 13 50.29 34 95 327.87 122.61 55 197.34 75 269.50 14 53.15 35 96 330.26 126.26 56 201.09 76 272.85 l 15 56.06 36 97 332.59 129.92 . 57 204.84 77 276.16 16 59.01 37 98 3*4.85 133.59 58 208.58 78 279.42 17 62.00 38 99 337.04 i 137.28 59 212.31 79 282.64 18 65.03 39 100 339.16 40 140.98 60 216.02 80 285.80 19 68.10 20 71.2C
- 17.84 gal to top of tank l
~ APPROVED AUG 141989 a n n ,,
1805 4. 6. 2.1.d.1 Rovision 2 Appendia A trAr.Act sources cHrcrtisI Listed below are various components and valve locations that could potentially be sources of leakage. When trying to locate a source of leakage, recent system manipulations should be correlated to the order in which equi teent is checked. An example of this would be a seal injection filter that was aligned in the last few days. This would be a high probability source of leakage and should be checked first. ALARt concerns should be considered es well when deternining the order of checks. It should be noted that a leak rate calculation need not be perfortmed af ter isolating each component. Maintaining Erganurinat_layal and IAn constant will result in the slope of the VC7 level recorder trace showing a close approximation of actual leakage. If the slope has not changed af ter a component is isolated, then this component can be slininnted as a source of leakage. eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemone neesene a tem; *
- Escess letdown has ng cleatnup capability. Therefore t. lie *
- normal letdown flowpath should only be isolated for as *
- long as it takes to determine whether it is n source of *
- 1eakage, e
.....eeeeeeeeeeeeeeeen *eeneeeeeeeene enenaneamenneeeeeeeeemaene A quick and effective method of eliminating a large portion of potential leak areas would be to place the excess letdown system in service and secure the pormal letdown flovpath. If this proved to be a source of leakage, then f urther steps could be taken once normal letdown is restored. Switching letdown heat eschangers, bypassing domineralisers, bypassing the RC filter, and isolating the 1CV112A flowpath to the HUT's are all steps that should be considered.
Any components listed below'that have been checked for proper alignment should be initialed as such in the appropriate space. This will prevent unnecessary techecks and decrease the amount of time spent finding and isolating leaks. Utilise the following procedure for each section of valves for isolation and leak detection.
- 1. VERIFT/ ISOLATE the valves / components one at a time (unless otherwise authorised by the S.E.) and check for leakage.
- 2. RETURN the valve (s) to the "As found" position if no leakage is indicated. ,
- 3. INITIAL in the space provided indicating the check is complete.
APPROVED AUG 141969, (0793V/0068V/070889) * * *
- 150$ 4.6. 2.1.6 1 R3visies 3 eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee It0IE
- O
- Notify Rad Chem prior to changing t.be position of any e Q
- proeses sampling valves.
neeeeeeeeeee...noneeeeeeenesseneneeeeeeeeeeeeeeeeeeeeeeeeeeeeeen e m egge samm11ne 1PS9354A PER Sta Sample Inside Isol Viv 1PM11J 1PS93548 PZR Sta Sample Outside Isol V1v 1PH11J 1PSW355A PER Lig Sample Inside Isol V1v 1PH11J l 1PS93558 PZR Lig Sample Outside Isol Viv 1PH11J f 1PS9356A RC Loop fample Inside Isol Viv 1PH11J [ i IPS9356B EC Loop Sample Outside Isol viv 1PH11J I 1PS9358A RC CL Sample Isol V1v Loop 1 1PS27J ; l 1PS9350B RC CL Sample Isol V1v 1,oop 2 1PS27J 1PS9350C RC CL Sample Isol V1v Loop 3 1PS27J 1PS9358D RC CL Sample Isol Viv Loop 4 1PS27J ! 1PS9351A RC ML Sample Isol V1v Loop 1 1PS27J l i-O 1PS93515 E RC ML Sample Isol V1v Loop 3 iPS27J
$ 3 1PS9350A PER Stm Sample Isol Viv IPS27J
, 1PS93508 PZR Lig Sample Isol Viv IPS27J l
1PS152 L17Mel NK Sample Isol V1v 1PS27J I iPS153 CV Denla Sample Isol V1v 1PS27J 1PS154 BR Domin Sample Isol V1v 1PS27J 1PS198 RC Filter Sample Isol Viv 1PS27J La tdown Raat Em ehma== r 1CV011A LTD4N IDt 1A Shell Vent V1v 383' V16 1CVo32A LTDNN IDL 1A Tube Vent V1v 383' V16
. APPROVED ,
AUG1419#
- 1. 8. O. S. R. ;
(0793V/oossV/070ss9) 1 ___m , . - - , .,_.,mw-. m. -, ._,
- -.- - - ,._...,c- --w. - . . .v. - -, _ -
1908 4. 6. 2.1. d.1 R3viel@2 2 l r Latdown Raat Emehamaar (continuedl i 1CV228A LTDWN IIK 1A !alet Vest V1v 383' U16 ! O 1CV229 LTDWN IRE 1A Outlet Vent Viv 364' U14 i i 1CV0118 L*tVWW EK lt Shell Vest V1v 383' U16 t 1CV0128 LTDWN E 13 Tube Vest Viv 383' U16 l 1CV2288 LTDWN MK 19 Inlet Vent V1v 383* U1$ Verify no flow through the followlag sigotglassest i 1WE13MA LTDWM ItK 1A Shell Dra Sightglass 383' U15 l{ IVF10MA LTDWW MK 1A 51 9 htglass 383' V16 , INE14MA LTDWW ltK 1A Shell vent Sightglass 383' U15 { 1WE13MS LTDWN MK 13 Shell Dra S19h tglass 383' V1$ [ IVT10MS LTDWN RK 13 Sightglass_ 383' U16 ! 1WK14MB L7VWN EK 13 shell Vent Sightglass 343' V15 l Emal Water M1 ( I 1CV000k Seal Water IIK Tube Vent Viv 38?' E16 l 1CV0088 seal Water EK Shell Vent Viv 383' 516 1CV010A Seal Water NK Tube Dra Viv 383' 516 -
'I 1CV0105 Seal Water HK Shell Dru Viv 383* 516 -f i
1CY208 Seal Water NK !alet Vent V1v 383' 516 ! Verify se flow through the sightglasa [ 1VF09M 5eal Water EK Sightglass 383' $16 { Ltal cmLa mz j 1BR010A LTDWW CELA MK shell Vent V1v 346' U16 193010B LTDWN CELR EK Tube Vest V1v 346' U16 ; i 13R013A - LTDWN CIELt ItX Shell Dra Viv 346 ' U16 , l 4 l t
- l. 1BR0135 LTDWW CMLR HK Tube Dra V1v 346' U16 APPROVED h "-
AUC 141909
<o>,,V,0068V,,,088,, = o = a-
190S 4. 6. 2.1. d-1 R:vist:03 Verify no flow through the following sightglarsest [O %.) IVT12H LTDWN CHLR HK Vent Sightglass 346' U16 1WE10KA LTDWN CHLR HK Shell Drn sightglass 346' U16 1WE10Mk LTDWN CHLR HK Tube Drn Sightglass 346' U16 Lts nirt n 1BR002A LTDWH RHT HK shell Vent Viv 346' U20 1BR0028 LTDWN RET HK Tube Vent V1v .346' U16 - 1BR003A LTDWN RHT HK Shell Drn V;v 346' U16 18R0038 LTDWN RET HK ',fube Drn V1v 346' U16 verify no flow through the tollowing sightglasses: 1VT13M LTDWN RET HK Vent Sightglass 346' U16 1WE12MA LTDWN RET HK Shell Drn Sightglass 346' U16 > 1WE12MB LTDWH RET HK Tube Drn Sichtglass 346' U16 Leal Iniection Filters
'} 1CV8385A 1A Seal Inj F3.1'ter Vent V1v 383' P11 J
1Cv8386A 1A Soal Inj Filter Drn V1v 383' P11 1Cv63855 lb Sent Inj rilter Vent Viv 383' P11 1CV83868 1B Seal Inj ritter Dro Viv 383' P11 Verify no flow through the following sightglasses: 1VT06MA 1A Seal Inj Filter Vent Sightglass 383' P11 IWE04MA 1A Seal Inj Tilter Drn Sightglass 383' P11 1VT06MB 18 Seal Inj Tilter Vent Sightglass 383' P11 1WE04MB 1B Seal Inj rilter Drn Sightglass 383' P11 Seal Return Filter i 1CV8533 Seal Wtr Etra Filter Vent Viv 383' Pil 1Cv8534 Seal Wtr Rtra rilter Drn V1v 363' P11 APPROVED /O, () Al5141989 8.O.S.R.
. (0793V/00687/070889)
1905 4.6.2.1.d.1 Revision 2 Verify no flow through the following sightglasses: 1VF07M Seal Wtr Rtra Filter Sightglass 383'P11 1WE0$N Seal Wtr Rtro Drn $1ghtglass 383'P11 RC F11ter 1CV8423 BC Filter Vent V1v 383' P11 1 1CV8424 RC Filter Drn V1v 383' P11 Verify no flow through the following sightglasses: 1VT11M RC Filter Vent Sightglass 383'P11 1WE09H RC Filter Drn Sightglass 383'P11 _ CV Domina 1CVB515 CV Cation Domin Rosin Fill / Flush V1v 410' $17 1CV8517 CV Cation Domin vent Viv 401' 517 1CV8520 CV Cation Demin Dru Viv 401' 517 1CV8523A CV MB Domin 1A Resin Fill / Flush V1v 410' 517 1CV8525A CV MB Domin 1A Vent Viv 401' 517 1CV8528A CV MB Domin 1A Drn Viv 401' 517 1CV230A CV b Domin 1A Inlet Vent Viv 410' S17 1CV8523B CV MB Domin 1B Resin Till/ flush V1v 410' 517 1CV85255 CV MB Domin la Vent Viv 401' 517 1CV8528B CV MB Demir 15 Dra V1v 401' 517 1CV2308 CV MB Domin IB Inlet Vent V1v 410' 817 ___. BE Basminn { IBR7011A StrP to 1A Domin Isol V1v 416 ' v1't 1BR70115 SRTP to 1B Domin Isol 'ily 416' V17 1BR7011C SRTP to IC Domin Isol Viv (16' 417 1BR7011D SRTP to 1D Domin Isol Viv 416' V17 APPROVED AUG 141989 (0793V/0068V/070809) B.0.S.R.
1805 4.6.2.1.d.1 Rsvisloa 2 1BR?011E SRFP to 1E Domin Isol V1v 416' V17 1BR7012A 1A Damin Edr Drn Viv 4 01' U17 , 1BR70128 1B Domin Edr Drn V1v 401' U17 1ER7012C 1C Domin Bar Prn V1v 401' U17 1BR7012D 1D Domin Bor Drn V1v 401' U17 1BR70122 1E Domin Bor Drn Viv 401' U17 1BR7016A 1A Domin Bar Drn V1v 401' U17 1BR7016B 1B Domin Edr Dra Viv 401' U17 , IBR7016C 1C Domin Edr Drn V1v 401' V17 IBR7016D 1D Domin Edr Drn V1v 401' V17 / 1BR7016E 1E Domin Bar Drn V1v 401' V17 4 seenemmenneeeeeeeeeeeee*********memenamenenneeeeeeeeeeeeeeeeee . If2IT. * . The thwpath to the HUT from the ICV 112A valve should only *
- be isolated for as long as it takes to determine whether a
- it is a leaksgo source. e eneoenneneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemenene
(). ICV 112A
- OA38249 AB Evap Td Domin Inlet Bypass Viv 401' Q17 OAB8584A AB Evap To Domin Inlet Coat V1v
- Upstress Isol Viv 401' Q17 c
APPROVED O " ' "
- B. t3. S. R. j
-13 ;
(0793V/0068V/070889) l
1805 4.e.2.1.d-1 ! APPEGVED Ravision 2 i i
- AUG 141939 Appendia B 3
I
- 5. O. S. R.
- CCMPUTER EI!ROR CODES AND VALIDATION BASELINE NUMBERS MARNI)4G/ ERR 0a .'.ihSAGE REQUIRED ACTICM i
**** WARNING - PRIMARY WATER / BORIC Indicates a software problem. LEAKRATE ACID ADDITICM NOT CCMPENSATED RESULTS UNACCEPTABLE. Perform Hand Calculation Method. Notify Management Information Services of error message.
ERROR MESSAGES RAVE OCCURRED: LEAKRATE RESULTS ACCEPTARLE. ; SEND UUTPUT TO TYPER TO SEE THEM No action required. '
****0NE PRESSURIEER LEVEL INPUT WAS LEAKRATE RESULTS ACCEPTABLE. No LOCTED OUT MINUTES AGO DUE to laumediate action required. Notify (DEVIATICM DETECTION, MANUAL LOCKCUT, Tech Staff that error message occured. '
BAD QUALITY)**** L
****0NE PRES $URIEER PRESFURE INFin LEAKRATE RESULTS ACCEPTABLE.
'WAS LOCKED MINUTES AGO DUE 7.3 No inusediate action required. ' *
(DEVIATION DETECTICM, MANUAL LOCR7JT, Notify Tech Staff that error BAD QUALITT)**** message occurred. [
**** TIME INTERVAL SELECTED IS LESS Minimum reconenended interva.1 is one bour for Least Squares Fit method and THAN RECOMMENDED INTERVAL **** *
~ Point to Point seethod. Notify SE/SCRE +
l to determine if leakage res'ults are acceptable. ' i
****CCHTIDENCE ERROR GREATER TIL%N When this applies to the REAC7OR ACCEPTABLE LIMIT **** COOLANT GROSS LEAKAGE parameter (Co.nfidence Error > 0.2) the LEAKRATE RESULTS ARC UNACCEPTABT.E.
Perform Point to Point calculation or Manual calculation. ;
**** CORRELATION COEFFICIENT LOWER When thin applies to the REACTOR TRAN ACCEPTABLE LIMIT **** COOLANT GROSS LEAKAGE parameter ,
(Correlation Coefficient c 0.7) LEAKRATE RESULTS ARE UNACCEPTABLE. ! Perform Point to Point calculation or Manual calculation. ,
^ AN IMPROPER KASS VALUE RAS BEEN LEAKRATE RESULTS UNACCEPTABLE.
DETECTED Perform Point to Point calculation or I Manual calculation. . DOBAL READ / WRITE ERROR IN LEAKPNT Indicates a hardware problem. I LEAKRATE RESULTS UNACCEPTABLE. [ Perform Manual Calculation Method. Notify Management Information Settvices O of error message. 19 , (0793V/0068V/080389) k
--n- - - , , , , ,,nn---,,w. - , - - -,n-a-,_ - , . . . , - . - - , - ,
1BOS 4.6.2.1.d.1 R0visics 2 APPENDIX B i COMPUTER ERROR CODES AND VALIDATION BASELINE NUMBERS w/ 4 MARNING/ ERROR MESSAGE REOUInto AcTIcm j 1 ENTRY PIELD UNREADABLE - TRY AGAIN Improper entry. Re-enter data. REQUESTED DEVICE IS PRESENTLY Improper entry. Re-enter data. UNAVAILABLE, TRY ANOTHEd CALC KETHOD ENTRY OUT OF BOUNDS Improper entry. Re-enter data. DEVICE ENTRY OUT OF BOUNDS. Improper entry. Re-enter data. I INTERVAL ENTRY OUT OF BOUNDS Improper entry. Re-enter data. ' INTERVAL ENTRY GREATER TRAN NUMBtR Improper entry. Re-enter data. l OF VALUES STORED l2
' r DOBAL READ / WRITE ERROR IN PROGRAM Indicates a hardware problem. '
LEAKSCN LEAKRATE RESULTS UNACCEPTABLE.
' i.
Perform Manual Calculation Method.' Notify MIS of error message. ;
***eA LEAKRATh' CALCULATION CANNOT Perform Manual Calculation Method. < BE PERFORMED. AVERAGE PRESSURIZEt i I LEVEL COULD HCr ' BE CONPUTED - WOT !
ENOUGE GOOD IN1'UTS**** -
****A LEAKRATE CALCULATION CANNOT.
Perform Manual Calculation Method. . DE PERFORMED. ?iVERAGE PRESSURIZER i PRESSURE COULD JOT BE CCMPUTED - NOT ENOUGH GOOD INPUTS **** APPROVED (] AUG 141969 (0793V/0068V/070889) 8.O.S.R.
l 1805 4. 6. 2.1. d-1 R vis103 2 ; REACNR COOLANT SYSTEM ; WATER INVENTORY BALANCE SURVEILLANCE , PROCESS COMPUTER DATA SHEET DATE , PARAMETER INITIAL DATA r!NAL DATA
-4a PRIMARY WATER / BORIC ACID TOTAL FLOW INTEGRATOR (b RCDT Level RCDT Temperature 9
'4c Time & Initials / ~/
4 i t
~
i 6 4 t b APPROVED : D-2 N! (0793V/0068V/070889) ' k
~ n - , c., ,, _
.w. , , , , - --
1BOS 4.6.2.1.d 1 Revis103 2 PROCESS CCHPUTER DATA SHEET ('
~/ 12a. Method used: Least Squares or Point to Point (Circle one) 12b. TCrfAL IDENTIFIED LhhCE RATE f
RCS Known Leakage + S/G Tube Leakage a Total Identified Leakage 9Pm + 9Pa
- W 9Pm
. (Total Identified Leakage i 10 gpm) 12c TOTAL E/G TURE LEAKAGE
_. W gym (1 1_ gym reactor to secondary leakage through all j S/G not isolated from the RCS) j 12d INDIVIDUAL S/C TUBt mLAKAGE 4 W gpd (1 500 gallons per day through any 1 S/G) . 1 12e 11NIDENTIFIED LEAKAGE RATE !I
. t :
RCS Gross Leakage - Total Identified Leakage a Unidentified Leakage l gym - gpa = d 9Pa** . (Unidentified Leakage i 1 gyn) , (h e V
~
12f RCDT Pumps ' tne AUTO position. Initzals INDEPENDENT VERIFICATION 12g Acceptance Criteria Satisfied YES/NO / Initial Date
** If negative, redo surveillance using Hand Calculation (No LCOAR required).
APPROVED O
,V- D-3 AUG 141909' 0793V/0068V/070889)
B.0.S.R.
1BOS 4.6.2.1.d.1 R3visies 2 REACTOR COOLANT SYSTD4 WATER INVENTORY BALANCE SURtEILLANCE G MANUAL CALCULATICE DATA SRECT
- () . .
DATE M 143 CCMPUTER PARAMETER POINTfS) USED INITIAL DATA FINAL DATA 1*/' 60,l 5#.*. ~" % S4 M 4.4 PZR Level .
- b. PER Temperature 70480 b61 M'0 M" 65t
- c. Allli b'. I 47.7 VCT Level LO112
- d. Total Flow Integrator None p T,' y 0
- e. Average Tave .UO484- % ,'I I ' ? ') i 69 ,"
L <'s n
- f. Hot Leg WR Temp 10419 (pt A ,$N $ 3 .' l Wg
'^
(N/A 1 530*T) 70439 .St 20459 ,n ,
~
.3: -
70479 "' .C
.*n' .
9 Cold Leg WR Temp 70406 S5Z T M' W* SS2i
. (N/A .t 530'T) 70426 I ~~~ ~
~
;rr c
'!O446 3' Ar -* ;
s' ;
"~ f
[ ,
-b. PRT Level 7046'6
'b'
". O LO485 3/ . 'l '
l e .
- 1. PRT Temperature 70485 ) i
' S S.) ' #3 $
56,6 erb :: C"
$$ f
- j. RCDT Level None. . n +- - ' ' ' *
' 's * > .
- k. TIME / INITIALS None O* C /W M'./ M I _ (co")
i
- APPROVED i
( . AUG 141989 (0793V/0068V/070889) .
~
- dB APPROVED isOs 4.6.2.1.d-1 Revision 2 B.O.S.R. nanuxL CAtcut.AT10w oxTA saEtT GROSS LEAEAGE RATE PARAMETERS :
r
. DO bo o
'! 6. APIB I % - PZR L i T %] a 128 gal /% = 0 91 g . 1 aic.t., . yoj o, locr... 3 1 vus. = (PIR L f_ LI7 7 47 9 Ca .71 b' ~~ %
- I gal (+ indicates a volume Increase)
- 7. AVCT = [VCT L g % - VCT L g %) s 19.3 gal /% =
O o o 0 (+ Indicates a volimme increase)
- 8. AK/U = TUIAL FLOW INT UD gal - TOTAL FLOW INT, W O gal = gal C3 W.') '5 M 7 ggg,7 Tave D S *r + Tave S'M *T Syy6 *r ( AVE RCS Tave)
- 9. Tave 1 530 *F r i =
?
2 *I < OR y j 20. Tave < 530*r TOTAL T = 70419 + 704 3 9 + 70459 + 70479 + T0406 + 70426 + 70446 + 10466
,. ,. ,. ,. ,. ,= ,
,, = ,. , .
l y' T 1= r. r. r. r. r. r. r. r= r Tave(f) = i = *F Tave(i) 1 = *rs l 8 8 i' i Ave RCS Tave = "'*f
* *1 = *F 2
~
0%
- 11. ap = I a(Tave g- Tave g) =(-) SO /M a i 41 M 'r) =M 3
(- Indicates-a
*F *F ft volume increase)
- O
- 12. AMC
- 10386.5 :t (4i OTO /ft ) -qy "
98
- n ca es a v le increase)
VOL = 8.2178 / gal w
~ --
J % l- 0 1905 4.6.2.1.d-1 Revision 2 MANUAL CALCULATION DATA SHEET GaOSE LEAEAGE MATE PARAMETERS Usz Giz 652
"** T * #** T
- 13. ave rza T =-
r 1 = bS3 6 *r 2 p Pza = /ft
'37.l(
GROSS LEAEAGE RATE CALCULATI(El (GLR) GIVENS Assume VCT and TOTAL FLOW water temperature of 100*F Assume aCDT density is constaat p VCT 4 62 /ft p Total TLow = 62 /ft . p re(erence = 62.31 /ft g , (AM/U n a pM/U)-(APza yg a prza) - (AvCT' yg pvCT) ,anc ygL 1g,, ,,31,,,, ATIME x p reference 4 TIME ATIuE c>.79 is t *r e, ou = ( gal 62 I "/ft )-( 3 O gal , - 1*/ft')-( ~ % I gal n 62 * /rt3) , * " gai i lo.s 9 1 I3 min s 62.31 /ft 9 w* c,"3 16 s q . .' ,Z ^I 3%1.e t O .% t},y , ' t a gal Ibn/ft3 - o gal Ibn/rt3 -
*;.7 gal Ibn/rt3 -
, i7 gpm i
- 7) gpm gg , __
pio,93 ' min Ibse,g 3 8741.1 GLa = "'l - gym 2 21 gym - APPROVED
,2S'T r ,53 AUG 141969 . . g mm --- B.O.S.R.
1BOS 4.6.2.1.d-1 Revision 2 MANUAL CALCULATION DATA SHEET 1DDITIFIED LEAKAGE R_ ATE CALC 11LATICR4 l O
- 15. APRT m ~
3 (PRTVOLf ' f VOLi
- i
'O APRT gg = ( '9"hI gal a ) - ( '0465 gal -
)
- 16. APRT g gg = 7 -c5 gal APRTgAgg
- 17. APRT a A TIME a p reference 71 eE gal Ib"/ft3 O min x 62.31 lbmfg,3
. a ll gal / min
- 18. ARCDT e RCDTyot g . RCDTyon 1 -
A TIME
-..o
; 5 gal -
-mi 5 S ' 3 . gal
' 'l min
= 9 gal / min
- 19. RCS Known Leakage a APRT (Step 17) + ARCDT (Step 18)
= '3 gal / min
- O 981/ min
= I gal / min APPROVED O .
aus i 4 i9se (0793V/0068V/080389) D-7
, _. ._ _ ~ - . -
IBOS 4.6.3.1.d-1 ' R3 vision 2 MANUAL CALCULATION DATA SHEET
,I 20. TOTAL IDENTIFIED LEAKACE RATE %) .
RCS KNOWN LEAR,Agg + TOTAL S/G 'nJEE LEAFAGE a TOTAL IDENTIFIED LEAKAGE
'l #
gym + gpm =
- O t gpm (1 10 gpm)
TtyrAL s/G Tunt f.r1KicE - (Primary to secondary leakage through all steam generators not isolated l O t gpd (1 1.0 gym) INDIVIDUAL s/C *EIBE LEAKAGE (Primary to secondary leakage through any one steam generators.) ; 6 # gpd (1 500 gpd or i .347 gpm) ;
- 21. UNIDENTIFIED LEAKAGE RATE CALCULATist(
(GROSS LEAKAGE) - TOTAL IDENTITIED LEAKAGE = UNIDENTIFIED LEAKAGE m ,,a , .c ,,m) - . e ,,a . u. D c ,,a , .r ,,m,, u 1 ,,m) l
- 22. RCDT Pumps in the AUTO. Initials M INDEPENDENT VERIT N '
\
! r *
- 23. Acceptance Criteria Satisfied YES/NO. MI / "W #' 0 !
Initial /Date O . ggIg .
\
- I Because of' instrument tolerances and inherent calcula. * !
- tional errors in estimating RCS gross leakage, a total
- p
- possible error of a 10.6 gallons has been used as a a i
- bounding value. The actual penalty in leakage rate in
- l
- terms of gym is dependent on the duration of the test. *
- For example: A 30 minute leakage test will result in a a
- tolerance of A 0.35 gym on both the gross and *
- unidentified leakage rate, whereas a 2 hour-test will
- l
*- result in a 1 0.09 gym tolerance. Hegative values of *
- unidentified leakage may result due to the above stated * ,
- errors and are acceptable provided they are less than or
- i
- equal to the tolerance value. Negative values for * >
a leakage in excess of the tolerance value require a rerun * .
- of the RCS leakage determination procedure and does not
- i
- constitute entry into an action requirement unlees the *
- time interval for this surveillance is exceeded. * -
- Excessive negative values for leakage may be due to *
- either 1)' Transient conditions in the RCS during the *
- 1eakage test, 2) Leakage from sources other than the RCS
- l
- Into the PRT & RCDT or 3) Inleakage into the CVCS *
- Charging or Letdown. * ;
.....................................................a..........
? APPROVED
\
(rinal)
. AUG 141989 ;
(0793V/0065V/070889 D-8 i B. O. S. R. I i 1
- . - _ ._a_m-' --
-c- e gm r .r 7 y y n gw y - - - , - - - w -wr<<
16C5 6.2.3.0-1 Itovision 6 REACTOR CONTAINMENT FAN COOLER MCMTRLY SURVE!LLANCE f k A. STATEMENT OF APPLIf*AEILITYr This procedure applies to the Mei.thly Verification of Reactor Containment ran Cooler Operability in Modes 1,-2, 3, and 4. B. REFERENCES 1
- 1. Technical Specification 3.6.2.3
- 2. Technical Specification 3.6.1.5
- 3. TSAR 9.4.8.1
- 4. LCOAR 1BOS 6.2.3-la
- 5. BOP SK-1
- 6. BOP VF-1
- 7. Station Comunitments
- a. 6-90-0079
) C. PREREGJIEITEE t i i A' 1. Receive permission from the Shift Engineer or designated SRO licensed bj assistant prior to performing this surveillance by having the Data j Package Cover Sheet signed and dated. D. PRECAUTICME .
- 1. ENSURE the containment air temperature is maintained within limits during the performance of this surveillance.
E. LIMITATIOEE AMD ACTI(Mai 4
- 1. As stated la Technical Specification Limiting Condition for Operation 3.6.2.3.
-2. Fans should be run in pairs; Fan IVP01CA with IVP01CC and IVP01CB with IVP01CD due to 5% or NO Line-ups.
- 3. In the event the Acceptnuce Criteria is not met during the i performance of this surveillance, IM(EDIATELY notify the Shift Engineer.to initiate LCOAR procedure 1905 6.2.3-la.
l 4. The SK System is flow balanced to provide required RCFC flow when two
- 1. SK Pps are running.
APPROVED Q- AUG 2 31990
,1,,
D.O.S.R. i: (1218v/0099V/082190) 5 I
1BOS 6.2.3.a.1 R3 vision 6 j
- 5. LOCALLY RECORD flow retos from th3 cyprspricto flow itdicators listod l on Data Sheet for the RCFC's started in step F.3, then log on Data 3 Sheet.
[ ) (__/ ..........................................................r.....
- HQIE *
- Each RCFC has two flow indicators that must be sunned to
- l
. attain total SK flow rate. .
- 6. SUN the actual flow rates for each RCFC started in step F.3, and LOG l total flow and VERITY 12660 gym on Data Sheet. ,
i'
- 7. RETURN the RCFC's started in step F.3 to the "As Found" position and log stop time on the Data Sheet.
- 8. ENTER the run time for the oppropriate RCFC and VERITY 215 on the
. Data Sheet.
- 9. REFEAT steps F.3 through F.8 for the remaining pair of RCFC's, if desired. .
i
- 10. RETURN 1A and 13 EK Pps to desired status and indicate position on Data Sheet. Independent verification is required.
- 11. RETURN RCFC's to desired position and indicate position on Data Sheet. Independent verification is requirwd.
G. ACCEPTANCE CRITERIAt ' 1. Each Reactor Containment ran Ccolor must' be started from the Control
, Room and operate for at least 15 minutes in low speed.
- 2. Essential service water flow rate must be greater than or equal to 2660 gym.
l APPROVED (Final) AUG 2 81990 B. O. S. R. l (1218v/0097V/082190)
IBOS 6.2.3.c-1 i Rovision 6 i
- 5. Operation of an-RCFC may affect the' associated RCP's temperature ,
sensitise seal cavity and allow the 02 Seal to open causing 41 Seal l' Leakoff Rate to decrease. The affected RCP may be operated under [ this condition with the following precautions.
\ ,
- a. Monitor for increased 42 Seal Leakage causing 42 Seal Leakoff Flow High Alarm, increased flow to the RCDT and possible RCP
- Standpipe Level Alarm. ;
t
- b. Monitor RCP bearing temperature. l l
- c. Consider switching RCFC's to verify cause of leakoff problem.
F. MAIN BODYr
....e. me.**............. ... ....ee.............. ne..........e e NCTTE
- li
- This surveillance may be performed as a partial *
- surveillance to prove operability of any component listed
- i
- on the data sheet. provided all Prerequisites, Precautions, *
- and Actions are verified and/or followed.
- j onen...eeeeeeeeeeeeeeeeeeeee...ee......eeeeeeeen........... .... ,.
- 1. RECORD the "As Found" position of the MCB C/S for all RCFC's, , ,
IVP01CA, B, C and D and SK Pps, 1EK01PA and 1SK01PB on Data Sheet. l t
- 2. VERITY / START 1A and 15 SK Pps per EOF EK-1
*, 7.a 1
D en.eeen....eeeen...een.aene eeeeen ee... .e**ene eeeen.. ....e.
- CAUTIGt a i f
*. ENSURE THE CGtTAINMENT AIR TEMPERATURE IS MAINTAINED WITHIN * ;
- LIMITS DURING THE PERFORMANCE OF THIS SURVEILLANCE * ,
sene.e eeeeeeeeeeeeeeeeeeeeeeeen neeeeeeeeeeeeeeeeeee***eeeeeee. ,
- 3. VERIFY / START'1VP01CA and IVP01CC or IVP01CB and IVP01CD in low speed !
per BOP VP-1. e...........eeeeeeeeeeeeeeeeeeeeeen.eamene.......ne nenneen..... , e gggg a
- Each Fan group must run in low speed for at least 15 minutes.* ,
en.....ee.........................e ..ee........................ g I
- 4. LOG the start time for the appropriate fans on Data Sheet.
f i I
?
APPROVED < 'vO AUG 2 81990 B.O.S.R. i (1218V/0099V/082190) l f
~
l ' APPROVED 1Bos 6.2.3..-1 Revision 6 b2 - REACTOR CONTAINMENT FAN COOLER MONTHLY SURVEILLANCE' B.O.S.R. (1) (10 and 11) . EOUIPM NT AS rrwann POSITICM F r ass r _ pagITICM OPre A*IDE ' IMITI AL INDEP mnENT VERITICATIM 1A RCFC HI SPenn g( [jO.J g( [A[ jfj IA RCFC ID SPern A7 A7 gg 1B RCFC HI SPern 4c [d) /C b'[ IB RCFC ID SPern 47 A7 6Uk ! 1C RCFC HI SPern AC hgd g( I//e[ IC RCFC ED SPern A7 A7 6A[ 1D RCFC HI SPern 4/ A7 6 1D RCrC iD SPenn 47 47 648 j 1A S1 PP b (~ ^ * % ;-,e / C. b 1B S1 PP NI II - (4) (7) (8) (5) (6) RCFC START STOP RGE TIME SK ACTUAL TOIAL SK TIME TIME 115 MIN FLOW INSTR FLOW (GPM) FIDW 12660 gpse 1A RCFC . 1FI KY122 (377* RO-161 3: .,/d , n'r < /c LO SPEED Cl13 6i N e W <. 1FI KY112 (377' RO-141 r e , 6// //w e/ t vis e 1C RCFC 1FI KY113 (401' RO-4) } 7cc a j f.,/j .- 3 fc/pm LO SPrrn fill eifd t t ek 1FI KY124 (377* RO-1) 1 F ~ '#* 'd ii5 e IB RCFC 1FI EY123 f401* RO-16) eg (,,/ 7 4,r y LO SPEED f 1# A1 C ' '/ N t v(t IFI-SX115'f377* RO1191 e ws t 1D RCFC , 1FI-SY121 (401* E0-71
- 37/f ppfg LO SPEED [ 'll1 C960 t #16 1FI KY125 i401* E0-101 e v75 e (Final)
(121BV/0099V/082190) -D2-
..__y i
1908 7.3.1 ! Revision 51A ; i CDipolGNT emm NATUt SYSTDI VAEVE , _V Q LINEUP TO SAFETY RELATED EQUIPMENT M3NTHL.T SURVEILIANCE A. STATDIENT OF_ APPLICARILITY: ; This procedure applies to the monthly verification of the valve lineups i' for the Component Cooling Mater System servicing safety related equipment in Modes 1, 2, 3 and 4. l B. REFERANCES: i
- 1. Technical Specification 3.7.3 l
- 2. BOP CC N-1 .
- 3. P & ID M-66, Component Cooling ]
i i C. PREREQUISITESt , i
- 1. Receive permission from the Shif t Engineer or his designated SRO licensed assistant prior to performing this surveillance by having i his sign the Data Package Cover Sheet signed and dated. [
P D. PRE:AUTIONSt 1 1._ Do not attempt to change any throttled valve position. Flow [
= indication may be used to verify valve position on throttle valves ,
. that have no position indication. This will prevent upsetting a previously established flow balance. ;
.- {
E. LDEITATICBIS AND ACTIGISt :
?
- 1. As stated in Technical Specification Limiting Condition for Operation t (140) 3.7.3 ;
- 2. In the event the Acceptance Criteria is not met during the performance of this surveillance, De(EDIATELY notify the Shift Engineer to initiate ICOhR 1908 7.3 .'La. ,
?
F. MhIN BODTt i[
................................................................ i
- NOTE .
- This surveillance may be performed as a pactial
'
- surveillance to prove oterability of any conecnent listed
- i l
- on the data sheet, provided all Prerequisites, Precautions * }
(
- and Actions are verified and/or followed. l I
- 1. RECORD Time and Date on all data sheets. [
- 2. PERFORM the valve position checklist by recording the actual valve j position on the data sheet. ;
^""aoveo i
O (2651P) 4 DEC 111987 i l B.O.S.R. l l i.
- - - . - - -. ..--. ~ - . . __ .-
1306 7.3.1-1 [ Revicion 51A ! i
- Wort *
- Proper Flow Indication will be used to verify proper valve *
...P.osition for throttled valves 10C9506A and 10C9474A
............................................................ p
- 3. rnstv VERIFY the flow rate for the valves listed on data sheet ;
(D-4) and record in the appropriate section. Q. ACCEPrANCE OtITERIA: f i
- 1. All valves should be in the required position as listed on the data !
sheets.
- 2. All Flow rates should be within the required F3ow rate tolerances as listed on the data sheets.
7 l f O e I l i 1 g APPROVED v crin.1) DEC11 ss7 (2651P/0180p) B.O.S.R.
. m ,,-.-e*,e.c. v wrmn+-- *w**--*-1T- *-*"-"*N"WW8' "E*
O O O , IBOS 7.3.1-1 Revision 51A CEBEO Wfr tvrrJun 3TET M t j VALVE LIIEUP TO SAFEff a'M AT E EQUIPIWff l IIDIfrIE.Y SIMPElfJM l DATA WEEE
- 1. TIRE: CifT DhTE: T-// 'I/ ,
ACTR L
- CEEWOIWf1 REQUIRE
- 2. seu numrmrPrrou tocaTras pos m 0N POBmW g I
i ICC95065 1A M Pp CC Inlet Isol N/4 V1v, + 3' 343' U12 RIB 1 0 FBI d l
- I 10C0034 1A El PP CC Outlet - t l 1FIS-446 EA Side Isol viv. +17' 364' U16 AB OPBf N/4 d
- Iccessc 1A IEE Pp OC Outlet .
' 1FIS-446 MI Side Isol Viv. +17' 364' U16 AB OPBf f/ /A d I 10C9504A IEI HK 1A CC Inlet Isol V1v, +14' 364' 516 AB 0 FBI o FE -) i i
i 10C9507A 1A NE HK Otstlet Butterfly TimDffLB 1 VI,+ 12' 364' S16 AB 35% OPBf YOh d i> ICC9412A MDW CC to Mt EK 1A Isol **CIESED V1v +12' 364' 316 AB ***0PBf C/C 5 E O d f 1A IEE MK OC Rtra leer. . i, ICC0954 ' !l 1FT-689 Ni Side Isol Viv. + 7' 364' P17 AB OPBf //4 d loc 09ss 1A mi uK oC mera nec :
- v/,4 To 1FT-439 to Side Isol V1v. +7 364' P17 AB QPBf d .l i
I ; l ** Applicable when ist is not in operation !
! *** App 11emble when 158 is in operation !
I i i i APPROVED j (2651P/0180F) -D2- N 1 l' W 3.O.S.R. t + ,- -- y
O O IBCS 7.3.1-1 O Revision 51A B TRAIN RH
- 1. TIE 2: ice t DATE: 9-IPl! .
ACIUAL CCBtPWINT RBQUIRED ILCATIN POSITI(Et POSITICN
- 2. EPW DESCRIPTIN ICC9474B IB RH Pp CC Inlet FCV, v/4 d J43 X12 RKB1 OPEN
+6' ICC0838 15 RH Pp CX: Outlet JM g 1FIS-667 to Side Isol Viv. +13'
- 364' U17 AB OPEN 10CD83D IB RH PP CC Outlet 04 g To IFIS-647 Hi Side Isol V1v. +13' 364' U17 AB OPEN ICC9504B 1B RH HX CC Inlet Isol V1v. + 12' 364' V17 AB OPEN c/fd d THROTTLED >
IB RH HK Outlet Butterfly V1v. + 12' ICC9507B 364' V17 AB 20% OPEN b' 4' (
** CLOSED 10C94125 NOV CC TO RH HK IB Isol Viv, + 12 ***OPEN C tesEd g 364' V17 AB ICC085A IB NH HK OC Rtra Hde OPEN a b4 g IFT-688, Hi Side Isol Viv. + 12' 364' U17 AB ICX 385B IB RH HK OC Rtra Mar OPEN N// g 1FT-688, Hi Side Isol Viv. + 12' 364' U17 AB ICX:945E (%1 Pp Dsch Hde Isol OPEN C FEM g V19, +10' 364' L17 AB ICC9459A CX! Pp Suct Hde Xtie OPEN Offd g viv, +8' 364' N18 AB ICC9459B CX: Pp Suct Hdr Itie Isol 364' L17 AB #4 OPEN c /'/1/ g Viv, +8' ICC9467A CC HK Doch Hdr Men Xtie Isol ,
364' N15 AB OPEN 0/Yd g V1v,_+9' CC HK Doch Hde Man Etie Isol o fL/ g ICC94678 364' M16 AB ## OPEN Viv, +9' ICC9467C CC HK Sup Hde Xtle Isol OPEN o /E d g V1v, +10' 364' L17 AB ICC9473A MOV CC Pp Doch Hdr Xtie 364' L17 AB 94 OPEN r ITN g V1v, +10' 10C9473B MOV CC Pp Doch Hor Xtie 364' L18 AB ## OPEN cf'D) g
! Viv, +10'
** CLOSED: applicable when RH is not in operation APPROVED
***OPEN: applicable when RH is in operation
#4These U-1 valves are normally Open, while the analogous U-2 gjjg valvss are Administratively OOS. IF these valves are not in the required position, the S.E. arhould evaluate for CC Operability. B. O. & R.
-D3-(2651P/01?'sP) l
O . O O 13013 7.3.1-1 Itevielem 51A Cl39Geff mrm ggGM SYSTM VALVE LIHWP TO SAPErY EEATED E@i!Plmff mairrnLY EunvEItuscs DATA BBET
- 1. TIM: /f 01 DhTE: 9-17-N .
CN T m POS W EED (3) ACTUAL FLOK ' IM5T. !
- 3. EPH meinNYPTIGr FEml ytgL nm ytDWWE (GRI) FT4lf RATE (GPN) 1557. LOCATIGt 1A M PP C1g Ute 11L81JA ICC9506A Outlet FCV 1/4 TINBf 6.0 to 9.0 g d 1FIS-446 364' Q-17 l la M Pp C1g Htr IPL81JB ICC9474A Outlet FCV 1/4 TUIBf 6.0 to 9.0 h d IFIS-647 364' 8-17 l i
e (Finst) APPROVEET
-o._ DEC11 r387 (2651P/0180P) g_
1BOS 7.3.2.c-1 l Revision 51A COMP 0KDIT COOLING WATER PUMP p OPERABILITY MONTEY SURVEILLANCE O A. STATDENT OF APPLICABILITY: This procedure applied to the monthly verification of the operability of the component cooling pumpe. B. REFERJ:NCES t
- 1. Technical Specifications 3.7.3 & 4.7.3.2A
- 2. BOP CC-2(9), BOP CC-15(10), BOP CC-El and BOP CX:-M1
- 3. P & ID M-66 Component Cooling C. W.u.vJISITE2S
- 1. Receive permission froe the Shift Engineer or' designated SRO licensed assistant prior to performing this surveillance by having the Data Package Cover Sheet signed and dated.
- 2. Ensure BOP CC-M1 has been completed.
D. PRECAUTION 3:
- 1. Ensure the CC surge tank is within its normal operating level. (35%
to 65%).
- 2. Taking a control switch from the Pull-to-lock position can auto-start the pumps due to low system pressure.
- 3. Use applicable procedures when starting, stopping or swapping pumps.
E. LIMITATICBIS AND ACTIONS:
- 1. As stated in Technical Specifications Limiting Condition for Operation 3.7.3.
- 2. In the event the Acceptance Criteria is not met during the performance of this procedure DMEDIATELY notify the Shift Engineer to initiate 140AR 1BOS 7.3-la. -
F. MAIN BODY:
. yyrE *
- Initial each step in the space provided adjacent to the *
- Main Body step number AFTER the step has been SUCCESS 7VLLT *
- completed. Persons performing INDEPENDENT VERITICATICBI *
- abould initial in the space provided below the 'tep. *
......................................e.........................
O -s ^"eaov"o (5182P/0303P) DEC i1 W B. O. S. R.
1806 7.3.2.c-1 Revision 51A e......................e**e..................................s .
*
- NOTE
- p o Q
- In order to verify the operability of a component / system the Shift Engineer may elect to perfom individual steps *
- of this proceure provided all Prerequisites, Precautions
- and Limitations and Actions are observed.
- e ee....... eeeeee **e ...eeeeeeeeeeeeeeeeeeeeeee****eneme*** e
- 1. DrrDt the date and time.
DATE J-/M/ TIME ef71
- E7FE *
- The start time for a running pump shall be the time when *
- the surveillance is started.
..............................a eee *eeeeee.....................
t 04 2. ENTER the start time for each running pump on CC pump Data Chart. 3c -;n Sh/' 3. INTER data for each running psamp(s) in the Data Chart after 14-hours from the time recorded in step F.2.
.......................e**e..........e******e .................e
- R7tE *
- If-necesrary to swap pumps than refer to BOP CC-15.
- e*****eeeen..........................................eeen neeee.
7c u hJ h*h 4. RUN each non-operating pump for t-4-hours and record data w Data Chart. CC PLMP DATA CHARI 0:: PUMPS 1CC01PA 1CC01PB OCC01P kf0UIRED DATA
" (517 c r, f4 / c *(4
"#A M CURRET t/f- eff gf i 50 AMPS 85 System 150 PUNP DSCE PRESS /32 /3) /3/ peig ( Pressure < psig HX CUTLET TEMP 7[ t gg ( 7f g < 118'F N/A
( fl 69 / c 49 / / '/ 7
" " " OA
- se -.s
- ce .s
- sD:[ I ..,, . . A t. /c n-,, r: . .t n s u 1.L C C. pp c.
,p g ,hes ;.,y remfp
- 5. e s, *. - r* , fra. . n //
f5- *, fr.S ' / r e ... H.l,t y L,lt' y ;,,,, - APPROVED DEC1i sB7 (5182P/0303P) B. O. S. R.
1806 7.3.3.o-1 Revision 51A
- . 5. VERIFY 2 CC pumps will auto-start on an ESF actuation ;
A V a. Initial the OPERABLE CC pump on Div. 11 34 [ 1A CC pump racked in to BUS 141 and E in Pull-out ca..
^/ ' 0 CC pump racked is to BUS 141 and E in Pull-out and 1A l CC pump in Pull-out. ?
IMDEPENDENT VERIFICATICM + /-/
- b. Initial the OPERABLE CC pump on Div. 12: '
jd 1B CC pump racked in to BUS 142 and E in Pull-out. .
-CR- i i
eM 0 CC pump racked in to BUS 142 and NOT in Pull-out and 1B CC pump in Pull-out. INDEPENDENT *VERIFICATI(3f ,./W
$t d c. VERIFY one CC pump OPERABLE on each Div. in F.5.a and F.5.b -{
above. . n G. ACCEPTANCE CRITERIA:
- 1. At least two component cooling water pumps shall be demonstrated ;
operable by verifyino that each pump starts upon actuation, operates , for at least four he*rs, . satisfies the cooling requirements for the ; routine operation of the composant cooling water system, and is i capable of auto-starting on an EEF actuation. l
...................................a........e........e.......... ;
E
- k
- If a CC pump is running then it shall be laylied that the >
- pump has started upon actuation.
- l
- (Final) APPROVED i DEC 111987 (5182P/0303P) ;
_ B.O.S.R.
- - - - ~ . . . . , , _
.m ..........
Revision 2 UNIT CNE 1 A DIESEL GENERATOR OPERABILITY MONTHLY (STAGGERED) AND SEMI-ANNUAL (STAGGERED) SURVEILLANCE O A. STATEMrNT OF APPLICABILIII
- 1. This procedure outlines the steps necessary to verify, for Unit 1.
the OPERABILITY of the 1A Diesel Generator. This Unit 1 requirement is applicable when Unit 1 is in Modes 1-6.
- 2. Also verified, f or Unit 2, the EApAhillLy of the 1A Diesel Generator to be crosatied to Bus 241 (HnL actually crosstled). This Unit 2 requirement is applicable prior to entry into and during Unit 2 operation in Modes 1, 2 and 3.
ene neameneseneeeeeeeeeeeeeeeeeeeee**eneeeeeeeeeeeeeeeeeeeen. .. e ggIg e e It Unit 1 is in Modes 5 or 6, only one Diesel Generator is *
- required to be OPERABLE for Unit 1. If the 1A Diesel e Generator is inoperable, then ensure the 18 Diesel a e
- Generator is OPERABLE.
e *eneeeeeeeeeeeeeeeeeeeeeemanneameneeseeeeeeeeeeeeeeeeeeeeeeeen eenene................. eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen.
- tiCIK .
- Inoperability of the 1A Diesel Generator may impact Unit 2 *
- operations if Unit 2 is in or entering Modes 1. 2 c 3. *
- The impact of the 1A Diesel Generator inoperability snust *
-
- be evaluated by the Shift Engineer.
- ene.....noneseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene B. REFERTNCES ,
- 1. Cooper Bessemer KSV Diesel Generator Instruction Manuals Vol 1 & 2.
- 2. NRC Regulatory Guide 1.108.
- 3. Technical Specifications:
- a. Lisoiting Conditions for Operation (LCO's):
- 1) 3.8.1.1.b - AC Electrical Power Sources - Operating
- 2) 3.8.1.2.b - AC Electrical Power Sources - Shutdown
- b. Surveillance Eequirements:
- 1) 4.8.1.1.2.a. 3) 4.8.1.1.2.c.
- 2) 4.8.1.1.2.b. 4) 4.8.1.1.2.1.2.
APPROV [D0RREFE DEC 1 e 1969 9 (1178V/0095V/120289) _1 gggg
ansd 6.4.A 4.a-a Rovision 2
- 4. Statloa Proccourost
- a. BOP DG-11, Diesel Generator Startup.
- b. BOP DG-1171, Diesel Generator Start /Stop Log.
- c. BOP DG-1172, Diesel Generator Operating Log.
- d. BOP DG-12, Diesel Generator Shutdown.
- e. DOP DC-13, Trouble-Shooting Diesel Generators.
- f. 1BOS 3.2.1-806, Unit One ESFAS Instrumentation Slave Relay Surveillance - Train A Auto SI - K611.
- g. 180S 8.1.1.2.a-2, Unit One 18 Diesel Generator Operability Monthly (Staggered) rnd Semi-Annual (Staggered) Surveillance.
h, 2BOS 8.1.1.2.j-1, Bus 141 to 241 Crosstle 18 Month Surveillance.
- 1. 1BOS 8.1.1-16, LCOAR - AC Sources - Operating.
- j. IBOS 8.1.2-la, LCOAR - AC Sources - Shutdown.
- k. 2BOS 8.1.1-la, LCOAR - AC Sources - Operating.
- 5. US NRC Inspection Report 50-456/86052; 50-457/86040 (Braidwood) dated 12 Nov 1986 (Enclosure 2, item 2.0).
- 6. Station Commit 7ents:
r
- a. 6-87-046
- b. 6-87-056 .
- c. 6-87-019 C. PREREQUISITES
- 1. Receive permission from the Shif t Engineer or designated SRO licensed assistant prior to performing this surveillance by having the Data Package Cover Sheet signed and dated.
- 2. All Diesal Generator protective trips should be in force during Diesel Generator unit testing.
l
- 3. Request and sign out an accuracy checked stopwatch from the '
Shift Engineer or designee.
- 4. The operator shall have available a blank Diesel Generator Start /Stop Log (BOP DG-1171) and Diesel Generator Operating Log (BOP DG-1172) when performing this surveillance.
APPROVED l DEC 161989
-2 (1178V/0095V/120289) Eg,(),g,lg, l
. , . . . .~ ~ - . _ _ . - .- --
seva_o.s.s.s.a.s-tsvision te D.- PHCAUTICBIE
- 1. The Diesel Generator will Auto Start if an emergency signal is -
received.
't b -2. -If the pressure drop across the full-flow Lubricating 011 filter reaches _ M-psi, the elements must be replaced before further operation of the Diesel.
3._ Ear protection should be worn by personnel in the Diesel Generator Room during Diesel operation.
- 4. An operator'shall be stationed in the Diesel Generator Room whenever the. Diesel'is started lfor testing. _
.5. Do not start or continue to operate the Diesel if the Diesel Generator Room temperature escoeds 122'F.
- 6. Do not escoed Diesel Generator rating of_ HM KW or HH amps load for greater than 2 hours.
- 7. -Operate only 13lT. Emergency Diesel Generator per_ Unit.in parallel with offsite power _at-any_one time. This will prevent damage to more than one Diesel Generator per Unit if a fault condition develops on the grid.
-8. In order to prevent Isochronous Operation when a Diesel Generator-is in the Emergency Mode and paralleled to the grid, DO NOT return the
~
L Emergency Mode Speed Voltage Control Switch to AUTO if it is
-currently in the MANUAL EMERGENCY position.
9.- Do not crosstie the 1A Diesel Generator to sus 241 unless also j'_ performing 2308 8.1.1.2.j-1 (Bus 141 to 241 crosstle 18 month surveillance) in conjunction with this procedure. .
.E. LIMITATIGt5 AND ACTICEIS I
1.' As stated in Technical Specifications Limiting Condition for
- Operation-(LCO) 3.8.1.1 and 3.8.1.2. _
l 2. The Tech Spec requirement for the Diesel to start from ambient and L- accelerate to at least AM RPM in less L than or ' equal to M seconde L shall be considered ~ met if' frequency escoeds R Es within M seconds. l 3. -The routincly scheduled Monthly and Semi-Amaual portions of this ' ! surveillance each Ahall be perftsraed on a Staggered Test Basis with 1805 0.1.1.2.a-2. i' 4. Vetrify/ Maintain at least H percent fuel oil level in the Diesel Fuel
- l. Oil Storage Tanks during'the Diessi Generator run'(unless the DG is h a ready INOPERABLE).
f-APPROVED DEC 1 - 81969
-(1178V/0095V/120289) .B.O.S.R. -
Ausa e.6 4...a . 8;visies 2
- 5. In th) ov0ct th) Acecptesco Critoric (W) is ist m3t durlag :
performance of this surveillmace, IMMED157ELY notify the Shift ' Enginser or designee to initiate LCOAR 1BOS 8.1.1-la if in Modes 1 4 or LCOAR 1BOS 8.1.2-la if in Modes 5 6. (' ' ' i
- 6. Inoperability of the 1A Diesel Generator may impact Unit 2 operations if Unit 2 is in nr entering Modes 1, 2 or 3. The impact of the 1A Diesel Generator inoperability must be evaluated by the Sh!ft Engineer. !
- 7. If this surveillance or a portion of this surveillance is performed for purposes other than scheduled testing, NO CREDIT shall be taken for its performance on .the surveillance schedule. The Shift Engineer or designee shall designate those portions to be performed.
Notaticas should be entered in the comments section of the Data Package Cover Sheet containing the reason for performing the i surveillance. ; L F. HAIN BODI 1 one.nene.. ..eeenne eeeeeeee..eeneeeeeeeeeeeeeeeeeeeeeeeeeeeeeen j e ggIg a
- Initial each step in the SPACE provided adjacent to the *
[
- procedure step number ATTER the stop has been SUCCESSH!LLI
- t a completed. Person (s) performing INDEPENDENT VER1r1 CATION e *
- shall initial in the space provided af ter the step. * ,
eeneneeeeeee..........eeeeeeeeeeeeeeeeeeeen.eeeeeeeeeeeeeeeee... ; r.0 Subsections F.1, T.4, r.7 F.8, T.9 and T.10 must always be perf ormed sequentially. Parallel Subsections T.2/r.3 and T.5/r.6 are
~
[ r- s independent of one another so that either subsection may be i ( pe r f o rmed. Only one of each parallel subssction may be perforned. ; The Shift Engineer or designee shall designate which subsections shall be performed (Normally shown on the Surveillance Schedule). .
...eeeeeeee.eeeeeeeeeee.eeeeeeeeeeeeeeeeeeeeeeeeeeemene.een.een. ;
- NOTE *
- Sequential performance of the required Subsections and the * *
- following parallel Subsections provides * ,
*
- T . 2 and F . 5 *
- Manual local start and gradual loading. * !
- e F.3 and T.5 *
- Auto start from EST and gradual loading. *
- e F.2 and T.6 * !
- Manual local start and i in ese loading. *
* . F . 3 and - F . 6 *
- Auto start from EST and i in see loading. *
.......... .... ......... ..... .ee..... eee.ne.eeee.nen.eenen.. .
f APPROVED . Of;C 161969 : (. ~4- p
\m (1178V/0095V/120289) gg,(),g(pg,
suso s.s.s.s.e.s R;visios 2 T.0 SIARI llLl Initial Conditions I I Auto Start from Manual Local l,. Ll llLl , EST (2BOS 2.2.1-806) Stert (BOP DG-11) 'N (Quatterly)
'n-; s- '
llLl Intermediate Conditions and verifications p. Load to t,11QQ RW Lodd to 1 51Q2 RW (Gradual) llLl llLl / '(within AQ seconds). (Monthly) (Semi-Annually) y-llLl Crosstle capability Verification l1Ll Fuel Oil TransCer Operability llLl One Bour Loaded Run and Shutdown t s l l' ' ll1Ql Final Conditions END F.1 Initini conditions
- a. RECORD the.f0110 wings [$@3 DATEl fj W)h TIME:
""/-A W/P*
9 MODE: l
- b. RECORD the following for the stepwatch:
Inst QA la Calibration date l
- c. RECORD the Diesel Tuel Oil Day Tank level f rom ILI-DOO35:
i d' % (2 li 18)- l> l APPROVED DEC 181969 0 -5 \ ( (1178V/0095V/120289) B. O. S. R. l
save o.s...... . R3 vision 3 F.1 ene ne neeeeeen... eeeeeeenneeseeenneeeeeeeeeeeeeeeeeeeeeeeeeee. e ggg e
- Verity / Maintain at least 25 percent fuel oil level in the
- O
- Diesel ruel Oil Storage Tanks during the Diecal Generator
- run (unless the DG is already INOPERABLE).
e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene .....
- d. Calculate the total fuel oil in the Diesel fuel Oil Storage Tanks in the following manner ( Acceptance Criteria (t) N/A if the 1A DG is already IHOPERAt:LE):
~~
- 1) RECORD 1A DG TO Sto Tk 1A Level from 1LI-DOOO1A __ %.
s1
- 2) RECORD 1A DG TO Sto Tk 1C Level from ILI-DOO21A %.
- 3) ADD both tank levels and RECORD totals ~~__ %.
- 4) DIVIDE total by 2 and RECORD results: W
~~
(1 2341 f il) F.2 ganumi Local Start (BOP DC 11) neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee***enee a ugg e
- Prior to starting the Diesel, ensure a stopwatch is *
'N .
- available to record the time it takes for the Diesel to *
- reach > 1229 volts.
- a+eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemene A
- a. RECORD the DG Right & Lef t Bank A.ir Receiver air pressures at 7'
( 1PLD7J
- 1) Riq1t Ba.ga psig -
- 2) Left Banks psig *. 6.a
- b. VERITY / PLACE the DG 1A ACB 1413 Auto ,Teclose Circuit Arm ,
Selector Switch in the SURV TEST position at IPM01J. *, 6.c
- c. Locally at IPLO7J, START the Diesel per BOP DG-11.
- d. At the same time the Diesel is started, START the stopwatch. As soon as the Diesel reaches > iaQ2 volts, STOP the stopwatch and then basediately verify 1 192 RPM and f requency between ital to 1121 Br. *. 6.b APPROVED DEC 161969
\ (1170V/0095V/120289) [3,(),g3,pg, 1
1905 4.1.1.2 0 1
-R:vleles 2 r.3 Ag!,o._stae(f rom nr naos 1.2.1-anal [U ,(,N < ..eeeeeeen,- .....,seeeeeeeeeeeeeeeeeeeeeeee...eeeeeeeeeeee......
- cAUT10s a
(
- 1905 3.2.1 806 WILL ENERGIZE SLAVE RELAY R611 WHICH W!t.1,
- S'AART DIEEEL GENERATOR 1 A IN THE D(ERGDICY MODE. UNTIL e
* .l
- THE DC IS SELECTED TO W4fUAL IN 1906 3.2.1 006, ALL NORMAL
- e PRCrTECTIVE FEATVtts ARE BYFASSED. !r ARMORMAL CC3fD1710NS *
- ARISE, STOP THE DC USING THE EMEAGDICY STOP PUSHbUTTCDI AT *
- 1PLO7J.
- I ennee.e.eeeeeeeeee.. .een.een.ee .e eeeeeeeeen.eeeeeeeeeeeeeenne l l
e e ......... ente.......eeeeeen.e..............................
. grIg a !
- Pric, to starting the Diesel, ensure a stopwatch is *
- available to record the time it takes for the Diesel to * <
a . reach a 19A0 volts. *
.....eeeeeeeeeeen eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenen t
- a. RECORD the DG Right & Lef t Bank Air Receiver alt pressures at l kPLO7Je
- 1) Right Banke psig i
- 2) Left Banks - Psig *, 6.a
- b. VERITY / PLACE the DG 1A ACB 1413 Auto Reclose Circuit Arie
(' 8 elector. Switch in the SURV TEST position at 1P9001J. *, 6.c '
- c. START the 1A Diesel Generator per 1906 3.2.1 806.
f.'. d. At the same time the Test Switch 5834 is depressed in 1905 3.2.1-006 to start the Diesel, START the stopwateb. As soon as .-
/wYp geK,. the Diesel senches > 10.09 volts, STOP the stopwatch and thea 4 i isseedthtely verify 110A RPM and frequency between iLA to ;
11d Es. *. 6.b . 4, Inta tue diata conditlh ag(_Vatificatlema eneseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene ...eeeeeen .....een
. 5Q25
- 1
- Monitor the Diosel for abnormal conditione. If trouble
- i
- occurs, refer to 90P' DG-13 or the appropriate BAR.
- eeeeeeeeeeeeeeeenneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen l-
- a. !M(EDIATELY RECORD the DG Right & Lef t Bank Air Receiver air <
- . pressures at 1FLO7J and VER!rY a pressyre decrease f rom the <
l value recorded in 6teps T.2.s or F.3.a as applicable: 1
- 1) Right Banks psig
- 2) Le t t ' Bank s psig ;
^
- 3) Pressure decrease verifled in both Air Receivers. *, 6.a
. . APPROVED I
(117eV/00:5V/12cres) I B.O.S.R.
eewe e.......s . R3visies 2 r.4 e' b. VERIFT 1A and/or 1C f uel 011 Transf er Pump STARTfD. t c. RECORD the following datet
- 1) fra the stopwatch.
time for the DC to reach 4 cc .
> 10s.Q voltet j5 f Y sec (i 19)
- 2) D0 running RPM W b RPM (igt to 112)
- 3) D0 runnlag voltaget /,4 "db dl 90 V (1110 to 1110)
- 4) DO running frequency: 608< WS us ( st. to in.2)
~
- d. . UPDATE DOP DO-1171. Diesel Cenerator start Stop Log.
" e. VERIFT/ PLACE the DG 1A Control hade Selector Switch la the RD40TE polition at 1PLO7J.
^
5 kgAd to 1 5100 W lqta$nall eeementeneseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene MQIE *
- erste the Diesel Generator for approslantely 1 minutes e *
- betore loading. When perfotining t.he following stop, the *
- Diosa Generator should be loaded gradually to reduce
- e therma stresses in the cy11oder heads. When lacreating e
- load frogg RW to 1100 RW, the load should be app 11od in
- O
- 1992 RW steps over a period of 1 to i minutes.
seeeeeeeeeeeeeeeeneseeeeeeeeeees!. eeeeeeeeeseseeeeeeeeeeeeeeeese a l a.
. \ .
Request that the M80 synchronise the Diesel Generator to its associated ESF has and gradually load it to 1 1190 KW as per DOP DG 11. \N N
- b. When the Diesel Generator output reaches 1 1102 RW, RECORD the followings \
\
Clock time when the Diesel Gentsstor cutput i 1100 RW8 \ t, T.6 Load to 1 5500 Itw (within so seconAal enenseensneeeeeeeeeeeeeeeeeeeneseeeeee*esenneeeeeeeeeeeeeeeeeene a gggg- .
- _ Before synchronising the Diesel Generator to its associated
- 1
- _EST bus, have o stopwatch ready to~ measure the time it *'
- takes to reach 2 liQD RW. a eeeeeeeeeeeeemeneneseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenenseeeeeenen APPROVED DEC 161969 B.. O. S. R.
(1178V/0095V/120289) k ..
4ew, e.......... R3 vision 2 f.6
....eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen......
e ucIg e
- When loading the DC to 1 5500 KW in 1 60 seconds. utilise .
- as much of the 60 seconds er possible to minimise stress e Os e on the engine and turbocharger. e eeeeeeeeeeeeeeeeeeeeeeemeneewoneeeeeeeeeeeeeeeen.......... .....
- a. Pequest tnst the NSO synchronise the Diesel Generator to its associated EST bus and load it to 111aD KW as per BOP DG-11.
When closing the 'steaker, OBSERVE and PERTORM the f ollowing ON 1) At the svae time the Diesel Generator Output Br0aker is closed, $7 ART the stopwatch. E' '/ N'
- 2) LOAD the Diesel Generator to 1112D KW per BOP DG-11 within 10 seconds.
f,[:F 3) When the Diesel Generator output reaches 1 ilDD KW, STOP the stopwatch and RECORD Lhe followings a) Tine it,took for the Diesel Generator to loads t MT see (1 AQ) b) Clock time when thg. Diesel Generator output i liQD ItWe C9 hl' , r.7 Crosstle capability Verifica*,1ga eeeeeeeeeens............. ...................................... e ggg a tO
- Steps T.7.a and T.7.b mu11 be perforned independently of
- each other. .
- a. Cycle ACB 1414 as follows:
- 1) VERITY /OFEN ACB 1411.
- 2) Turn OH the synchscope for Div 11 EST bus crosstle breaker ACB 1414.
t 3) CLOSE Div 11 EST bus crosatie breaker ACB 1414.
- 4) OPEN Div 11 EST bus crosstle breaker ACB 1414.
k INDEPENDENT VERIr! CATION
- 5) Turn Orr the synchscope for Div 11 EST bus crosstle breaker ACB 1414.
APPROVED DEC 161989 () (1178V/0095V/120289)
'~
El.C).si,pt,
1606 s.1.1.2.a.1 Revision 2 r.7 l b. Cycle ACB 2414 as f 0110wsi
- 1) VER1rY/OPEH ACB 2411.
2) Turn Cri the synchscope for Div 21 EST bus crosstie breaker ACB 2414. t_ 3) CLOSE Div 21 EST bus crosstle breater ACB 2414.
- 4) OPEH Div 21 EST bus crosette breaker ACB 2414.
INDEPDIDENT VERITICATICH 5) Turn Orr the synchscope for Div 21 ESr bus crosstle breaker ACB 2414. r.8 f.ggl,2rangler Pump Onerabi11tv VerifIeaLinn eneeenoeseeeeeeeeeeeeeeeeeeeeeeeemeneseeeeeeeeeeee gtgIy, e e
- a Step r.8.a and b verlfles that the ruel Oil Transfer F m ps e
- transfer fuel frors the oli storage tanks to the day tank. *
- This step should be started shortly after the DG is fully * .
- loaded. Both transf er pumps should be tested, however, If a *
- only one transfer pump is Insultad to be OPERABLE.
- a transf er pump is Out-of-Service, mark the step f or testing *
- it H/A.
ene......eemenee...e eeeemene ne ne ...eeenemoneensenese
- a. VERITY 1A ruel Oil Transfer Pump Aaintains Day Tank level.
VERITY / PLACE 1A Tuol Oil Transfer Purnp to the AUTO posicion. 1) 2) VER1rY/ PLACE 1C ruel Oil Transf er Pump to the Orr position.
- 3) VERITY Day Tank level is maintained for 15 rainutes.
(__
- 4) PLACE IC ruel Oil Transfer f> ump to the AUTO position.
b. VER1rT 1C ruel Oil Transf er Pump maintains Day Tank level. VER1rY/ PLACE 1C ruel Oil Transf er Pump to the AUTO position. 1) l VERITY / PLACE 1A fuel Oil Transfer Purnp to the Orr position. 2)
- 3) VER1rf Day Tank level is maintained for 16 minutes.
t __ 4) PLACE 1A fuel Oil Transfer Pump to the AUTO positlon. 4 APPROVED DEC 161969 B. O. S. R. h (lu sv/consv/120:se) j
&bph b.&e4.d.a.A R0visloc 2 f.9 ene Hour tended agg_and shutdown eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen p
- 11 2 I 1 *
- The Diesel Generator must be maintained at 1112D KW for *
()
- the duration of the test (1 12 mins). H0HITOR CLOSELY and * '
- ADJUST KW output to maintain i 1190 KW. e seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenneeeeeeeeeeeeeeeeeeee
- a. After the Diesel Generator has run loaded at 1 112D rw for 1 10 minutes, SHUTDOWN the Diesel Generator per BOP DG-12 and i RECORD the f ollowing data:
- 1) Clock time KN output c 1120 KW
- 2) Clock time KW output A 11DD KW f rom step r.5.b. or step r.6.a.3)b) as applicablet
- 3) Total time KW output 1 1120 KWI f min (1 AD) r.10 Elmal conditions
- a. VERIFY / PLACE the DG 1A ACB 1413 Auto Reclose Circuit Arm Selector Switch in the NORM position at IPM01J.
INDEPENDENT VERITICATION I
- b. Af ter the Diesel Generator is shutdown and the cooldown cycle is ,
complete ALIGN he Diesel Generator for standby operation by (Ng performing the following: '
\-_/
i t 1)' VERITY the " UNIT AVAILABLE TOR EMERGENCY" Immp is lit.
. I t 2) VERIFT all 4 DC Power indicators are lit.
t 3) VERITY / PLACE the DG 1A Control Mode Selector Switch in the
- REMOTE position at 1PLO7J. !
I INDEPENDENT VERITICATION ; t
- 4) REMOVE the key and return it to the Shift Engineer or l designee. !
t 5) VERITY all the local annunciators are not lit. If any annunciator is lit. NOT!rY the Shif t Engineer or designee for evaluation and RECORD lit annunciators. f APPROVED l DEC 181969 - l 11 l (117eV/0095V/1202e9) II' C)* !5' II'
4 ewe 6.......a.. R3 vision 2 r.10.b LOCAL ANNUNCIAM RS LIT + EVALUATED ACCEPTABLE: SE or designee r 6) VERITY the Diesel Generator Output Breaker in AFTER TRIP. INDEFENDDf7 VERIr!CATIC38
- c. VERIFT/ PLACE 1A Tuol 011 Transf er Pump in the AUTO position.
INDEFENDENT VERIT! CATION _
- d. VER!rf/ PLACE 1C Fuel Oil Transfer Pump in t.he AUM position.
INDEFENDDff VERIFICATION
- e. RECORD the Diesel fuel 011 Day Tank level f rom 1LI-DOO3$s , ,
t t _ %(11500) INDEPENDENT VERITICATION
- f. TILL the 1A DC fuel Oil Storage Tanks, as necessary.
( ,
- g. CALCULATE the ptal fuel oil in the Diesel Tuel Oil Storage .
Tanks in the ioAlowing manner:
- 1) RECORD 1A DG FO Sto Tk 1A Level from 1L1-D0001A %.
- 2) -RECORD 1A DG TO Sto Tk 1C Level from 1L1-D0021A %.
- 3) ADD both tank levels and RECORD totals %.
t 4) DIVIDE total by 2 and RECORD results: # %. (1 21J lil) INDEPENDENT VERIFICATION
- h. WHEN the respective air compressors have cycled off. RECORD the l DG Right & Left Bank Air Receiver air pressures at 1PLO7J and l VERIFT pressure greater than or equal to 2.19 psig in at least nat of the two
- 1) Right Banks psig (123D)
APPROVED O (1170V/0095V/120289) l
J' 6pa e.......e . Revistos 2 F.10.h
- 1) Left Banks , psig (a lid) l g t 1) Pressure verlfled 1 lis pelg in at least gag of the two.
I
\ 1. DRAIN water of f the Diesel Generator ruel 011 Day Tank by performing the following steps:
- 1) OPEN 1D0116A. 1A D/C Day 7ank Instrtument Leg Drain Velve.
t 2) CLOSE 1D0116A when the drain flow is free of water. INDEPENDENT VERITICATICH
- 3) Cavan up any residual oil on the floor.
- j. VERIrY the Eshaust $11encer Rupture Disc is Antact,
- k. DRAIN any water present. f rom each air receiver by performing the following steps:
- 1) OPEN 18A147A and 1SA147C,1A DG Starting Air Receiver Drain Valves.
t b. CLOSE 15A147A and 1SA147C when drals is itse of water. INDEPENDENT VEN!FICATICM eeeeeeeeeeeeeeeeeene neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e ggn: e (
- 10 Percentage which is equal to 110 gallons contained in
- l e the ruel Day Tank as required by Technical a e Specifications.
- e Gli Percentage is equal to the required tank level necessary * .
to meet Technical Specification limits (,11J00 pal) s
- plus the unusable f uel percentr.go (1d%).
- e..... ........................ eeeeee nenee ..eeeeeeeeeeee.....
G. ACCEPTANCE CRITERIA All the data entered is within the limits specified in the steps designated as acceptance criteria by W for Modes 1-6. Steps containing data have the acceptable parameter f ollowing the data blank in l (parenthesis). Steps containing a required action meet acceptance criteria when signed off. l (rinal) APPROVED l DEC 161969 O (,1,. , ..s.,,1,1..) a.o.s.a.
eso ........c.. R visica 2 (4117 CNE IB DIESEL CMERATOR OPERABILITY HCHTifLY (STAGGERED)
, '~ 1 AND SEMI- ANNUAL (STAGGERED) SURVEILLANCE l
s A. SIAIDi!2fI-.0L.AEf11CARILIII This procedure outlines the steps necessary to verify the OPERABILITY of the IB plesel Generator. This requirement is applicable in Modes 1-6.
...ee...neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee.
- ttQII *
- It Unit 1 is in Modes 5 or 6. only one Diesel Generator is e a required to be OPERABLE for Unit 1. If the IB Diesel e
- Generator is looperable. then ensure the 1A Diesel Generator *
- As OPLRABLE.
- eseeemenomeneeeeeeeeeeeeee**eeneeeeeeeeeeeeeeeeeeeeeeeeeeeeen...
B. EIII1Z2iCIS
- 1. Cooper Bessemer KSV Diesel Generator Instruction Manuals Vol 1 & 2.
- 2. NRC Regulatory Guide 1.108.
- 3. Technical Specificationes
- a. Lisniting Conditions for Operation (LCO's):
,. 1) 3.8.1.1.b - AC Electrical Power Sources - Operating i
c) 2) 3.8.1.2.b - AC Electrical Power. Sources - Shutdown
- b. Surveillance Requirements .
- 1) 4.8.1.1.2.a. 3) 4 . 8.1.1. 2. c .
- 2) 4.8.1.1.2.b. 4) 4. 8.1.1. 2.1. 2.
- 4. Station Procedures
- a. BOP DG-11. DAesel Generator Startup.
- b. BOP D3-1271. Diesel Generator Start /Stop Log.
- c. BOP DG-1172, Diesel Generator Operating 1.49
- 4. BOP DG-12. Diesel Generator Shutdown.
- e. BOP DG-13. Trouble-Shooting Diesel Generetor APPROVED DEC 161989 1 \
i (1176V/0095V/120289) B. O. S. R.
4pve e.......... R3 vision 2
- f. 1BOS 3.2.1 816, Unit One ESTAS Instrumentation Slave i
Relay Surveillance - Train B Auto 61 - K611. O g. 180! 8.1.1.2.a-1 Unit One 1A Diesel Generator Operability Monthly (Staggered) and Semi-Annual (Staggered) Surveillance.
- h. 1 DOS 8.1.1-la. LCOAR - AC Sources - Operating.
- 1. 1805 8.1.2-la, LCOAR - AC SourcJa - Shutdown.
- 5. US HRC Inspection Report 50-456/860L2s 50-457/06040 (Braidwood) dated 12 Nov 1986 (Enclosure 2, item 2.o).
- 6. Station Commitments:
- a. 6-87-048
- b. 6-87-056
- c. 6 87-019 C. Egtytoufsitts
- 1. Receive permission from the Shift Engineer or designated SRO licensed assistant prior to performing this surveillance by having the Data Package Cover Sheet signed and dated.
- 2. All Diesel Generator protective trips should be in force during Diesel Generator unit testing.
- 3. Request and sign out an accuracy checked stopwatch f rom the Shift Engineer or designee. .
- 4. The operator shall have available a blant Diesel Generator Start /Stop Log (BOP DG-1171) and Diesel Generator Operating Log (BOP DG-1172) when perf orming this surveillance.
D. PRECAUT12($
- 1. The D'Ssel Generator will kato Start if an emergency signal is received.
- 2. If the pressure drop across the full-flow Lubricating Oil filter reaches 12 psi, the elements must be replaced before further operation of the Diesel.
- 3. Ear protection should be worn by personnel in the Diesel Generator Room during Diesel operation.
- 4. An operator shall be stationed la the Dierel Generator Room whentver the Diesel is started for testing.
APPROVED DEC 161969 B.O.S.R. (1176V/0095V/120289)
R3vielen 2
$. Do not start or costlaue to operate the Diesel !! the Diesel Generator Room temperature escoeds 111't.
O 6. Do not escoed Diesel Generator rating of AAM RW or 1010 emps load for greater than 2 hours.
}
.7. Operate only C311 Emergency Diesel Generator per Unit in parallel with offsite power at any one time. This will prevent damage to more than one Diesel Generator per Unit if ,
.a fault condition develops on the grid. l
- 8. In order.to prevent !sochronous Operation when a Diesel !
Generator is la the Emergency Mode and parallele6 to the I grid. Do MOT return the Emergency Mode speed Voltage Control !
- Switch to AUM if it is currently in the MANUAL EMERGENCY '
positlom.
-E.: LIMITATICatt AND ACTICat4 1.- As stated in Technical Specifications ~ Limiting Condition for ,
Operation (LCO) 3.8.1.1 and 3.8.1.2. [ 4
- 2. The Tech spec requirement for the Diesel to start from l ambient and accelerate to at least MQ RPM in less than or !
equal.to 10 seconds shall be considered met if frequency . : escoeds AA Be withia 10 seconde. !
- 3. The. routinely scheduled Monthly and leemi-Annual portions of f this surveillance each shall be performed on a staggered l 7est Basis with 1908. 8.1.1. 2. e-l'. !
l t O 4. Verify / Maintain at least H percent fuel oil level in the , I'. Diesel Fuel Oil Storage Tanks durlag the Diesel Generator . i run (unless the DC is already IMOPERABLE). ' i
- 5. In the event the Acceptance Criteria (s!) is not met durlag performance of this surveillance, De4EDIATELY notify the {
Shift Engineer or designee to faltlete LCOAR 1908 0.1.1-la , af la Modes 1-4 or LCOAR 1908 0.1.2 1s if la Modes $.6. L
-6. If this surveillance or a portion of tlas surveillance is {
performed for purposes other than scheduled testleg, l NO CREDIT shall be takes for its- performance on the i surveillance schedule. The Shift Englooer or designee shall ! designate those portions to be performed. Notations should
~
be estored la the comunents section of the Data Package Cover Sheet containlag the ressen.for performing the surveillance. 4 i APPROVED ! r DEC 161949 ! I L 3 B.O.S.R.
.(117sv/oossv/120:se) ,
$ h 1 i .
. - _ - . . . . . - - .. -. . - . = _ . - . - - .-.- ._.- J
aun e. .....e.. R vis!SO 2 T. MAIM BQQ1 eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen
- RQIE
- s
- Initial each step in the SPACE provided adjacent to the e e
- procedure stop number ACIKE the step has been BECEsstill,1,2 e
- completed. Person (s) performing INDEPENDENT VER!r! CATI (M a shall inittel in the space provided after the step. *
..eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee T.0 Subsections F.1. F.4. F.7, r.8 and F.9 must alwayA be performed sequentially. Perallel Subsections F.2/r.3 and F.$/F.6 are independent of one another so that alther subsection may be performed. Only one of each parallel subsection may be performed.
The Shift Engineer or designee shall designate which subsections shall be performed (Normally shown on the Surveillance Schedule).
............eeeeeeeeeeeeeeeeeeeeeeeeaneeeeeeeeeeeeeeeeeeeeeeeeee e gorg .
- Sequential pertoriaance of the required Subsections and the *
- following parallel Subsectione provide *
- e F.2 and r.$ *
- Manual local start and gradual loading. e a e F.3 and r.5 *
- Auto start from ESF and gradual loading. * .
*
- r.2 mad F.6 *
- Manual local start and 1 10 sec loading. *
*
- r.3 and F.6 *
- Auto start from EST and 1 AD sec loading.
- e eeeeeeeeeeen.eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen.eeeeeen i
gL l ' 32ARI l l . . l . F.1.. l Initial Conditions l Manual Local I l Auto Start from 2l Start (DOP DG-11) l l r 3 l_ ESr (1905 3.2.1 816) (Quarterly) 3atermediate Concitions l r 4. . l and Verifications Lead to A ,5100 RW l . I Load to 111RQ IM (Gradual) lM1.l l _,, lSl (within 10 seconds) (Semi-Annually) (Monthly) l Fuel Transfer Pump l.Ll l Operability O l.L1l one nour Loaded Run and Shutdown g,Ng W g _ 8, c.a . rinal Conditions A g3 ( l9l END S 6 -4 (1176V/0095V/120289) i L
ee- e.....e.e . , 20vists:n 2 ! r.1 Initlai conditions
- a. RECORD the follow!ngs DATE: ' 'l TIME: L 3 NODE: !
- b. RECORD the followlog for the stojwatchs f Inst QA $3 f
~
Calibration dates i
- c. RECORD the Diesel fuel 011 Day Tank level from 1L1-D0038:
~~~~~
t % (2 M lt) [ eeeeeeee mene eeeeeeeeeeeeee_ enenneen.....e e eee sseeeeeeeeene i
- RQ11.
- a Verify / Maintain at least M percent fuel 011 level in the *
- Diesel fuel 011 Storage Tanks during the Diesel Generator e
- run (unless the DG !s already INOPERABLE).* a ;
seeeeeeeeeeeeeeeeeeeeee3eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene
- d. Calculate the total fust oil in the Diesel 7uel O!! Storage Tanks in the following seanner (Acceptance Criteria (f) N/A if ,
the 1A DG is already IMOPERASLE):
- 1) RECORD 15 DG FO Sto Tk 1B Level from 1L1-D0002A %
l
. /
- 2) RECORD it DG r0 Sto Tk 1D Level f ros 1L1-D0022A %
!' NJ e l 3) ADD both tank levels and RECORD totals % l s /*
- 4) D1 VIDE tot.a1 by 2 and RECORD results: # %
(1 93.8 til) F.2 Manual Local start inoe DC.11) eeeeeeeeeeeeeeeeeesseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e gggg *
- Prior to starting the Djosel, ensure a stopwatch is *
- available to record Lhe ti.mo it takes for the Diesel to e
- reach > 1992 volts.
- eseeeeeeeeeensoneeeeseceaseeeeeeeeetseeeeeeeeeeeeeeeeeeeeeeeeeen j
- a. RECORD the DG Right i, Left Bank Air Receiver air pressures et 1PLO4J l
1)- Right Banks psig APPROVED s
- 2) Left Banks peig e, 6.a 8.O.S.R.
O
\J (1176v/0095v/1202ss)
.s.
AbW 6 4 1 4.s.2 R visito 2 P,4. a b. VER!rY/ PLACE the DG lli Act 1423 Auto teclose Circuit Ann Selector Switch in the SURV TEST position at 1PM01J. *. 6.c
. Locally at 1PLOBJ, START the Diesel per DOP DG-11.
eY d.- At the same time the Diesel is started. START the stopwatch. As soon as the Diesel reaches 19A2 volts, STOP the stopwatch and then Inusediately verify 2102 RPM and f requency between inj to iL2 Ns. *. 6.b s T. Auto start from ItAr i120s.3.2.1 818) eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e CAUTICE *
- 3.2.1-816 WILL ENERGIEE SLAVE RELAY R611 WN!CN WILL e e S RT DIESEL GENERATOR 18 IN THE EMERGENCY MODE. UNTIL *
- THE IS SELECTED TO MANUAL IM 1908 3.2.1-816. ALL NORMAL e :
- PROTE IVE PEATURES ARE BYPAS$tD. IP AENORMAL CONDITIONS e i e ARISE, P THE DG USING THE EMERGENCY STOP PUSMBUT20N AT e f
- 1PLO6J. e j
ene.. neneenen eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenne g
\
eeeeeeeeeeeeeeeemeneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee " t I
, e
\ E2ZE Prior to starting the Diesel. essure a stopwatch is e
j t
- evallable to record the time it takes for, the Diesel to e I
[
- reach > ADAQ volts. \
- l
( seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee j i
- a. RECORD the DG Right & Left' Sank Air Receiver air pressures at .f 1PLOBJ .
-{
- 1) Right Banks peig
- 2) Left taakt psig *, 6.a ,
_ i
'* s b. VERIFT/ PLACE the DG 19 ACB 1423 Auto Reclose Circuit Arm .
Selector Switch la the SURV TEST position at 1PM01J. *. 6.c .!
\
I
- c. START-the 15 Diesel Generator per 1506 3.2.1-816. [
\ .!
- d. At the same time the Test Switch 8834 is depressed in 1906 I 3.2.1-816 to start the Diesel, START the stopwatch. As soon as j the Diesel reaches > 1992 volts. STOP the stopwatch and then .}
1 e.ediately verify 2- 102 RPM and f requency between. ins to ; iL,2 Es.. *. 6.b. ! APPROVED DEC 161969 1 i B. O. S. R. l l (1176V/009$V/120289) { i ;
)
i I
. i
, , , . . . m, ,_s._ ,,__ _, ~.. _ _- . . ._. , , , , _ _ _ . . . . - , .-
..,.,,,...,-a._-_.-.-__._..~.,.,.d
abub s.4 4...a.. 23vieles 2 ! i T.4 Internadiat. conditions and Verificatinaa unza . ; Moalter the D!esel for abnormal conditloss. If trouble * ! occurs, refer to top DG 13 or the appropriate BAR. . l
- a.- I m tDIATELY RECORD the DG Right & Left Sank Air Receiver air pressures at IPLO8J and VER!tT a presrure decrerse from the !
value-recorded la steps F.2.a or F.3.a a6 appilcables
" f
- 1) Right Banks psig l
- 2) Lett Banks pelg !
# 3) Pressure decrease-verifled in both Air Receivers. *, 6.a i i
e b. VERITY 18 and/or ID Fuel 011 Transfer Pump STARTED. t s c. RECORD the following data:
- 1) From the stopwatch, time for the DG to reach
> 1992 volts e see (.t 10) .
- 2) DG ruaalog RPNI W OO RPM (ill to 112) -
- 3) DG running voltages ,
WDN V (12.1Q to (119) -f
- 4) DG runnlag frequency: # b Na (ild to iL.2)
_-+ d.- UPDATE DOP DG-1171. Diesel Generator Start Stop Log. .
. / e. VERITY / PLACE the DG lt control Mode Selector Switch la the REMOTE position at '1PL08J. i i
F.5 japad to 1 6500 Bf f Gradiam11 - L N aars
- Operate the Diesel Generator for approximately 1 minutes
- j before loading.- When performing the followlag step, the-
- j Diesel Generator should be loaded gradually to reduce
- i thermal stresses, la the cylinder heads. When increaslag .' l
*' load f on A RW to W RW, the load should be applied la * [
* '1929 RW ste over n' period of a to 1 minutes.- *
..............P.se................................................ !
t
- a. Request that the NSO synchroelse the Diesel Generator-to its
,-associated ESF bus and gradually load it to 1 110A RW as per j DOP DG-11. ?
APPROVED t DEC 161989 O- 8. 0. S. R. 1 (1176V/0055V/1202s9) ! 3 t I r r
, , , ,..- ~ ..,. - -.m.. . . . _ , . , _ - - _ - - . _ _ _ . - . _ _ _ . _ - _ - . . . - . _ _ - _ , . . _ _ . _ _ _ . . . - - _ . _ .. _ _ - _ - _ _ _ _ _ _ _
wve e.s.....e . Revision 2 T.5 N
- b. When the Diesel Generator output reaches 11100 W, RECORD the followingt \\
O Clock time when $he Diesel Generator output
\
1 iMQ WI F.6 1.D.Ad to 15500 FM (within 60 secondal seenneeeeeeeeeemeneseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene e e ggry, e Before synchronising the Diesel Generator to its associated e*
- EST bus, have a stopwatch ready to rosasure the time it
- takes to reach 1 1520 KW.
e......eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen
....... eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenenneeeeene e
e ggIg e
- When loading the DG to 15500 m in 160 seconds, ut111:e e as much of the 60 seconds as possibles to minimise stress *
- on the engine and turbocharger.
eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemene
- a. Request that the HSO synchronise the Diesel Generator to its associated EST bus and load it to 1152D KW as per BOP DC.12.
When closing the breaker, OBSERVE and PERTORM the ic110 wing j 1) At the same time the Diesel Generator Output Breaker is 7 ' closed, START the stopwatch. O .1f/ I
.,. 2) LOAD the Diesel Generator to 11120 W per BOP DG-11 within 10 seconds. *
- 3) When the Diesel Generator output reaches 1 11Q0 W , STOP the stopwatch and RECORD the followkogi a) Time it took for the Diesel Generator to loads t OC sec (1 12) b) Clock time when the Diesel Generator output i 1122 EW @ #
APPROVED DEC 161969 (1176V/0095V/120289)
ACW 6 1.a...e-4 l R3vieles 2 f.7 Egal.IIAn11gr Pump oograS111tv variflsatina I g) .......eeeeeeeeeeeeeeeeeeeeeeeee ......................(e. ... . ; e EDIE V
- e Step r.7.a and b ver!fles that the fuel Oil Transfer Pumps e
- transfer fuel from the oli storage tanks to the day tank. * [
e This step should be started shortly after the DG la fully e l e loaded. Both transfer purops should be tested, however, e
- only one transfer pump is Is.guirnd to be OPERABLE. If a
- a transfer pump is Out-of-Service. mark the step for testing
- e e it N/A. t one.............. eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee ........
- a. VERIFT 18 Fuel 011 Transf er Pump maintains Day Tank level. ,
- 1) VER1rY/ PLACE 1B fuel 011 Transf er Purnp to the AUTO position.
- 2) VERITY / PLACE 1D ruel Oil Transfer Purnp to the Off position.
t ?) VERITY Day Tank level is innintained for 15 minutes. i
- 4) PLACE ID Fuel 011 Transfer Pump to the AUM position. l a, . VERITY 1D Tuel Oil Transfer Pump maintains Day Tank level. {
- 1) VERITT/ PLACE 1D Fuel Oil Transfer Pump to the AUTO position.
- 2) VERITY / PLACE 18 Fuel 011 Transfer Pump to the OFT positior). ;
, r_ 3) VER!rY Day Tank level is maintained for 15 minutes.
- 4) PLACE IB ruel 011 Transfer Pump to the AUTO position.
F.8 One.Ecur_ Leaded Run and Ehutdown neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenneeenseeeeeeeeeeeeeene e gggg a
- The Diesel Generator must be maintained at i 1100 p for e
- the duration of the test (110 mins). MCMITOR CLOSELY and *
- ADJUST RW output to malata!n i 1100 RW.
- eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenneen i
- a. After the Diesel Generator has run loaded at i 110A N for 1 12 minutes. SHUTDOWil the Diesel Generator per DOP DG-12 and ;
RECORD the following datas t
- 1) Clock time p output.< 1102 W:
- 2) Clock-time p output 1 1100 W from step r.5.b or step r.6.a.3)b) as appilcables l
- 3) Total time RW output 1 1100 W I f min (1 10)
. APPROVED l
M \ 0 II89
. ' (1176V/0095V/120289)
B.O.S.R. . t
. _ _ _ _ . , . _m..
A na 6 4 6.. . a-. R3visies 2 r.9 I.intLCondi tlens
- a. VER1rY/ PLACE the DO 18 ACP 1423 Auto Reclose Circuit Arm O Selector Switch in the NORM position at 1PN01J. e. 6.c INDEPENDENT VERIFICATION
- b. Af ter the Diesel Genek ator is shutdown and the cooldown cycle is complete, ALIGN the Diesel Generator for standby operation by perforning the foDowings r 1) VER1rY the UNIT AVAILABLE FOR EMERGENCY" lamp is lit.
t 2) VERITY all 4 DC Power indicators age lit. t 3) VERITY / PLACE the DG 18 Control Mode Selector Switch in the RF. MOTE position at 1PLOBJ. INDEPENDENT VERITICATION
- 4) REMOVE the key and return it to tho' Shift Engineer or designee.
t_ 5) VERITY all the local annunciators are not lit. If any annunciator is lit, NOT!rY the Shif t Eugineer or designee for evaluation and RECORD lit annunciators. LOCAL ANNUNCIATORS LIT . O l V l l EVALUATED ACCEPTABLE: . SE or designee t 6) VERITY the Diesel Generator Output Breaker in ATTER TRIP. INDEPENDENT VERITICATICBI
- c. VER1rY/PLhCE IS Fuel 011 Transfer Pump in the AtTIO posation.
INDEPENDENT VERITICATICBI
- d. VER1rY/ PLACE AD Tuol Oil Transfer Pump in the AU't0 positlan.
INDEPENDENT VERIFICATION t e. RECORD the Diesel Tuel Oil Day Tank level ! rom 1L!.DOO38:
# ' '1 "'
APPROVED INDEPENDENT VERITICATION l-l B.O.S.R. l -10 (1176V/0095V/120289)
1B05 6.1.1.2.a 2 Revision 2 F.9.
- f. r!LL the 18 DG Tuel 011 Storage Tanks, as necessary.
- g. CALCULATE the total f uel oil in the Diesel Fuel Oil Storage Tanks in the following marner
- 1) REC 01D 1B DG TO Sto Tk 18 Level from ILI.D0002A
- 2) RECORD 18 DG TO Sto Tk 1D Level f rom 1L1-D0022A
- 3) ADD both tank levels and RECORD totals DIVIDE total by 2 and RECORD results t %.
t 4) (1 1142 til) INDEPENDENT VERITICATION
- h. WHEN the respective air compressors have cycled of f, RECORD the DG Right & Left Bank Air Receiver air pressures at IPL0fJ and VER1rY pressure greater than or equal to lia psig in at least QDS of the twot
- 1) Right Banks psig (1 119)
- 2) Lef t Bankt psig (1 119) -
t 3) Pressure verified 1 110 psig in at least ant of the two.
- i. DRA1H water of f the Diesel Generator Fuel Oil Day Tank by O performing the following steps:
OPEN 1D0116B, 18 D/G Day Tank lustrument Leg Drain Valve,
,__ 1) s .
t E) CLOSE 1D0116B when the drain flow is f ree of water. INDEPENDENT VERIFICA710H . .
- 3) Clean up any residual oil on the floor.
3 VERITT the Eshaust Silencer Rttpture Dise is (ntact.
- k. DRAIN any water present, from each air receiver by performing the followiag steps:
- 1) OPEN 15A147B and 15A147D,1B DG Starting Air Receiver Drain Valves.
APPROVED DEC 161969 B. O. S. R. 7-. all. (1176V/0095V/120289)
1605 a.1.1.2.o.2 Revisica 2 , T.9.j i CLOSE ISA1478 and ISA147D when drain is f ree of water, j ( W 2) i INDEFENDEN7 VERITICATICM :
...................... ........................e................ j
- If2II *
(
- ll Percentage which is equal to 110 gallons contained in the* j
- Fuel Day Tank as required by Technical Specifications. * '
e . ;
- lli Percentage is equal to the required tank level necessary
- l
- to meet Techuleal Specification limits (> 11d(tQ gal) e t
* -plus the unusable f uel percentage (Ll%).
- e...........een..en.nesee.eeeee.nes.een.ne ..eaneesee.eeene.....
G. . ACCEPTANCE _.CA11111A I All the data entered is within the limits specified in the steps designated as acceptance criteria by W for Modes 1 6. Steps containing i data have the acceptable parameter following the data blank in [ (parenthesis). Steps containing a required action meet acceptance y criteria when signed off. ; i r I I f, O ! r i
)
?
I i I APPROVED ! 1 DEC 161969 ! B.O.S.R. l (rimal) . I (1176V/0095V/120289) ., O f
- . . _ , . , . . . ~ __ ..-,, . , . _ , _ , - . ._....,-,._m.__..%.-.,,_ , _ ~ - _ , _ . . . , , , , . . - - _ . , ,, . . . - .
4ppnoVED inos s.2.1.1-1 001 14 8 Revision 1 DC SUS TRAIN DPERABILITY WEEKLY SURVEILLANCE A. STATEbefT Or APPLICARILITY1 This procedure applies to the weekly verification of 125VDC Bus 111 sad /or 112 operability la MODES 1-6. eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene
- NOTE e
- If the Unit is la MODES 1-4, both 125VDC ESF Sus e a trelas are required tc be operable. If the unit e
- is la M00ts 5-6, only one 125VDC Esr sus train *
- is required to be operable. e neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemeneseeeeeeeeeeeene
- 3. R1rER2atetti
- 1. Technical Specificatica 4.8.2.1.1.
- 2. Technical Specification 4.8.2.2.
C. FRERECIIIIITERI
- 1. Receive permissies from the Shift Engineer or his designated SRO licensed assistaat prior to perforetag this surveillance by having him-sign and date the Data Package Cover Ebeet.
D. 233C&UTIME1
. 1. .on.
E. LIMITATICERE AMD ACTIMBt
- 1. As stated la Technical Specifications Limittag Condition for Operation 1.8.2.1 sad 1.8.2.2.
- 2. In the evoG !%e Acceptance Criteria is not met during the performance of *:his procedure, IMMEDIATELY actify the Shif t ,tagineer to initiate LC0ha precedure 1908 4.2.1-la it la Moots 1-4 or LCOAR precedurs 190s 8.2.2-la if la MODES 5-6.
T. MAIN BCIN eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee$seeeeeen EZIX * ; This surveillance may be performed as a partial surveillance
- f as applicable la modes 5 and 6 or to prove operability of
- any. individual component. * !
eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen $ i
- 1. ENTER Time, Date, and Unit Mode on Data Sheet D-2.
I
- 2. For the desired bus (busses) listed on the Data Sheet, perform the f
followingt i (0618v/0057V/100388) [ e ,m-- - --w,, c..,-,--,.,..,--n,m,-rm--,-- ,,-,,,,-vac-- , , -,,ew,--- ,~m,,me~w~,nnnr m- -ev,: , v ., --
.__. . . . . . . - . - - - . _ ~ _ . .. -- . - . - . - . ._- , _ . _ . . - . . - - - - - _ .
1905 s.2.1.1-1 Revision 1 Wa. RECORD DC Bus Voltage ) ( ) tb. RECORD Battery charger feed breaker position I tc. RECORD Charger AC input breaker position. I (d. RECORD Charger DC output breaker position. go. RECORD reed Breaker fran Battery Charger (cub Arl) position. df. RECORD reed Breaker from battery (cub Ar2) position
- g. RECORD Bus tie breaker (cub Drl) position. [
- 3. Circle any actual data not meeting the required conditions prior to returning data sheets to the Shift Engineer. !
G. ACCEPTalICE CRITERIA: ;
- 1. MODES 1 Actual data recorded om data sheet meets the required conditions listed on the data sheet for 125VDC Esr aus .
111 AND 112. '
- 2. MODES S-6: Actual data recorded on data sheet meets the required ,
conditions listed on the data sheet for 125VDC EST Bus i 111 OR 112. ' i O l
?
t i t 5
?
5 APPROVED l O (rar. 1) OCT 141988 B. O. S. R. i (061sv/co577/ looses) i 1 I Y
. _ _ . . _ _ . . . _. - . _ , _ _ - . . - _ _ = _ - . _ - - . . . - - - = . _
v 1908 8.2.1.1 1 l Revision 1 l
- t DC WE TRAIN OPERABILITY WEEKLY SURVE!LLANCE ;
L t i t
- 1. Tfurt /0 f 7 DATre 4 l%9/ tftf1T brme t i
i t 125 VDC ESF Bus 111 Raoulted actug L Minimwn of ga. Bun Voltana 12B VDc d / 7 ),., 2h. Battery charner fand bramhar ( Rum 111X cuh 43) clamed e c h4ff) . 2e. r* harmer Ac lanut bramhar cinand dMU/ 2d. Pharmar DC nutnut bramhar cleand d A'M [ Ni^ i 2a. Faed bramhar from_ A ttery Phareer feuh AF1) cingad d M' p */l 2f. Faad hramhar frare tattery (euh AF2) cinand d(itb/O f l 2a. Rua tie bramhar to DC bus 211 (cub DF1) fached Onan D%# [ U I i 125 VDC ERP Bus 112 Raoulred actual m Minimum i et , l 2a. Rua volt - 125 VDC d I24 i Ib. Battery akeraar f u branhar (num 112X cuh 43) clamad d _r t.c S! O je. Pharmer Ac immut branhar finand e .dIA
. l.
i 2d. Phaeaar Dc autant branhar finand d 4A_4 q 2a. Faed brankar fram Rattery Pharmer fenh Arl) cloaad WNA i 1 2f. Faed bramhar from Battery fenh AF2n cinand eClhfU [ e 2a. Rua tie bramhar to DC bum-212 feuh DF1) tackad Onan ' TI8 M 5 i L
- In WODES 1-4 both BUS 111 and 112 must. be operable.
j In MODES 5 Qt 6 only WB 111 CR 112 must be operable. APPROVED
,O i 'V o-a I (0618v/0057V/100388) OCT 141988 MNE B.O.S.R.
BYRON SlHULATOR AN51/ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT. SEPTEMDER, 1991 BYRON SIMULATOR REAL TIME TEST The objective of the Real Time Test is to verify that the Byron Simulator perforfrance meets the criteria of ANSI /ANS-3.5-1985 Appendix A.3.1. The Real Time Test Acceptance Test Procedure consisted of timing and recording several ' valve travel times during normal plant operation and then during a loss of coolant accident with a loss of off-site power. The results of the Real ilme tests were satisfactory, with a less than 1% difference in the steady state travel times and the accident condition travel times. ; I t O l l f3J (BYRONSIM 113/67 08/22/91) l
l I BYRON S1HULATOR l ANSI /ANS-3.5-1985 CERTlf! CATION REPORT !; INITIAL REPORT. SEPTEMBER, 1991 p ! l BYRON S!HULATOR TRANSIENT TESTS j The objective of the Byron Simulator Transient Tests is to verify the ability of the ! simulator to perform the transients as required by ANSI /ANS-3.5-1985 Appendix B.2.2. ! All Appendix 8.2.2-Transients were performed. Data was collected as prescribed in ANSI /ANS-3.5-1985 Appendix B.2.2 at 0.5 second intervals. Transients were run until ' stable conditions were-reached, f ! The simulator response was reviewed by the Byron Simulator Transient Test Review Poard. f The acceptance. criteria for-these tests is that the observable change in parameters correspond in the same direction to those expected from a best estimate, do not violate { the physical laws.of nature, and do not detract from training. An abstract of each test along with plotted data is included in this Attachment. The makeup of the -lent Test Review Board is located in Appendix 4. As indicated on the enclosed transient test review sheets, the Transient T' t Review Board accepted the individual data plots and the overall test results with lie understanding that any discrepancy reports (DR's) written as a result of the transient review w11_1 explain or correct the problem. The discrepancy reports written as a result of the transient review are noted in Section A.3. The following page is a description of how to interpret the transient data plots. NOTE Individual _ loop steam flow and feed flov were used because total steam flow and total feed
. . . f. .l o. .w. . a. r e.... u. n................................
- a. v. a. .i l a. b .l e.
LO (BYRONSIM 113/68 08/22/91) 1
.. . . _ _ . _ . , . ~ _ .
__ . . _ , _ - . _ ~ . _ . , . ~ , _ , _ _ _ . _ _ _ . . _ , ~ . . .
DESCRIPTION OF TERMS AND UNITS USED IN TRANSIENT DAT A PLOTS f} TI TL E, DATE ANO Q) TIME THAT THE DA TA WA5 P1 of TfD ,,,,,,,y,nu,,,,,,,,,,,,,,,,,,,n,,,,, , e,,,, ,,,, < THE EL APSED TINE OF :- omstow . 71 os Stcowos EACH TRAN5IENT WA5 (0 - OlV10E0 INTO 20 INTERVALS .I I I I I I I I I I I I I I I i (DIVISIONS) FOR PLOTTING , Y _ THE EL AP5ED TIME Of a _ ,,. EACH OlVl510N IS LISTED IN SECON05 '
- I DI VISION \
6 . THE VERTICAL AXIS Of
- EACH PLOT DIVIDES THE VARIA0lt RANGE (LIS TED * ~ ~
DEL O W) B Y I 0. FOR THIS PLOT, THE VERTICLE AXIS WOULO BE 2 - FROH 555 TO 565*F, WITH EACH OIVIsl0N BEING l*f . . i l I I I i 1 l I 1 inAl i I l ' d 0 5 10 15 20 TINT
- 14xT A !6(1) ( $$5, . 565 3 01200 LOOD f AB.! .
l f % VARIABL E NAllE VARIABLE RANGE DESCRIPfl0N OF VARIABLE r s VARI ABLE UNITS FLOW VARIABLES (Except RCS Loop f lo w). . . . . . . . . . IOm/ s e c RC5 LOOP F l o w. . .. ... . .. . . . . . % TEMPERA TURE VA RI ABL ES.. .. . . . . . . ... .... . ... ... . D e gr e e 's F LEVEL V A R I A 6 L E 5. . . . . . . . . . . . . . . . . . . .. . . .......... . .. . . % PRESSURE VARIABLES (Except Pressurtter Pre s s ure)... .. , . psta Pressurlier Pr e s s ur e. .. .. .... ... . .... ....... .. . ... . ... pstg NEUTRON FLUX VARIABLES: Power Rangt. . . ... ... ... ... ... .. . , . . .% Source Range. . . .. . .. . . .. . . . . . . counts /sec 5
-- e - ., n ,e ~ ,
w
l BYRON SIMULATOR l TRANSIENT TEST REVIEW ! O' TRANSIENT TEST: 7.2.1/ #/ TITLE MANUAL RX TRIP DATE : AUGUST 19, 1991
- 1. Baselino data utilized for test comparison in order of proforence (highlight appropriato cholcos) ;
- a. Actual plant transient data EVENT : i
- b. Analytical or design data DATA: j
- c. Transient data from similar plant PLANT : BRAIDWOOD i LER 20190 008 -
- d. Panel of experts (best estimate) !
COMMENTS: !
- 2. Data Comparison Summary [
VARIABLE COMMtiNTS RESOLUTION RX PWR - PR M ACCEPTED > IO
" AUC HI TAVE SIMULATOR @ 560*F, PLANT @ 557'F ACCEPTED W/
WR 08 910006 PZR Pf4ESS M ACCEPTED r PZR LEVEL , M ACCEPTED l PZR VAPOR TEMP ,VERY SLIGHT INCREASE AT 18 MINUTES ACCEPTED HOT LEG TEMP M, ACCEPTED l COLD LEG TEMP SIMULATOR @ 560*F, PLANT @ 557'F ACCEPTED W! >
- WR 08 910006 ,
1 A S/G PRESS SIMULATOR @ 1112#, PLANT @ 1090# ACCEPTED W/ l WR 08 910006 ; 1A S/G LEVEL AF THROTTLED @ 6 MINUTES ON SIMULATOR ACCEPTED i 1 A S/G FW FLOW PLANT RESTORED MAIN FW FLOW ACCEFED ; 1 A S/G STM FLOW SLIGHT SPIKE AT TIME OF TRIP ACCEPTED W/ i WR 08 91-0007 1 A S/G WR LEVEL LEVEL DROPPED FURTHER ON PLANT ACCEPTED W/ WR ,08-91-0009 i O
BYRON SIMULATOR TRANSIENT TEST REVIEW VARIABLE COMMENTS RESOLUTION
- 3. Comparison Results Simulator capability to reproduce the defined transient: (circle one) g 'a'. AUCEPTABLE))
- b. UNACCEPTABLE
- 4. Review Board Signatures ( differing opinions must be documented )
O aa., , .jpg.,};
&{L cd 00 ~
SL, w ff - ION &c~$h! COMMENTS: g M__ w - -- gg
"'"* - en e 98 - _g N mm O
i l O ! I
)
ATP 721 YCN0049 05/20/91 09:09:05 i 1 DIVISION = 60.00 SECONDS : it f I I I I I I I I I I I I I I I I ! 8 __ _. t l e :... __ j P [
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Q s ATP 721 RXTAVG 05/20/91 09:12:30 1 DIVISION = PC 00 SECONDS 1r I I i I I I I I I I I i l I I I 6 __ _ 6 . . _ j
- k O - -
2 __ __ i i i I i l I ; I I I I I I I I O 5 10 15 20 TIME RXTAVG. ( 520. . 620. ) 01200 LOOP TABLE O
,,~, , 'd ATP 721 YCP0480 05/20/91 09:4't26 1 DIVISION = 60.00 SECONDS I I I I I I I I I I I I I I l l 8 _
l l ! 6 __ _ t 1 p) b 4 - _ 2 _ _ I I I I I I I I I I I I I I I i 1 ! 0 5 10 15 20 l t TIME YCP0480 ( .200E+04, . 240E +04) 06720 PRESSURIZER PRESS PT-455
,m,
O ATP 721 YCLO480 05/20/91 09:25:47 1 DIVISION = 60.00 SECONDS 1 I I I I I I I I I I I I I I I 8 _ 6 4 _. 9 2 __ l i I i i l I I i l i I I I I I l 1 0 5 10 15 20 TIME YCLO480 ( 10.0 , 60.0 ) 06550 PRESSUitIZEP LEVEL LT-459 9
O ATP 721 YCT0481- 05/20/91 09:48:50 1 DIVISION = 80.00 SECONDS-1r I I I I I I I I I I I I I I I l 6 t 8 _ f r I 6 l
/ -
[ I
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-h I i i i I I I I l l l- l l l l l j 0 5 10 15 20 ,
TIE i YCT04P1 ( 820. , 670. )- 91250 PRESSURIZER STM T~ , '~ r j
--.-,..----..2-....... -
.--. ._...~ ~ - _ . . , , - . - . _ . . - _ , . . . . , - . _ _ . . - . . . - - . . . _ _ . - - . -
.. . - . - - . - . - - . . . . - . - ~ - . - - . . . . _ . . .-.. - --- - - . -
1 -
-i i
08/11/91 ATP-721 YCT0418 13:11:40
^
1 DIVISION = 00.00 SECOWS If I I I I I I I l- 1 I I I I I I -l h s _ _ j l 8 _ : i i t
. . 6 9
4 l f e 2 _ _ l l E . l- l- l- -l I 1 I I I 1 I I 1 i I l- , O. 5 10 15 20 i I TIIE YCT0419 ( 520. 620. ) 06830 RC LOOP 1A WR HOT LEC T h l [ Q ! t k i i 3
- r
l O ATP 721 YCT0406 06/11/91 13:16:08 1 DIVISION = 60.00 SECONOS It I I I I I I I I I I I I I I I I 8 4 O' r - 2 I I I I I I I I I I I I I I I I 0 5 10 15 20 TIE YCT0406 ( 520. , 620. ) 08825 RC LOOP 1 A WR COLD LEG T O
_ _ . . . . ~ _ _ . _ 5 O ! ATP 721 YCP0400 04/11/81 13:08:42 f i 1 DIVISION = 80.00 SECONOS : If ! I I I I I I I I I I I I I I I I _ _ l I j 8 __ l
-f
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P 1 1 I I I I I I I I I I I I I I 0 5 to 15 to i
- . i TIN 2 l >
l i YCP0400 ( 800. . 120EM4) 06590 S/G 1 A STM.INE PRESS PT-S , r l I l i 6
l O , i ATP 721 YCL0400 08/11/91 13:28:20 ! i 1 DIVISION = 40.00 SECONDS i If ; I I I I I I I I I I I I I I I I . 8 i s _' _ : O* - - 2 l e I I I I I I I I I I I I I I I I 0 5 10 15 to 1 TIIE YCLO400 ( .000 , 100. ) 06350 S/C 1A NAR RNG LEVEL LT-51 t L O : r
-- --. ._ _ . . . .- . - -. ~ _ . . _ . . _ _ _ _ _ . . _ . . , . . - _ . . _ _ . _ . -
. . - . . .. .-. - . _. . - .. ~.. _- - .-. . - - - - .
i r [ I ATP 721 YCF0403 08/11/91 13:21:55 i t 1 DIVISION = 80.00 SECONDS ! If i l I .I I I I I I I I I I I I I I :
. - r 8 - i O - - _ ,
I l 4 l O .i l k 2 _ _ ! i
. em 6
I I I I I I I I I I I I I I I I j
.0' 5 to 15 20 l
TIE l P L YCF0403 ( .000 . 400E+04) 06040 S/G FW F FT-510 i P u ;
?
O ATP 721 YCF0405 06/11/91 13:30:19 1 DIVISION = 60.00 SECONDS 1r I I i I I I I I I I I I I I I I 8 _. ._ a ._ ._ Q4 ' 2 _. ._ l Li ! l ! l i ! ! ! ! ! ! ! ! 0 5 10 15 20 TIDE YCF0405 ( .000 . . 400E+04) 06060 S/G 1 A STEAM y F T-512 O
G i V ' f i ATP 721 YCLO404 08/11/91 13:38:17 ; 1 DIVISION = 40.00 SECONDS ; le _ i l I I I I I I i I I I I I I I I s _ _ e _i i i l 4 .- - j 2 _ _ j l l I I i l I I I l I I I I I l l l 0 5 10 15 to l TIE l i YCLO404 ( .000 , 100. ) 06390 S/G 1A WIDE RNG LEVEL LT-5 ,
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O ATP 722 RXTAVG C6/11/91 13:45:36 1 DIVISION = 55,00 SECONDS I I I I I I I I I I I I I l~a I 8 ._ 6 __ __ M 2 __ I i 1 I I I I I I I I I I I I I 0 5 10 15 20 TIE RXTAVG ( S20. 820. ) 01200 LOOP TABLE O
O ATP 722 YCP0480 06/11/91 13:54:01 1 DIVISION = 55.00 SECONDS If I I I I I I I I I I I I I I I I a _ _ e _ l l 4 - _ 2 _ _ W _ _! I I I I I I I I I I l i I I i 0 5 10 15 20 TIE YCP0480 ( .200E+04, . 400E+04) 06720 PRESSURIZER PRESS PT-455
G ATP 722 YCL0480 06/11/91 13:57:58 1 DIVISION = 55.00 SECONOS It i I I I I I I I I I I I I I I I 8 _ . 6 _ g 4 _ 2 _ l 1 1 I I I I I I I I I I I I i 0 5 10 15 20 TIE YCLO480 ( 10.0 , 60.0 ) 06550 PRESSURIZER LEVEL LT -459 9
i i t t i ATP 722 YCT0481 08/12/91 04:39:21 i 1 DIVISION = 55.00 SECONDS 1 te I I I I I I I I I I I I I I l l l 8 _ _ i
-i
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O ATP 722 YCT0406 06/12/91 04:47:26 1 DIVISION = 55.00 SECONDS tr I I I I I I I I I I I i i I i I 6 ._ ._ 6 __ __ 4 ----- ._ 2 __ I I I I I I I I I I I I I I I I o 5 10 15 20 TIW. YCT0406 ( 520. , 620. ) 06825 RC LOOP 1 A WR COLD LEG T O
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O l r ATP 722 YCP0400 04/12/91 04:51:34 1 DIVISION = 55.00 SECONDS ! It . : I I I I I I I I I I I I I I I I l s __ _ I ! e _ _ : _J Y ! i I i 4 _. _ j t l l 2 _ _ j
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